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Sample records for wipp programs administered

  1. Waste characterization program plan for WIPP experimental waste

    International Nuclear Information System (INIS)

    1991-01-01

    This program plan is being issued by the Department of Energy (DOE) to reflect the current status of the waste characterization program. Not all methods of compliance with the requirements imposed by the regulators have been fully developed. Although the Environmental Protection Agency has issued the Conditional No-Migration Determination for the Waste Isolation Pilot Plant (WIPP), several activities have to be studied for recommendations of optimum courses of action. Therefore, as the DOE determines compliance methodologies for the requirements of the No-Migration Determination and for the requirements of the New Mexico Environmental Improvement Division, this program plan will be revised and reissued as often as necessary. It should also be understood that the DOE will comply with all regulations prior to making any shipment of transuranic waste to the WIPP for the experiments. 14 refs., 4 figs., 5 tabs

  2. Weatherization Innovation Pilot Program (WIPP): Technical Assistance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Hollander, A.

    2014-09-01

    The U.S. Department of Energy (DOE) Energy Efficiency and Renewable Energy (EERE) Weatherization and Intergovernmental Programs Office (WIPO) launched the Weatherization Innovation Pilot Program (WIPP) to accelerate innovations in whole-house weatherization and advance DOE's goal of increasing the energy efficiency and health and safety of low-income residences without the utilization of additional taxpayer funding. Sixteen WIPP grantees were awarded a total of $30 million in Weatherization Assistance Program (WAP) funds in September 2010. These projects focused on: including nontraditional partners in weatherization service delivery; leveraging significant non-federal funding; and improving the effectiveness of low-income weatherization through the use of new materials, technologies, behavior-change models, and processes.

  3. WIPP Salado hydrology program data report No. 1

    International Nuclear Information System (INIS)

    Saulnier, G.J. Jr.; Domski, P.S.; Palmer, J.B.; Roberts, R.M.; Stensrud, W.A.; Jensen, A.L.

    1991-05-01

    WIPP Salado Hydrology Program Data Report number-sign 1 presents hydrologic data collected during permeability tests of the Salado Formation performed from August 1988 through December 1989. Analysis and interpretation of the test data are presented in a separate report. The report presents the results of the drilling and testing of six boreholes drilled from the WIPP underground facility 655 m below ground surface in the Salado Formation. Permeability tests were conducted using multipacker test tools with inflatable packers to isolate borehole intervals to allow formation pore-pressure buildup and subsequent pulse-withdrawal tests. Test data include pressures and temperatures in brine-filled, packer-isolated test intervals and borehole-closure and axial test-tool-movement measurements. Permeability tests were performed after installing multipacker test tools in test boreholes, inflating the packers, and allowing pressures to build up in the isolated intervals. Pulse-withdrawal tests were performed after buildup pressures approached the apparent formation pore pressure. Pulse injections were sometimes performed to increase the fluid pressures in isolated intervals. Compliance tests were conducted in lengths of steel and stainless-steel casing to evaluate the mechanical performance of the multipacker test tools. The stainless-steel compliance-test chamber was installed with externally mounted thermocouples in a downward-angled borehole in Experimental Room 4. Compliance tests included leak tests and simulated pulse-injection and pulse-withdrawal sequences. 9 refs., 143 figs., 2 tabs

  4. The Brine Sampling and Evaluation Program (PSEP) at WIPP

    International Nuclear Information System (INIS)

    Deal, D.E.; Roggenthen, W.M.

    1989-01-01

    The Permian salt beds of the WIPP facility are virtually dry. The amount of water present in the rocks exposed in the excavations that is free to migrate under pressure gradients was estimated by heating salt samples to 95 degrees C and measuring weight loss. Clear balite contains about 0.22 weight percent water and the more argillaceous units average about 0.75 percent. Measurements made since 1984 as part of the Brine Sampling and Evaluation Program (BSEP) indicate that small amounts of this brine can migrate into the excavations and does accumulate in the underground environment. Brine seepage into drillholes monitored since thy were drilled show that brine seepage decreases with time and that many have dried up entirely. Weeping of brine from the walls of the repository excavations also decreases after two or more years. Chemical analyses of brines shows that they are sodium-chloride saturated and magnesium-rich

  5. Test plan: Potash Core Test. WIPP experimental program borehole plugging

    International Nuclear Information System (INIS)

    Christensen, C.L.

    1979-09-01

    The Potash Core Test will utilize a WIPP emplaced plug to obtain samples of an in-situ cured plug of known mix constituents for bench scale testing. An earlier effort involved recovery at the salt horizon of Plug 217, a 17 year old plug in a potash exploration hole for bond testing, but the lack of particulars in the emplacement precluded significant determination of plug performance

  6. The development of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) offers a perspective on the value of designing flexibility into a public affairs program to enable it to grow with and complement a project's evolution from construction through to operations. This paper discusses how the WIPP public affairs program progressed through several stages to its present scope. During the WIPP construction phase, the public affairs program laid a foundation for Project acceptance in the community. A speaker's bureau, a visitors program, and various community outreach and support programs emphasized the educational and socioeconomic benefits of having this controversial project in Carlsbad. Then, in this past year as the project entered a preoperational status, the public affairs program emphasis shifted to broaden the positive image that had been created locally. In this stage, the program promoted the project's positive elements with the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management and transportation program. Currently, an even broader, more aggressive public affairs program is planned. During this stage public affairs will be engaged in a comprehensive institutional and outreach program, explaining and supporting WIPP's mission in each of the communities and agencies affected by the operation of the country's first geologic repository

  7. WIPP Pecos Management Reports

    Science.gov (United States)

    These reviews and evaluations compiled by Pecos Management Services, Inc. encompass the current and future WIPP activities in the program areas of TRU waste characterization, transportation, and disposal.

  8. Construction quality assurance program plan for the WIPP project, Carlsbad, NM

    International Nuclear Information System (INIS)

    1987-05-01

    The purpose of this plan is to describe the Quality Assurance (QA) Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Major Project Participants: the Architect-Engineer (Bechtel), the Construction Manager (US Army Corps of Engineers), the Scientific Advisor (Sandia National Laboratory), and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the construction, including site evaluation, design, and turnover phases of WIPP. Other work in progress during the same period is controlled by DOE documents applicable to that work effort. The prime responsibility for ensuring the quality of construction rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Construction Manager, the Construction Contractors, the Management and Operating Contractor, and the Architect-Engineer. Inspection and burden of proof of acceptability rests with the Construction Contractor as defined by the technical provisions of the contract and as otherwise specified by the DOE WIPP Project Office on an individual work-package basis. To the maximum extent possible, acceptance of work will be based upon first-hand witnessing by the Construction Manager and other representatives of the DOE organization

  9. Joint state of Colorado-US Department of Energy WIPP Shipment Exercise Program: TRANSAX '90

    International Nuclear Information System (INIS)

    1990-01-01

    In July 1990, the United States Secretary of Energy requested the DOE conduct a transportation emergency exercise before the end of CY 1990. The tasking was subsequently directed to the Director of DOE's Office of Environmental Restoration and Waste Management (EM) to plan and conduct an exercise, based on a Waste Isolation Pilot Plant (WIPP) shipment scenario. The state of Colorado was asked to participate. Colorado, in turn, invited the DOE to integrate the exercise into its own series of WIPP-related tabletop and field exercises for which the state had already begun planning. The result was a joint USDOE/Colorado full-scale (orientation) exercise called Transportation Accident Exercise 1990 (TRANSAX '90). The state of Colorado's exercise program was a follow-on to previously conducted classroom training. The program would serve to identify and resolve outstanding issues concerning inspections of the WIPP shipment transporter as it entered and passed through the state on the designated Interstate 25 transportation corridor; criteria for movement under various adverse weather and road conditions; and emergency response to accidents occurring in an urban or rural environment. The USDOE designed its participation in the exercise program to test selected aspects of the DOE Emergency Management System relating to response to and management of DOE off-site transportation emergencies involving assistance to state and local emergency response personnel. While a number of issues remain under study for ultimate resolution, others have been resolved and will become the basis for emergency operations plans, SOPs, mutual aid agreements, and checklist upgrades. Concurrently, the concentrated efforts at local, state, and federal levels in dealing with WIPP- related activities during this exercise program development have given renewed impetus to all parties as the beginning of actual shipments draws nearer. Three tabletop scenarios are discussed in this report

  10. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  11. The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

    International Nuclear Information System (INIS)

    Patterson, Russ; Klein, Thomas; Van Luik, Abraham

    2013-01-01

    The Department of Energy/Carlsbad Field Office (DOE/CBFO) is responsible for managing all activities related to the disposal of TRU and TRU-mixed waste in the geologic repository, 650 m below the land surface, at WIPP, near Carlsbad, New Mexico. The main function of the Passive Institutional Controls (PIC's) program is to inform future generations of the long-lived radioactive wastes buried beneath their feet in the desert. For the first 100 years after cessation of disposal operations, the rooms are closed and the shafts leading underground sealed, WIPP is mandated by law to institute Active Institutional Controls (AIC's) with fences, gates, and armed guards on patrol. At this same time a plan must be in place of how to warn/inform the future, after the AIC's are gone, of the consequences of intrusion into the geologic repository disposal area. A plan was put into place during the 1990's with records management and storage, awareness triggers, permanent marker design concepts and testing schedules. This work included the thoughts of expert panels and individuals. The plan held up under peer review and met the requirements of the U.S. Environmental Protection Agency (EPA). Today the NEA is coordinating a study called the 'Preservation of Records, Knowledge and Memory (RK and M) Across Generations' to provide the international nuclear waste repository community with a guide on how a nuclear record archive programs should be approached and developed. CBFO is cooperating and participating in this project and will take what knowledge is gained and apply that to the WIPP program. At the same time CBFO is well aware that the EPA and others are expecting DOE to move forward with planning for the future WIPP PIC's program; so a plan will be in place in time for WIPP's closure slated for the early 2030's. The DOE/CBFO WIPP PIC's program in place today meets the regulatory criteria, but complete feasibility of implementation is questionable, and may not be in conformance

  12. Department of Energy Operation Quality Assurance Program for the Waste Isolation Pilot Plant (WIPP) Project (Carlsbad, New Mexico)

    International Nuclear Information System (INIS)

    1987-12-01

    The purpose of this plan is to describe the Quality Assurance (QA)reverse arrow Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Project Participants: the Scientific Advisor (Sandia National Laboratory) and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the Pre-Operational and Operational phases of the WIPP Project not addressed under the construction phase. This plan also requires the QA Programs for DOE and Project Participants to be structured so as to comply with this plan and ANSI-ASME NQA-1. The prime responsibility for Operational Quality Assurance rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Scientific Advisor and the Management and Operating Contractor. Overviews of selected operational and testing activities will be are conducted in accordance with prescribed requirements and that adequate documentation of these activities is maintained. 4 figs

  13. The evolution of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    As a first-of-a-kind facility, the Waste Isolation Pilot Plant (WIPP) presents a unique perspective on the value of designing a public affairs program that grown with and complements a project's evolution from construction to operations. Like the project itself, the public affairs programs progressed through several stages to its present scope. During the construction phase, foundations were laid in the community. Then, in this past year as the project entered a preoperational status, emphasis shifted to broaden the positive image that had been created locally. In this stage, public affairs presented the project's positive elements to the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management program. Most recently, and continuing until receipt of the first shipment of waste in October 1988, an even broader, more aggressive public affairs program is planned

  14. Waste Isolation Pilot Plant (WIPP) research and development program: in situ testing plan, March 1982

    International Nuclear Information System (INIS)

    Matalucci, R.V.; Christensen, C.L.; Hunter, T.O.; Molecke, M.A.; Munson, D.E.

    1982-12-01

    The WIPP in southeast New Mexico is being developed as an R and D facility to demonstrate the safe disposal of radioactive defense wastes in bedded salt. The tests are done first without radioactive materials and then with transuranic (TRU) waste and Defense High-Level Waste (DHLW). The thermal/structural itneraction experiments include (a) geomechanical evaluations of access drifts, vertical shafts, and isothermal TRU disposal rooms during the Site and Preliminary Validation Program, (b) tests that represent the reference DHLW room configuraton (5.5 m x 5.5 m) and areal thermal loading of 12 W/m 2 , (c) an overtest of the DHLW congfiguration heated to about four times the reference thermal loading; (d) geomechanical evaluations of various room widths up to 9.1 m, variable pillar widths, and a long-drift intersection, (e) an 11-m-dia axisymmetric heated pillar test, and (f) miscellaneous tests to determine stress field and clay seam sliding resistance. The plugging and sealing experiments include (a) salt permeability tests, (b) tests to determine effects of size and scale on behavior of plugs and to determine backfill material behavior and emplacement techniques, and (c) a plug test matrix to evaluate candidate sealing materials. Waste package interaction experiments include (a) simulated-waste package tests that use several design options and engineered barrier materials under reference and accelerated DHLW environments, (b) confirmatory brine migration tests, (c) TRU drum durability tests in dry and wet conditions, (d) options for radiation-source tests using cesium capsules, and (e) actual DHLW tests using up to 40 canisters for technical demonstrations and for addressing concerns of wasteform chemistry, leaching, and near-field radionuclide migration

  15. WIPP Project Records Management Handbook

    International Nuclear Information System (INIS)

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) Records Management Handbook provides the WIPP Project Records Management personnel with a tool to use to fulfill the requirements of the WIPP Records Program and direct their actions in the important area of records management. The handbook describes the various project areas involved in records management, and how they function. The handbook provides the requirements for Record Coordinators and Master Record Center (MRC) personnel to follow in the normal course of file management, records scheduling, records turnover, records disposition, and records retrieval. More importantly, the handbook provides a single reference which encompasses the procedures set fourth in DOE Order 1324.2A, ''Records Disposition'' ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities'' and DOE-AL 5700.6B, ''General Operations Quality Assurance.'' These documents dictate how an efficient system of records management will be achieved on the WIPP Project

  16. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    Energy Technology Data Exchange (ETDEWEB)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository.

  17. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    International Nuclear Information System (INIS)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository

  18. Successes and Experiences of the WIPP Project

    International Nuclear Information System (INIS)

    Chu, Margaret S.Y.; Weart, Wendell D.

    2000-01-01

    In May 1998, the US Environmental Agency (EPA) certified the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) as being in compliance with all of the applicable regulations governing the permanent disposal of spent nuclear fuel, high-level waste, and transuranic radioactive waste. The WIPP, a transuranic waste repository, is the first deep geologic repository in the US to have successfully demonstrated regulatory compliance with long-term radioactive waste disposal regulations and be certified to receive wastes. Many lessons were learned throughout the 25-year history of the WIPP--from site selection to the ultimate successful certification. The experiences and lessons learned from the WIPP may be of general interest to other repository programs in the world. The lessons learned include all facets of a repository program: programmatic, managerial, regulatory, technical, and social. This paper addresses critical issues that arose during the 25 years of WIPP history and how they influenced the program

  19. 2002 WIPP Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2002-09-30

    DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

  20. WIPP Hydrology Program Waste Isolation Pilot Plant southeastern New Mexico. Hydrologic data report No. 2

    International Nuclear Information System (INIS)

    1985-12-01

    This report contains basic hydrologic data for aquifer tests and water-level measurements conducted at the Waste Isolation Pilot Plant (WIPP) site over the period 1983 through November 1985. Part A summarizes data collected during a series of pumping and slug tests conducted during 1983 and 1984 in wells at the H-2 and H-9 hydropads, and in well H-12. Water-level data collected in 1983 and 1984 at the H-2 hydropads and Appendixes tabulate water-level, drawdown, millivolt, and pressure data collected with automated Data Acquisition Systems (DAS's) during the aquifer tests for both the test wells and the observation wells, and water-level data collected with electric water-level sounders. Part B is a detailed presentation of pumping tests conducted at the H-11 hydropad in May and June, 1985. Part B discusses the automated DAS, water-level measurement devices, the discharge measurement system, well and equipment configurations, and provides plots of pressure or water-level response in both the pumping and observation wells. Pressure data collected with the DAS, depth to water collected with the water-level sounders in observation wells, and measured pumping rate data are tabulated. Part C presents January through November, 1985 water-level data collected from wells in the observation-well network at and near the WIPP site. The types of devices utilized are discussed and the water-level plots obtained from the water-level data for the Magenta, the Culebra, the Rustler-Salado contact zone, the Bell Canyon Formation, and the Salado/Castile Formations are presented. Water levels are tabulated

  1. WIPP Hydrology Program: Waste Isolation Pilot Plant, southeastern New Mexico, Hydrologic Data Report No. 5: Parts, A-WIPP-13 multipad test; B-H-4c, P-17, ERDA-9, and Cabin Baby-1 slug tests; C-Engle and Carper well pumping tests; D-WIPP-12, H-14, and H-15 drill-stem tests; E-Water-level data

    International Nuclear Information System (INIS)

    Stensrud, W.A.; Bame, M.A.; Lantz, K.D.; LaVenue, A.M.; Palmer, J.B.; Saulnier, G.J. Jr.

    1987-01-01

    Part A of this report describes the objectives, scope, design, equipment, and methodology for a long-term pumping test conducted at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The test was conducted to provide technical assistance as part of the ongoing hydrologic characterization of the WIPP site. The test is referred to as the northern multipad pumping test, because it was designed to create a hydraulic stress over a wide area of the northern half of the WIPP site. The fluid-pressure and water-level recovery in both pumping and observation wells were monitored for a minimum of 72 days. The test interval was the Culebra Dolomite Member of the Rustler Formation. Twenty-three observation wells completed in the Culebra dolomite were monitored at least once a month as part of the regional water-level monitoring program. Severl wells completed in the Magenta Dolomite Member of the Rustler Formation were monitored during the test to assess the possibility of Magenta-Culebra communication in the expected area of influence of this test. The succeeding sections of this part of Hydrologic Data Report No. 5 present detailed descriptions of the test objectives, pretest data collection, test equipment and test-well configuration, the observation-well network, and test results. 3 refs., 147 figs., 107 tabs

  2. 40 CFR 147.2801 - EPA-administered program.

    Science.gov (United States)

    2010-07-01

    ... Section 147.2801 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Commonwealth of the... lands in the Commonwealth of the Northern Mariana Islands is administered by EPA. This program consists...

  3. 40 CFR 147.2851 - EPA-administered program.

    Science.gov (United States)

    2010-07-01

    ... Section 147.2851 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Trust Territory of the... the Pacific Islands, including all Indian lands, is administered by EPA. This program consists of the...

  4. 40 CFR 147.2850 - State-administered program. [Reserved

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administered program. 147.2850 Section 147.2850 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Trust Territory of the...

  5. WIPP 2004 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2005-09-30

    The mission of Waste Isolation Pilot Plant (WIPP) is to safely and permanently dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States (U.S.). In 2004, 8,839 cubic meters (m3) of TRU waste were emplaced at WIPP. From the first receipt of waste in March 1999 through the end of 2004, 25,809 m3 of TRU waste had been emplaced at WIPP. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of WIPP environmental resources. DOE Order 450.1, Environmental Protection Program; DOE Order 231.1A, Environment, Safety, and Health Reporting; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2004 Site Environmental Report (SER) summarizes environmental data from 2004 that characterize environmental management performance and demonstrate compliance with applicable federal and state regulations. This report was prepared in accordance with DOE Order 231.1A, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2004 (DOE, 2005). The order and the guidance require that DOE facilities submit an annual SER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) further requires that the SER be provided to the New Mexico Environment Department (NMED).

  6. 40 CFR 147.3000 - EPA-administered program.

    Science.gov (United States)

    2010-07-01

    ... Section 147.3000 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Lands of the Navajo... Utah. This program consists of the UIC program requirements of 40 CFR parts 124, 144, 146, 148, and...

  7. 40 CFR 147.1900 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Injection Control Program Legal Counsel's Statement,” October 1983, signed by the Assistant Attorney General... Section 147.1900 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Oregon § 147.1900...

  8. Instrumentation development for the Waste Isolation Pilot Plant (WIPP) borehole plugging program (BHP)

    International Nuclear Information System (INIS)

    Cook, C.W.

    1979-11-01

    This report discusses the instrumentation development needs of the borehole testing program as it now exists. Although requirements may change as the program progresses, the items indicated are basic to any borehole plugging program. Instrumentation is discussed both for the plug environment and for the plug itself. For the plug environment, a probe for measuring the disturbed region and a coordinate logging tool are required. For the plug itself, instrumentation includes measurements above, within, and below the plug. Instrumentation for most measurements above the plug is currently available; for measurements within and below the plug, however, further development is required. Specifically, resistivity, induction, and acoustic probes; an in situ stressmeter; and a hardwire, feedthrough system need to be developed

  9. 40 CFR 147.1100 - State-administered program.

    Science.gov (United States)

    2010-07-01

    .... (c) Statement of legal authority. “Underground Injection Control Program—Attorney General's Statement... Section 147.1100 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Massachusetts § 147...

  10. 40 CFR 147.1300 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Section 147.1300 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Missouri § 147.1300...) Opinion Letter No. 63 and attached Memorandum Opinion, signed by Attorney General of Missouri, March 16...

  11. 40 CFR 147.2500 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... State-administered program: (1) Chapter 144, Water, Sewage, Refuse, Mining and Air Pollution, Wisconsin... Section 147.2500 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS... Treatment Works, Wisconsin Administrative Code § 210.05 Natural Resources Board Order No. WQ-25-82, approved...

  12. Laboratory creep and mechanical tests on salt data report (1975-1996): Waste Isolation Pilot Plant (WIPP) thermal/structural interactions program

    Energy Technology Data Exchange (ETDEWEB)

    Mellegard, K.D. [RE/SPEC Inc., Rapid City, SD (United States); Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States)

    1997-02-01

    The Waste Isolation Pilot Plant (WIPP), a facility located in a bedded salt formation in Carlsbad, New Mexico, is being used by the U.S. Department of Energy to demonstrate the technology for safe handling and disposal of transuranic wastes produced by defense activities in the United States. In support of that demonstration, mechanical tests on salt were conducted in the laboratory to characterize material behavior at the stresses and temperatures expected for a nuclear waste repository. Many of those laboratory test programs have been carried out in the RE/SPEC Inc. rock mechanics laboratory in Rapid City, South Dakota; the first program being authorized in 1975 followed by additional testing programs that continue to the present. All of the WIPP laboratory data generated on salt at RE/SPEC Inc. over the last 20 years is presented in this data report. A variety of test procedures were used in performance of the work including quasi-static triaxial compression tests, constant stress (creep) tests, damage recovery tests, and multiaxial creep tests. The detailed data is presented in individual plots for each specimen tested. Typically, the controlled test conditions applied to each specimen are presented in a plot followed by additional plots of the measured specimen response. Extensive tables are included to summarize the tests that were performed. Both the tables and the plots contain cross-references to the technical reports where the data were originally reported. Also included are general descriptions of laboratory facilities, equipment, and procedures used to perform the work.

  13. Pretest characterization of WIPP experimental waste

    International Nuclear Information System (INIS)

    Johnson, J.; Davis, H.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, is an underground repository designed for the storage and disposal of transuranic (TRU) wastes from US Department of Energy (DOE) facilities across the country. The Performance Assessment (PA) studies for WIPP address compliance of the repository with applicable regulations, and include full-scale experiments to be performed at the WIPP site. These experiments are the bin-scale and alcove tests to be conducted by Sandia National Laboratories (SNL). Prior to conducting these experiments, the waste to be used in these tests needs to be characterized to provide data on the initial conditions for these experiments. This characterization is referred to as the Pretest Characterization of WIPP Experimental Waste, and is also expected to provide input to other programmatic efforts related to waste characterization. The purpose of this paper is to describe the pretest waste characterization activities currently in progress for the WIPP bin-scale waste, and to discuss the program plan and specific analytical protocols being developed for this characterization. The relationship between different programs and documents related to waste characterization efforts is also highlighted in this paper

  14. WIPP fire hazards and risk analysis

    International Nuclear Information System (INIS)

    1991-05-01

    The purpose of this analysis was to conduct a fire hazards risk analysis of the Transuranic (TRU) contact-handled waste receipt, emplacement, and disposal activities at the Waste Isolation Pilot Plant (WIPP). The technical bases and safety envelope for these operations are defined in the approved WIPP Final Safety Analysis Report (FSAR). Although the safety documentation for the initial phase of the Test Program, the dry bin scale tests, has not yet been approved by the Department of Energy (DOE), reviews of the draft to date, including those by the Advisory Committee on Nuclear Facility Safety (ACNFS), have concluded that the dry bin scale tests present no significant risks in excess of those estimated in the approved WIPP FSAR. It is the opinion of the authors and reviewers of this analysis, based on sound engineering judgment and knowledge of the WIPP operations, that a Fire Hazards and Risk Analysis specific to the dry bin scale test program is not warranted prior to first waste receipt. This conclusion is further supported by the risk analysis presented in this document which demonstrates the level of risk to WIPP operations posed by fire to be extremely low. 15 refs., 41 figs., 48 tabs

  15. The WIPP journey to waste receipt

    International Nuclear Information System (INIS)

    Barnes, G.J.; Whatley, M.E.

    1997-01-01

    In the early 1970s the federal government selected an area in southeastern New Mexico containing large underground salt beds as potentially suitable for radioactive waste disposal. An extensive site characterization program was initiated by the federal government. This site became the Waste Isolation Pilot Plant, better known as WIPP. It is now 1997, over two decades after the initial selection of the New Mexico site as a potential radioactive waste repository. Numerous scientific studies, construction activities, and environmental compliance documents have been completed. The US Department of Energy (DOE) has addressed all relevant issues regarding the safety of WIPP and its ability to isolate radioactive waste from the accessible environment. Throughout the last two decades up to the present time, DOE has negotiated through a political, regulatory, and legal maze with regard to WIPP. New regulations have been issued, litigation initiated, and public involvement brought to the forefront of the DOE decision-making process. All of these factors combined to bring WIPP to its present status--at the final stages of working through the licensing requirements for receipt of transuranic (TRU) waste for disposal. Throughout its history, the DOE has stayed true to Congress' mandates regarding WIPP. Steps taken have been necessary to demonstrate to Congress, the State of New Mexico, and the public in general, that the nation's first radioactive waste repository will be safe and environmentally sound. DOE's compliance demonstrations are presently under consideration by the cognizant regulatory agencies and DOE is closer than ever to waste receipt. This paper explores the DOE's journey towards implementing a permanent disposal solution for defense-related TRU waste, including major Congressional mandates and other factors that contributed to program changes regarding the WIPP project

  16. WIPP Repository Reconfiguration

    Science.gov (United States)

    On August 30, 2011, the U.S. Department of Energy (DOE) provided a proposed planned change request that will relocate Panels 9 and 10 from the main north-south access drifts to south of the existing Panels 4 and 5 in the WIPP repository.

  17. Geotechnical Perspectives on the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Francke, Chris T.; Hansen, Frank D.; Knowles, M. Kathyn; Patchet, Stanley J.; Rempe, Norbert T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first nuclear waste repository certified by the United States Environmental Protection Agency. Success in regulatory compliance resulted from an excellent natural setting for such a repository, a facility with multiple, redundant safety systems, and from a rigorous, transparent scientific and technical evaluation. The WIPP story, which has evolved over the past 25 years, has generated a library of publications and analyses. Details of the multifaceted program are contained in the cited references. Selected geotechnical highlights prove the eminent suitability of the WIPP to serve its congressionally mandated purpose

  18. WIPP Gas-Generation Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Frank S. Felicione; Steven M. Frank; Dennis D. Keiser

    2007-05-01

    An experimental investigation was conducted for gas generation in contact-handled transuranic (CH TRU) wastes subjected for several years to conditions similar to those expected to occur at the Waste Isolation Pilot Plant (WIPP) should the repository eventually become inundated with brine. Various types of actual CH TRU wastes were placed into 12 corrosion-resistant vessels. The vessels were loosely filled with the wastes, which were submerged in synthetic brine having the same chemical composition as that in the WIPP vicinity. The vessels were also inoculated with microbes found in the Salado Formation at WIPP. The vessels were sealed, purged, and the approximately 750 ml headspace in each vessel was pressurized with nitrogen gas to approximately 146 atmospheres to create anoxic conditions at the lithostatic pressure estimated in the repository were it to be inundated. The temperature was maintained at the expected 30°C. The test program objective was to measure the quantities and species of gases generated by metal corrosion, radiolysis, and microbial activity. These data will assist in the specification of the rates at which gases are produced under inundated repository conditions for use in the WIPP Performance Assessment computer models. These experiments were very carefully designed, constructed, instrumented, and performed. Approximately 6 1/2 years of continuous, undisturbed testing were accumulated. Several of the vessels showed significantly elevated levels of generated gases, virtually all of which was hydrogen. Up to 4.2% hydrogen, by volume, was measured. Only small quantities of other gases, principally carbon dioxide, were detected. Gas generation was found to depend strongly on the waste composition. The maximum hydrogen generation occurred in vessels containing carbon steel. Visual examination of carbon-steel coupons confirmed the correspondence between the extent of observable corrosion and hydrogen generation. Average corrosion penetration rates

  19. Environmental monitoring and cooperative resource management at the WIPP site

    International Nuclear Information System (INIS)

    1992-01-01

    This poster session by the Environmental Monitoring Section of the US DOE Waste Isolation Pilot Plant is to demonstrate that the DOE is committed to sound environmental management. This WIPP poster session demonstrates radiological as well as nonradiological environmental monitoring activities conducted routinely at the WIPP. And how data collected prior to the WIPP being operational is used to establish a preoperational baseline for environmental studies in which the samples collected during the operational phase will be compared. Cooperative Resource Management is a relatively new concept for governments agencies. It allows two or more agencies the ability to jointly share in funding a program or project and yet both agencies can benefit from the outcome. These programs are usually a biological type study. The WIPP cooperative agreement between the US BLM, DOE and its contractors is to continue the ongoing documentation of the diversity of the Chihuahuan desert

  20. 25 CFR 26.4 - Who administers the Job Placement and Training Program?

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Who administers the Job Placement and Training Program... PLACEMENT AND TRAINING PROGRAM General Applicability § 26.4 Who administers the Job Placement and Training Program? The Job Placement and Training Program is administered by the Bureau of Indian Affairs or a...

  1. Test Plan: WIPP bin-scale CH TRU waste tests

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1990-08-01

    This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs

  2. WIPP startup: Overcoming unprecedented challenges

    International Nuclear Information System (INIS)

    Hunt, Arlen E.

    1992-01-01

    Since its authorization by the U.S. Congress in Public Law 96-164, the Waste Isolation Pilot Plant Program has achieved significant progress. Subsequent to a Record of Decision based on the October 1980 Final Environmental Impact Statement (FEIS), the scientific and engineering challenge of constructing a 100-acre mined repository to demonstrate the safe and environmentally sound disposal of defense program generated transuranic waste became reality. Since initial conception, however, a complex program has evolved. Demonstration of compliance with the requirements of the Resource Conservation and Recovery Act (RCRA) and Environmental Protection Agency (EPA) disposal Standards defined in 10 CFR 191, Subpart B (yet to be repromulgated), became prerequisites to a disposal decision. On June 13, 1990, based on a supplement to the 1980 FEIS, the decision was made to redefine the program to include a formal test phase. This decision required an addendum to the Final Safety Analysis Report to assure commitment to safety considerations, an intensive operational readiness review effort, and the need for a No-Migration Determination for the Environmental Protection Agency. In addition to meeting the technical challenges, the need to satisfy a broad spectrum of oversight groups (some directly funded by the Department of Energy) was required. With the decision making process publicly displayed on the Secretary of Energy's Decision Plan, the unprecedented challenges of the WIPP Program were painstakingly met, one by one, in an accountable and visible manner. (author)

  3. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

  4. Sandia WIPP calibration traceability

    Energy Technology Data Exchange (ETDEWEB)

    Schuhen, M.D. [Sandia National Labs., Albuquerque, NM (United States); Dean, T.A. [RE/SPEC, Inc., Albuquerque, NM (United States)

    1996-05-01

    This report summarizes the work performed to establish calibration traceability for the instrumentation used by Sandia National Laboratories at the Waste Isolation Pilot Plant (WIPP) during testing from 1980-1985. Identifying the calibration traceability is an important part of establishing a pedigree for the data and is part of the qualification of existing data. In general, the requirement states that the calibration of Measuring and Test equipment must have a valid relationship to nationally recognized standards or the basis for the calibration must be documented. Sandia recognized that just establishing calibration traceability would not necessarily mean that all QA requirements were met during the certification of test instrumentation. To address this concern, the assessment was expanded to include various activities.

  5. 40 CFR 147.1700 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ...) Statement of legal authority. (1) Underground Injection Control Program, Attorney General's Statement (June 15, 1982); (2) Amendment to Underground Injection Control Program, Attorney General's Statement... Section 147.1700 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS...

  6. 40 CFR 282.50 - Alabama State-Administered Program.

    Science.gov (United States)

    2010-07-01

    ... financial responsibility for hazardous substance underground storage tank systems. (2) Statement of legal... administered by the Alabama Department of Environmental Management, was approved by EPA pursuant to 42 U.S.C... obtained from the Ground Water Branch, Alabama Department of Environmental Management, 1751 W.L. Dickinson...

  7. 40 CFR 147.1500 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Administrator, EPA Region I, “Re: Attorney General's Statement—Underground Injection Control Program,” March 23...: Attorney General's Statement—Underground Injection Control Program,” July 1, 1982. (d) The Program... Section 147.1500 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS...

  8. 40 CFR 272.1601 - New Mexico State-Administered Program: Final Authorization.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false New Mexico State-Administered Program... (CONTINUED) SOLID WASTES (CONTINUED) APPROVED STATE HAZARDOUS WASTE MANAGEMENT PROGRAMS New Mexico § 272.1601 New Mexico State-Administered Program: Final Authorization. (a) Pursuant to section 3006(b) of RCRA...

  9. 40 CFR 147.950 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Attorney General of Louisiana to EPA, “Re: Louisiana Underground Injection Control Program Authorization... Attorney General of Louisiana to EPA, “Re: Louisiana Underground Injection Control Program Authorization... Section 147.950 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS...

  10. A screening program for dancers administered by dancers.

    Science.gov (United States)

    Wilson, Margaret; Deckert, Jennifer L

    2009-01-01

    Students enrolled in a dance kinesiology class were trained to administer a screening protocol on younger dancers in the same department. The dance kinesiology students gained experience assessing alignment and functional symmetry in their peers, and then recommended exercises for gaining awareness and developing balanced patterns of movement. This "low stakes" assessment created both dialogue and peer support centered on helping the screened dancers understand and effectively work with their individual capacities and limitations. The project was designed to contribute to a culture of wellness and education within the dance department.

  11. 40 CFR 147.550 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Resources, Environmental Protection Division, Water Quality Control, GA. COMP. R. & REGS. Chapter 391-3-6... Injection Control Program, Attorney General's Statement, February 4, 1982; (3) Amended Attorney General's... Section 147.550 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS...

  12. 40 CFR 147.2600 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Environmental Protection Agency, Underground Injection Control Regulations, Chapters 1-9, as revised by... Administrator, Region IX, “Re: Attorney General's Statement for Underground Injection Control Program (UIC... Section 147.2600 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS...

  13. The Waste Isolation Pilot Plant (WIPP) integrated project management system

    International Nuclear Information System (INIS)

    Olona, D.; Sala, D.

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission of demonstrating the safe disposal of transuranic (TRU) radioactive wastes. This unique project was authorized by Congress in 1979 in response to the national need for long-term, safe methods for disposing of radioactive by-products from our national defense programs. The WIPP was originally established in December of 1979, by Public Law 96-164, DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980. Since the inception of the WIPP Project, work has continued to prepare the facility to receive TRU wastes. Studies continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, environmental regulations, and DOE Orders. The objectives of implementing an integrated project management system are to assure compliance with all regulatory and federal regulations, identify areas of concern, provide justification for funding, provide a management tool for control of program workscope, and establish a project baseline from which accountability and performance will be assessed. Program management and project controls are essential for the success of the WIPP Project. The WIPP has developed an integrated project management system to establish the process for the control of the program which has an expected total dollar value of $2B over the ten-year period from 1990-2000. The implementation of this project management system was motivated by the regulatory requirements of the project, the highly public environment in which the project takes place, limited funding and resources, and the dynamic nature of the project. Specific areas to be addressed in this paper include strategic planning, project organization, planning and scheduling, fiscal planning, and project monitoring and reporting

  14. WIPP - Pre-Licensing and Operations: Developer and Regulator Perspectives

    International Nuclear Information System (INIS)

    Peake, Tom; Patterson, R.

    2014-01-01

    The Waste Isolation Pilot Plant (WIPP) is a disposal system for defense-related transuranic (TRU) radioactive waste. Developed by the Department of Energy (DOE), WIPP is located in Southeastern New Mexico: radioactive waste is disposed of 2,150 feet underground in an ancient layer of salt with a total capacity of 6.2 million cubic feet of waste. Congress authorized the development and construction of WIPP in 1980 for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States. This paper makes a historical review of the site development, site operations (waste disposal operations started in 1999), communications between US EPA and DOE, the chronology of pre-licensing and pre-operations, the operational phase and the regulatory challenges, and the lessons learned after 12 years of operations

  15. 40 CFR 147.2050 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Health and Environmental Control, approved by EPA pursuant to section 1422 of the SDWA. Notice of this... Department of Health and Environmental Control, Ground-Water Protection Division, Underground Injection...) “Underground Injection Control Program, Attorney General's Statement for Class I, II, III, IV and VA and VB...

  16. Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP`s environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence.

  17. Optimization of waste operations at WIPP

    International Nuclear Information System (INIS)

    Halverson, T.W.; Cole, L.T.

    1986-01-01

    The Waste Isolation Plant (WIPP) will receive nuclear waste in late 1988. The unique material-handling of contact- and remote-handled transuranic waste containers has resulted in handling systems with unique features and complications. Optimum waste handling at WIPP requires cooperation and design considerations at the waste generator site, the transportation system, and at WIPP. This cooperation reduces costs for all three parties. Best WIPP handling considerations require (1) maximizing transuranic package transporter (TRUPACT) payload, (2) minimizing operational steps, (3) minimizing lifting operations (slide loads instead of lifting), and (4) automating processes where practical. Conclusions and recommendations reached for WIPP operations are presented

  18. Science to compliance: The WIPP success story

    International Nuclear Information System (INIS)

    Howarth, S.M.; Chu, M.S.; Shephard, L.E.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed to provide in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. The success of the program, however, is defined by the regulator in the context of compliance with performance criteria, rather than by the in-depth technical understanding typical of most scientific programs. The WIPP project was successful in making a transformation from science to compliance by refocusing and redirecting programmatic efforts toward the singular goal of meeting regulatory compliance requirements while accelerating the submittal of the Compliance Certification Application (CCA) by two months from the April 1994 Disposal Decision Plan (DDP) date of December 1996, and by reducing projected characterization costs by more than 40%. This experience is unparalleled within the radioactive waste management community and has contributed to numerous lessons learned from which the entire community can benefit

  19. 40 CFR 147.2100 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... authority. (1) “Underground Injection Control Program for Class II Wells: Attorney General's Statement... wells. 147.2100 Section 147.2100 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...

  20. 40 CFR 147.1750 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ...) Statement of legal authority. “Underground Injection Control Program Attorney General's Statement,” as... wells. 147.1750 Section 147.1750 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...

  1. 40 CFR 147.1400 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... 23, 1982; (2) “Re: Nebraska Underground Injection Control Program, Addendum to Attorney General's... wells. 147.1400 Section 147.1400 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...

  2. WIPP: why are we waiting?

    International Nuclear Information System (INIS)

    Barker, K.

    1991-01-01

    Rooms cut into salt almost half a mile below the state of New Mexico could become the United States' first underground repository for defence generated transuranic waste. The Department of Energy (DoE) was hoping to ship the first waste to the Waste Isolation Pilot Plant (WIPP) this August, but the $800 million project has faced bureaucratic delays and a definite date has yet to be set. The state of New Mexico established the Environmental Evaluation Group (EEG) to perform an independent technical evaluation of the project with respect to potential radiation exposure for people or environmental degradation in the area around the WIPP site. The Waste Isolation Pilot Plant has two objectives: to perform scientific investigations into the behaviour of salt rock and its interactions with transuranic and mixed waste under a variety of conditions; and to demonstrate that transuranic waste can be safely handled, transported and stored in a geologic repository. The EEG is unhappy about proposed in-repository tests to assess the long term performance of WIPP. (author)

  3. WIPP/SRL in-situ tests

    International Nuclear Information System (INIS)

    Mamsey, W.G.

    1990-01-01

    The Materials Interface Interactions Test (MIIT) is the only in-situ program involving the burial of simulated high-level waste forms operating in the United States. Fifteen glass and waste form compositions and their proposed package materials, supplied by 7 countries, are interred in salt at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. A joint effort between Sandia National Laboratories and Savannah River Laboratory, MIIT is the largest international cooperative in-situ venture yet undertaken. The objective of the current study is to document the waste form compositions used in the MIIT program and then to examine compositional correlations based on structural considerations, bonding energies, and surface layer formation. These correlations show important similarities between the many different waste glass compositions studied world wide and suggest that these glasses would be expected to perform well and in a similar manner

  4. 40 CFR 147.100 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... wells. 147.100 Section 147.100 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...) Statement of Legal Authority. Statement from the Attorney General of the State of Alaska, signed by the...

  5. 40 CFR 147.2251 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... wells. 147.2251 Section 147.2251 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS...,” “Statement of Legal Authority,” and “Certification by the Attorney General,” by Assistant Attorney General...

  6. 40 CFR 147.250 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... wells. 147.250 Section 147.250 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS... Deputy Attorney General to the Administrator of EPA, “Re: Legal Authority of California Division of Oil...

  7. 40 CFR 147.1600 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... wells. 147.1600 Section 147.1600 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS... Division, New Mexico Energy and Minerals Department, and Assistant Attorney General of New Mexico, to...

  8. 40 CFR 147.1251 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... wells. 147.1251 Section 147.1251 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS... Regional Administrator on October 31, 1988. (c) Statement of legal authority. Statement from the Attorney...

  9. 78 FR 23777 - Notice of Proposed Information Collection: Comment Request: HUD-Administered Small Cities Program...

    Science.gov (United States)

    2013-04-22

    ... Information Collection: Comment Request: HUD- Administered Small Cities Program Performance Assessment Report... program provides HUD with financial and physical development status of each activity funded. These reports[email protected] fax: 202-395-5806. FOR FURTHER INFORMATION CONTACT: Colette Pollard, Reports...

  10. Operations program plan: Revision 3

    International Nuclear Information System (INIS)

    1988-07-01

    This document, the Operations Program Plan (OPP), has been developed as the seven-year master plan for operation of WIPP. The OPP was authorized by the Albuquerque Field Office of the Department of Energy (DOE-AL) and that organization's WIPP Project Office (DOE-WPO) in Carlsbad, New Mexico. The OPP is the directive from the DOE-WPO Project Manager as to how the WIPP is to be managed, operated, and administered. As the top tier management document for WIPP, the OPP establishes organizational responsibilities and an organizational structure for the Waste Isolation Division (WID) of Westinghouse Electric Corporation. The OPP sets policy and tone for conducting WIPP operations; it requires and specifically authorizes implementing documents (e.g., manuals). It has also proven instrumental in the budgeting and planning process, most particularly in expediting the preparation of specific budgets and detailed schedules for each of the numerous work packages. The OPP is also used to communicate information about WIPP operations

  11. Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992

    International Nuclear Information System (INIS)

    Francis, A.J.; Gillow, J.B.

    1993-09-01

    Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term ( 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation

  12. Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    1993-07-01

    This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP's environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence

  13. 40 CFR 147.52 - State-administered program-Hydraulic Fracturing of Coal Beds.

    Science.gov (United States)

    2010-07-01

    ... R. Craig Kneisel, Chief, Environmental Division, Office of the Attorney General, dated October 8... Fracturing of Coal Beds. 147.52 Section 147.52 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL...

  14. 40 CFR 147.1401 - State administered program-Class I, III, IV and V wells.

    Science.gov (United States)

    2010-07-01

    ... of Environmental Control, August 7, 1981; (3) Letter from Attorney General (of Nebraska), by Assistant Attorney General, to Director, (Nebraska) Department of Environmental Control, April 29, 1982; (4... program administered by the Nebraska Department of Environmental Control, approved by EPA pursuant to...

  15. 41 CFR 302-14.100 - How should we administer our home marketing incentive payment program?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 4 2010-07-01 2010-07-01 false How should we administer our home marketing incentive payment program? 302-14.100 Section 302-14.100 Public Contracts and Property Management Federal Travel Regulation System RELOCATION ALLOWANCES RESIDENCE TRANSACTION ALLOWANCES...

  16. New Mexico Environmental Evaluation Group - experience in reviewing WIPP

    International Nuclear Information System (INIS)

    Neill, R.H.

    1983-01-01

    The purpose of the New Mexico Environmental Evaluation Group is to conduct an independent evaluation of the potential radiation exposure to people from WIPP--a radioactive waste facility intended to permanently dispose transuranic radioactive waste generated from the nation's nuclear weapons program. The concept of a State review of a proposed radioactive waste facility has been endorsed by both Federal and State legislative and executive agencies, and the experiences and interactions of the past four years to solve problems of this first-of-a-kind radioactive waste facility has led to many innovations in conflict resolution. The multidisciplinary Group's position is neither pro nor anti-WIPP and results are published and given broad dissemination to insure technical and public scrutiny of its work

  17. WIPP Compliance Certification Application calculations parameters. Part 2: Parameter documentation

    International Nuclear Information System (INIS)

    Howarth, S.M.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed, which provided in depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. Nearly 1,500 parameters were developed using information gathered from this program and were input to numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations. The CCA probability models require input parameters that are defined by a statistical distribution. Developing parameters begins with the assignment of an appropriate distribution type, which is dependent on the type, magnitude, and volume of data or information available. Parameter development may require interpretation or statistical analysis of raw data, combining raw data with literature values, scaling laboratory or field data to fit code grid mesh sizes, or other transformations. Documentation of parameter development is designed to answer two questions: What source information was used to develop this parameter? and Why was this particular data set/information used? Therefore, complete documentation requires integrating information from code sponsors, parameter task leaders, performance assessment analysts, and experimental principal investigators. This paper, Part 2 of 2 parts, contains a discussion of the WIPP CCA PA Parameter Tracking System, document traceability and retrievability, and lessons learned from related audits and reviews

  18. A comprehensive assessment program to improve blood-administering practices using the FOCUS-PDCA model.

    Science.gov (United States)

    Saxena, Sunita; Ramer, Lois; Shulman, Ira A

    2004-09-01

    The Joint Commission on the Accreditation of Healthcare Organizations requires that hospitals have a planned approach to systematically collect data on processes related to the use, ordering, and administering of blood components. This study describes how a comprehensive blood-administering assessment program and the FOCUS-PDCA approach improved overall blood-administering practices. Nurses were trained to observe blood issuance, blood administering, and patient monitoring steps, and to audit patient's charts to measure compliance with blood-ordering procedures. The observations were recorded on a standardized scannable form, which allowed automatic entry of recorded data directly into a computer database. A total of 982 assessments were completed during the 51-month study period. Documentation of informed consent improved from 80 percent to 100 percent. Compliance with a California law that requires patients to receive information on the risks, benefits, and alternatives to transfusion rose from 30 percent to 100 percent. Physicians' compliance in specifying the rate of blood administration improved from 30 percent to 100 percent, and verification of information on the patient's identification band with the patient's self-identification rose from 50 percent to 100 percent. For all other blood-administering steps, compliance remained high throughout the study period. For the past 9 months, 100-percent compliance has been maintained for all transfusion processes, and during this period no mistransfusions or blood administration near-misses have been reported. The blood-administering assessment program described above has improved transfusion practice, reduced the number of near-miss events, and may have prevented mistransfusions.

  19. Logistical and fiscal sustainability of a school-based, pharmacist-administered influenza vaccination program.

    Science.gov (United States)

    Fontanesi, John; Jue-Leong, Sierra

    2012-01-01

    To assess the fiscal and logistical viability of school-based, pharmacist-administered influenza vaccination programs. Econometric observational study. Nine schools in the Rincon Unified School District, Santa Rosa, CA. Safeway Pharmacies; Rincon Unified School District; California Department of Public Health, Immunization Branch; and University of California, San Diego. Assessment of direct workflow observations and administrative data. Unit costs, productivity, and effectiveness of school-based, pharmacist-administered influenza vaccination programs. The results showed a unit cost of $23.63 (compared with $25.60 for mass vaccination and $39.79 for walk-in shot-only vaccination clinics). The productivity index ($0.88) and efficiency index ($1.12) were better compared with data reported for comparable vaccination programs. School-based, pharmacist-administered vaccination programs are fiscally and logistically self-sustaining, viable alternatives to medical office-based or community-based mass vaccination clinics, and may offer a practical strategy for vaccinating children and adolescents.

  20. WIPP performance assessment: impacts of human intrusion

    International Nuclear Information System (INIS)

    Anderson, D.R.; Hunter, R.L.; Bertram-Howery, S.G.; Lappin, A.R.

    1989-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is a research and development facility that may become the USA's first and only mined geologic repository for transuranic waste. Human intrusion into the WIPP repository after closure has been shown by preliminary sensitivity analyses and calculations of consequences to be an important, and perhaps the most important, factor in long-term repository performance

  1. The cosmic ray muon flux at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Esch, E.-I. [Los Alamos National Laboratory, LANSCE-3, MS H855, Los Alamos, NM 87545 (United States) and II. Physikalisches Institut, Justus Liebig Univeritaet Giessen, Giessen (Germany)]. E-mail: ernst@lanl.gov; Bowles, T.J [Los Alamos National Laboratory, LANSCE-3, MS H855, Los Alamos, NM 87545 (United States); Hime, A. [Los Alamos National Laboratory, LANSCE-3, MS H855, Los Alamos, NM 87545 (United States); Pichlmaier, A. [Los Alamos National Laboratory, LANSCE-3, MS H855, Los Alamos, NM 87545 (United States); Reifarth, R. [Los Alamos National Laboratory, LANSCE-3, MS H855, Los Alamos, NM 87545 (United States); Wollnik, H. [II. Physikalisches Institut, Justus Liebig Univeritaet Giessen, Giessen (Germany)

    2005-02-11

    In this work, a measurement of the muon intensity at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM, USA is presented. WIPP is a salt mine with a depth of 655m. The vertical muon flux was measured with a two panel scintillator coincidence setup to {phi}{sub vert}=(3.10{sub -0.07}{sup +0.05})10{sup -7}s{sup -1}cm{sup -}2sr{sup -1}.

  2. WIPP: a perspective from ten years of operating success - 16189

    International Nuclear Information System (INIS)

    Gregory, Phillip C.

    2009-01-01

    The Waste Isolation Pilot Plant (WIPP), located 35 miles east of Carlsbad, New Mexico, USA is the first and, to the author's knowledge, only facility in the world for the permanent disposal of defense related transuranic (TRU) waste. Soon after plutonium was first synthesized in 1940 by a team of scientists at the University of California Berkeley Laboratory, the need to find a permanent repository for plutonium contaminated waste was recognized due to the more than 24,000 year half-life of Plutonium-239 ( 239 Pu). In 1957 the National Academy of Sciences published a report recommending deep geological burial in bedded salt as a possible solution. However, more than 50 years passed before the solution was achieved when in 1999 WIPP received the first shipment of TRU waste from Los Alamos National Laboratory. Ten years later, more than 7,600 shipments of TRU waste have been disposed of in rooms mined in an ancient salt bed more than 2,000 feet underground. This paper provides a brief history of WIPP with an overview of the technical, regulatory, and political hurdles that had to be overcome before the idea of a permanent disposal facility became reality. The paper focuses primarily on the safe, uneventful transportation program that has moved 100,000- plus containers of TRU waste from various U.S. Department of Energy (DOE) generator and/or storage sites across the Unites States to southeastern New Mexico. (author)

  3. Actinide Solubility and Speciation in the WIPP [PowerPoint

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Donald T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-11-02

    The presentation begins with the role and need for nuclear repositories (overall concept, international updates (Sweden, Finland, France, China), US approach and current status), then moves on to the WIPP TRU repository concept (design, current status--safety incidents of February 5 and 14, 2014, path forward), and finally considers the WIPP safety case: dissolved actinide concentrations (overall approach, oxidation state distribution and redox control, solubility of actinides, colloidal contribution and microbial effects). The following conclusions are set forth: (1) International programs are moving forward, but at a very slow and somewhat sporadic pace. (2) In the United States, the Salt repository concept, from the perspective of the long-term safety case, remains a viable option for nuclear waste management despite the current operational issues/concerns. (3) Current model/PA prediction (WIPP example) are built on redundant conservatisms. These conservatisms are being addressed in the ongoing and future research to fill existing data gaps--redox control of plutonium by Fe(0, II), thorium (analog) solubility studies in simulated brine, contribution of intrinsic and biocolloids to the mobile concentration, and clarification of microbial ecology and effects.

  4. Preliminary identification of interfaces for certification and transfer of TRU waste to WIPP

    International Nuclear Information System (INIS)

    Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.

    1982-02-01

    This study complements the national program to certify that newly generated and stored, unclassified defense transuranic (TRU) wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The objectives of this study were to identify (1) the existing organizational structure at each of the major waste-generating and shipping sites and (2) the necessary interfaces between the waste shippers and WIPP. The interface investigations considered existing waste management organizations at the shipping sites and the proposed WIPP organization. An effort was made to identify the potential waste-certifying authorities and the lines of communication within these organizations. The long-range goal of this effort is to develop practicable interfaces between waste shippers and WIPP to enable the continued generation, interim storage, and eventual shipment of certified TRU wastes to WIPP. Some specific needs identified in this study include: organizational responsibility for certification procedures and quality assurance (QA) program; simple QA procedures; and specification and standardization of reporting forms and procedures, waste containers, and container labeling, color coding, and code location

  5. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2000-02-25

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA

  6. WIPP Facility Work Plan for Solid Waste Management Units

    International Nuclear Information System (INIS)

    2000-01-01

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A

  7. Preliminary safety assessment of the WIPP facility

    International Nuclear Information System (INIS)

    Balestri, R.J.; Torres, B.W.; Pahwa, S.B.; Brannen, J.P.

    1979-01-01

    The efforts to perform a safety assessment of the WIPP facility being proposed for southeastern New Mexico are summarized. This preliminary safety assessment of the WIPP facility is limited to a consequence assessment in terms of the dose to a maximally exposed individual as a result of introducing the radionuclides into the biosphere. No attempt has been made to extend the consequences to population dose or to weight the dose with probability of the events. The general methodology, geosphere transport, and biosphere transport are described. The consequences of the various models developed to represent the loss of containment are summarized

  8. Modification of the ventilation system at Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Sethi, S.C.

    1987-01-01

    The WIPP (Waste Isolation Pilot Plant) Project near Carlsbad, New Mexico, is a research and development project sponsored by the US Department of Energy, designed to demonstrate the safe disposal of radioactive waste. A mine (repository) is being developed 2,150 feet below the surface in a thick salt bed, which will serve as the disposal medium. The underground ventilation system for the WIPP project was originally designed based on a fixed project scope. The design criteria and ventilation requirements were developed for the performance of various activities as then envisioned towards the achievement of this goal. However, in light of new information and actual site-specific experience at WIPP leading to a clearer definition of the scope-related programs and activities, it was realized that the existing ventilation system may need to be modified

  9. Salt impact studies at WIPP effects of surface storage of salt on microbial activity

    International Nuclear Information System (INIS)

    Rodriguez, A.L.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) currently under construction in southeastern New Mexico is a research and development facility to demonstrate the safe disposal of transuranic waste in a deep geological formation (bedded salt). The Ecological Monitoring Program at WIPP is designed to detect and measure changes in the local ecosystem which may be the result of WIPP construction activities. The primary factor which may affect the system prior to waste emplacement is windblown salt from discrete stockpiles. Both vegetation and soil microbial processes should reflect changes in soil chemistry due to salt importation. Control and experimental (potentially affected) plots have been established at the site, and several parameters are measured quarterly in each plot as part of the soil microbial sampling subprogram. This subprogram was designed to monitor a portion of the biological community which can be affected by changes in the chemical properties at the soil surface

  10. Brief Video-Module Administered Mindfulness Program for Physicians: A Pilot Study.

    Science.gov (United States)

    Pflugeisen, Bethann Mangel; Drummond, Dike; Ebersole, Drew; Mundell, Kate; Chen, David

    2016-01-01

    The purpose of this study was to evaluate the feasibility of implementing a video-module-based mindfulness pilot program intended to reduce stress, improve well-being, and develop mindfulness skills in physicians in a community hospital setting. Preliminary findings are presented. Using a single-sample, pre-post study design, we administered an eight-week mindfulness training offered as part of a wellness initiative for medical staff in a suburban community hospital. Participants enrolled on a first-come, first-served basis. Participants engaged in three 90-min in-person trainings, weekly online video-module trainings, and weekly teleconference coaching calls. Video-module trainings were available at all times, to be accessed at the participants׳ convenience. Journals and a guided meditation audio library were also provided. Physician stress, well-being (emotional exhaustion, depersonalization of patients, and sense of personal accomplishment), and mindfulness skills (observing, describing, acting with awareness, and accepting without judgment) were evaluated at baseline, end-of-program, and eight weeks post-intervention using well-validated instruments. A total of 23 physicians enrolled and 19 completed the program. Compared to baseline, statistically significant decreases in stress, personal accomplishment, and emotional exhaustion were observed at end-of-program and eight weeks post-intervention (all P mindfulness skills were observed at end-of-program; these increases persisted for describing, acting with awareness, and accepting without judgment at eight weeks post-intervention (all P mindfulness program can decrease stress, increase well-being, and develop lasting mindfulness skills in physicians. Copyright © 2016 Elsevier Inc. All rights reserved.

  11. Hanford to WIPP - What a Trip: The Road from Hanford is now Open

    International Nuclear Information System (INIS)

    FRENCH, M.S.

    2001-01-01

    The road leading from Hanford's Waste Receiving and Processing (WRAP) Facility to the Waste Isolation Pilot Plant (WJPP) in New Mexico developed a few bumps and detours over the past year, but it has now been successfully traversed. There were challenges obtaining Carlsbad Area Office and New Mexico Department of Ecology certification of the Hanford characterization program. After months of work, when initial certification appeared imminent, the issuance of the WIPP Hazardous Waste Permit changed the Waste Analysis Plan (WAP) required for characterizing waste for acceptance at WIPP. After a ceremony dedicating the ''Washington'' room at WIPP, the inaugural shipment from WRAP to WIPP was scheduled for June 2000. This first shipment was planned based on shipping a number of containers that had been characterized before the issuance of the WIPP Mixed Waste Permit. However, the New Mexico Department of Ecology initially declined to accept the characterization data generated before the permit was issued, necessitating revision to the planned shipment. Because of the difficulties inherent in scheduling the TRUPACT-II transport and coordination with all of the states through which the shipment would pass, it was decided to proceed with the first shipment in early July with only the drums that had been characterized after Hanford compliance with the new WIPP WAP requirements had been certified. Following the initial shipment, previously certified containers were recertified using a process approved through negotiation with the New Mexico Environment Department, and additional full shipments have been successfully completed. This paper will present an overview of the challenges overcome and lessons learned in obtaining certification, coordination with the involved states, and eventual successful1 implementation of a routine shipping program

  12. 40 CFR 147.1801 - State-administered program-Class I, III, IV and V wells.

    Science.gov (United States)

    2010-07-01

    ... Injection Control Program—Attorney General's Statement,” July 25, 1984. (e) The Program Description and any..., III, IV and V wells. 147.1801 Section 147.1801 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Ohio § 147.1801 State-administered program—Class I, III, IV and V wells. The UIC program...

  13. 40 CFR 147.2000 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ...: Attorney General's Statement, Underground Injection Control Program,” January 17, 1984. (e) The Program..., III, IV, and V wells. 147.2000 Section 147.2000 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Rhode Island § 147.2000 State-administered program—Class I, II, III, IV, and V wells. The...

  14. A Historical Review of WIPP Backfill Development

    Energy Technology Data Exchange (ETDEWEB)

    Brush, L.H.; Krumhansl, J.L.; Molecke, M.A.; Papenguth, H.W.

    1999-07-15

    Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. It's introduction was motivated by the need to scavenging CO{sub 2} [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits.

  15. EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999

    Energy Technology Data Exchange (ETDEWEB)

    Channell, J.K.; Walker, B.A.

    2000-05-01

    Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

  16. WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development

    International Nuclear Information System (INIS)

    Howarth, S.M.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed, which provided in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. Nearly 1,500 parameters were developed using information gathered from this program; the parameters were input to numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations. The CCA probabilistic codes frequently require input values that define a statistical distribution for each parameter. Developing parameter distributions begins with the assignment of an appropriate distribution type, which is dependent on the type, magnitude, and volume of data or information available. The development of the parameter distribution values may require interpretation or statistical analysis of raw data, combining raw data with literature values, scaling of lab or field data to fit code grid mesh sizes, or other transformation. Parameter development and documentation of the development process were very complicated, especially for those parameters based on empirical data; they required the integration of information from Sandia National Laboratories (SNL) code sponsors, parameter task leaders (PTLs), performance assessment analysts (PAAs), and experimental principal investigators (PIs). This paper, Part 1 of two parts, contains a discussion of the parameter development process, roles and responsibilities, and lessons learned. Part 2 will discuss parameter documentation, traceability and retrievability, and lessons learned from related audits and reviews

  17. 40 CFR 147.1050 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... authority. Statement from the Maryland Attorney General on the Underground Injection Control Program, as..., III, IV, and V wells. 147.1050 Section 147.1050 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Maryland § 147.1050 State-administered program—Class I, II, III, IV, and V wells. The UIC...

  18. 40 CFR 147.1250 - State-administered program-Class I, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... Control, State Underground Injection Control (UIC) Program; Statement of the Attorney General of the State..., III, IV, and V wells. 147.1250 Section 147.1250 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Mississippi § 147.1250 State-administered program—Class I, III, IV, and V wells. The UIC...

  19. WIPP's Hazardous Waste Facility Permit Renewal Application

    International Nuclear Information System (INIS)

    Most, W.A.; Kehrman, R.F.

    2009-01-01

    Hazardous waste permits issued by the New Mexico Environment Department (NMED) have a maximum term of 10-years from the permit's effective date. The permit condition in the Waste Isolation Pilot Plant's (WIPP) Hazardous Waste Facility Permit (HWFP) governing renewal applications, directs the Permittees to submit a permit application 180 days prior to expiration of the Permit. On October 27, 1999, the Secretary of the NMED issued to the United States Department of Energy (DOE), the owner and operator of WIPP, and to Washington TRU Solutions LLC (WTS), the Management and Operating Contractor and the cooperator of WIPP, a HWFP to manage, store, and dispose hazardous waste at WIPP. The DOE and WTS are collectively known as the Permittees. The HWFP is effective for a fixed term not to exceed ten years from the effective date of the Permit. The Permittees may renew the HWFP by submitting a new permit application at least 180 calendar days before the expiration date, of the HWFP. The Permittees are not proposing any substantial changes in the Renewal Application. First, the Permittees are seeking the authority to dispose of Contact-Handled and Remote-Handled TRU mixed waste in Panel 8. Panels 4 through 7 have been approved in the WIPP Hazardous Waste Facility Permit as it currently exists. No other change to the facility or to the manner in which hazardous waste is characterized, managed, stored, or disposed is being requested. Second, the Permittees also seek to include the Mine Ventilation Rate Monitoring Plan, as Attachment Q in the HWFP. This Plan has existed as a separate document since May 2000. The NMED has requested that the Plan be submitted as part of the Renewal Application. The Permittees have been operating to the Mine Ventilation Rate Monitoring Plan since the Plan was submitted. Third, some information submitted in the original WIPP RCRA Part B Application has been updated, such as demographic information. The Permittees will submit this information in the

  20. WIPP Benchmark calculations with the large strain SPECTROM codes

    Energy Technology Data Exchange (ETDEWEB)

    Callahan, G.D.; DeVries, K.L. [RE/SPEC, Inc., Rapid City, SD (United States)

    1995-08-01

    This report provides calculational results from the updated Lagrangian structural finite-element programs SPECTROM-32 and SPECTROM-333 for the purpose of qualifying these codes to perform analyses of structural situations in the Waste Isolation Pilot Plant (WIPP). Results are presented for the Second WIPP Benchmark (Benchmark II) Problems and for a simplified heated room problem used in a parallel design calculation study. The Benchmark II problems consist of an isothermal room problem and a heated room problem. The stratigraphy involves 27 distinct geologic layers including ten clay seams of which four are modeled as frictionless sliding interfaces. The analyses of the Benchmark II problems consider a 10-year simulation period. The evaluation of nine structural codes used in the Benchmark II problems shows that inclusion of finite-strain effects is not as significant as observed for the simplified heated room problem, and a variety of finite-strain and small-strain formulations produced similar results. The simplified heated room problem provides stratigraphic complexity equivalent to the Benchmark II problems but neglects sliding along the clay seams. The simplified heated problem does, however, provide a calculational check case where the small strain-formulation produced room closures about 20 percent greater than those obtained using finite-strain formulations. A discussion is given of each of the solved problems, and the computational results are compared with available published results. In general, the results of the two SPECTROM large strain codes compare favorably with results from other codes used to solve the problems.

  1. Basic data report for drillhole WIPP 30 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1980-04-01

    WIPP 30 was drilled in east-central Eddy County, New Mexico, in NW 1/4, Sec. 33, T21S, R31E, to obtain drill core for the study of dissolution of near-surface rocks. The borehole encountered from top to bottom, the Dewey Lake Red Beds (449' including artificial fill for drill pad), Rustler Formation (299'), and the upper 160' of the Salado Formation. Continuous core was cut from the surface to total depth. Geophysical logs were taken the full length of the borehole to measure acoustic velocities, density, and distribution of potassium and other radioactive elements. Information from this borehole will be included in an interpretive report on dissolution in Nash Draw based on combined borehole data, surface mapping and laboratory analyses of rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt. Administration policy as of February 1980 is to hold the WIPP site in reserve until the first disposal site can be chosen from several potential sites, including the WIPP

  2. Basic data report for drillhole WIPP 30 (Waste Isolation Pilot Plant - WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    WIPP 30 was drilled in east-central Eddy County, New Mexico, in NW 1/4, Sec. 33, T21S, R31E, to obtain drill core for the study of dissolution of near-surface rocks. The borehole encountered from top to bottom, the Dewey Lake Red Beds (449' including artificial fill for drill pad), Rustler Formation (299'), and the upper 160' of the Salado Formation. Continuous core was cut from the surface to total depth. Geophysical logs were taken the full length of the borehole to measure acoustic velocities, density, and distribution of potassium and other radioactive elements. Information from this borehole will be included in an interpretive report on dissolution in Nash Draw based on combined borehole data, surface mapping and laboratory analyses of rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt. Administration policy as of February 1980 is to hold the WIPP site in reserve until the first disposal site can be chosen from several potential sites, including the WIPP.

  3. WIPP site and vicinity geological field trip

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1980-10-01

    The Environmental Evaluation Group is conducting an assessment of the radiological health risks to people from the Waste Isolation Pilot Plant. As a part of this work, EEG is making an effort to improve the understanding of those geological issues concerning the WIPP site which may affect the radiological consequences of the proposed repository. One of the important geological issues to be resolved is the timing and the nature of the dissolution processes which may have affected the WIPP site. EEG organized a two-day conference of geological scientists, on January 17-18, 1980. On the basis of the January conference and the June field trip, EEG has formed the following conclusions: (1) it has not been clearly established that the site or the surrounding area has been attacked by deep dissolution to render it unsuitable for the nuclear waste pilot repository; (2) the existence of an isolated breccia pipe at the site unaccompanied by a deep dissolution wedge, is a very remote possibility; (3) more specific information about the origin and the nature of the brine reservoirs is needed. An important question that should be resolved is whether each encounter with artesian brine represents a separate pocket or whether these occurrences are interconnected; (4) Anderson has postulated a major tectonic fault or a fracture system at the Basin margin along the San Simon Swale; (5) the area in the northern part of the WIPP site, identified from geophysical and bore hole data as the disturbed zone, should be further investigated to cleary understand the nature and significance of this structural anomaly; and (6) a major drawback encountered during the discussions of geological issues related to the WIPP site is the absence of published material that brings together all the known information related to a particular issue

  4. The WIPP transportation system: Demonstrated readiness

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially-designed trailer, a lightweight tractor, the DOE ''TRANSCOM'' vehicle tracing system, and uniquely qualified and highly-trained drivers. In June of 1989, the National Academy of Sciences reviewed the transportation system and concluded that: ''The system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels.'' The next challenge facing the DOE was demonstrating that this system was ready to transport the TRU waste to the WIPP site in the safest manner possible. Not only did the DOE feel that it was necessary to convince itself that the system was safe, but also representatives of the 23 states through which it traveled

  5. The WIPP transportation system: Demonstrated readiness

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially- designed trailer, a lightweight tractor, the DOE ''TRANSCOM'' vehicle tracking system, and uniquely qualified and highly-trained drivers. In June of 1989, the National Academy of Sciences reviewed the transportation system and concluded that: ''The system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels'' (emphasis added). The next challenge facing the DOE was demonstrating that this system was ready to transport the TRU waste to the WIPP site efficiently and in the safest manner possible. Not only did the DOE feel that is was necessary to convince itself that the system was safe, but also representatives of the 20 states through which it would travel

  6. Basic data report for drillhole WIPP 32 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1980-11-01

    WIPP 32 is an exploratory borehole drilled to examine the subsurface at a small topographic high in Nash Draw. The borehole is located in east-central Eddy County, New Mexico, in NE 1/4 SE 1/4 Sec. 33, T.22S., R.29E. and was drilled in August, 1979. The hole was drilled to a depth of 390 feet, and encountered, from top to bottom, the Rustler Formation (166') and the upper Salado Formation (224'). Core was taken from 4 to 353 feet. Geophysical logs were run the full length of the hole to measure formation properties. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  7. WIPP conceptual design report. Addendum L. Mine safety code review for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1977-06-01

    An initial review of New Mexico and Federal mining standards and regulations has been made to determine their applicability to the WIPP conceptual design. These standards and regulations are reviewed point by point and the enclosed listing includes comments and recommendations for those which will affect the design and/or eventual operations of WIPP. The majority of the standards, both federal and state, are standard safe mining practices. Those standards are listed which are thought should be emphasized for development of the design; also those that would increase the hazard risk by strict compliance. Because the WIPP facility is different in many respects from mines for which the regulations were intended, strict compliance in some respects would provide an increased hazard, while in other instances the regulations are less strict than is desirable. These are noted in the attached review

  8. Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992

    Energy Technology Data Exchange (ETDEWEB)

    Francis, A.J.; Gillow, J.B.

    1993-09-01

    Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term (< 6 months) and long-term (> 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation.

  9. 40 CFR 147.1601 - State-administered program-Class I, III, IV and V wells.

    Science.gov (United States)

    2010-07-01

    ... lands, is the program administered by the New Mexico Water Quality Control Commission, the Environmental.... “Attorney General's Statement,” signed by the Assistant Attorney General for the Environmental Improvement..., III, IV and V wells. 147.1601 Section 147.1601 Protection of Environment ENVIRONMENTAL PROTECTION...

  10. 40 CFR 147.2800 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... General Commonwealth of the Northern Mariana Islands, “Underground Injection Control Program—Attorney..., III, IV, and V wells. 147.2800 Section 147.2800 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Commonwealth of the Northern Mariana Islands § 147.2800 State-administered program—Class...

  11. 40 CFR 147.1301 - State-administered program-Class I, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ..., III, IV, and V wells. 147.1301 Section 147.1301 Protection of Environment ENVIRONMENTAL PROTECTION... CONTROL PROGRAMS Missouri § 147.1301 State-administered program—Class I, III, IV, and V wells. The UIC... Administrator on October 10, 1984. (d) Statement of Legal Authority. Opinion No. 123-84, signed by Attorney...

  12. 20 CFR 408.1235 - How does the State transfer funds to SSA to administer its recognition payment program?

    Science.gov (United States)

    2010-04-01

    ... administer its recognition payment program? 408.1235 Section 408.1235 Employees' Benefits SOCIAL SECURITY... fifth business day following such date. (b) Accounting of State funds. (1) As soon as feasible after the... balance of the State's cash on deposit with SSA. (2) SSA will provide the State with an accounting of...

  13. 40 CFR 147.2400 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... Washington, chapter 90.48 (Bureau of National Affairs, 1986 Laws), entitled “Water Pollution Control.” (c)(1... legal authority. Letter from Attorney General of the State of Washington, by Senior Assistant Attorney... CONTROL PROGRAMS Washington § 147.2400 State-administered program—Class I, II, III, IV, and V wells. The...

  14. Extent of the Disturbed Rock Zone Around a WIPP Disposal Room

    Science.gov (United States)

    Herrick, C. G.; Park, B. Y.; Holcomb, D. J.

    2008-12-01

    that cause dilatant damage can be defined in terms of the ratio of stress invariants, which allow reasonable models of DRZ evolution and devolution. The change of DRZ extent with time is calculated based on a dilatant damage potential criterion: D = (C · I1) / √J2 where D is the damage potential, I1 is the first invariant of the stress tensor, and J2 is the second invariant of the deviatoric stress tensor. When D resist its deformation and damage to the salt decreases. The maximum extents of the DRZ calculated below and above a room reach approximately 2.25 m and 4.75 m, respectively. The maximum lateral DRZ extent in the side of the room is estimated to be roughly 2 m. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S. Department of Energy.

  15. Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA

    International Nuclear Information System (INIS)

    Thakur, P.

    2016-01-01

    After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m 3 for 241 Am and 10.2 μBq/m 3 for 239+240 Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m 3 of 241 Am and 5.8 μBq/m 3 of 239+240 Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

  16. Basic data report for drillhole WIPP 19 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1980-03-01

    WIPP 19 is an exploratory borehole whose objective was to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between April 6 and May 4, 1978. The hole was drilled to a depth of 1038.2 feet and encountered, from top to bottom, surficial Holocene deposits (7', including artificial fill for drill pad), the Mescalero caliche (7'), the Santa Rosa Sandstone (82'), the Dewey Lake Red Beds (494'), the Rustler Formation (315'), and the upper portion of the Salado Formation (143'). Cuttings were collected at 10-foot intervals. A suite of geophysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 19 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  17. Basic data report for Drillhole WIPP 22 (Waste Isolation Pilot Plant, WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    WIPP 22 is an exploratory borehole whose objective is to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between March 14 and 30, 1978. The hole was drilled to a depth of 1448 feet and encountered, from top to bottom, surficial Holocene deposits (6', including artificial fill for drill pad), the Mescalero caliche (7'), the Santa Rosa Sandstone (68'), the Dewey Lake Red Beds (492'), the Rustler Formation (311'), and the upper portion of the Salado Formation (565'). Cuttings were collected at 10-foot intervals. A suite of geophysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 22 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt.

  18. Basic data report for drillhole WIPP 21 (Waste Isolation Pilot Plant - WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    WIPP 21 is an exploratory borehole whose objective is to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between May 24 and 26, 1978. The hole was drilled to a depth of 1046 feet and encountered, from top to bottom, surficial Holocene deposits (6', including artificial fill for drill pad), the Mescalero caliche (6'), the Santa Rosa Sandstone (34'), the Dewey Lake Red Beds (487'), the Rustler Formation (308'), and the upper portion of the Salado Formation (178'). Cuttings were collected at 10-foot intervals. A suite of goephysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 21 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt.

  19. Basic data report for Drillhole WIPP 28 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1979-08-01

    WIPP 28 was drilled in Nash Draw (NE 1/4, sec. 18, T.21S., R.31E.) in Eddy County, New Mexico, to determine subsurface stratigraphy and examine dissolution features above undisturbed salt in the Salado Formation. Determination of dissolution rates will refine previous estimates and provide short-term (geologically) rates for WIPP risk assessments. The borehole encountered, from top to bottom, Mescalero caliche (12 ft with fill material for pad), Dewey Lake Red Beds (203 ft), Rustler Formation (316 ft), and the upper 270 ft of the Salado Formation. A dissolution residue, 58 ft thick, is at the top of the Salado Formation overlying halite-rich beds. In addition to obtaining nearly continuous core from the surface to total depth (801 ft), geophysical logs were taken to measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole basin data, surface mapping, and laboratory analyses of Nash Draw rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt

  20. Basic data report for drillhole WIPP 26 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1979-08-01

    WIPP 26 was drilled in Nash Draw (SE 1/4 NE 1/4, sec. 29, T22S, R30E) in Eddy County, New Mexico, to determine subsurface stratigraphy and examine dissolution features above undisturbed salt in the Salado Formation. Determination of dissolution rates will refine previous estimates and provide short-term (geologically) rates for WIPP risk assessments. The borehole encountered, from top to bottom, surficial deposits (10 ft with full materials for pad), Rustler Formation (299 ft), and the upper 194 ft of the Salado Formation. A dissolution residue, 11 ft thick, is at the top of the Salado Formation overlying halite-rich beds. In addition to obtaining nearly continuous core from the surface to total depth (503 ft), geophysical logs were taken to measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole basin data, surface mapping, and laboratory analyses of Nash Draw rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt

  1. WIPP conceptual design report. Addendum A. Design calculations for Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1977-04-01

    The design calculations for the Waste Isolation Pilot Plant (WIPP) are presented. The following categories are discussed: general nuclear calculations; radwaste calculations; structural calculations; mechanical calculations; civil calculations; electrical calculations; TRU waste surface facility time and motion analysis; shaft sinking procedures; hoist time and motion studies; mining system analysis; mine ventilation calculations; mine structural analysis; and miscellaneous underground calculations.

  2. WIPP: construction and progress on a successful nuclear waste repository

    International Nuclear Information System (INIS)

    Cooper, W.R.; Sankey, C.A.

    1985-01-01

    The Department of Energy is constructing the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico. The facility will retrievably store transuranic waste from defense activities of the United States and conduct experiments with Defense high-level waste which will be retrieved at the end of the experiments. This paper describes the progress and the present status of activities at WIPP. 4 refs

  3. WIPP Magnesium Oxide (MgO) - Planned Change Request

    Science.gov (United States)

    On April 10, 2006, the DOE submitted a planned change request pertaining to the amount of MgO emplaced in the WIPP repository. MgO is an engineered barrier that DOE included as part of the original WIPP Certification Decision.

  4. Mechanical Modeling of a WIPP Drum Under Pressure

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Jeffrey A. [Sandia National Laboratories, Albuquerque, NM (United States)

    2014-11-25

    Mechanical modeling was undertaken to support the Waste Isolation Pilot Plant (WIPP) technical assessment team (TAT) investigating the February 14th 2014 event where there was a radiological release at the WIPP. The initial goal of the modeling was to examine if a mechanical model could inform the team about the event. The intention was to have a model that could test scenarios with respect to the rate of pressurization. It was expected that the deformation and failure (inability of the drum to contain any pressure) would vary according to the pressurization rate. As the work progressed there was also interest in using the mechanical analysis of the drum to investigate what would happen if a drum pressurized when it was located under a standard waste package. Specifically, would the deformation be detectable from camera views within the room. A finite element model of a WIPP 55-gallon drum was developed that used all hex elements. Analyses were conducted using the explicit transient dynamics module of Sierra/SM to explore potential pressurization scenarios of the drum. Theses analysis show similar deformation patterns to documented pressurization tests of drums in the literature. The calculated failure pressures from previous tests documented in the literature vary from as little as 16 psi to 320 psi. In addition, previous testing documented in the literature shows drums bulging but not failing at pressures ranging from 69 to 138 psi. The analyses performed for this study found the drums failing at pressures ranging from 35 psi to 75 psi. When the drums are pressurized quickly (in 0.01 seconds) there is significant deformation to the lid. At lower pressurization rates the deformation of the lid is considerably less, yet the lids will still open from the pressure. The analyses demonstrate the influence of pressurization rate on deformation and opening pressure of the drums. Analyses conducted with a substantial mass on top of the closed drum demonstrate that the

  5. Achieving WIPP certification for software. A white paper

    International Nuclear Information System (INIS)

    Matthews, S.D.; Adams, K.; Twitchell, K.E.

    1998-07-01

    The NMT-1 and NMT-3 organizations within the Chemical and Metallurgical Research (CMR) facility at the Los Alamos National Laboratory (LANL) is working to achieve Waste Isolation Pilot Plant (WIPP) certification to enable them to transport their TRU waste to WIPP. In particular, the NMT-1 management is requesting support from the Idaho National Engineering and Environmental Laboratory (INEEL) to assist them in making the Laboratory Information Management System (LIMS) software WIPP certifiable. Thus, LIMS must be compliant with the recognized software quality assurance (SQA) requirements stated within the QAPD. Since the Idaho National Engineering and Environmental Laboratory (INEEL) has achieved WIPP certification, INEEL personnel can provide valuable assistance to LANL by sharing lessons learned and recommendations. Thus, this white paper delineates the particular software quality assurance requirements required for WIPP certification

  6. Construction of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Munson, D.E.; Matalucci, R.V.; Hoag, D.L.; Blankenship D.A.

    1997-02-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories has the responsibility for experimental activities at the WIPP and has emplaced several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The construction of the tests relied heavily on earlier excavations at the WIPP site to provide a basis for selecting excavation, surveying, and instrumentation methods, and achievable construction tolerances. The tests were constructed within close tolerances to provide consistent room dimensions and accurate placement of gages. This accuracy has contributed to the high quality of data generated which in turn has facilitated the comparison of test results to numerical predictions. The purpose of this report is to detail the construction activities of the TSI tests

  7. Preferences and satisfaction towards a screening program with self-administered human papilloma virus detection tests

    OpenAIRE

    Morán, Flavia; Facultad de Medicina, Universidad Peruana Cayetano Heredia, Lima, Perú. Estudiante de Medicina; Cárcamo, César; Facultad de Salud Pública y Administración, Universidad Peruana Cayetano Heredia. Lima, Perú. médico, doctor en Epidemiología; Valderrama, María; Facultad de Salud Pública y Administración, Universidad Peruana Cayetano Heredia. Lima, Perú. obstetra, magister en Obstetricia; García, Patricia J.; Facultad de Salud Pública y Administración, Universidad Peruana Cayetano Heredia. Lima, Perú. médico, doctora en Medicina

    2017-01-01

    Cross-sectional study describing preferences and satisfaction towards a cervical cancer screening program with selfadministered rapid tests for the detection of human papillomavirus (HPV). Of 2 090 users picked by the program in Ventanilla Callao - Peru, 97 were randomly selected to be surveyed. In addition, interviews were conducted with women leaders of the community, in charge of providing the evidence. 74.2% of the users felt, at least, satisfied with the program. 68% of women prefer to t...

  8. When should I attempt my centrally administered summative assessments in the RANZCP competency-based training program?

    Science.gov (United States)

    Kealy-Bateman, Warren; Kotze, Beth; Lampe, Lisa

    2016-12-01

    To provide information relevant to decision-making around the timing of attempting the centrally administered summative assessments in the Royal Australian and New Zealand College of Psychiatrists (RANZCP) 2012 Fellowship Program. We consider the new Competency-Based Fellowship Program of the RANZCP and its underlying philosophy, the trainee trajectory within the program and the role of the supervisor. The relationship between workplace-based and external assessments is discussed. The timing of attempting centrally administered summative assessments is considered within the pedagogical framework of medical competencies development. Although successful completion of all the centrally administered summative assessments requires demonstration of a junior consultant standard of competency, the timing at which this standard will most commonly be achieved is likely to vary from assessment to assessment. There are disadvantages attendant upon prematurely attempting assessments, and trainees are advised to carefully consider the requirements of each assessment and match this against their current level of knowledge and skills. Trainees and supervisors need to be clear about the competencies required for each of the external assessments and match this against the trainee's current competencies to assist in decision-making about the timing of assessments and planning for future learning. © The Royal Australian and New Zealand College of Psychiatrists 2016.

  9. WIPP shaft seal system parameters recommended to support compliance calculations

    International Nuclear Information System (INIS)

    Hurtado, L.D.; Knowles, M.K.; Kelley, V.A.; Jones, T.L.; Ogintz, J.B.; Pfeifle, T.W.

    1997-12-01

    The US Department of Energy plans to dispose of transuranic waste at the Waste Isolation Pilot Plant (WIPP), which is sited in southeastern New Mexico. The WIPP disposal facility is located approximately 2,150 feet (650 m) below surface in the bedded halite of the Salado Formation. Prior to initiation of disposal activities, the Department of Energy must demonstrate that the WIPP will comply with all regulatory requirements. Applicable regulations require that contaminant releases from the WIPP remain below specified levels for a period of 10,000 years. To demonstrate that the WIPP will comply with these regulations, the Department of Energy has requested that Sandia National Laboratories develop and implement a comprehensive performance assessment of the WIPP repository for the regulatory period. This document presents the conceptual model of the shaft sealing system to be implemented in performance assessment calculations conducted in support of the Compliance Certification Application for the WIPP. The model was developed for use in repository-scale calculations and includes the seal system geometry and materials to be used in grid development as well as all parameters needed to describe the seal materials. These calculations predict the hydrologic behavior of the system. Hence conceptual model development is limited to those processes that could impact the fluid flow through the seal system

  10. WIPP shaft seal system parameters recommended to support compliance calculations

    Energy Technology Data Exchange (ETDEWEB)

    Hurtado, L.D.; Knowles, M.K. [Sandia National Labs., Albuquerque, NM (United States); Kelley, V.A.; Jones, T.L.; Ogintz, J.B. [INTERA Inc., Austin, TX (United States); Pfeifle, T.W. [RE/SPEC, Inc., Rapid City, SD (United States)

    1997-12-01

    The US Department of Energy plans to dispose of transuranic waste at the Waste Isolation Pilot Plant (WIPP), which is sited in southeastern New Mexico. The WIPP disposal facility is located approximately 2,150 feet (650 m) below surface in the bedded halite of the Salado Formation. Prior to initiation of disposal activities, the Department of Energy must demonstrate that the WIPP will comply with all regulatory requirements. Applicable regulations require that contaminant releases from the WIPP remain below specified levels for a period of 10,000 years. To demonstrate that the WIPP will comply with these regulations, the Department of Energy has requested that Sandia National Laboratories develop and implement a comprehensive performance assessment of the WIPP repository for the regulatory period. This document presents the conceptual model of the shaft sealing system to be implemented in performance assessment calculations conducted in support of the Compliance Certification Application for the WIPP. The model was developed for use in repository-scale calculations and includes the seal system geometry and materials to be used in grid development as well as all parameters needed to describe the seal materials. These calculations predict the hydrologic behavior of the system. Hence conceptual model development is limited to those processes that could impact the fluid flow through the seal system.

  11. Contamination control aspects of attaching waste drums to the WIPP Waste Characterization Chamber

    International Nuclear Information System (INIS)

    Rubick, L.M.; Burke, L.L.

    1998-01-01

    Argonne National Laboratory West (ANL-W) is verifying the characterization and repackaging of contact-handled transuranic (CH-TRU) mixed waste in support of the Waste Isolation Pilot Program (WIPP) project located in Carlsbad, New Mexico. The WIPP Waste Characterization Chamber (WCC) was designed to allow opening of transuranic waste drums for this process. The WCC became operational in March of 1994 and has characterized approximately 240 drums of transuranic waste. The waste drums are internally contaminated with high levels of transuranic radionuclides. Attaching and detaching drums to the glove box posed serious contamination control problems. Prior to characterizing waste, several drum attachment techniques and materials were evaluated. An inexpensive HEPA filter molded into the bagging material helps with venting during detachment. The current techniques and procedures used to attach and detach transuranic waste drums to the WCC are described

  12. Office of Energy Research collaborative research programs administered by Oak Ridge Associated Universities: Annual report, FY 1987

    International Nuclear Information System (INIS)

    1988-02-01

    The US Department of Energy's (DOE) Office of Energy Research (OER) sponsors programs designed to encourage and support interaction between US colleges and universities and DOE research facilities. Faculty members, graduate students, undergraduates, and recent postgraduates participate in research and receive advanced training at DOE laboratories. Staff members from DOE laboratories visit campuses to deliver energy-related lectures and participate in seminars and classroom discussions. Oak Ridge Associated Universities (ORAU) has been involved in the developemnt and administration of these collaborative research programs since their inception. During FY 1987, ORAU administered appointments for the Office of Energy Research under the following two umbrella programs: University/DOE Laboratory Cooperative Program (Lab Co-op); Science and Engineering Research Semester (SERS). In addition, ORAU participated in a project to collect and assess information from individuals who had held research appointment as undergraduate students during a four-year period from 1979 to 1982. All of these activities are summarized in this report

  13. Certifying the Waste Isolation Pilot Plant: Lessons Learned from the WIPP Experience

    International Nuclear Information System (INIS)

    Anderson, D.R.; Chu, Margaret S.Y.; Froehlich, Gary K.; Howard, Bryan A.; Howarth, Susan M.; Larson, Kurt W.; Pickering, Susan Y.; Swift, Peter N.

    1999-01-01

    In May 1998, the US Environmental Protection Agency (EPA) certified the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) as being in compliance with applicable long-term regulations governing the permanent disposal of spent nuclear fuel, high-level, and transuranic radioactive wastes. The WIPP is the first deep geologic repository in the US to have successfully demonstrated regulatory compliance with long-term radioactive waste disposal requirements. The first disposal of TRU waste at WIPP occurred on March 26, 1999. Many of the lessons learned during the WIPP Project's transition from site characterization and experimental research to the preparation of a successful application may be of general interest to other repository programs. During a four-year period (1992 to 1996), the WIPP team [including the DOE Carlsbad Area Office (CAO), the science advisor to CAO, Sandia National Laboratories (SNL), and the management and operating contractor of the WIPP site, Westinghouse Electric Corporation (WID)] met its aggressive schedule for submitting the application without compromising the integrity of the scientific basis for the long-term safety of the repository. Strong leadership of the CAO-SNL-WID team was essential. Within SNL, a mature and robust performance assessment (PA) allowed prioritization of remaining scientific activities with respect to their impact on regulatory compliance. Early and frequent dialog with EPA staff expedited the review process after the application was submitted. Questions that faced SNL are familiar to geoscientists working in site evaluation projects. What data should be gathered during site characterization? How can we know when data are sufficient? How can we know when our understanding of the disposal system is sufficient to support our conceptual models? What constitutes adequate ''validation'' of conceptual models for processes that act over geologic time? How should we use peer review and expert judgment? Other

  14. The WIPP transportation system: Dedicated to safety

    International Nuclear Information System (INIS)

    Ward, T.; McFadden, M.

    1993-01-01

    When developing a transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites, the Department of Energy (DOE) recognized and addressed many challenges. Shipments of waste to the Waste Isolation Pilot Plant (WIPP) were to cover a twenty-five year period and utilize routes covering over twelve thousand miles in twenty-three states. Enhancing public safety by maximizing the payload, thus reducing the number of shipments, was the primary objective. To preclude the requirement for overweight permits, the DOE started with a total shipment weight limit of 80,000 pounds and developed an integrated transportation system consisting of a Type ''B'' package to transport the material, a lightweight tractor and trailer, stringent driver requirements, and a shipment tracking system referred to as ''TRANSCOM''

  15. Radionuclide transport in sandstones with WIPP brine

    International Nuclear Information System (INIS)

    Weed, H.C.; Bazan, F.; Fontanilla, J.; Garrison, J.; Rego, J.; Winslow, A.M.

    1981-02-01

    Retardation factors (R) have been measured for the transport of 3 H, /sup 95m/Tc, and 85 Sr in WIPP brine using St. Peter, Berea, Kayenta, and San Felipe sandstone cores. If tritium is assumed to have R=1, /sup 95m/Tc has R=1.0 to 1.3 and therefore is essentially not retarded. Strontium-85 has R = 1.0 to 1.3 on St. Peter, Berea, and Kayenta, but R=3 on San Felipe. This is attributed to sorption on the matrix material of San Felipe, which has 45 volume % matrix compared with 1 to 10 volume % for the others. Retardation factors (R/sub s/) for 85 Sr calculated from static sorption measurements are unity for all the sandstones. Therefore, the static and transport results for 85 Sr disagree in the case of San Felipe, but agree for St. Peter, Berea, and Kayenta

  16. [The role of regional research laboratories of the local government in administering regional EQA programs].

    Science.gov (United States)

    Ohishi, Hisae; Mikuriya, Hisatoshi; Kumasaka, Kazunari

    2005-04-01

    In 1981, the Japanese Ministry of Health and Welfare revised the enforcement of regulations of the Medical Technologists' Act. The amendments stipulate that all independent laboratories are legally obliged to introduce laboratory quality assurance programs and are responsible for the quality of all test results. To ensure adherence to these regulations, regional research laboratories of local governments such as the Tokyo Metropolitan Research Laboratory of Public Health should conduct regional external quality assessment (EQA) programs. We did a survey, in the form of a questionnaire, of the regional research laboratories of public health across the country. We found that commitment to the regional EQA in almost all of these public laboratories is insufficient. The main problem is that restructuring of local governments has resulted in lower budgets and so they are short of human resources. Nationwide EQA programs are only able to detect gross errors and use invalid methods for evaluating routine performance. We conclude that the regional EQA should be further developed.

  17. Administering for Change Program Innovation Process Study. Work Unit 12, Milestone 2.

    Science.gov (United States)

    Temkin, Sanford; Clark, Carolyn

    The work reported here is exploratory and investigative in nature, but it is expected to lead to a systematic research program designed to test the validity of propositions about the innovation process. Part 1 is introductory. Part 2 sets the stage for discussion of the Research for Better Schools, Inc. (RBS) field research. Part 3 enumerates the…

  18. 40 CFR 147.1800 - State-administered program-Class II wells.

    Science.gov (United States)

    2010-07-01

    ... Control Program—Attorney General's Statement,” signed by the Assistant Attorney General, Chief, Environmental Law Section, for the Attorney General of Ohio, September 30, 1982. (d) The Program Description and... wells. 147.1800 Section 147.1800 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

  19. A Synergistic Model for a Juvenile Court Administered Alternative Education Program.

    Science.gov (United States)

    Herbst, Dominic P.; Sontheimer, Henry G.

    1987-01-01

    Describes Alternative Education program coordinated by a juvenile probation department providing tutorial instruction by university students to secondary school students who have been referred through the juvenile court for minor delinquency and/or truancy. Discusses benefits which include providing an option for school districts for chronic…

  20. Description of how the Atomic Energy Control Board research and development program is administered

    International Nuclear Information System (INIS)

    1985-06-01

    The Regulatory Research Program should be seen as augmenting and extending the capability of in-house resources. The overall objective of the research program is to produce pertinent and independent information that will assist the Board and its staff in making correct, timely and credible decisions on regulating atomic energy. Within the framework of the general objective, the specific objectives are: (i) to verify information, claims or analyses from licensees in support of licensing actions; (ii) to fill gaps in knowledge to enable the Board to contribute to the establishment of health and safety requirements or guidelines or to aid in arriving at licensing decisions; (iii) to stimulate licensees to do more work on certain topics relating to health, safety or security; (iv) to develop information on the regulatory process and the evaluation of the regulatory process; (v) to develop equipment or procedures to enhance health, safety or security in those cases where the industry is not competent or inclined to do so; and (vi) to enhance the competence of the Board and its credibility in the eyes of licensees and the public

  1. Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA.

    Science.gov (United States)

    Thakur, P

    2016-01-01

    After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m(3) for (241)Am and 10.2 μBq/m(3) for (239+240)Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m(3) of (241)Am and 5.8 μBq/m(3) of (239+240)Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

  2. Waste Isolation Pilot Plant (WIPP) fact sheet

    International Nuclear Information System (INIS)

    1993-01-01

    Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all terms and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993

  3. Basic data report for drillhole WIPP 15 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1981-11-01

    WIPP 15 is a borehole drilled in Marformation.h, 1978, in section 18, T.23S., R. 35E. of south-central Lea County. The purpose of WIPP 15 was to examine fill in San Simon Sink in order to extract climatic information and to attempt to date the collapse of the sink. The borehole was cored to total depth (810.5 feet) and encountered, from top to bottom, Quaternary calcareous clay, marl and sand, the claystones and siltstones of the Triassic Santa Rosa Formation. Neutron and gamma ray geophysical logs were run to measure density and radioactivity. The sink was about 547 feet of Quaternary fill indicating subsidence and deposition. Diatomaceous beds exposed on the sink margin yielded samples dated by 14 C at 20,570 +- 540 years BP and greater than 32,000 years BP; these beds are believed stratigraphically equivalent to ditomaceous beds at 153 to 266 feet depth in the core. Aquatic fauna and flora from the upper 98 feet of core indicate a pluvial period (probably Tohokan) followed by an arid or very arid time before the present climate was established. Aquifer pump tests performed in the Quaternary sands and clays show transmissivities to be as high as 600 feet squared per day. As the water quality was good, the borehole was released to the lessee as a potential water well

  4. Basic data report for drillhole WIPP 15 (Waste Isolation Pilot Plant-WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1981-11-01

    WIPP 15 is a borehole drilled in Marformation.h, 1978, in section 18, T.23S., R. 35E. of south-central Lea County. The purpose of WIPP 15 was to examine fill in San Simon Sink in order to extract climatic information and to attempt to date the collapse of the sink. The borehole was cored to total depth (810.5 feet) and encountered, from top to bottom, Quaternary calcareous clay, marl and sand, the claystones and siltstones of the Triassic Santa Rosa Formation. Neutron and gamma ray geophysical logs were run to measure density and radioactivity. The sink was about 547 feet of Quaternary fill indicating subsidence and deposition. Diatomaceous beds exposed on the sink margin yielded samples dated by /sup 14/C at 20,570 +- 540 years BP and greater than 32,000 years BP; these beds are believed stratigraphically equivalent to ditomaceous beds at 153 to 266 feet depth in the core. Aquatic fauna and flora from the upper 98 feet of core indicate a pluvial period (probably Tohokan) followed by an arid or very arid time before the present climate was established. Aquifer pump tests performed in the Quaternary sands and clays show transmissivities to be as high as 600 feet squared per day. As the water quality was good, the borehole was released to the lessee as a potential water well.

  5. Brine inflow to WIPP disposal rooms: Data, modeling, and assessment

    Energy Technology Data Exchange (ETDEWEB)

    Nowak, E.J.; McTigue, D.F.; Beraun, R.

    1988-09-01

    A WIPP data base that characterizes brine movement and accumulation is summarized and analyzed. The data are interrupted in terms of a model for flow in a saturated porous medium. The model, summarized in this report, embodies the Darcy-flow assumption and storage due to linearly elastic compression of the salt and brine. Comparisons between model calculations and brine inflow rates measured in the WIPP show order-of-magnitude agreement for permeabilities in the range of 10/sup/minus/21/ to 10/sup/minus/20/ m/sup 2/ (1-10 nanodarcies) 2/. These values of permeability are in accord with independent, in situ determinations of permeability in the salt. Expected accumulations of brine in typical WIPP waste disposal rooms were calculated by numerical methods using a mathematical description for the brine inflow model. The expected brine accumulation in a disposal room was calculated to be in the range of 4 m/sup 3/ to 43 m/sup 3/ in 100 years. WIPP disposal rooms, filled with waste and backfilled, are expected to be virtually completely reconsolidated due to host rock creep in about 100 years, preventing further accumulation of brine. Calculations show that water-absorbing tailored backfill materials can readily absorb the maximum expected brine accumulations in WIPP disposal rooms while maintaining adequate mechanical strength. 59 refs., 20 figs., 4 tabs.

  6. Concentration of uranium in the drinking and surface water around the WIPP site

    International Nuclear Information System (INIS)

    Khaing, H.; Lemons, B.G.; Thakur, P.

    2016-01-01

    Activity concentration of uranium isotopes ( 238 U, 234 U and 235 U) were analyzed in drinking and surface water samples collected in the vicinity of the WIPP site using alpha spectroscopy. The purpose of this study was to investigate the changes in uranium concentrations (if any) in the vicinity of the WIPP site and whether the February 14, 2014 radiation release event at the WIPP had any detectable impact on the water bodies around the WIPP. (author)

  7. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume IV contains the following attachments for Module IV: VOC monitoring plan for bin-room tests (Appendix D12); bin emission control and VOC monitoring system drawings; bin scale test room ventilation drawings; WIPP supplementary roof support system, underground storage area, room 1, panel 1, DOE/WIPP 91-057; and WIPP supplementary roof support system, room 1, panel 1, geotechnical field data analysis bi-annual report, DOE/WIPP 92-024

  8. Status and Growth of Underground Science at WIPP

    Science.gov (United States)

    Rempe, Norbert T.

    2008-10-01

    The science community is increasingly taking advantage of research opportunities in the government-owned Waste Isolation Pilot Plant (WIPP), 655m underground near Carlsbad, NM. Discoveries so far include viable bacteria, cellulose, and DNA in 250 million-year old salt, preserved in an ultra-low background-radiation setting. Supplementing the overburden's shielding against cosmic radiation, terrestrial background from the host formation is less than five percent that of average crustal rock. In the past, WIPP accommodated development and testing of neutral current detectors for the Sudbury Neutrino Observatory and dark matter research, and it currently hosts two experiments pursuing neutrino-less double-beta decay. That scientists can listen to whispers from the universe in proximity to megacuries of radioactive waste lends, of course, credibility to the argument that WIPP itself is very safe. Almost a century of regional petroleum and potash extraction history and more than three decades of WIPP studies have generated a comprehensive body of knowledge on geology, mining technology, rock mechanics, geochemistry, and other disciplines relevant to underground science. Existing infrastructure is being used and can be expanded to fit experimental needs. WIPP's exemplary safety and regulatory compliance culture, low excavating and operating cost, and the high probability of the repository operating at least another 40 years make its available underground space attractive for future research and development. Recent proposals include low-photon energy counting to study internal dose received decades ago, investigations into ultra-low radiation dose response in cell cultures and laboratory animals (e.g., hormesis vs. linear no-threshold) and detectors for dark matter, solar and supernova neutrinos, and proton decay. Additional proposals compatible with WIPP's primary mission are welcome.

  9. Test plan: Gas-threshold-pressure testing of the Salado Formation in the WIPP underground facility

    International Nuclear Information System (INIS)

    Saulnier, G.J. Jr.

    1992-03-01

    Performance assessment for the disposal of radioactive waste from the United States defense program in the WIPP underground facility must assess the role of post-closure was generation by waste degradation and the subsequent pressurization of the facility. be assimilated by the host formation will Whether or not the generated gas can be assimilated by the host formation will determine the ability of the gas to reach or exceed lithostatic pressure within the repository. The purpose of this test plan is (1) to present a test design to obtain realistic estimates of gas-threshold pressure for the Salado Formation WIPP underground facility including parts of the formation disturbed by the underground of the Salado, and (2) to provide a excavations and in the far-field or undisturbed part framework for changes and amendments to test objectives, practices, and procedures. Because in situ determinations of gas-threshold pressure in low-permeability media are not standard practice, the methods recommended in this testplan are adapted from permeability-testing and hydrofracture procedures. Therefore, as the gas-threshold-pressure testing program progresses, personnel assigned to the program and outside observers and reviewers will be asked for comments regarding the testing procedures. New and/or improved test procedures will be documented as amendments to this test plan, and subject to similar review procedures

  10. Evaluation of the proposed WIPP site in southeast New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Weart, W.D.

    1979-01-01

    Five years of earth science characterization of the proposed Waste Isolation Pilot Plant (WIPP) site provide a high level of assurance that the area is satisfactory for development of a geologic repository. Ecological investigations and socioeconomic studies have indicated only relatively benign impacts will occur from construction, operation and long-term aspects of the repository.

  11. Evaluation of the proposed WIPP site in southeast New Mexico

    International Nuclear Information System (INIS)

    Weart, W.D.

    1979-01-01

    Five years of earth science characterization of the proposed Waste Isolation Pilot Plant (WIPP) site provide a high level of assurance that the area is satisfactory for development of a geologic repository. Ecological investigations and socioeconomic studies have indicated only relatively benign impacts will occur from construction, operation and long-term aspects of the repository

  12. Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards

    International Nuclear Information System (INIS)

    Neill, R.H.; Chaturvedi, L.; Clemo, T.M.

    1996-03-01

    The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites' compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site

  13. Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Clemo, T.M. [and others

    1996-03-01

    The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites` compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site.

  14. Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States). Repository Isolation Systems Div.; Hoag, D.L.; Blankenship, D.A.; DeYonge, W.F.; Schiermeister, D.M. [RE/SPEC, Inc., Albuquerque, NM (United States); Jones, R.L.; Baird, G.T. [Tech Reps, Inc., Albuquerque, NM (United States)

    1997-04-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information.

  15. Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Munson, D.E.; Jones, R.L.; Baird, G.T.

    1997-04-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information

  16. Description and Evaluation of a Home-Based, Parent-Administered Program for Teaching Enhanced Natural Gestures to Individuals With Angelman Syndrome.

    Science.gov (United States)

    Calculator, Stephen N

    2016-02-01

    This article describes and presents outcomes of a home-based, self-administered version of the Enhanced Natural Gestures (ENG) program for individuals with Angelman syndrome. Parents of 18 individuals (11 boys and 7 girls) with Angelman syndrome, in consultation with their speech-language pathologists, participated in a quasi-experimental "B" design in which they self-administered an instructional program to teach their children to use enhanced natural gestures at home and/or in the community. Parents integrated 2 teaching methods, Mand-Model with time delay and Molding-Shaping, into their everyday interactions with their children. Parents reported outcomes of the program through goal attainment scaling and completion of the ENG Acceptability Rating Form. Children's overall achievements acquiring ENGs generally met or exceeded program (and parent) expectations. Most parents reported little difficulty self-administering the ENG program with their children and regarded the program positively across multiple dimensions. ENGs may, in conjunction with other forms of augmentative and alternative communication, represent a viable method of communication for many individuals with Angelman syndrome. Further research is warranted to explore the feasibility of ENGs with other populations of individuals with severe disabilities and complex communication challenges.

  17. Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

    International Nuclear Information System (INIS)

    1994-02-01

    WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18 TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs

  18. Constitutive representation of damage development and healing in WIPP salt

    International Nuclear Information System (INIS)

    Chan, K.S.; Bodner, S.R.; Fossum, A.F.; Munson, D.E.

    1994-01-01

    There has been considerable interest in characterizing and modeling the constitutive behavior of rock salt with particular reference to long-term creep and creep failure. The interest is motivated by the projected use of excavated rooms in salt rock formations as repositories for nuclear waste. It is presumed that closure of those rooms by creep ultimately would encapsulate the waste material, resulting in its effective isolation. A continuum mechanics approach for treating damage healing is formulated as part of a constitutive model for describing coupled creep, fracture, and healing in rock salt. Formulation of the healing term is, described and the constitutive model is evaluated against experimental data of rock salt from the Waste Isolation Pilot Plant (WIPP) site. The results indicate that healing anistropy in WIPP salt can be modeled with an appropriate power-conjugate equivalent stress, kinetic equation, and evolution equation for damage healing

  19. Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18 TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs.

  20. Assessment of allowable transuranic activity levels for WIPP wastes

    International Nuclear Information System (INIS)

    1987-12-01

    This study provides a technical evaluation for the establishment of an upper limit on the transuranic content of waste packages to be received. To accomplish this, the predicted radiological performance of WIPP is compared to the radiological performance requirements applicable to WIPP. These performance requirements include radiation protection standards for both routine facility operations and credible operational accidents. These requirements are discussed in Chapter 2.0. From the margin between predicted performance and the performance requirements, the maximum allowable transuranic content of waste packages can then be inferred. Within the resulting compliance envelope, a waste acceptance criterion can be established that delineates the allowable level of transuranic radioactivity content for contact handled (CH) and remote handled (RH) waste packages. 13 refs., 8 tabs

  1. HVAC fault tree analysis for WIPP integrated risk assessment

    International Nuclear Information System (INIS)

    Kirby, P.; Iacovino, J.

    1990-01-01

    In order to evaluate the public health risk from operation of the Waste Isolation Pilot Plant (WIPP) due to potential radioactive releases, a probabilistic risk assessment of waste handling operations was conducted. One major aspect of this risk assessment involved fault tree analysis of the plant heating, ventilation, and air conditioning (HVAC) systems, which comprise the final barrier between waste handling operations and the environment. 1 refs., 1 tab

  2. Identification of issues relevant to the first recertification of WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Lawrence E. [Environmental Evaluation Group, Albuquerque, NM (United States); Silva, Matthew K. [Environmental Evaluation Group, Albuquerque, NM (United States); Channell, James K. [Environmental Evaluation Group, Albuquerque, NM (United States)

    2002-09-30

    One goal of the WIPP Land Withdrawal Act was to assure the safe disposal of the nation’s defense transuranic waste into a deep repository in southeast New Mexico. The governing legislation required the U.S. Department of Energy (DOE) to provide to the U.S. Environmental Protection Agency (EPA) analyses of the anticipated performance of the repository. Disposal operations could not begin until the EPA determined that the project demonstrated compliance with EPA Standards (40 CFR 191) and EPA Criteria (40 CFR 194) for such disposal. The Land Withdrawal Act inherently recognized that the EPA Certification would have to rely on best available knowledge at the time when the application was submitted. The Act also recognized that after the initial certification of WIPP and start of disposal operations, operating experience and ongoing research would result in new technical and scientific information. Thus, the legislation requires recertification of the WIPP every five years, following the first receipt of waste. This report updates issues that the Environmental Evaluation Group (EEG) considers important as the Department of Energy (DOE) works towards the first recertification. These issues encompass a variety of technical areas including actinide solubility, fluid injection scenarios, solution mining, Culebra flow and transport, spallings modeling, and non-random waste emplacement. Given the 24,000-year half life of 239Pu, understanding the characteristics of plutonium in the WIPP environment is obviously important to the validity of long-term performance assessment of the repository. Some uncertainty remains in the understanding of the persistence of higher oxidation states because of reliance on modeling (with its associated assumptions) and limited experimental results. The EEG recommends additional experimental work towards parameters for a proposed conceptual kinetic model of plutonium solubility. In addition, the EEG recommends an intrusion scenario

  3. The WIPP transportation system -- ''Safer than any other''

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially designed trailer, a lightweight tractor, the DOE TRANSCOM satellite-based vehicle tracking system, and uniquely qualified and highly trained drivers. The DOE has demonstrated that this system is ready to transport the TRU waste to the WIPP site efficiently and safely. Since the system was put in place in November 1988, it has been repeatedly upgraded and enhanced to incorporate additional safety measures. In June of 1989, the National Academy of Sciences (NAS) reviewed the transportation system and concluded that ''the system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels'' (emphasis added). The NAS conclusion was made before the DOE implemented the Enhanced Driver Training Course for carrier drivers. The challenge facing the DOE was to examine the transportation system objectively and determine what additional improvements could be made to further enhance safety

  4. WIPP gets thumbs up; Ward Valley time runs out

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    Legislation passed in late September clears the way for the Department of Energy to begin shipment of national defense transuranic (TRU) radioactive waste to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, NM, as early as November 1997. On September 23, President Clinton signed the Fiscal Year 1997 Defense Authorization Bill, which contained amendments to the 1992 WIPP Land Withdrawal Act. The implementation of the law will help the DOE in its cleanup sites nationwide, and will enhance public health and safety by providing for the disposal of the waste in a 2150-ft underground salt formation, far away from population centers. Key components of the legislation include the following: (1) The US Environmental Protection Agency (EPA) will continue as primary regulator of WIPP. (2) The EPA will have one year to review the Compliance Certification Application, which the DOE was to submit by October 31, 1996. Upon EPA certification (expected in October 1997), the DOE will begin shipping transuranic waste in November 1997. (3) A six-month waiting period for waste shipments has been removed (previously, the DOE was required to wait 180 days after the Energy Secretary's decision to begin disposal operations). (4) New Mexico will receive $20 million immediately, and annually for 14 years, with the funds to be used for infrastructure and road improvements in the state

  5. A coupled mechanical/hydrologic model for WIPP shaft seals

    International Nuclear Information System (INIS)

    Ehgartner, B.

    1991-06-01

    Effective sealing of the Waste Isolation Pilot Plant (WIPP) shafts will be required to isolate defense-generated transuranic wastes from the accessible environment. Shafts penetrate water-bearing hard rock formations before entering a massive creeping-salt formation (Salado) where the WIPP is located. Short and long-term seals are planned for the shafts. Short-term seals, a composite of concrete and bentonite, will primarily be located in the hard rock formations separating the water-bearing zones from the Salado Formation. These seals will limit water flow to the underlying long-term seals in the Salado. The long-term seals will consist of lengthly segments of initially unsaturated crushed salt. Creep closure of the shaft will consolidate unsaturated crushed salt, thereby reducing its permeability. However, water passing through the upper short-term seals and brine inherent to the salt host rock itself will eventually saturate the crushed salt and consolidation could be inhibited. Before saturating, portions of the crushed salt in the shafts are expected to consolidate to a permeability equivalent to the salt host rock, thereby effectively isolating the waste from the overlying water-bearing formations. A phenomenological model is developed for the coupled mechanical/hydrologic behavior of sealed WIPP shafts. The model couples creep closure of the shaft, crushed salt consolidation, and the associated reduction in permeability with Darcy's law for saturated fluid flow to predict the overall permeability of the shaft seal system with time. 17 refs., 6 figs., 1 tab

  6. A comparison of real-time radiography results and visual characterization results with emphasis on WIPP WAC and TRAMPAC compliance issues

    International Nuclear Information System (INIS)

    Hailey, S.M.

    1994-01-01

    Visual characterization provides a means of confirming the real-time radiography (RTR) certification process and process knowledge. RTR and visual characterization have been conducted on thirty-three drums containing transuranic (TRU) waste in support of the Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP) at the Idaho National Engineering Laboratory. Argonne National Laboratory - West (ANL-W) detected a small can of liquid in one of these drums during the visual examination, resulting in a WIPP Waste Acceptance Criteria (WIPP-WAC) miscertification. The remaining thirty-two drums were certified correctly by the RTR system at the Stored Waste Examination Pilot Plant (SWEPP) for WIPP-WAC and TRUPACT-II Authorized Methods for Payload Control (TRAMPAC) requirements. TRAMPAC contains restrictions on the weights of specific materials allowed in the waste, based on the shipping category. Items on the restricted list for a given shipping category are allowed in quantities less than 1 percent of the weight of the waste. RTR can estimate the weights of certain broad categories in homogeneous waste forms, however, the capability to estimate weights at the 1 percent level is not presently realistic. Process knowledge forms the basis of conformance to these weight requirements. Visual characterization suggests process knowledge is not completely adequate at this level

  7. Radioactive waste disposal: Waste isolation pilot plants (WIPP). (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-09-01

    The bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, and examine research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in separate bibliographies. (Contains a minimum of 228 citations and includes a subject term index and title list.)

  8. Leveraging Radioactive Waste Disposal at WIPP for Science

    Science.gov (United States)

    Rempe, N. T.

    2008-12-01

    Salt mines are radiologically much quieter than other underground environments because of ultra-low concentrations of natural radionuclides (U, Th, and K) in the host rock; therefore, the Waste Isolation Pilot Plant (WIPP), a government-owned, 655m deep geologic repository that disposes of radioactive waste in thick salt near Carlsbad, New Mexico, has for the last 15 years hosted highly radiation-sensitive experiments. Incidentally, Nature started her own low background experiment 250ma ago, preserving viable bacteria, cellulose, and DNA in WIPP salt. The Department of Energy continues to make areas of the WIPP underground available for experiments, freely offering its infrastructure and access to this unique environment. Even before WIPP started disposing of waste in 1999, the Room-Q alcove (25m x 10m x 4m) housed a succession of small experiments. They included development and calibration of neutral-current detectors by Los Alamos National Laboratory (LANL) for the Sudbury Neutrino Observatory, a proof-of-concept by Ohio State University of a flavor-sensitive neutrino detector for supernovae, and research by LANL on small solid- state dark matter detectors. Two currently active experiments support the search for neutrino-less double beta decay as a tool to better define the nature and mass of the neutrino. That these delicate experiments are conducted in close vicinity to, but not at all affected by, megacuries of radioactive waste reinforces the safety argument for the repository. Since 2003, the Majorana collaboration is developing and testing various detector designs inside a custom- built clean room in the Room-Q alcove. Already low natural background readings are reduced further by segmenting the germanium detectors, which spatially and temporally discriminates background radiation. The collaboration also demonstrated safe copper electro-forming underground, which minimizes cosmogenic background in detector assemblies. The largest currently used experimental

  9. 20 CFR 669.130 - What unit within the Department administers the National Farmworker Jobs Program funded under WIA...

    Science.gov (United States)

    2010-04-01

    ... the National Farmworker Jobs Program funded under WIA section 167? 669.130 Section 669.130 Employees' Benefits EMPLOYMENT AND TRAINING ADMINISTRATION, DEPARTMENT OF LABOR NATIONAL FARMWORKER JOBS PROGRAM UNDER... the Division of Seasonal Farmworker Programs (DSFP), or its successor organization, within the...

  10. Basic data report for drillhole ERDA 9 (Waste Isolation Pilot Plant WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    ERDA 9 was drilled in eastern Eddy County, New Mexico, to investigate and test salt beds for the disposal of nuclear wastes. The hole was placed near the SE corner of section 20, T22S,R31E. It was drilled between April 28 and June 4, 1976, to a depth of 2889 ft (measured from a kelly bushing altitude of 3,420.4 ft MSL). The borehole encountered, from top to bottom, Holocene deposits (including artificial fill) of 22 ft, the Pleistocene Mescalero Caliche (5 ft) and Gatuna Formation (27 ft), 9 ft of the Triassic Santa Rosa Sandstone, and 487 ft of the Dewey Lake Red Beds, 290 ft of the Rustler Formation, 1976 ft of the Salado Formation and 53 ft of the Castile Formation, all of Permian age. Cuttings were collected at 5-ft intervals for the land surface to a depth of 1090 ft, and consecutive cores were taken to a depth of 2876.6 ft. A suite of wireline geophysical logs was run the full length of the borehole to measure distribution of radioactive elements and hydrogen, and variations in rock density and elastic velocity. On the basis of the borehole findings and related hydrological and geophysical programs, the site was judged suitable to pursue the extensive geological characterization program which followed. The core from ERDA 9 provided a suite of samples extensively tested for rock mechanics, physical properties, and mineralogy. Drill-stem tests in ERDA 9 indicated no significant fluids or permeability in the Salado beds of interest. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  11. Origin of the brines near WIPP from the drill holes ERDA-6 and WIPP-12 based on stable isotope concentrations of hydrogen and oxygen

    International Nuclear Information System (INIS)

    Spiegler, P.; Updegraff, D.

    1983-03-01

    Pathways which might alter the isotopic compositions of deuterium and oxygen-18 meteoric water, seawaters, and in hydration waters in gypsum to the isotopic compositions of brines encountered at ERDA-6 and WIPP-12 are discussed. Present geologic conditions do not favor the alteration of the isotopic compositions of waters that exist near the WIPP site to those of the brines by these pathways. It is concluded that the brines encountered at ERDA-6 and WIPP-12 are probably derived from ancient ocean waters that have been isotopically enriched in oxygen-18 by exchange interaction with rock. The dehydration of gypsum as a process of origin of these brines cannot be ruled out

  12. Proposed waste isolation pilot project (WIPP) and impacts in the state of New Mexico: a socio-economic analysis. Final report

    International Nuclear Information System (INIS)

    Cummings, R.D.; Burness, H.S.; Norton, R.D.

    1981-04-01

    This document is a final report for research conducted concerning the socio-economic impacts in the State of New Mexico that might attend the construction and operation of the proposed Waste Isolation Pilot Plant (WIPP). The proposed site for the WIPP, known as the Los Medanos site, is in Southeastern New Mexico's Eddy County, some 25 miles east of Carlsbad, New Mexico and some 40 miles from Hobbs, New Mexico, in adjacent Lea County. The purpose as set out in the US Department of Energy's environmental impact statements is for storage of TRU waste from the US defense program and the construction of a research and development area for experiments concerning the isolation of all types of nuclear waste in salt. The intended purpose of the study is to identify, measure (when possible) and assess the range of potential socio-economic impacts in the State that may be attributable to the WIPP. Every effort has been made by the authors to approach this task in an objective manner. In efforts to provide an objective analysis of the WIPP, however, particular attention was required in providing a comprehensive review of potential impacts. This means that however unlikely an impact might seem, the authors have purposely avoided pre-judging the potential magnitude of the impact and have applied their best efforts to measure it. On the other hnd, this study is not intended to provide a definitive calculation regarding the net balance of WIPP-related benefits and costs. To help ensure objectivity, two advisory boards, Technical Advisory Board and Public Advisory Board, were formed at the outset of the project for the purpose of providing periodic reviews of research efforts

  13. Virginia Solar Pathways Project: Economic Study of Utility-Administered Solar Programs: Soft Costs, Community Solar, and Tax Normalization Considerations

    Energy Technology Data Exchange (ETDEWEB)

    Reiter, Emerson [National Renewable Energy Lab. (NREL), Golden, CO (United States); Lowder, Travis [National Renewable Energy Lab. (NREL), Golden, CO (United States); Mathur, Shivani [National Renewable Energy Lab. (NREL), Golden, CO (United States); Mercer, Megan [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-06-23

    This report presents economic considerations for solar development in support of the Virginia Solar Pathways Project (VSPP), an effort funded by the U.S. Department of Energy (DOE) SunShot Initiative that seeks to develop a collaborative utility-administered solar strategy for the Commonwealth of Virginia. The results presented are intended to be considered alongside the results of other studies conducted under the VSPP that evaluate the impacts of solar energy on the electric distribution, transmission, and generation systems in Virginia.

  14. Hanford Tank Waste to WIPP - Maximizing the Value of our National Repository Asset

    International Nuclear Information System (INIS)

    Tedeschi, Allan R.; Wheeler, Martin

    2013-01-01

    Preplanning scope for the Hanford tank transuranic (TRU) waste project was authorized in 2013 by the Department of Energy (DOE) Office of River Protection (ORP) after a project standby period of eight years. Significant changes in DOE orders, Hanford contracts, and requirements at the Waste Isolation Pilot Plant (WIPP) have occurred during this time period, in addition to newly implemented regulatory permitting, re-evaluated waste management strategies, and new commercial applications. Preplanning has identified the following key approaches for reactivating the project: qualification of tank inventory designations and completion of all environmental regulatory permitting; identifying program options to accelerate retrieval of key leaking tank T-111; planning fully compliant implementation of DOE Order 413.3B, and DOE Standard 1189 for potential on-site treatment; and re-evaluation of commercial retrieval and treatment technologies for better strategic bundling of permanent waste disposal options

  15. Tracer tests performed in the field for WIPP in southeastern New Mexico

    International Nuclear Information System (INIS)

    Gonzalez, D.D.; Hill, L.R.

    1979-01-01

    A two-well recirculating tracer test began in October, 1979, to define as accurately as possible the hydraulic character of a fractured carbonate aquifer, the Culebra dolomite member of the Rustler Formation at the WIPP site in Eddy and Lee Counties, New Mexico. The Culebra dolomite overlies a zone planned for isolation of transuranic contaminated waste generated by the United States defense programs. The storage zone of the proposed facility is in nearly pure halite and about 1400 feet (427 meters) below the Culebra dolomite, the most likely pathway for the migration of radionuclides to the biosphere in the event the repository is breached by groundwater. Included in the definition of the hydraulic character of the Culebra aquifer are natural groundwater velocities, aquifer porosity and components of dispersivity. The proposed tracer test using sodium benzoate, a homologous series of chlorofluoromethanes and pentafluorobenzoic acid as tracers is described. Results of the test will be reported at a later date

  16. Hanford Tank Waste to WIPP - Maximizing the Value of our National Repository Asset

    Energy Technology Data Exchange (ETDEWEB)

    Tedeschi, Allan R.; Wheeler, Martin

    2013-11-11

    Preplanning scope for the Hanford tank transuranic (TRU) waste project was authorized in 2013 by the Department of Energy (DOE) Office of River Protection (ORP) after a project standby period of eight years. Significant changes in DOE orders, Hanford contracts, and requirements at the Waste Isolation Pilot Plant (WIPP) have occurred during this time period, in addition to newly implemented regulatory permitting, re-evaluated waste management strategies, and new commercial applications. Preplanning has identified the following key approaches for reactivating the project: qualification of tank inventory designations and completion of all environmental regulatory permitting; identifying program options to accelerate retrieval of key leaking tank T-111; planning fully compliant implementation of DOE Order 413.3B, and DOE Standard 1189 for potential on-site treatment; and re-evaluation of commercial retrieval and treatment technologies for better strategic bundling of permanent waste disposal options.

  17. On the road to WIPP: Or remote packaging of transuranic waste

    International Nuclear Information System (INIS)

    Ledbetter, J.M.; Field, L.R.

    1994-01-01

    At the Los Alamos National Laboratory (LANL) Hot Cell facility, highly productive programs in reactor research spanning three decades have generated appreciable quantities of legacy waste. Hot cell capability had become virtually useless due to the storage of this waste. As a result of concentrated efforts by LANL staff, in cooperation with Westinghouse Waste Isolation Pilot Plant (WIPP), a solution was arrived at that allowed the facility to become productive once again. Equipment has been designed and fabricated to remotely handle 55-gal. waste drums, load waste canisters, perform canister weld closure, leak test welds, grapple the waste canister and transport the canister to an interim storage site. It is our contention that the technology and acquired equipment produced from this effort should be used to further benefit other DOE sites

  18. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP). Attachments: Volume 4 of 4

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    Volume IV contains the following attachments for Module IV: VOC monitoring plan for bin-room tests (Appendix D12); bin emission control and VOC monitoring system drawings; bin scale test room ventilation drawings; WIPP supplementary roof support system, underground storage area, room 1, panel 1, DOE/WIPP 91-057; and WIPP supplementary roof support system, room 1, panel 1, geotechnical field data analysis bi-annual report, DOE/WIPP 92-024.

  19. 40 CFR 147.2650 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ..., Headquarters, 401 M St., SW., room E1101A, Washington, DC 20460; or the National Archives and Records.... (2) Letter from the Governor of the Commonwealth of Puerto Rico requesting the program, dated July 16... Injection Control Program, dated with the effective date October 30, 1986. [57 FR 33446, July 29, 1992] ...

  20. The WIPP RCRA Part B permit application for TRU mixed waste disposal

    International Nuclear Information System (INIS)

    Johnson, J.E.

    1995-01-01

    In August 1993, the New Mexico Environment Department (NMED) issued a draft permit for the Waste Isolation Pilot Plant (WIPP) to begin experiments with transuranic (TRU) mixed waste. Subsequently, the Department of Energy (DOE) decided to cancel the on-site test program, opting instead for laboratory testing. The Secretary of the NMED withdrew the draft permit in 1994, ordering the State's Hazardous and Radioactive Waste Bureau to work with the DOE on submittal of a revised permit application. Revision 5 of the WIPP's Resource Conservation and Recovery Act (RCRA) Part B Permit Application was submitted to the NMED in May 1995, focusing on disposal of 175,600 m 3 of TRU mixed waste over a 25 year span plus ten years for closure. A key portion of the application, the Waste Analysis Plan, shifted from requirements to characterize a relatively small volume of TRU mixed waste for on-site experiments, to describing a complete program that would apply to all DOE TRU waste generating facilities and meet the appropriate RCRA regulations. Waste characterization will be conducted on a waste stream basis, fitting into three broad categories: (1) homogeneous solids, (2) soil/gravel, and (3) debris wastes. Techniques used include radiography, visually examining waste from opened containers, radioassay, headspace gas sampling, physical sampling and analysis of homogeneous wastes, and review of documented acceptable knowledge. Acceptable knowledge of the original organics and metals used, and the operations that generated these waste streams is sufficient in most cases to determine if the waste has toxicity characteristics, hazardous constituents, polychlorinated biphenyls (PBCs), or RCRA regulated metals

  1. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Chapter E, Appendix E1, Chapter L, Appendix L1: Volume 12, Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP) Project was authorized by the US Department of Energy 5 (DOE) National Security and Military Applications of the Nuclear Energy Authorization Act of 1980 (Public Law 96-164). Its legislative mandate is to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from national defense programs and activities. To fulfill this mandate, the WIPP facility has been designed to perform scientific investigations of the behavior of bedded salt as a repository medium and the interactions between the soft and radioactive wastes. In 1991, DOE proposed to initiate a experimental Test Phase designed to demonstrate the performance of the repository. The Test Phase activities involve experiments using transuranic (TRU) waste typical of the waste planned for future disposal at the WIPP facility. Much of this TRU waste is co-contaminated with chemical constituents which are defined as hazardous under HWMR-7, Pt. II, sec. 261. This waste is TRU mixed waste and is the subject of this application. Because geologic repositories, such as the WIPP facility, are defined under the Resource Conservation and Recovery Act (RCRA) as land disposal facilities, the groundwater monitoring requirements of HWMR-7, PLV, Subpart X, must be addressed. HWMR-7, Pt. V, Subpart X, must be addressed. This appendix demonstrates that groundwater monitoring is not needed in order to demonstrate compliance with the performance standards; therefore, HWMR-7, Pt.V, Subpart F, will not apply to the WIPP facility.

  2. Evaluation of proposed panel closure modifications at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Lawrence E.; Silva, Matthew K.; Channell, James K.; Abel, John F.; Morgan, Dudley R.

    2001-12-31

    A key component in the design of the WIPP repository is the installation of concrete structures as panel seals in the intake and exhaust drifts after a panel has been filled with waste containers. As noted in the EPA final rule, the panel seal closure system is intended to block brine flow between the waste panels at the WIPP. On April 17, 2001, the DOE proposed seven modifications to the EPA concerning the design of the panel closure system. EPA approval of these modifications is necessary since the details of the panel design are specified in EPA’s final rule as a condition for WIPP certification. However, the EPA has not determined whether a rulemaking would be required for these proposed design modifications. On September 4, 2001, the DOE withdrew the request, noting that it would be resubmitted on a future date. The Environmental Evaluation Group (EEG) contracted with two engineers, Dr. John Abel and Dr. Rusty Morgan, to evaluate the proposed modifications. The EEG has accepted the conclusions and recommendations from these two experts: 1) replacement of Salado Mass Concrete with a generic salt-based concrete; 2) replacement of the explosion wall with a construction wall; 3) replacement of freshwater grouting with salt-based grouting; 4) option to allow surface or underground mixing; and 5) option to allow up to one year for completion of closure. The proposed modification to allow local carbonate river rock as aggregate is acceptable pending demonstration that no problems will exist in the resulting concrete. The proposed modification to give the contractor discretion in removal of steel forms is not supported. Instead, several recommendations are made to specifically reduce the number of forms left, thereby reducing potential migration pathways.

  3. A regional water balance for the WIPP site and surrounding area

    International Nuclear Information System (INIS)

    Hunter, R.L.

    1987-01-01

    A water balance or budget is developed as an accounting of the components of a closed hydrologic system. In the WIPP study area, water-budget techniques have previously been used to compute leakage from Lake Avalon and from potash refinery spoil ponds. A general expression for a closed hydrologic system is presented. In a developed area like the WIPP region, the water budget must include many usage factors, such as municipal or industrial pumpage. In the WIPP water-budget study area, inflows are precipitation, surface- and ground-water inflow, and the artificial addition of surface and ground water. Outflows are surface runoff, evaporation and transpiration, and ground-water outflow. Changes in storage in the WIPP region have also been documented. The WIPP water balance described here is based on a combination of long-term averages and figures for 1980. 12 refs., 5 figs., 1 tab

  4. Sandia Review of High Bridge Associates Report: Comparison of Plutonium Disposition Alternatives: WIPP Diluted Plutonium Storage and MOX Fuel Irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Shoemaker, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Park, HeeHo Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brady, Patrick Vane [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rechard, Robert P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-08-01

    The subject report from High Bridge Associates (HBA) was issued on March 2, 2016, in reaction to a U.S. Department of Energy (DOE) program decision to pursue down-blending of surplus Pu and geologic disposal at the Waste Isolation Pilot Plant (WIPP). Sandia National Laboratories was requested by the DOE to review the technical arguments presented in the HBA report. Specifically, this review is organized around three technical topics: criticality safety, radiological release limits, and thermal impacts. Questions raised by the report pertaining to legal and regulatory requirements, safeguards and security, international agreements, and costing of alternatives, are beyond the scope of this review.

  5. Basic data report for drillhole ERDA 6 (Waste Isolation Pilot Plant - WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    ERDA 6 was drilled in eastern Eddy County, New Mexico, to investigate a candidate site for a nuclear waste repository. The site was subsequently rejected on the basis of geological data. ERDA 6 was drilled in the NE 1/4 SE 1/4, section 35, T21S,R31E. The borehole encountered, from top to bottom, 17 ft of Quaternary deposits, 55 ft of the Triassic Santa Rosa Sandstone, 466 ft of the Dewey Lake Red Beds, 273 ft of the Rustler Formation, 1785.5 ft of the Salado Formation and 374.5 ft of the upper Castile Formation, all of Permian age. Cores or drill cuttings were taken throughout the hole. A suite of wireline geophysical logs was run to a depth of 883 ft to facilitate the recognition and correlation of rock units, to assure identification of major lithologies and to provide depth determinations independent of drill-pipe measurements. The site at ERDA 6 was rejected because the structure of the lower Salado and the Castile is too severe to develop a repository along a single set of beds. The borehole also intersected a reservoir of pressurized brine and gas at about 2710'. The pore volume for the reservoir was estimated to be in the range from about 200,000 to about 2 million barrels. ERDA 6 was re-entered in 1981 by the Department of Energy (DOE) for the purpose of further testing the brine reservoir. Those tests are described in separate reports by the DOE and its contractors. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes.

  6. Preoperational radiation surveillance of the WIPP project by EEG during 1992

    International Nuclear Information System (INIS)

    Kenney, J.W.

    1994-02-01

    The purpose of the EEG preoperational monitoring program is to document the existing concentrations of selected radionuclides in various environmental media collected from the vicinity of the WIPP site to provide a basis of comparison of any effects of future WT-PP operations. The basic methodology for conducting environmental surveillance both on-site and off-site was outlined by Spiegler (1984). This report represents a continuation of the EEG baseline data beginning in 1985, previously reported in EEG-43, EEG-47, EEG-49 and EEG-51. Such radionuclide baseline data are important in order to determine whether future WIPP operations with radioactive waste have affected concentrations of these radionuclides in the environment. EEG data are consistent with similar environmental measurements obtained by DOE beginning in 1985. Since late 1985, the EEG has collected or received as split samples 2 443 air filters with particulates, 202 water samples, 16 biota samples and 13 soil/sediment samples. A total of 5,946 specific radionuclide analyses have been performed on these samples. As reported previously by EEG (EEG-43, EEG-47, EEG-49 and EEG-51), observed concentrations of U-238 daughter radionuclides were not in equilibrium with the parent radionuclide in water samples. This observation is consistent with different radionuclide mobility in the environment. In a notice of proposed rule making for 40 CFR 141 (US EPA 1991), the Environmental Protection Agency (EPA) National Primary Drinking Water Regulations reflect this in the calculated activity-to-mass ratio of 1.3 pCi/μg of uranium using a geometric mean of the U-234:U-238 ratio in water supplies of 2.7. Ra-226 and Ra- 228 were reported in a number of water samples in concentrations similar to those previously published by EEG and DOE

  7. Structural evaluation of WIPP disposal room raised to clay seam G

    International Nuclear Information System (INIS)

    Park, Byoung Yoon; Holland, John F.

    2007-01-01

    An error was discovered in the ALGEBBRA script used to calculate the disturbed rock zone around the disposal room and the shear failure zone in the anhydrite layers in the original version. To correct the error, a memorandum of correction was submitted according to the Waste Isolation Pilot Plant (WIPP) Quality Assurance program. The recommended course of action was to correct the error, to repeat the post-process, and to rewrite Section 7.4, 7.5, 8, and Appendix B in the original report. The sections and appendix revised by the post-process using the corrected ALGEBRA scripts are provided in this revision. The original report summarizes a series of structural calculations that examine effects of raising the WIPP repository horizon from the original design level upward 2.43 meters. Calculations were then repeated for grid changes appropriate for the new horizon raised to Clay Seam G. Results are presented in three main areas: (1) Disposal room porosity, (2) Disturbed rock zone characteristics, and (3) Anhydrite marker bed failure. No change to the porosity surface for the compliance re-certification application is necessary to account for raising the repository horizon, because the new porosity surface is essentially identical. The disturbed rock zone evolution and devolution are charted in terms of a stress invariant criterion over the regulatory period. This model shows that the propagation of the DRZ into the surrounding rock salt does not penetrate through MB 139 in the case of both the original horizon and the raised room. Damaged salt would be expected to heal in nominally 150 years. The shear failure does not occur in either the upper or lower anhydrite layers at the moment of excavation, but appears above and below the middle of the pillar one day after the excavation. The damaged anhydrite is not expected to heal as the salt in the DRZ is expected to

  8. Basic data report for drillhole ERDA 6 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    ERDA 6 was drilled in eastern Eddy County, New Mexico, to investigate a candidate site for a nuclear waste repository. The site was subsequently rejected on the basis of geological data. ERDA 6 was drilled in the NE 1/4 SE 1/4, section 35, T21S,R31E. The borehole encountered, from top to bottom, 17 ft of Quaternary deposits, 55 ft of the Triassic Santa Rosa Sandstone, 466 ft of the Dewey Lake Red Beds, 273 ft of the Rustler Formation, 1785.5 ft of the Salado Formation and 374.5 ft of the upper Castile Formation, all of Permian age. Cores or drill cuttings were taken throughout the hole. A suite of wireline geophysical logs was run to a depth of 883 ft to facilitate the recognition and correlation of rock units, to assure identification of major lithologies and to provide depth determinations independent of drill-pipe measurements. The site at ERDA 6 was rejected because the structure of the lower Salado and the Castile is too severe to develop a repository along a single set of beds. The borehole also intersected a reservoir of pressurized brine and gas at about 2710'. The pore volume for the reservoir was estimated to be in the range from about 200,000 to about 2 million barrels. ERDA 6 was re-entered in 1981 by the Department of Energy (DOE) for the purpose of further testing the brine reservoir. Those tests are described in separate reports by the DOE and its contractors. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  9. A Cost-Effectiveness Evaluation Approach to Improving Resource Allocations for School Systems. Administering for Change Program. A Professional Paper.

    Science.gov (United States)

    Temkin, Sanford

    This dissertation begins with a description of some methods employed in making public-sector resource-allocation decisions, with conclusions on the appropriateness of each method for evaluating the ongoing programs of a school system. The second section has been rewritten and published as "A Comprehensive Theory of Cost-Effectiveness" (EA 002…

  10. 40 CFR 147.2250 - State-administered program-Class I, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... Department of Health, Division of Environmental Health, Bureau of Water Pollution Control, to EPA Region VIII..., 1982; (3) Addendum to Underground Injection Control Program, Attorney General's Statement signed by..., III, IV, and V wells. 147.2250 Section 147.2250 Protection of Environment ENVIRONMENTAL PROTECTION...

  11. PASS: a component of Desk Top PA for the WIPP

    International Nuclear Information System (INIS)

    Crawford, M.B.; Wilmot, R.D.; Galson, D.A.; Swift, P.N.; Fewell, M.E.

    1998-01-01

    There is a growing recognition internationally of the need to demonstrate comprehensiveness in order to build confidence in performance assessments (PAs) for radioactive waste disposal projects. This has resulted in a number of methodologies being developed to formalize the process of defining and documenting the decision basis that underlies a PA. Such methodologies include process influence diagrams and the rock engineering system (RES) matrix. However, these methodologies focus mainly on the conceptualization of the disposal system and do not provide a ready framework to document the decisions behind the model development and parameterization of the PA system. The Performance Assessment Support System (PASS) is a flexible electronic tool designed to increase the transparency and traceability of decision making in the entire PA process. An application of PASS has been developed for the Waste Isolation Pilot Plant (WIPP) where it forms an important component of Desk Top PA, a PC-based PA computational environment under development at Sandia National Laboratories to document, plan, and support management decisions and to assess performance for the WIPP recertification process. This desk-top PA environment is also aimed at providing scientifically-based decision support for assessing the performance of nuclear and hazardous waste management and environmental clean-up systems

  12. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    International Nuclear Information System (INIS)

    Betsill J, David; Elkins, Ned Z.; Wu, Chuan-Fu; Mewhinney, James D.; Aamodt, Paul

    2000-01-01

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ''The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic

  13. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    BETSILL,J. DAVID; ELKINS,NED Z.; WU,CHUAN-FU; MEWHINNEY,JAMES D.; AAMODT,PAUL

    2000-01-27

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only

  14. The waste isolation pilot plant regulatory compliance program

    International Nuclear Information System (INIS)

    Mewhinney, J.A.; Kehrman, R.F.

    1996-01-01

    The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

  15. Tracing early breccia pipe studies, Waste Isolation Pilot Plant, southeastern New Mexico: A study of the documentation available and decision-making during the early years of WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Power, D.W. [HC 12, Anthony, TX (United States)

    1996-01-01

    Breccia pipes in southeastern New Mexico are local dissolution-collapse features that formed over the Capitan reef more than 500,000 years ago. During early site studies for the Waste Isolation Pilot Plant (WIPP), the threat to isolation by these features was undetermined. Geophysical techniques, drilling, and field mapping were used beginning in 1976 to study breccia pipes. None were found at the WIPP site, and they are considered unlikely to be a significant threat even if undetected. WIPP documents related to breccia pipe studies were assembled, inspected, and analyzed, partly to present a history of these studies. The main objective is to assess how well the record reflects the purposes, results, and conclusions of the studies from concept to decision-making. The main record source was the Sandia WIPP Central File (SWCF). Early records (about 1975 to 1977) are very limited, however, about details of objectives and plans predating any investigation. Drilling programs from about 1977 were covered by a broadly standardized statement of work, field operations plan, drilling history, and basic data report. Generally standardized procedures for peer, management, and quality assurance review were developed during this time. Agencies such as the USGS conducted projects according to internal standards. Records of detailed actions for individual programs may not be available, though a variety of such records were found in the SWCF. A complete written record cannot be reconstructed. With persistence, a professional geologist can follow individual programs, relate data to objectives (even if implied), and determine how conclusions were used in decision-making. 83 refs.

  16. Tracing early breccia pipe studies, Waste Isolation Pilot Plant, southeastern New Mexico: A study of the documentation available and decision-making during the early years of WIPP

    International Nuclear Information System (INIS)

    Power, D.W.

    1996-01-01

    Breccia pipes in southeastern New Mexico are local dissolution-collapse features that formed over the Capitan reef more than 500,000 years ago. During early site studies for the Waste Isolation Pilot Plant (WIPP), the threat to isolation by these features was undetermined. Geophysical techniques, drilling, and field mapping were used beginning in 1976 to study breccia pipes. None were found at the WIPP site, and they are considered unlikely to be a significant threat even if undetected. WIPP documents related to breccia pipe studies were assembled, inspected, and analyzed, partly to present a history of these studies. The main objective is to assess how well the record reflects the purposes, results, and conclusions of the studies from concept to decision-making. The main record source was the Sandia WIPP Central File (SWCF). Early records (about 1975 to 1977) are very limited, however, about details of objectives and plans predating any investigation. Drilling programs from about 1977 were covered by a broadly standardized statement of work, field operations plan, drilling history, and basic data report. Generally standardized procedures for peer, management, and quality assurance review were developed during this time. Agencies such as the USGS conducted projects according to internal standards. Records of detailed actions for individual programs may not be available, though a variety of such records were found in the SWCF. A complete written record cannot be reconstructed. With persistence, a professional geologist can follow individual programs, relate data to objectives (even if implied), and determine how conclusions were used in decision-making. 83 refs

  17. Relationship between Self-Administered Cues and Rehabilitation Outcomes in Individuals with Aphasia: Understanding Individual Responsiveness to a Technology-Based Rehabilitation Program.

    Science.gov (United States)

    Des Roches, Carrie A; Mitko, Annette; Kiran, Swathi

    2017-01-01

    An advantage of rehabilitation administered on computers or tablets is that the tasks can be self-administered and the cueing required to complete the tasks can be monitored. Though there are many types of cueing, few studies have examined how participants' response to rehabilitation is influenced by self-administered cueing, which is cueing that is always available but the individual decides when and which cue to administer. In this study, participants received a tablet-based rehabilitation where the tasks were selfpaced and remotely monitored by a clinician. The results of the effectiveness of this study were published previously (Des Roches et al., 2015). The current study looks at the effect of cues on accuracy and rehabilitation outcomes. Fifty-one individuals with aphasia completed a 10-week program using Constant Therapy on an iPad targeted at improving language and cognitive deficits. Three questions were examined. The first examined the effect of cues on accuracy collapsed across time. Results showed a trend where the greater the cue use, the lower the accuracy, although some participants showed the opposite effect. This analysis divided participants into profiles based on cue use and accuracy. The second question examined how each profile differed in percent cue use and on standardized measures at baseline. Results showed that the four profiles were significantly different in frequency of cues and scores on WAB-R, CLQT, BNT, and ASHA-FACS, indicating that participants with lower scores on the standardized tests used a higher percentage of cues, which were not beneficial, while participants with higher scores on the standardized tests used a lower frequency of cues, which were beneficial. The third question examined how the relationship between cues and accuracy was affected by the course of treatment. Results showed that both more and less severe participants showed a decrease in cue use and an increase in accuracy over time, though more severe

  18. Chemistry of brines in salt from the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico: a preliminary investigation

    International Nuclear Information System (INIS)

    Stein, C.L.; Krumhansl, J.L.

    1986-03-01

    We present here analyses of macro- and microscopic (intracrystalline) brines observed within the WIPP facility and in the surrounding halite, with interpretations regarding the origin and history of these fluids and their potential effect(s) on long-term waste storage. During excavation, several large fluid inclusions were recovered from an area of highly recrystallized halite in a thick salt bed at the repository horizon (2150 ft below ground level). In addition, 52 samples of brine ''weeps'' were collected from walls of recently excavated drifts at the same stratigraphic horizon from which the fluid inclusion samples are assumed to have been taken. Analyses of these fluids show that they differ substantially in composition from the inclusion fluids and cannot be explained by mixing of the fluid inclusion populations. Finally, holes in the facility floor that filled with brine were sampled but with no stratographic control; therefore it is not possible to interpret the compositions of these brines with any accuracy, except insofar as they resemble the weep compositions but with greater variation in both K/Mg and Na/Cl ratios. However, the Ca and SO 4 values for the floor holes are relatively close to the gypsum saturation curve, suggesting that brines filling floor holes have been modified by the presence of gypsum or anhydrite, possibly even originating in one or more of the laterally continuous anhydrite units referred to in the WIPP literature as marker beds. In conclusion, the wide compositional variety of fluids found in the WIPP workings suggest that (1) an interconnected hydrologic system which could effectively transport radonuclides away from the repository does not exist; (2) brine migration studies and experiments must consider the mobility of intergranular fluids as well as those in inclusions; and (3) near- and far-field radionuclide migration testing programs need to consider a wide range of brine compositions rather than a few reference brines

  19. Increases in muscle strength and balance using a resistance training program administered via a telecommunications system in older adults.

    Science.gov (United States)

    Sparrow, David; Gottlieb, Daniel J; Demolles, Deborah; Fielding, Roger A

    2011-11-01

    Resistance training programs have been found to improve muscle strength, physical function, and depressive symptoms in middle-aged and older adults. These programs have typically been provided in clinical facilities, health clubs, and senior centers, which may be inconvenient and/or cost prohibitive for some older adults. The purpose of this study was to investigate the effectiveness of an automated telemedicine intervention that provides real-time guidance and monitoring of resistance training in the home. A randomized clinical trial in 103 middle-aged or older participants. Participants were assigned to use of a theory-driven interactive voice response system designed to promote resistance training (Telephone-Linked Computer-based Long-term Interactive Fitness Trainer; n = 52) or to an attention control (n = 51) for a period of 12 months. Measurements of muscle strength, balance, walk distance, and mood were obtained at baseline, 3, 6, and 12 months. We observed increased strength, improved balance, and fewer depressive symptoms in the intervention group than in the control group. Using generalized estimating equations modeling, group differences were statistically significant for knee flexion strength (p = .035), single-leg stance time (p = .029), and Beck Depression Inventory (p = .030). This computer-based telecommunications exercise intervention led to improvements in participants' strength, balance, and depressive symptoms. Because of their low cost and easy accessibility, computer-based interventions may be a cost-effective way of promoting exercise in the home.

  20. 1979 New Mexico legislative session: energy issues and legislation. [WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Barsumian, L.; Vandevender, S.G.

    1979-10-01

    This report is an account of the energy legislation and associated issues considered during the 1979 session of the 34th New Mexico Legislature. The session's major issue was the federal study of a proposed nuclear Waste Isolation Pilot Plant (WIPP) in New Mexico. A large proportion of time and effort was spent on resolving the state's formal position toward the federal project. However, other energy concerns were also significant even though they were neither as controversial nor as visible as the primary issue. The two most important laws enacted were the Radioactive Waste Consultation Act and the Radioactive Waste Transportation Act. The Legislature considered 47 other energy-related bills, of which 17 were enacted.

  1. Stochastic modelling of groundwater flow at the WIPP site

    International Nuclear Information System (INIS)

    Cliffe, K.A.; Jackson, C.P.

    1993-01-01

    A stochastic approach to modelling the groundwater flow in the vicinity of the WIPP site in New Mexico is described. A geostatistical model of the transmissivity of the Culebra dolomite was constructed on the basis of experimental measurements. The uncertainty in various quantities of interest in a repository performance assessment, such as the time to travel to the boundary of the model domain, were studied using a Monte-Carlo technique. The results indicate that conditioning the transmissivity on the measured values can lead to a significant reduction in uncertainty. The issue of validation of statistical models is also addressed. Several statistical tests were applied to the models and it is suggested that hypothesis testing can be a useful technique for validation

  2. WIPP Waste Characterization: Implementing Regulatory Requirements in the Real World

    International Nuclear Information System (INIS)

    Cooper Wayman, J.D.; Goldstein, J.D.

    1999-01-01

    It is imperative to ensure compliance of the Waste Isolation Pilot Project (WIPP) with applicable statutory and regulatory requirements. In particular, compliance with the waste characterization requirements of the Resource Conservation and Recovery Act (RCRA) and its implementing regulation found at 40 CFR Parts 262,264 and 265 for hazardous and mixed wastes, as well as those of the Atomic Energy Act of 1954, as amended, the Reorganization Plan No. 3 of 1970, the Nuclear Waste Policy Act of 1982, as amended, and the WIPP Land Withdrawal Act, as amended, and their implementing regulations found at 40 CFR Parts 191 and 194 for non-mixed radioactive wastes, are often difficult to ensure at the operational level. For example, where a regulation may limit a waste to a certain concentration, this concentration may be difficult to measure. For example, does the definition of transuranic waste (TRU) as 100 nCi/grain of alpha-emitting transuranic isotopes per gram of waste mean that the radioassay of a waste must show a reading of 100 plus the sampling and measurement error for the waste to be a TRU waste? Although the use of acceptable knowledge to characterize waste is authorized by statute, regulation and DOE Orders, its implementation is similarly beset with difficulty. When is a document or documents sufficient to constitute acceptable knowledge? What standard can be used to determine if knowledge is acceptable for waste characterization purposes? The inherent conflict between waste characterization regulatory requirements and their implementation in the real world, and the resolution of this conflict, will be discussed

  3. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2001-02-25

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  4. Performance assessment in support of compliance certification application for the WIPP project

    International Nuclear Information System (INIS)

    Jow, H.N.; Anderson, D.R.; Marietta, M.; Helton, J.; Basabilvazo, G.

    1998-03-01

    The Waste Isolation Pilot Plant (WIPP) is being developed by the US Department of Energy for the geologic (deep underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP (1) for such disposal was submitted to the US Environmental Protection Agency (EPA) in October, 1996, and is currently under review, with a decision anticipated in late 1997. An important component of the CCA is a performance assessment (PA) for the WIPP carried out by Sandia National Laboratories. The final outcome of the PA is a complementary cumulative distribution function (CCDF) for radionuclide releases from the WIPP to the accessible environment and an assessment of the confidence with which this CCDF can be estimated. This paper describes the computational process used to develop the CCDF. The results of uncertainty and sensitivity analysis are also presented

  5. Mineralogy in the Waste Isolation Pilot Plant (WIPP) facility stratigraphic horizon

    International Nuclear Information System (INIS)

    Stein, C.L.

    1985-09-01

    Forty-six samples were selected for this study from two cores, one extending 50 ft up through the roof of the WIPP facility and the other penetrating 50 ft below the facility floor. These samples, selected from approximately every other foot of core length, represent the major lithologies present in the immediate vicinity of the WIPP facility horizon: ''clean'' halite, polyhalitic halite, argillaceous halite, and mixed polyhalitic-argillaceous halite. Samples were analyzed for non-NaCl mineralogy by determining weight percents of water- and EDTA-insoluble residues, which were then identified by x-ray diffraction. In general, WIPP halite contains at most 5 wt % non-NaCl residue. The major mineral constituents are quartz, magnesite, anhydrite, gypsum, polyhalite, and clays. Results of this study confirm that, in previous descriptions of WIPP core, trace mineral quantities have been visually overestimated by approximately an order of magnitude. 9 refs., 5 figs., 5 tabs

  6. Geotechnical evaluation of the proposed WIPP site in southeast New Mexico

    International Nuclear Information System (INIS)

    Weart, W.D.

    1978-10-01

    The Department of Energy is proposing to demonstrate the acceptability of geologic disposal of radioactive waste by locating a Waste Isolation Pilot Plant (WIPP) in the salt beds 26 miles east of Carlsbad, New Mexico. The WIPP will serve as a permanent repository for defense generated transuranic contaminated waste and will also be used as a facility in which experiments and demonstrations with all radioactive waste types can be conducted. The present area being proposed for the WIPP is the second such location in the Delaware Basin for which new site data have been developed; the first site proved geologically unacceptable. Ecologic and socioeconomic aspects have been investigated and extensive geophysical, geological and hydrologic studies have been conducted to allow an evaluation of site acceptability. Geotechnical aspects of site characterization are examined. These studies are now sufficiently complete that the site can be recommended for further development of the WIPP

  7. Use of Performance Assessment in Support of Waste Isolation Pilot Plant (WIPP) Programmatic Activity Planning

    International Nuclear Information System (INIS)

    BASABILVAZO, GEORGE; JOW, HONG-NIAN; LARSON, KURT W.; MARIETTA, MELVIN G.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is being developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP for such disposal was submitted to the U.S. Environmental Protection Agency (EPA) in October 1996, and was approved by EPA in May 1998. In June 1998, two separate, but related, lawsuits were filed, one against DOE and one against EPA. On March 22, 1999, the court ruled in favor of DOE, and on March 26, 1999, DOE formally began disposal operations at the WIPP for non-mixed (non-hazardous) TRU waste. Before the WIPP can begin receiving mixed (hazardous) TRU waste, a permit from the State of New Mexico for hazardous waste disposal needs to be issued. It is anticipated that the State of New Mexico will issue a hazardous waste permit by November 1999. It is further anticipated that the EPA lawsuit will be resolved by July 1999. Congress (Public Law 102-579, Section 8(f)) requires the WIPP project to be recertified by the EPA at least as frequently as once every five years from the first receipt of TRU waste at the WIPP site. As part of the DOE's WIPP project recertification strategy, Sandia National Laboratories (SNL) has used systems analysis and performance assessment to prioritize its scientific and engineering research activities. Two 1998 analyses, the near-field systems analysis and the annual sensitivity analysis, are discussed here. Independently, the two analyses arrived at similar conclusions regarding important scientific activities associated with the WIPP. The use of these techniques for the recent funding allocations at SNL's WIPP project had several beneficial effects. It increased the level of acceptance among project scientists that management had fairly and credibly compared alternatives when making prioritization decisions. It improved the ability of SNL and its project sponsor, the Carlsbad Area Office of the DOE, to

  8. Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-01-01

    This volume contains Appendix D2, engineering design basis reports. Contents include: Design considerations for the waste hoist of the Waste Isolation Pilot Plant (WIPP); A site-specific study of wind and tornado probabilities at the WIPP Site in southeast New Mexico; Seismic evaluation report of underground facilities; and calculations for analysis of wind loads and tornado loads for WHB, seismic calculations, calculations for VOC-10 monitoring system, and for shaft at station A

  9. Hydraulic Characterization Activities in Support of the Shaft-Seals Fluid-Flow Modeling Integration into the WIPP EPA Compliance Certification Application

    International Nuclear Information System (INIS)

    Knowles, M.K.; Hurtado, L.D.; Dale, Tim

    1997-12-01

    The Waste Isolation Pilot Plant (WIPP) is a planned geologic repository for permanent disposal of transuranic waste generated by the U.S. Department of Energy. Disposal regions consist of panels and drifts mined from the bedded salt of the Salado Formation at a depth of approximately 650 m below the surface. This lithology is part of the 225 million year old Delaware Basin, and is geographically located in southeastern New Mexico. Four shafts service the facility needs for air intake, exhaust, waste handling, and salt handling. As the science advisor for the project, Sandia National Laboratories developed the WIPP shaft sealing system design. This design is a fundamental component of the application process for facility licensing, and has been found acceptable by stakeholders and regulatory agencies. The seal system design is founded on results obtained from laboratory and field experiments, numerical modeling, and engineering judgment. This paper describes a field test program to characterize the fluid flow properties in the WIPP shafts at representative seal locations. This work was conducted by Duke Engineering and Services under contract to Sandia National Laboratories in support of the seal system design

  10. Actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP): FY94 results

    International Nuclear Information System (INIS)

    Novak, C.F.

    1995-08-01

    This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media

  11. Making change happen: a case study of the successful establishment of a peer-administered naloxone program in one Australian jurisdiction.

    Science.gov (United States)

    Lancaster, Kari; Ritter, Alison

    2014-09-01

    Analysis of how policy processes happen in real-world, contemporary settings is important for generating new and timely learning which can inform other drug policy issues. This paper describes and analyses the process leading to the successful establishment of Australia's first peer-administered naloxone program. Within a case study design, qualitative data were collected using semi-structured interviews with key individuals associated with the initiative (n=9), and a collaborative approach to data analysis was undertaken. Central to policy development in this case was the formation of a committee structure to provide expert guidance and support. The collective, collaborative and relational features of this group are consistent with governing by network. The analysis demonstrates that the Committee served more than a merely consultative role. We posit that the Committee constituted the policy process of stakeholder engagement, communication strategy, program development, and implementation planning, which led to the enactment of the naloxone program. We describe and analyse the roles of actors involved, the goodwill and volunteerism which characterised the group's processes, the way the Committee was used as a strategic legitimising mechanism, the strategic framings used to garner support, emergent tensions and the evolving nature of the Committee. This case demonstrates how policy change can occur in the absence of strong political imperatives or ideological contestation, and the ways in which a collective process was used to achieve successful outcomes. Copyright © 2014 Elsevier B.V. All rights reserved.

  12. Status Report on the Microbial Characterization of Halite and Groundwater Samples from the WIPP

    International Nuclear Information System (INIS)

    Swanson, Juliet S.; Reed, Donald T.; Ams, David A.; Norden, Diana; Simmons, Karen A.

    2012-01-01

    This report summarizes the progress made in the ongoing task of characterizing the microbial community structures within the WIPP repository and in surrounding groundwaters. Through cultivation and DNA-based identification, the potential activity of these organisms is being inferred, thus leading to a better understanding of their impact on WIPP performance. Members of the three biological domains - Bacteria, Archaea, and Eukarya (in this case, Fungi) - that are associated with WIPP halite have been identified. Thus far, their activity has been limited to aerobic respiration; anaerobic incubations are underway. WIPP halite constitutes the near-field microbial environment. We expect that microbial activity in this setting will proceed from aerobic respiration, through nitrate reduction to focus on sulfate reduction. This is also the current WIPP performance assessment (PA) position. Sulfate reduction can occur at extremely high ionic strengths, and sulfate is available in WIPP brines and in the anhydrite interbeds. The role of methanogenesis in the WIPP remains unclear, due to both energetic constraints imposed by a high-salt environment and substrate selectivity, and it is no longer considered in PA. Archaea identified in WIPP halite thus far fall exclusively within the family Halobacteriaceae. These include Halobacterium noricense, cultivated from both low- and high-salt media, and a Halorubrum-like species. The former has also been detected in other salt mines worldwide; the latter likely constitutes a new species. Little is known of its function, but it was prevalent in experiments investigating the biodegradation of organic complexing agents in WIPP brines. Bacterial signatures associated with WIPP halite include members of the phylum Proteobacteria - Halomonas, Pelomonas, Limnobacter, and Chromohalobacter - but only the latter has been isolated. Also detected and cultivated were Salinicoccus and Nesterenkonia spp. Fungi were also isolated from halite. Although

  13. Status Report on the Microbial Characterization of Halite and Groundwater Samples from the WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, Juliet S. [Los Alamos National Laboratory; Reed, Donald T. [Los Alamos National Laboratory; Ams, David A. [Los Alamos National Laboratory; Norden, Diana [Ohio State University; Simmons, Karen A. [Los Alamos National Laboratory

    2012-07-10

    This report summarizes the progress made in the ongoing task of characterizing the microbial community structures within the WIPP repository and in surrounding groundwaters. Through cultivation and DNA-based identification, the potential activity of these organisms is being inferred, thus leading to a better understanding of their impact on WIPP performance. Members of the three biological domains - Bacteria, Archaea, and Eukarya (in this case, Fungi) - that are associated with WIPP halite have been identified. Thus far, their activity has been limited to aerobic respiration; anaerobic incubations are underway. WIPP halite constitutes the near-field microbial environment. We expect that microbial activity in this setting will proceed from aerobic respiration, through nitrate reduction to focus on sulfate reduction. This is also the current WIPP performance assessment (PA) position. Sulfate reduction can occur at extremely high ionic strengths, and sulfate is available in WIPP brines and in the anhydrite interbeds. The role of methanogenesis in the WIPP remains unclear, due to both energetic constraints imposed by a high-salt environment and substrate selectivity, and it is no longer considered in PA. Archaea identified in WIPP halite thus far fall exclusively within the family Halobacteriaceae. These include Halobacterium noricense, cultivated from both low- and high-salt media, and a Halorubrum-like species. The former has also been detected in other salt mines worldwide; the latter likely constitutes a new species. Little is known of its function, but it was prevalent in experiments investigating the biodegradation of organic complexing agents in WIPP brines. Bacterial signatures associated with WIPP halite include members of the phylum Proteobacteria - Halomonas, Pelomonas, Limnobacter, and Chromohalobacter - but only the latter has been isolated. Also detected and cultivated were Salinicoccus and Nesterenkonia spp. Fungi were also isolated from halite. Although

  14. Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

    International Nuclear Information System (INIS)

    1977-06-01

    The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems

  15. Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems. (DLC)

  16. Examining the Impact of a Highly Targeted State Administered Merit Aid Program on Brain Drain: Evidence from a Regression Discontinuity Analysis of Missouri's Bright Flight Program

    Science.gov (United States)

    Harrington, James R.; Muñoz, José; Curs, Bradley R.; Ehlert, Mark

    2016-01-01

    The adoption of state-funded merit-based aid programs has become increasingly popular among policy-makers, particularly in the southeastern part of the United States. One of the primary rationales of state-funded merit-based aid is to provide scholarships to the best and brightest students as a means to retain high quality human capital in the…

  17. Improved Balance Confidence and Stability for Elderly After 6 Weeks of a Multimodal Self-Administered Balance-Enhancing Exercise Program

    Science.gov (United States)

    Hafström, Anna; Malmström, Eva-Maj; Terdèn, Josefine; Fransson, Per-Anders; Magnusson, Måns

    2016-01-01

    Objective: To develop and assess the efficacy of a multimodal balance-enhancing exercise program (BEEP) designed to be regularly self-administered by community-dwelling elderly. The program aims to promote sensory reweighting, facilitate motor control, improve gaze stabilization, and stimulate continuous improvement by being constantly challenging. Method: Forty participants aged 60 to 80 years performed 6 weeks of BEEP training, on average for 16 min four times weekly, in a randomized one-arm crossover design. Results: One-leg standing time improved 32% with eyes open (EO), 206% with eyes closed (EC) on solid surface, and 54% EO on compliant surface (p balance improvements when perturbed on solid and compliant surfaces with EO and EC (p ≤ .033). Walking, step stool, and Timed Up and Go speeds increased (p ≤ .001), as did scores in Berg Balance and balance confidence scales (p ≤ .018). Discussion: Multimodal balance exercises offer an efficient, cost-effective way to improve balance control and confidence in elderly. PMID:28138495

  18. Basic Data Report for Drillholes on the H-19 Hydropad (Waste Isolation Pilot Plant--WIPP)

    International Nuclear Information System (INIS)

    Mercer, J.W.; Cole, D.L.; Holt, R.M.

    1998-01-01

    Seven holes were drilled and wells (H-19b0, H-19b2, H-19b3, H-19b4, H-19b5, H-19b6, and H-19b7) were constructed on the H-19 hydropad to conduct field activities in support of the Culebra Transport Program. These wells were drilled and completed on the Waste Isolation Pilot Plant (WIPP) site during February to September 1995. An eighth hole, H-19b1, was drilled but had to be abandoned before the target depth was reached because of adverse hole conditions. The geologic units penetrated at the H-19 location include surficial deposits of Holocene age, rocks from the Dockum Group of Upper Triassic age, the Dewey Lake Redbeds, and Rustler Formation of the Permian age. The Rustler Formation has been further divided into five informal members which include the Forty-niner Member, Magenta Member, Tamarisk Member, Culebra Dolomite Member, and an unnamed lower member. The Rustler Formation, particularly the Culebra Dolomite Member, is considered critical for hydrologic site characterization. The Culebra is the most transmissive saturated unit above the WIPP repository and, as such, is considered to be the most likely pathway for radionuclide transport to the accessible environment in the unlikely event the repository is breached. Seven cores from the Culebra were recovered during drilling activities at the H-19 hydropad and detailed descriptions of these cores were made. On the basis of geologic descriptions, four hydrostratigraphic units were identified in the Culebra cores and were correlated with the mapping units from the WFP air intake shaft. The entire length of H-19b1 was cored and was described in detail. During coring of H-19b1, moisture was encountered in the upper part of the Dewey Lake Redbeds. A 41-ft-thick section of this core was selected for detailed description to qualify the geologic conditions related to perched water in the upper Dewey Lake. In addition to cuttings and core, a suite of geophysical logs run on the drillholes was used to identify and

  19. Basic Data Report for Drillholes on the H-19 Hydropad (Waste Isolation Pilot Plant--WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Mercer, J.W.; Cole, D.L.; Holt, R.M.

    1998-10-09

    Seven holes were drilled and wells (H-19b0, H-19b2, H-19b3, H-19b4, H-19b5, H-19b6, and H-19b7) were constructed on the H-19 hydropad to conduct field activities in support of the Culebra Transport Program. These wells were drilled and completed on the Waste Isolation Pilot Plant (WIPP) site during February to September 1995. An eighth hole, H-19b1, was drilled but had to be abandoned before the target depth was reached because of adverse hole conditions. The geologic units penetrated at the H-19 location include surficial deposits of Holocene age, rocks from the Dockum Group of Upper Triassic age, the Dewey Lake Redbeds, and Rustler Formation of the Permian age. The Rustler Formation has been further divided into five informal members which include the Forty-niner Member, Magenta Member, Tamarisk Member, Culebra Dolomite Member, and an unnamed lower member. The Rustler Formation, particularly the Culebra Dolomite Member, is considered critical for hydrologic site characterization. The Culebra is the most transmissive saturated unit above the WIPP repository and, as such, is considered to be the most likely pathway for radionuclide transport to the accessible environment in the unlikely event the repository is breached. Seven cores from the Culebra were recovered during drilling activities at the H-19 hydropad and detailed descriptions of these cores were made. On the basis of geologic descriptions, four hydrostratigraphic units were identified in the Culebra cores and were correlated with the mapping units from the WFP air intake shaft. The entire length of H-19b1 was cored and was described in detail. During coring of H-19b1, moisture was encountered in the upper part of the Dewey Lake Redbeds. A 41-ft-thick section of this core was selected for detailed description to qualify the geologic conditions related to perched water in the upper Dewey Lake. In addition to cuttings and core, a suite of geophysical logs run on the drillholes was used to identify and

  20. Health Cost of a Nuclear Waste Repository, WIPP

    Science.gov (United States)

    Kula, Erhun

    1996-01-01

    The Waste Isolation Pilot Plant (WIPP), the United States of America’s first nuclear waste dumping site, has over the years generated a great deal of concern and controversy. The most sensitive aspect of this project is that it may impose serious health risks on future generations. The first leg of this project is about to be completed and at the time of writing the Department of Energy is planning to perform experiments with a small quantity of waste for operational demonstrations. If everything goes well, then towards the end of this decade large quantities of wastes will be transported to the site for disposal. This article reconsiders the health cost of this project from an economic perspective in light of recent developments in the field of social discounting. As in earlier studies, two cases of health risks are considered: total cancer and genetic deformity over a one million year cutoff period. The analysis shows that whereas ordinary discounting method wipes out the future health detriments, expressed in monetary terms, the modified discounting criterion retains a substantial proportion of such costs in economic analysis.

  1. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

  2. Implications of the presence of petroleum resources on the integrity of the WIPP

    International Nuclear Information System (INIS)

    Silva, M.K.

    1994-06-01

    The Waste Isolation Pilot Plant (WIPP) is a facility of the US Department of Energy (DOE), designed and constructed for the permanent disposal of transuranic (TRU) defense waste. The WIPP is surrounded by reserves of potash, crude oil, and natural gas. These are attractive targets for exploratory drilling which could disrupt the integrity of the transuranic waste repository. The performance assessment calculations published to date have identified future drilling for oil and gas reserves as an event that may disrupt the repository and may release radionuclides in excess of the standards. Therefore, the probability of inadvertent human intrusion into the repository by drilling and its impact on the integrity of the repository must be carefully assessed. This report evaluates: (1) the studies funded by the DOE to examine the crude oil potential in the immediate vicinity of the WIPP; (2) the use of an elicitation exercise to predict future drilling rates for use in the calculation of the repository performance; and (3) the observed limitations of institutional controls. This report identifies the following issues that remain to be resolved: (1) the limited performance of blowout preventers after drilling into high pressure zones immediately adjacent to the WIPP Site Boundary; (2) reported problems with waterflooding operations in southeastern New Mexico; (3) reported water level rises in several wells completed in the Rustler Formation, south of the WIPP Site, possibly due to oil and gas wells or leaking injection wells; and (4) reports of inadequate well abandonment practices on BLM leases and the continued absence of enforceable regulations

  3. Modeling gas and brine migration for assessing compliance of the WIPP

    International Nuclear Information System (INIS)

    Vaughn, P.; Butcher, B.; Helton, J.; Swift, P.

    1993-01-01

    The US DOE is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico as a facility for the long-term disposal of defense-related transuranic (TRU) wastes. Use of the WIPP for waste disposal is contingent on demonstrations of compliance with applicable regulations of the US EPA. This paper addresses issues related to modeling gas and brine migration at the WIPP for compliance with both EPA 40 CFR 191 (the Standard) and 40 CFR 268.6 (the RCRA). At the request of the WIPP Project Integration Office (WPIO) of the DOE, the WIPP Performance Assessment (PA) Dept. of Sandia National Labs. (SNL) has completed preliminary uncertainty and sensitivity analyses of gas and brine migration away from the undisturbed repository. This paper contains descriptions of the numerical model and simulations, including model geometries and parameter values, and a summary of major conclusions from sensitivity analyses. Because significant transport of contaminants can only occur in a fluid (gas or brine) medium, two-phase flow modeling can provide an estimate of the distance to which contaminants can migrate. Migration of gas or brine beyond the RCRA open-quotes disposal-unit boundaryclose quotes or the Standard's accessible environment constitutes a potential, but not certain, violation and may require additional evaluations of contaminant concentrations

  4. Analysis of Waste Isolation Pilot Plan (WIPP) Underground and MGO Samples by the Savannah River National Laboratory (SRNL)

    Energy Technology Data Exchange (ETDEWEB)

    Young, J. [Savannah River Site (SRS), Aiken, SC (United States); Ajo, H. [Savannah River Site (SRS), Aiken, SC (United States); Brown, L. [Savannah River Site (SRS), Aiken, SC (United States); Coleman, C. [Savannah River Site (SRS), Aiken, SC (United States); Crump, S. [Savannah River Site (SRS), Aiken, SC (United States); Diprete, C. [Savannah River Site (SRS), Aiken, SC (United States); Diprete, D. [Savannah River Site (SRS), Aiken, SC (United States); Ekechukwu, A. [Savannah River Site (SRS), Aiken, SC (United States); Gregory, C. [Savannah River Site (SRS), Aiken, SC (United States); Jones, M. [Savannah River Site (SRS), Aiken, SC (United States); Missimer, D. [Savannah River Site (SRS), Aiken, SC (United States); O' Rourke, P. [Savannah River Site (SRS), Aiken, SC (United States); White, T. [Savannah River Site (SRS), Aiken, SC (United States)

    2014-12-31

    Analysis of the recent WIPP samples are summarized in this report; WIPP Cam Filters 4, 6, 9 (3, 7, 11 were analyzed with FAS-118 in a separate campaign); WIPP Drum Lip R16 C4; WIPP Standard Waste Box R15 C5; WIPP MgO R16 C2; WIPP MgO R16 C4; WIPP MgO R16 C6; LANL swipes of parent drum; LANL parent drum debris; LANL parent drum; IAEA Swipe; Unused “undeployed” Swheat; Unused “undeployed” MgO; and Masselin cloth “smears”. Analysis showed that the MgO samples were very pure with low carbonate and water content. Other samples showed the expected dominant presence of Mg, Na and Pb. Parent drum debris sample was mildly acidic. Interpretation of results is not provided in this document, but rather to present and preserve the analytical work that was performed. The WIPP Technical Analysis Team is responsible for result interpretation which will be written separately.

  5. Cookoff Modeling of a WIPP waste drum (68660)

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, Michael L. [Sandia National Laboratories, Albuquerque, NM (United States)

    2014-11-24

    A waste drum located 2150 feet underground may have been the root cause of a radiation leak on February 14, 2014. Information provided to the WIPP Technical Assessment Team (TAT) was used to describe the approximate content of the drum, which included an organic cat litter (Swheat Scoop®, or Swheat) composed of 100% wheat products. The drum also contained various nitrate salts, oxalic acid, and a nitric acid solution that was neutralized with triethanolamine (TEA). CTH-TIGER was used with the approximate drum contents to specify the products for an exothermic reaction for the drum. If an inorganic adsorbent such as zeolite had been used in lieu of the kitty litter, the overall reaction would have been endothermic. Dilution with a zeolite adsorbent might be a useful method to remediate drums containing organic kitty litter. SIERRA THERMAL was used to calculate the pressurization and ignition of the drum. A baseline simulation of drum 68660 was performed by assuming a background heat source of 0.5-10 W of unknown origin. The 0.5 W source could be representative of heat generated by radioactive decay. The drum ignited after about 70 days. Gas generation at ignition was predicted to be 300-500 psig with a sealed drum (no vent). At ignition, the wall temperature increases modestly by about 1°C, demonstrating that heating would not be apparent prior to ignition. The ignition location was predicted to be about 0.43 meters above the bottom center portion of the drum. At ignition only 3-5 kg (out of 71.6 kg total) has been converted into gas, indicating that most of the material remained available for post-ignition reaction.

  6. An evaluation of the proposed tests with radioactive waste at WIPP

    International Nuclear Information System (INIS)

    Chaturvedi, L.; Silva, M.

    1992-01-01

    This paper discusses the Waste Isolation Pilot Plant (WIPP) a planned repository for permanent disposal of transuranic (TRU) radiative waste that has resulted from the defense activities of the U.S. Government over the past 50 years. Only the waste that is currently stored in an easily retrievable mode at ten U.S. Department of Energy (DOE) laboratories around the country will be shipped to WIPP. The waste consists of various kinds of trash including paper, rubber, rags and metal that is contaminated with radionuclides with very long half-lives. The decision to dispose of the waste permanently will be made based on projections of the behavior of the waste and the repository of 10,000 years or more. DOE has proposed shipping a limited amount of waste to WIPP for a five year Test Phase to demonstrating compliance with the U.S. Environmental Protection Agency (EPA) Standard for long-term isolation

  7. Rationale for the H-19 and H-11 tracer tests at the WIPP site

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Meigs, L.C.; Davies, P.B.

    1996-01-01

    The Waste Isolation Pilot Plant (WIPP) is a repository for transuranic wastes constructed in bedded Permian-age halite in the Delaware Basin, a sedimentary basin in southeastern New Mexico, USA. A drilling scenario has been identified during performance assessment (PA) that could lead to the release of radionuclides to the Culebra Dolomite Member of the Rustler Formation, the most transmissive water-saturated unit above the repository horizon. Were this to occur, the radionuclides would need to be largely contained within the Culebra (or neighboring strata) within the WIPP-site boundary through the period lasting for 10,000 years after repository closure for WIPP to remain in compliance with applicable regulations on allowable releases. Thus, processes affecting transport of radionuclides within the Culebra are of importance to PA

  8. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    2005-01-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New Mexico Administrative Code), 'Adoption of 40 CFR [Code of Federal Regulations] Part 264,'specifically 40 CFR 264.90 through 264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] 6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  9. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-07-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  10. Assessment of near-surface dissolution at and near the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    Bachman, G.O.

    1985-07-01

    The area at and near the WIPP site was examined for evidence of karst development on the geomorphic surface encompassing the site. Certain surficial depressions of initial concern were identified as blowouts in sand dune fields (shallow features unrelated to karstification). An ancient stream system active more than 500,000 yr ago contained more water than any system since. During that time (Gatuna, Middle Pleistocene), many karst features such as Clayton Basin and Nash Draw began to form in the region. Halite was probably dissolved from parts of the Rustler Formation at that time. Dissolution of halite and gypsum from intervals encountered in Borehole WIPP-33 west of the WIPP site occurred during later Pleistocene time (i.e., <450,000 yr ago). However, there is no evidence of active near-surface dissolution within a belt to the east of WIPP-33 in the vicinity of the WIPP shaft. 26 refs., 11 figs., 1 tab

  11. Assessment of near-surface dissolution at and near the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Bachman, G.O.

    1985-07-01

    The area at and near the WIPP site was examined for evidence of karst development on the geomorphic surface encompassing the site. Certain surficial depressions of initial concern were identified as blowouts in sand dune fields (shallow features unrelated to karstification). An ancient stream system active more than 500,000 yr ago contained more water than any system since. During that time (Gatuna, Middle Pleistocene), many karst features such as Clayton Basin and Nash Draw began to form in the region. Halite was probably dissolved from parts of the Rustler Formation at that time. Dissolution of halite and gypsum from intervals encountered in Borehole WIPP-33 west of the WIPP site occurred during later Pleistocene time (i.e., <450,000 yr ago). However, there is no evidence of active near-surface dissolution within a belt to the east of WIPP-33 in the vicinity of the WIPP shaft. 26 refs., 11 figs., 1 tab.

  12. WIPP conceptual design report. Addendum F. HVAC systems energy analysis for Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1977-04-01

    This report presents the results of a technical and economic analysis of alternative methods of meeting the heating, ventilating, and air conditioning requirements of the Waste Isolation Pilot Plant (WIPP) facilities proposed to be constructed in southeastern New Mexico. This report analyzes a total of ten WIPP structures to determine the most energy and economic efficient means of providing heating, ventilating, and air conditioning services. Additional analyses were performed to determine the merits of centralized versus dispersed refrigeration and heating facilities, and of performing supplemental domestic hot water heating with solar panels

  13. WIPP Regulatory Compliance Strategy and Management Plan for demonstrating compliance to long-term disposal standards

    International Nuclear Information System (INIS)

    1994-05-01

    The primary purpose of this document is to provide a strategy by which the WIPP will demonstrate its ability to perform as a deep geologic repository. The document communicates the DOE's understanding of the regulations related to long-term repository performance; and provides the most efficient strategy that intergrates WIPP Project elements, ensures the sufficiency of information, and provides flexibility for changes in the TRU waste generation system to facilitate the disposal of defense-generated TRU wastes. In addition, this document forms a focal point between the DOE and its various external regulators as well as other stakeholders for the purpose of arriving at compliance decisions that consider all relevant input

  14. Radiographic features of importance in the National Institute for Occupational Safety and Health-administered Coal Workers' Health Surveillance Program: characterising the use of the 'other symbols'.

    Science.gov (United States)

    Halldin, Cara N; Hale, Janet M; Blackley, David J; Laney, A Scott

    2017-08-11

    The National Institute for Occupation Safety and Health-administered Coal Workers' Health Surveillance Program (CWHSP) provides radiographic pneumoconiosis screening for US coal miners. Radiographs are classified by readers according to International Labour Office criteria. In addition to pneumoconiotic parenchymal and pleural lung abnormalities, readers document radiographic features of importance (other symbols). Other symbols are not meant to imply a diagnosis or interpretation but are relevant as they provide information beyond a pneumoconiosis classification for features related to dust exposure and other aetiologies. Our objective was to summarise other symbol data from 48 years of CWHSP participants. Chest radiograph classifications obtained from CWHSP participants between July 1968 and July 2016 were analysed. Any 'other symbol' indication from any of the readings were counted. Frequencies were tabulated by individual reader and those identified by any reader. Of the 469 922 radiographs included in this study, nearly 15% had at least one reader identify a radiographic feature of importance. The most commonly identified other symbol was cancer (excluding mesothelioma) (6.83%), followed by emphysema (1.68%). Some features were rarely identified over the 48 years of data collection such as rheumatoid pneumoconiosis (n=46), pneumothorax (n=32), mesothelioma (n=12) and rounded atelectasis (n=4). This is the largest study to date describing radiographic features of importance as part of routine chest radiographic surveillance. While these symbols are not diagnostic they can be used to describe features associated with dust exposure. One of the most commonly identified radiographic features in our population is emphysema which is associated with respirable dust exposure. These results can be compared with other dust exposed populations. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No

  15. Nurse-administered propofol sedation for endoscopy

    DEFF Research Database (Denmark)

    Jensen, J T; Vilmann, P; Horsted, T

    2011-01-01

    The aim of the present study was to perform a risk analysis during the implementation phase of nurse-administered propofol sedation (NAPS) and to validate our structured training program.......The aim of the present study was to perform a risk analysis during the implementation phase of nurse-administered propofol sedation (NAPS) and to validate our structured training program....

  16. Effects of a Home-Based and Volunteer-Administered Physical Training, Nutritional, and Social Support Program on Malnutrition and Frailty in Older Persons: A Randomized Controlled Trial.

    Science.gov (United States)

    Luger, Eva; Dorner, Thomas Ernst; Haider, Sandra; Kapan, Ali; Lackinger, Christian; Schindler, Karin

    2016-07-01

    The aim of this study was to examine the effects of a home-based and volunteer-administered physical training and nutritional intervention program compared with social support intervention on nutritional and frailty status in prefrail and frail community-dwelling older persons. This was a randomized controlled trial in which community-dwelling persons (mean age = 83 years) were recruited and randomly assigned to the physical training and nutritional intervention group (PTN, n = 39) and the social support group (SoSu, n = 41). The study was conducted by trained lay nonprofessionals. The community-dwelling older persons in both groups were visited twice a week by trained nonprofessional volunteers (buddies) in Vienna, Austria. Eighty prefrail and frail adults aged 65 years or older. In the PTN group, both the buddies and older persons performed 6 strength exercises within a circuit training session and discussed nutrition-related aspects. The active control group (SoSu) had the opportunity to perform cognitive training in addition to the social contact. Outcome measures as nutritional (Mini Nutritional Assessment long form [MNA-LF]) and frailty status (Frailty Instrument for Primary Care of the Survey of Health, Ageing and Retirement in Europe [SHARE-FI]) were obtained at baseline and after 12 weeks. Significant improvements in the MNA-LF score (1.54 points, 95% confidence interval [CI] 0.51-2.56; P = .004) and the SHARE-FI score (-0.71 discrete factor score values, 95% CI -1.07, -0.35; P malnutrition and frailty in older persons living at home. Furthermore, social support alone also can result in improvement. In particular, older adults with impaired nutritional status at baseline can benefit more from the intervention. Such a home visit program might also have the potential to prevent future health risks and could allay isolation and loneliness. Copyright © 2016 AMDA – The Society for Post-Acute and Long-Term Care Medicine. Published by Elsevier

  17. Use of and confidence in administering outcome measures among clinical prosthetists: Results from a national survey and mixed-methods training program.

    Science.gov (United States)

    Gaunaurd, Ignacio; Spaulding, Susan E; Amtmann, Dagmar; Salem, Rana; Gailey, Robert; Morgan, Sara J; Hafner, Brian J

    2015-08-01

    Outcome measures can be used in prosthetic practices to evaluate interventions, inform decision making, monitor progress, document outcomes, and justify services. Strategies to enhance prosthetists' ability to use outcome measures are needed to facilitate their adoption in routine practice. To assess prosthetists' use of outcome measures and evaluate the effects of training on their confidence in administering performance-based measures. Cross-sectional and single-group pretest-posttest survey. Seventy-nine certified prosthetists (mean of 16.0 years of clinical experience) were surveyed about their experiences with 20 standardized outcome measures. Prosthetists were formally trained by the investigators to administer the Timed Up and Go and Amputee Mobility Predictor. Prosthetists' confidence in administering the Timed Up and Go and Amputee Mobility Predictor was measured before and after training. The majority of prosthetists (62%) were classified as non-routine outcome measure users. Confidence administering the Timed Up and Go and Amputee Mobility Predictor prior to training was low-to-moderate across the study sample. Training significantly (p confidence in administering both instruments. Prosthetists in this study reported limited use of and confidence with standardized outcome measures. Interactive training resulted in a statistically significant increase of prosthetists' confidence in administering the Timed Up and Go and Amputee Mobility Predictor and may facilitate use of outcome measures in clinical practice. Frequency of outcome measure use in the care of persons with limb loss has not been studied. Study results suggest that prosthetists may not regularly use standardized outcome measures and report limited confidence in administering them. Training enhances confidence and may encourage use of outcome measures in clinical practice. © The International Society for Prosthetics and Orthotics 2014.

  18. Assessment of Contaminated Brine Fate and Transport in MB139 at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research Dept.; Malama, Bwalya [Sandia National Lab., Carlsbad, NM (United States). Performance Assessment Dept.

    2014-07-01

    Following the radionuclide release event of February 14, 2014 at the Waste Isolation Pilot Plant (WIPP), actinide contamination has been found on the walls and floor in Panel 7 as a result of a release in Room 7 of Panel 7. It has been proposed to decontaminate Panel 7 at the WIPP by washing contaminated surfaces in the underground with fresh water. A cost-effective cleanup of this contamination would allow for a timely return to waste disposal operations at WIPP. It is expected that the fresh water used to decontaminate Panel 7 will flow as contaminated brine down into the porosity of the materials under the floor – the run-of-mine (ROM) salt above Marker Bed 139 (MB139) and MB139 itself – where its fate will be controlled by the hydraulic and transport properties of MB139. Due to the structural dip of MB139, it is unlikely that this brine would migrate northward towards the Waste-Handling Shaft sump. A few strategically placed shallow small-diameter observation boreholes straddling MB139 would allow for monitoring the flow and fate of this brine after decontamination. Additionally, given that flow through the compacted ROM salt floor and in MB139 would occur under unsaturated (or two-phase) conditions, there is a need to measure the unsaturated flow properties of crushed WIPP salt and salt from the disturbed rock zone (DRZ).

  19. Seismic reflection data report: Waste Isolation Pilot Plant (WIPP) site, Southeastern New Mexico

    International Nuclear Information System (INIS)

    Hern, J.L.; Powers, D.W.; Barrows, L.J.

    1978-12-01

    Three seismic reflection (Vibroseis) surveys conducted from 1976 through 1978 by Sandia Laboratories to support investigations for the Waste Isolation Pilot Plant (WIPP) are described. Volume I describes the purpose, field parameters, and data processing parameters. Volume II contains uninterpreted processed lines and shotpoint maps. Data interpretations will be the subject of the subsequent reports. The data collected during these three surveys total 77 line miles; 72 line miles of this are on or very near the WIPP site. The first of the surveys (1976 SAN) covered 25 line miles and was conducted similarly to previous petroleum industry surveys in the area. 1976 SAN supplemented existing petroleum industry data. The two subsequent surveys (1977 X and 1978 Y) used shorter geophone spacings (110'), higher signal frequencies (up to 100 Hz), and higher data sampling rates (2 ms.) to better define the shallow zone (less than 4000') of primary interest. 1977 X contained 47 line miles on or near the WIPP site and over several structural features northwest of the site. 1978 Y contains 5 line miles over a one square mile area near the center of the WIPP site. These data show increasing discrimination of shallow reflectors as data collection parameters were modified. Data tables of recording and processing parameters are included. A fourth Vibroseis survey was conducted at the WIPP site in 1978 by Grant Geophysical Company for Bechtel; the data are not in final form and are not included. Petroleum industry data and an inconclusive weight-drop survey, conducted in 1976, are also not included in this report

  20. Evolution of hydrologic systems and brine geochemistry in a deforming salt medium: Data from WIPP brine seeps

    International Nuclear Information System (INIS)

    Deal, D.E.; Roggenthen, W.M.

    1991-01-01

    The Brine Sampling and Evaluation Program (BSEP) is a formalized continuation of studies that began in 1982 as part of the Site Validation Program. The program was established in 1985. The mission was to document and investigate the origins, hydraulic characteristics, extent, and composition of brine occurrences in the Permian Salado Formation and the seepage of that brine into the WIPP excavations. This document focuses on the cumulative data obtained from the BSEP. The overall activities of the BSEP described and quantified the brine. It includes documentation and study of brine inflow into boreholes in the facility. The BSEP investigated the occurrence and development of brine weeps, crusts, and brine geochemistry. The presence of salt-tolerant bacteria in the workings was recorded and their possible interactions with experiments and operations, was assessed. The formation properties associated with the occurrence of brine was characterized. The determination of formation properties included the water content of various geologic units, direct examination of these units in boreholes using a video camera system, and measurement of electrical properties relatable to the brine contents. Modeling examined the interaction of salt deformation near the workings and the flow of brine through the deforming rocks. 34 refs

  1. Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

    2006-01-01

    In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

  2. 9+ years of disposal experience at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Rempe, Norbert T.; Nelson, Roger A.

    2008-01-01

    With almost a decade of operating experience, the Waste Isolation Pilot Plant (WIPP) has established an enviable record by clearly demonstrating that a deep geologic repository for unconditioned radioactive waste in rock salt can be operated safely and in compliance with very complex regulations. WIPP has disposed of contact-handled transuranic (TRU) waste since 1999 and remote-handled TRU waste since 2007. Emplacement methods range from directly stacking unshielded 0.21-4.5 m 3 containers inside disposal rooms to remotely inserting highly radioactive 0.89 m 3 canisters into horizontally drilled holes (shield plugs placed in front of canisters protect workers inside active disposal rooms). More than 100 000 waste containers have been emplaced, and one-third of WIPP's authorized repository capacity of 175,000 m 3 has already been consumed. Principal surface operations are conducted in the waste handling building, which is divided into CH and RH waste handling areas. Four vertical shafts extend from the surface to the disposal horizon, 655 m below the surface in a 1000 m thick sequence of Permian bedded salt. The waste disposal area of about 0.5 km 2 is divided into ten panels, each consisting of seven rooms. Vertical closure (creep) rates in disposal rooms range up to 10 cm per year. While one panel is being filled with waste, the next one is being mined. Mined salt is raised to the surface in the salt shaft, and waste is lowered down the waste shaft. Both of these shafts also serve as principal access for personnel and materials. Underground ventilation is divided into separate flow paths, allowing simultaneous mining and disposal. A filter building near the exhaust shaft provides the capability to filter the exhaust air (in reduced ventilation mode) through HEPA filters before release to the atmosphere. WIPP operations have not exposed employees or the public to radiation doses beyond natural background variability. They consistently meet or exceed regulatory

  3. Should Pharmacy Technicians Administer Immunizations?

    Directory of Open Access Journals (Sweden)

    Dylan Atkinson

    2017-09-01

    Full Text Available Purpose. To describe the potential role for pharmacy technicians in administering immunizations – limited for this discussion to specifically inserting the needle into the patient’s arm and pressing down on the plunger – at the discretion of a supervising pharmacist as a way to enhance patient care and workflow efficiency. Summary. Pharmacy technicians currently play an important role in facilitating pharmacy-based immunization programs. Technicians routinely perform non-clinical tasks related to pharmacy-based immunizations, though nearly all states prohibit technicians from administering vaccines. Several studies demonstrate that untrained laypersons can safely administer intranasal or intradermal vaccines, and laypersons routinely administer medications through intramuscular or subcutaneous routes (e.g., patients with diabetes or rheumatic conditions. It stands to reason that a trained pharmacy technician could perform comparably on these techniques that laypersons have mastered. One state has adopted rules to allow pharmacy technicians to administer immunizations if the technician has completed specific training on administration techniques and on basic life support. This task is performed at the discretion of the supervising pharmacist, and the pharmacist would still be responsible for clinical aspects of immunizing such as prescribing the right vaccine to the right patient. Additional considerations factoring into the decision as to whether or not to involve pharmacy technicians in immunization administration are also summarized. Conclusion. If safety can be reasonably assured through training and supervision, it may be appropriate to delegate vaccine administration to appropriately trained pharmacy technicians. Such delegation may enhance workflow efficiency, which may confer added value for patient care and potentially improve access to community pharmacy-based immunizations.   Type: Commentary

  4. Assessment of the potential for karst in the Rustler Formation at the WIPP site.

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz, John Clay

    2006-01-01

    This report is an independent assessment of the potential for karst dissolution in evaporitic strata of the Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site. Review of the available data suggests that the Rustler strata thicken and thin across the area in depositional patterns related to lateral variations in sedimentary accommodation space and normal facies changes. Most of the evidence that has been offered for the presence of karst in the subsurface has been used out of context, and the different pieces are not mutually supporting. Outside of Nash Draw, definitive evidence for the development of karst in the Rustler Formation near the WIPP site is limited to the horizon of the Magenta Member in drillhole WIPP-33. Most of the other evidence cited by the proponents of karst is more easily interpreted as primary sedimentary structures and the localized dissolution of evaporitic strata adjacent to the Magenta and Culebra water-bearing units. Some of the cited evidence is invalid, an inherited baggage from studies made prior to the widespread knowledge of modern evaporite depositional environments and prior to the existence of definitive exposures of the Rustler Formation in the WIPP shafts. Some of the evidence is spurious, has been taken out of context, or is misquoted. Lateral lithologic variations from halite to mudstone within the Rustler Formation under the WIPP site have been taken as evidence for the dissolution of halite such as that seen in Nash Draw, but are more rationally explained as sedimentary facies changes. Extrapolation of the known karst features in Nash Draw eastward to the WIPP site, where conditions are and have been significantly different for half a million years, is unwarranted. The volumes of insoluble material that would remain after dissolution of halite would be significantly less than the observed bed thicknesses, thus dissolution is an unlikely explanation for the lateral variations from halite to mudstone and siltstone

  5. Evaluation of the US Department of Energy Weatherization Innovation Pilot Program (2010-2014)

    Energy Technology Data Exchange (ETDEWEB)

    Tonn, Bruce Edward [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Rose, Erin M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hawkins, Beth A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-05-01

    This report contains results from analysis conducted on each of the Weatherization Innovation Pilot Program (WIPP) grants awarded to 16 organizations by the US Department of Energy (DOE) in 2010. The purpose of WIPP was to explore the potential adoptability or replicability of innovative processes or technologies for the enhancement of DOE’s Weatherization Assistance Program (WAP). DOE initiated the WIPP grant to accelerate effective innovations in home energy efficiency and other WAP mission-related goals for income-qualifying households of low socioeconomic status. This study was performed alongside a broader, national evaluation of WAP conducted by Oak Ridge National Laboratory (ORNL) for DOE.

  6. Analysis report for WIPP colloid model constraints and performance assessment parameters

    Energy Technology Data Exchange (ETDEWEB)

    Mariner, Paul E.; Sassani, David Carl

    2014-03-01

    An analysis of the Waste Isolation Pilot Plant (WIPP) colloid model constraints and parameter values was performed. The focus of this work was primarily on intrinsic colloids, mineral fragment colloids, and humic substance colloids, with a lesser focus on microbial colloids. Comments by the US Environmental Protection Agency (EPA) concerning intrinsic Th(IV) colloids and Mg-Cl-OH mineral fragment colloids were addressed in detail, assumptions and data used to constrain colloid model calculations were evaluated, and inconsistencies between data and model parameter values were identified. This work resulted in a list of specific conclusions regarding model integrity, model conservatism, and opportunities for improvement related to each of the four colloid types included in the WIPP performance assessment.

  7. Summary of 1988 WIPP [Waste Isolation Pilot Plant] Facility horizon gas flow measurements

    International Nuclear Information System (INIS)

    Stormont, J.C.

    1990-11-01

    Numerous gas flow measurements have been made at the Waste Isolation Pilot Plant (WIPP) Facility horizon during 1988. All tests have been pressure decay or constant pressure tests from single boreholes drilled from the underground excavations. The test fluid has been nitrogen. The data have been interpreted as permeabilities and porosities by means of a transient numerical solution method. A closed-form steady-state approximation provides a reasonable order-of-magnitude permeability estimate. The effective resolution of the measurement system is less than 10 -20 m 2 . Results indicate that beyond 1 to 5 m from an excavation, the gas flow is very small and the corresponding permeability is below the system resolution. Within the first meter of an excavation, the interpreted permeabilities can be 5 orders of magnitude greater than the undisturbed or far-field permeability. The interpreted permeabilities in the region between the undisturbed region and the first meter from an excavation are in the range of 10 -16 to 10 -20 m 2 . Measurable gas flow occurs to a greater depth into the roof above WIPP excavations of different sizes and ages than into the ribs and floor. The gas flows into the formation surrounding the smallest excavation tested are consistently lower than those at similar locations surrounding larger excavations of comparable age. Gas flow measured in the interbed layers near the WIPP excavations is highly variable. Generally, immediately above and below excavations, relatively large gas flow is measured in the interbed layers. These results are consistent with previous measurements and indicate a limited disturbed zone surrounding WIPP excavations. 31 refs., 99 figs., 5 tabs

  8. Supplements to the release scenario analyses for the waste isolation pilot plant (WIPP)

    International Nuclear Information System (INIS)

    Bingham, F.W.; Merritt, M.L.; Tierney, M.S.

    1980-01-01

    This paper summarizes three analyses of long-term environmental impacts of the WIPP that were made subsequent to the publication of the DEIS in response to agency and public comments. Three supplemental scenarios are described in which activity is transported to the biosphere by groundwater. The scenarios are entitled: brine pocket rupture scenario, effects of water on domestic wells; and agricultural use of the Pecos River Water

  9. Analysis of the potential formation of a Breccia chimney beneath the WIPP repository

    International Nuclear Information System (INIS)

    Spiegler, P.

    1982-05-01

    This report evaluates the potential formation of a Breccia pipe beginning at the Bell Canyon aquifer beneath the WIPP repository and the resulting release of radioactivity to the surface. Rock mechanics considerations indicate that the formation of a Breccia pipe by collapse of a cavern is not reasonable. Even if rock mechanics is ignored, the overlying strata act as a barrier and would prevent the release of radioactivity to the biosphere. Gradual formation of a Breccia pipe is so slow that the plutonium-239 in the waste (one of the most important long-lived components) would decay during formation. If Bell Lake and San Simon Sinks are the surface manifestation of a regional deep dissolution wedge, such a wedge is too far removed to represent pipe forming activity near the WIPP site. The formation of a Breccia pipe under the WIPP repository is highly unlikely. If it did occur, the concentration of plutonium-239 in brine reaching the surface would be less than the maximum permissible concentration in water specified in the Code of Federal Regulation Title 10, part 20

  10. Politics and technology in repository siting: military versus commercial nuclear wastes at WIPP 1972-1985

    International Nuclear Information System (INIS)

    Downey, G.L.

    1985-01-01

    During the 1970s, attempts by the federal government to develop a comprehensive system for disposing of nuclear wastes in geologic repositories were plagued by two related political problems; (1) whether or not military and commercial wastes should be buried together in the same repository, and (2) how to define the host state's role in the repository siting mechanism. This article explains why these two problems were connected by showing how they proved to be of decisive importance in the development of the Waste Isolation Pilot Plant (WIPP) project in Carlsbad, New Mexico. Although WIPP was initially conceived as a wholly military facility, The Department of Energy triggered a three-year dispute over the project's scope by proposing in 1978 to include commercial wastes in the repository. The key issue in the dispute concerned the political legitimacy of decision-making mechanisms for repository siting, which depend upon the extent to which they both adequately represent the interests of affected groups and meet an indistinct technical/political criterion of acceptable safety. DOE's ill-fated proposal to mix military and commercial disposal at WIPP demonstrated that the two rely on somewhat different conditions for their legitimacy. The agency overlapped the legitimate authorities of the federal and state governments and gave itself the hopeless task of negotiating a new boundary between them. 50 references, 3 figures

  11. Position paper on flammability concerns associated with TRU waste destined for WIPP

    International Nuclear Information System (INIS)

    1991-04-01

    The Waste Isolation Pilot Plant (WIPP), in southeastern New Mexico,is an underground repository, designed for the safe geologic disposal of transuranic (TRU) wastes generated from defense-related activities of the US Department of Energy (DOE). The WIPP storage rooms are mined in a bedded salt (halite) formation, and are located 2150 feet below the surface. After the disposal of waste in the storage rooms, closure of the repository is expected to occur by creep (plastic flow) of the salt formation, with the waste being permanently isolated from the surrounding environment. This paper has evaluated the issue of flammability concerns associated with TRU waste to be shipped to WIPP, including a review of possible scenarios that can potentially contribute to the flammability. The paper discusses existing regulations that address potential flammability concerns, presents an analysis of previous flammability-related incidents at DOE sites with respect to the current regulations, and finally, examines the degree of assurance these regulations provide in safeguarding against flammability concerns during transportation and waste handling. 50 refs., 7 figs., 7 tabs

  12. Lessons Learned from WIPP Site Characteriztion, Performance Assessment, and Regulatory Review Related to Radionuclide Migration through Water-Conducting Features

    Energy Technology Data Exchange (ETDEWEB)

    Beauheim, R.L.: Larson. K.W.

    1998-11-11

    Many lessons have been learned over the past 24 years as the Waste Isolation Pilot Plant (WIPP) project has progressed from initial site characterization to final licensing that may be of relevance to other nuclear-waste-disposal projects. These lessons pertain to the manner in which field and laboratory investigations are planned, how experiments are interpreted, how conceptual and numerical models are developed and simplified~ and how defensibility and credibility are achieved and maintained. These lessons include 1) Site characterization and performance assessment (PA) should evolve together through an iterative process, with neither activity completely dominating the other. 2) Defensibility and credibility require a much greater depth of understanding than can be represented in PA models. 3) Experimentalists should be directly involved in model and parameter abstraction and simplification for PA. 4) External expert review should be incorporated at all stages of a project~ not just after an experiment or modeling activity is completed. 5) Key individuals should be retained for the life of a project or a process must be established to transfer their working knowledge to new individuals. 6) An effective QA program needs to be stable and consistent for the duration of a project and rests on best scientific practices. All of these lessons relate to the key point that consideration must be given from the earliest planning stages to maximizing the defensibility and credibility of all work.

  13. Enhancing Cognitive and Social-Emotional Development through a Simple-to-Administer Mindfulness-Based School Program for Elementary School Children: A Randomized Controlled Trial

    Science.gov (United States)

    Schonert-Reichl, Kimberly A.; Oberle, Eva; Lawlor, Molly Stewart; Abbott, David; Thomson, Kimberly; Oberlander, Tim F.; Diamond, Adele

    2015-01-01

    The authors hypothesized that a social and emotional learning (SEL) program involving mindfulness and caring for others, designed for elementary school students, would enhance cognitive control, reduce stress, promote well-being and prosociality, and produce positive school outcomes. To test this hypothesis, 4 classes of combined 4th and 5th…

  14. Studies of transuranic waste storage under conditions expected in the Waste Isolation Pilot Plant (WIPP). Interim summary report, October 1, 1977-June 15, 1979

    International Nuclear Information System (INIS)

    Kosiewicz, S.T.; Barraclough, B.L.; Zerwekh, A.

    1980-01-01

    The major focus of the program has been on the gas generation potential of organic wastes produced by radiolytic and thermal degradation under simulated WIPP storage conditions. The effects of TRU contamination level, temperature, waste type, pressure, and exposure time on radiolysis are presented. In addition, results from preliminary experiments on processed sludge dewatering are discussed. A summary is presented here of the results of a detailed study of all retrievably stored TRU wastes present at LASL before January 1, 1978. The data indicate a gross volume for the LASL inventory of 1610 m 3 with a total weight of nearly 1.24 x 10 6 kg (1240 metric tonnes). The dominant radionuclide contents of the waste are plutonium (primarily 238 Pu) and americium

  15. Brine Sampling and Evaluation Program

    International Nuclear Information System (INIS)

    Deal, D.E.; Case, J.B.; Deshler, R.M.; Drez, P.E.; Myers, J.; Tyburski, J.R.

    1987-12-01

    The Brine Sampling and Evaluation Program (BSEP) Phase II Report is an interim report which updates the data released in the BSEP Phase I Report. Direct measurements and observations of the brine that seeps into the WIPP repository excavations were continued through the period between August 1986 and July 1987. That data is included in Appendix A, which extends the observation period for some locations to approximately 900 days. Brine observations at 87 locations are presented in this report. Although WIPP underground workings are considered ''dry,'' small amounts of brine are present. Part of that brine migrates into the repository in response to pressure gradients at essentially isothermal conditions. The data presented in this report is a continuation of moisture content studies of the WIPP facility horizon that were initiated in 1982, as soon as underground drifts began to be excavated. Brine seepages are manifested by salt efflorescences, moist areas, and fluid accumulations in drillholes. 35 refs., 6 figs., 11 tabs

  16. Expert (Peer) Reviews at the Waste Isolation Pilot Plant (WIPP): Making Complex Information and Decision Making Transparent

    International Nuclear Information System (INIS)

    Eriksson, Leif G.

    2001-01-01

    On the 18th of May 1998, based on the information provided by the United Sates Department of Energy (DOE) in support of the 1996 Waste Isolation Pilot Plant (WIPP) Compliance Certification Application, the U.S. Environmental Protection Agency certified the proposed deep geological repository for disposal of long-lived, defense-generated, transuranic radioactive waste at the WIPP site in New Mexico, United States of America, was compliant with all applicable radioactive waste disposal regulations. Seven domestic and one joint international peer reviews commissioned by the DOE were instrumental in making complex scientific and engineering information, as well as the related WIPP decision-making process, both credible and transparent to the majority of affected and interested parties and, ultimately, to the regulator

  17. Training pharmacy technicians to administer immunizations.

    Science.gov (United States)

    McKeirnan, Kimberly C; Frazier, Kyle R; Nguyen, Maryann; MacLean, Linda Garrelts

    To evaluate the effectiveness of an immunization training program for pharmacy technicians on technicians' self-reported confidence, knowledge, and number of vaccines administered. A one-group pre- and posttest study was conducted with certified pharmacy technicians from Albertsons and Safeway community pharmacies in Idaho. Thirty pharmacy technicians were recruited to participate in an immunization administration training program comprising a 2-hour home study and a 2-hour live training. Pharmacy technician scores on a 10-question knowledge assessment, responses on a pre- and posttraining survey, and number of immunizations administered in the 6-month period following the training were collected. Twenty-five pharmacy technicians completed the home study and live portions of the immunization training program. All 29 pharmacy technicians who took the home study assessment passed with greater than 70% competency on the first attempt. Technicians self-reported increased confidence with immunization skills between the pretraining survey and the posttraining survey. From December 2016 to May 2017, the technicians administered 953 immunizations with 0 adverse events reported. For the first time, pharmacy technicians have legally administered immunizations in the United States. Trained pharmacy technicians demonstrated knowledge of vaccination procedures and self-reported improved confidence in immunization skills and administered immunizations after participating in a 4-hour training program. Copyright © 2018 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

  18. In-Situ Testing and Performance Assessment of a Redesigned WIPP Panel Closure - 13192

    International Nuclear Information System (INIS)

    Klein, Thomas; Patterson, Russell; Camphouse, Chris; Herrick, Courtney; Kirchner, Thomas; Malama, Bwalya; Zeitler, Todd; Kicker, Dwayne

    2013-01-01

    There are two primary regulatory requirements for Panel Closures at the Waste Isolation Pilot Plant (WIPP), the nation's only deep geologic repository for defense related Transuranic (TRU) and Mixed TRU waste. The Federal requirement is through 40 CFR 191 and 194, promulgated by the U.S. Environmental Protection Agency (EPA). The state requirement is regulated through the authority of the Secretary of the New Mexico Environment Department (NMED) under the New Mexico Hazardous Waste Act (HWA), New Mexico Statutes Annotated (NMSA) 1978, chap. 74-4-1 through 74-4-14, in accordance with the New Mexico Hazardous Waste Management Regulations (HWMR), 20.4.1 New Mexico Annotated Code (NMAC). The state regulations are implemented for the operational period of waste emplacement plus 30 years whereas the federal requirements are implemented from the operational period through 10,000 years. The 10,000 year federal requirement is related to the adequate representation of the panel closures in determining long-term performance of the repository. In Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194, the EPA required a specific design for the panel closure system. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has requested, through the Planned Change Request (PCR) process, that the EPA modify Condition 1 via its rulemaking process. The DOE has also requested, through the Permit Modification Request (PMR) process, that the NMED modify the approved panel closure system specified in Permit Attachment G1. The WIPP facility is carved out of a bedded salt formation 655 meters below the surface of southeast New Mexico. Condition 1 of the Final Certification Rulemaking specifies that the waste panels be closed using Option D which is a combination of a Salado mass concrete (SMC) monolith and an isolation/explosion block wall. The Option D design was also accepted as the panel closure of choice by the NMED. After twelve years of waste handling

  19. Evaluation of the WIPP Project`s compliance with the EPA radiation protection standards for disposal of transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M. [Environmental Evaluation Group, Albuquerque, NM (United States)]|[Environmental Evaluation Group, Carlsbad, NM (United States)

    1998-03-01

    The US Environmental Protection Agency`s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP`s compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy`s (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA`s proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA`s responses to EEG`s comments.

  20. WASTE ISOLATION PILOT PLANT (WIPP): THE NATIONS' SOLUTION TO NUCLEAR WASTE STORAGE AND DISPOSAL ISSUES

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, Tammy Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-07-17

    In the southeastern portion of my home state of New Mexico lies the Chihuahauan desert, where a transuranic (TRU), underground disposal site known as the Waste Isolation Pilot Plant (WIPP) occupies 16 square miles. Full operation status began in March 1999, the year I graduated from Los Alamos High School, in Los Alamos, NM, the birthplace of the atomic bomb and one of the nation’s main TRU waste generator sites. During the time of its development and until recently, I did not have a full grasp on the role Los Alamos was playing in regards to WIPP. WIPP is used to store and dispose of TRU waste that has been generated since the 1940s because of nuclear weapons research and testing operations that have occurred in Los Alamos, NM and at other sites throughout the United States (U.S.). TRU waste consists of items that are contaminated with artificial, man-made radioactive elements that have atomic numbers greater than uranium, or are trans-uranic, on the periodic table of elements and it has longevity characteristics that may be hazardous to human health and the environment. Therefore, WIPP has underground rooms that have been carved out of 2,000 square foot thick salt formations approximately 2,150 feet underground so that the TRU waste can be isolated and disposed of. WIPP has operated safely and successfully until this year, when two unrelated events occurred in February 2014. With these events, the safety precautions and measures that have been operating at WIPP for the last 15 years are being revised and improved to ensure that other such events do not occur again.

  1. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 3, Model parameters: Sandia WIPP Project

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-29

    This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter.

  2. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Chapter D, Appendix D1 (beginning), Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Lappin, A. R.

    1993-03-01

    The Waste Isolation Pilot Plant (WIPP), which is designed for receipt, handling, storage, and permanent isolation of defense-generated transuranic wastes, is being excavated at a depth of approximately 655 m in bedded halites of the Permian Salado Formation of southeastern New Mexico. Site-characterization activities at the present WIPP site began in 1976. Full construction of the facility began in 1983, after completion of ``Site and Preliminary Design Validation`` (SPDV) activities and reporting. Site-characterization activities since 1983 have had the objectives of updating or refining the overall conceptual model of the geologic, hydrologic, and structural behavior of the WIPP site and providing data adequate for use in WIPP performance assessment. This report has four main objectives: 1. Summarize the results of WIPP site-characterization studies carried out since the spring of 1983 as a result of specific agreements between the US Department of Energy and the State of New Mexico. 2. Summarize the results and status of site-characterization and facility-characterization studies carried out since 1983, but not specifically included in mandated agreements. 3. Compile the results of WIPP site-characterization studies into an internally consistent conceptual model for the geologic, hydrologic, geochemical, and structural behavior of the WIPP site. This model includes some consideration of the effects of the WIPP facility and shafts on the local characteristics of the Salado and Rustler Formations. 4. Discuss the present limitations and/or uncertainties in the conceptual geologic model of the WIPP site and facility. The objectives of this report are limited in scope, and do not include determination of whether or not the WIPP Project will comply with repository-performance criteria developed by the US Environmental Protection Agency (40CFR191).

  3. Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-12-01

    This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

  4. Stable isotope study of soil water, WIPP site New Mexico: estimation of recharge to Rustler aquifers

    International Nuclear Information System (INIS)

    Campbell, A.R.; Phillips, F.M.; Vanlandingham, R.J.

    1996-01-01

    Defining the hydrologic setting of the Waste Isolation Pilot Plant (WIPP) is an important step for site characterization and performance assessment. From past research there is a controversy about the timing of recharge to the aquifers in the Rustler Formation which overlies the repository. The stable isotopic composition (δD and δD 18 O) of the water has been used in this argument but with ambiguous conclusions. Soil cores from WIPP have been sampled for δD, δD 18 O, Cl - and water content. The data indicate that there is a small amount of infiltration (.2 to 2 mm/yr) through the desert soil. The δD and δD 18 O analyses suggest that meteoric water in the area can have a stable isotope composition similar to that in the Rustler Fm. Further supporting evidence come from the isotopic composition of drip and pool waters in nearby Carlsbad Caverns. This indicates that the water in the Rustler Fm. need not have been recharged in the past (>10,000 yrs.) under different climatic conditions. (author) 8 figs., 2 tabs., 16 refs

  5. WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2000-05-23

    This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

  6. WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2000-01-01

    This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

  7. Results from simulated remote-handled transuranic waste experiments at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1992-01-01

    Multi-year, simulated remote-handled transuranic waste (RH TRU, nonradioactive) experiments are being conducted underground in the Waste Isolation Pilot-Plant (WIPP) facility. These experiments involve the near-reference (thermal and geometrical) testing of eight full size RH TRU test containers emplaced into horizontal, unlined rock salt boreholes. Half of the test emplacements are partially filled with bentonite/silica-sand backfill material. All test containers were electrically heated at about 115 W/each for three years, then raised to about 300 W/each for the remaining time. Each test borehole was instrumented with a selection of remote-reading thermocouples, pressure gages, borehole vertical-closure gages, and vertical and horizontal borehole-diameter closure gages. Each test emplacements was also periodically opened for visual inspections of brine intrusions and any interactions with waste package materials, materials sampling, manual closure measurements, and observations of borehole changes. Effects of heat on borehole closure rates and near-field materials (metals, backfill, rock salt, and intruding brine) interactions were closely monitored as a function of time. This paper summarizes results for the first five years of in situ test operation with supporting instrumentation and laboratory data and interpretations. Some details of RH TRU waste package materials, designs, and assorted underground test observations are also discussed. Based on the results, the tested RH TRU waste packages, materials, and emplacement geometry in unlined salt boreholes appear to be quite adequate for initial WIPP repository-phase operations

  8. The influence of aerosol particle collection mechanisms on the WIPP alpha-6 CAM detection efficiency

    International Nuclear Information System (INIS)

    Bartlett, W.T.

    1996-01-01

    Alpha-6 continuous air monitors (CAMs) are used at the Waste Isolation Pilot Plant (WIPP) in the underground salt mine proposed for transuranic waste disposal near Carlsbad, New Mexico. Previous reviews of CAM operational data indicate that alpha spectra, background subtract methods, and alpha detection efficiency are significantly affected by salt aerosol. Gravimetric analyses of CAM sampling filters indicate that sampling-filter salt deposits are of sufficient magnitude to cause spectral degradation and efficiency losses. It was previously assumed that salt aerosol was mechanically collected on the surface of the sampling filter, but other aerosol collection mechanisms, such as electrostatic, diffusional, and inertial impaction, cannot be ruled out. Microscopic observations of the sampling filters indicate that particle form complex structures on the sampling filter surface, and that electrostatic, diffusional, and inertial impaction are occurring. Aerosol particles are likely to penetrate the complex surface salt matrix, and alpha particle energy will be lost before reaching the CAM detector. Penetration of a polydisperse aerosol into the sampling-filter salt deposits accounts for degraded spectra and efficiency loss observed at the WIPP. It was recommended that CAMs should not be considered operational when 0.5 to 2.0 mg cm -2 of sampling-filter salt is present on the sampling filter

  9. Potential release scenario and radiological consequence evaluation of mineral resources at WIPP

    International Nuclear Information System (INIS)

    Little, M.S.

    1982-05-01

    This report has reviewed certain of the natural resources which may be found at the site of the nuclear waste repository being considered for southeastern New Mexico, and discussed the scenarios which have been used to estimate the radiological consequences from the mining of these resources several hundred years after the radioactive waste has been emplaced. It has been concluded that the radiological consequences of the mining of potash or hydrocarbons (mostly natural gas) are probably bounded by the consequences of hydrologic breach scenarios already considered by the US Department of Energy, and by reports of EEG. These studies conclude that the resultant doses would not constitute a significant threat to public health. This report also evaluates the radiological consequences of solution mining of halite at the WIPP site. Although such mining in the Delaware Basin and particularly at the WIPP site, is not likely at the present time, significant economic, social or climatic changes a few hundred years after emplacement may make these resources more attractive. The DOE did not consider such mining at the site credible

  10. Geochemistry of Salado Formation brines recovered from the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Abitz, R.; Myers, J.; Drez, P.; Deal, D.

    1990-01-01

    Intergranular brines recovered from the repository horizon of the Waste Isolation Pilot Plant (WIPP) have major- and trace-element compositions that reflect seawater evaporation and diagenetic processes. Brines obtained from repository drill holes are heterogenous with respect to composition, but their compositional fields are distinct from those obtained from fluid inclusions in WIPP halite. The heterogeneity of brine compositions within the drill-hole population indicates a lack of mixing and fluid homogenization within the salt at the repository level. Compositional differences between intergranular (drill hole) and intragranular (fluid inclusions) brines is attributed to isolation of the latter from diagenetic fluids that were produced from dehydration reactions involving gypsum and clay minerals. Modeling of brine-rock equilibria indicates that equilibration with evaporite minerals controls the concentrations of major elements in the brine. Drill-hole brines are in equilibrium with the observed repository minerals halite, anhydrite, magnesite, polyhalite and quartz. The equilibrium model supports the derivation of drill-hole brines from near-field fluid, rather than large-scale vertical migration of fluids from the overlying Rustler or underlying Castile Formations. 13 refs., 6 figs., 6 tabs

  11. Petrographic study of evaporite deformation near the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Borns, D.J.

    1983-06-01

    The Delaware Basin of southeastern New Mexico contains about 1000 m of layered evaporites. Areas in the northern Delaware Basin, bordering the Capitan reef, have anomalous seismic reflection characteristics, such as loss in reflector continuity. Core from holes within this zone exhibits complex mesoscopic folds and extension structures. On a larger scale, anticlines and synclines are indicated by structure contours based on boreholes. The deformation is probably gravity-driven. Such a process is initiated by basin tilting during either a Mesozoic or Cenozoic period of uplift. Small-scale structures suggest that deformation was episodic with an early, syndepositional stage of isoclinal folding. Later, open-to-tight asymmetric folding is more penetrative and exhibits a sense of asymmetry opposite to that of the earlier isoclinal folding. The younger folds are associated with development of zonal crenulation cleavage and microboundinage of more competent carbonate layers. At the same time, halite beds developed dimensional fabrics and convolute folds in anhydrite stringers. Late-stage, near-vertical fractures formed in competent anhydrite layers. Microscopic textures exhibit rotated anhydrite porphyroblasts, stress shadow growth, and microboundinage. Except during late-stage deformation, anhydrite and halite recrystallized synkinematically. Drastic strength reduction in anhydrites through dynamic recrystallization occurs experimentally near 200 0 C. However, evaporites of the WIPP site never experienced temperatures > 40 0 C. Microscopic fabrics and P, T history of the evaporites suggest that pressure solution was the active mechanism during deformation of evaporites at the WIPP site

  12. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

  13. Guidelines for developing certification programs for newly generated TRU waste

    International Nuclear Information System (INIS)

    Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.; Geoffrion, R.R.

    1983-05-01

    These guidelines were prepared with direction from the US Department of Energy (DOE) Transuranic (TRU) Waste Management Program in support of the DOE effort to certify that newly generated TRU wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The guidelines provide instructions for generic Certification Program preparation for TRU-waste generators preparing site-specific Certification Programs in response to WIPP requirements. The guidelines address all major aspects of a Certification Program that are necessary to satisfy the WIPP Waste Acceptance Criteria and their associated Compliance Requirements and Certification Quality Assurance Requirements. The details of the major element of a Certification Program, namely, the Certification Plan, are described. The Certification Plan relies on supporting data and control documentation to provide a traceable, auditable account of certification activities. Examples of specific parts of the Certification Plan illustrate the recommended degree of detail. Also, a brief description of generic waste processes related to certification activities is included

  14. 40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.

    Science.gov (United States)

    2010-07-01

    ... accordance with § 194.24(c)(4), to confirm that the total amount of each waste component that will be... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Approval process for waste shipment from waste generator sites for disposal at the WIPP. 194.8 Section 194.8 Protection of Environment...

  15. Numerical simulation of ground-water flow in the Culebra dolomite at the Waste Isolation Pilot Plant (WIPP) site: Second interim report

    International Nuclear Information System (INIS)

    LaVenue, A.M.; Haug, A.; Kelley, V.A.

    1988-03-01

    This hydrogeologic modeling study has been performed as part of the regional hydrologic characterization of the Waste Isolation Pilot Plant (WIPP) Site in southeastern New Mexico. The study resulted in an estimation of the transmissivity distrubution, hydraulic potentials, flow field, and fluid densities in the Culebra Dolomite Member of the Permian Rustler Formation at the WIPP site. The three-dimensional finite-difference code SWIFT-II was employed for the numerical modeling, using variable-fluid-density and a single-porosity formulation. The modeled area includes and extends beyond the WIPP controlled zone (Zone 3). The work performed consisted of modeling the hydrogeology of the Culebra using two approaches: (1) steady-state modeling to develop the best estimate of the undisturbed head distribution, i.e., of the situation before sinking if the WIPP shafts, which began in 1981; and (2) superimposed transient modeling of local hydrologic responses to excavation of the three WIPP shafts at the center of the WIPP site, as well as to various well tests. Boundary conditions (prescribed constant fluid pressures and densities) were estimated using hydraulic-head and fluid-density data obtained from about 40 wells at and near the WIPP site. The transient modeling used the calculated steady-state freshwater heads as initial conditions. 107 refs., 112 figs., 22 tabs

  16. Numerical simulation of ground-water flow in the Culebra dolomite at the Waste Isolation Pilot Plant (WIPP) site: Second interim report

    Energy Technology Data Exchange (ETDEWEB)

    LaVenue, A.M.; Haug, A.; Kelley, V.A.

    1988-03-01

    This hydrogeologic modeling study has been performed as part of the regional hydrologic characterization of the Waste Isolation Pilot Plant (WIPP) Site in southeastern New Mexico. The study resulted in an estimation of the transmissivity distrubution, hydraulic potentials, flow field, and fluid densities in the Culebra Dolomite Member of the Permian Rustler Formation at the WIPP site. The three-dimensional finite-difference code SWIFT-II was employed for the numerical modeling, using variable-fluid-density and a single-porosity formulation. The modeled area includes and extends beyond the WIPP controlled zone (Zone 3). The work performed consisted of modeling the hydrogeology of the Culebra using two approaches: (1) steady-state modeling to develop the best estimate of the undisturbed head distribution, i.e., of the situation before sinking if the WIPP shafts, which began in 1981; and (2) superimposed transient modeling of local hydrologic responses to excavation of the three WIPP shafts at the center of the WIPP site, as well as to various well tests. Boundary conditions (prescribed constant fluid pressures and densities) were estimated using hydraulic-head and fluid-density data obtained from about 40 wells at and near the WIPP site. The transient modeling used the calculated steady-state freshwater heads as initial conditions. 107 refs., 112 figs., 22 tabs.

  17. Nurse-administered propofol sedation for endoscopy

    DEFF Research Database (Denmark)

    Jensen, J T; Vilmann, P; Horsted, T

    2011-01-01

    BACKGROUND AND STUDY AIMS: The aim of the present study was to perform a risk analysis during the implementation phase of nurse-administered propofol sedation (NAPS) and to validate our structured training program. PATIENTS AND METHODS: A structured training program was developed both for endosco......BACKGROUND AND STUDY AIMS: The aim of the present study was to perform a risk analysis during the implementation phase of nurse-administered propofol sedation (NAPS) and to validate our structured training program. PATIENTS AND METHODS: A structured training program was developed both...... for endoscopists and for endoscopy nurses who were administering propofol sedation. The nurses' program comprised a 6-week course including theoretical and practical training in airway management, and the endoscopists' program consisted of 2.5 h of theory and a short course in practical airway management....... In the implementation phase, data from 1822 endoscopic procedures in 1764 patients were prospectively collected. All adverse events related to sedation were recorded (defined as oxygen saturation change in blood pressure > 20 mmHg). RESULTS: 78 cases...

  18. Evaluation of the WIPP Project's compliance with the EPA radiation protection standards for disposal of transuranic waste

    International Nuclear Information System (INIS)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M.

    1998-03-01

    The US Environmental Protection Agency's (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP's compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy's (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA's proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA's responses to EEG's comments

  19. WIPP conceptual design report. Addendum D. A report to Holmes and Narver, Inc., Anaheim, California on alternative energy sources for Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    1977-03-01

    This report presents the results of a technical and economic analysis of alternative methods of meeting the energy needs of a proposed Waste Isolation Pilot Plant (WIPP) to be located in southeastern New Mexico. The WIPP is a facility for underground storage of radioactive wastes in a deep salt bed. The report analyzes a total of sixteen possible methods for meeting WIPP energy requirements, consisting of purchased electricity and on-site generation in various combinations from full purchased to full on-site

  20. Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

    International Nuclear Information System (INIS)

    Connolly, M.J.; Sayer, D.L.

    1993-11-01

    EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

  1. A probabilistic analysis of a catastrophic transuranic waste hoist accident at the WIPP

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.; Stanford Univ., CA

    1993-06-01

    This report builds upon the extensive and careful analyses made by the DOE of the probability of failure of the waste hoist, and more particularly on the probability of failure of a major component, the hydraulic brake system. The extensive fault tree analysis prepared by the DOE was the starting point of the present report. A key element of this work is the use of probability distributions rather than so-called point estimates to describe the probability of failure of an element. One of the authors (MAG) developed the expressions for the probability of failure of the brake system. The second author (TJS) executed the calculations of the final expressions for failure probabilities. The authors hope that this work will be of use to the DOE in its evaluation of the safety of the waste hoist, a key element at the WIPP

  2. In situ testing of titanium and mild steel nuclear waste containers at the WIPP site

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1990-01-01

    An overview of the Waste Isolation Pilot Plant (WIPP) in situ tests on the corrosion of titanium and mild steel for high level waste containers is presented. The tests at Sandia have moved out of the laboratory into a test underground facility in order to evaluate the performance of the waste package material. The tests are being performed under both near-reference and accelerated salt repository conditions. Some containers are filled with high level waste glass (non-radioactive); others contain electric heaters. Backfill material is either bentonite/sand or crushed salt. In other tests metals and glasses are exposed directly to brine. The tests are designed to study the corrosion and metallurgy of the canister and overpack materials; the feasibility and performance of backfill materials; and near-field effects such as brine migration

  3. Probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.; Stanford Univ., CA

    1998-01-01

    In its most recent report on the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP), the annual failure rate is calculated to be 1.3E(-7)(1/yr), rounded off from 1.32E(-7). A calculation by the Environmental Evaluation Group (EEG) produces a result that is about 4% higher, namely 1.37E(-7)(1/yr). The difference is due to a minor error in the US Department of Energy (DOE) calculations in the Westinghouse 1996 report. WIPP's hoist safety relies on a braking system consisting of a number of components including two crucial valves. The failure rate of the system needs to be recalculated periodically to accommodate new information on component failure, changes in maintenance and inspection schedules, occasional incidents such as a hoist traveling out-of-control, either up or down, and changes in the design of the brake system. This report examines DOE's last two reports on the redesigned waste hoist system. In its calculations, the DOE has accepted one EEG recommendation and is using more current information about the component failures rates, the Nonelectronic Parts Reliability Data (NPRD). However, the DOE calculations fail to include the data uncertainties which are described in detail in the NPRD reports. The US Nuclear Regulatory Commission recommended that a system evaluation include mean estimates of component failure rates and take into account the potential uncertainties that exist so that an estimate can be made on the confidence level to be ascribed to the quantitative results. EEG has made this suggestion previously and the DOE has indicated why it does not accept the NRC recommendation. Hence, this EEG report illustrates the importance of including data uncertainty using a simple statistical example

  4. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2001-01-01

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  5. Oak Ridge National Laboratory Transuranic Waste Certification Program

    International Nuclear Information System (INIS)

    Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

    1988-08-01

    The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs

  6. Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 7: Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    This permit application (Vol. 7) for the WIPP facility contains appendices related to the following information: Ground water protection; personnel; solid waste management; and memorandums concerning environmental protection standards.

  7. Resource Conservation and Recovery Act: Part B, Permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revison 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1992-03-01

    This report contains information related to the permit application for the WIPP facility. Information is presented on solid waste management; personnel safety; emergency plans; site characterization; applicable regulations; decommissioning; and ground water monitoring requirements.

  8. Performance demonstration program plan for RCRA constituent analysis of solidified wastes

    International Nuclear Information System (INIS)

    1995-06-01

    Performance Demonstration Programs (PDPS) are designed to help ensure compliance with the Quality Assurance Objectives (QAOs) for the Waste Isolation Pilot Plant (WIPP). The PDPs are intended for use by the Department of Energy (DOE) Carlsbad Area Office (CAO) to assess and approve the laboratories and other measurement facilities supplying services for the characterization of WIPP TRU waste. The PDPs may also be used by CAO in qualifying laboratories proposing to supply additional analytical services that are required for other than waste characterization, such as WIPP site operations. The purpose of this PDP is to test laboratory performance for the analysis of solidified waste samples for TRU waste characterization. This performance will be demonstrated by the successful analysis of blind audit samples of simulated, solidified TRU waste according to the criteria established in this plan. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess laboratory performance regarding compliance with the QAOs. The concentration of analytes in the PDP samples will address levels of regulatory concern and will encompass the range of concentrations anticipated in actual waste characterization samples. Analyses that are required by the WIPP to demonstrate compliance with various regulatory requirements and which are included in the PDP must be performed by laboratories that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses and the samples on which they are performed are referred to as WIPP samples for the balance of this document

  9. Fluid injection for salt water disposal and enhanced oil recovery as a potential problem for the WIPP: Proceedings of a June 1995 workshop and analysis

    International Nuclear Information System (INIS)

    Silva, M.K.

    1996-08-01

    The Waste Isolation Pilot Plant (WIPP) is a facility of the U.S. Department of Energy (DOE), designed and constructed for the permanent disposal of transuranic (TRU) defense waste. The repository is sited in the New Mexico portion of the Delaware Basin, at a depth of 655 meters, in the salt beds of the Salado Formation. The WIPP is surrounded by reserves and production of potash, crude oil and natural gas. In selecting a repository site, concerns about extensive oil field development eliminated the Mescalero Plains site in Chaves County and concerns about future waterflooding in nearby oil fields helped eliminate the Alternate II site in Lea County. Ultimately, the Los Medanos site in Eddy County was selected, relying in part on the conclusion that there were no oil reserves at the site. For oil field operations, the problem of water migrating from the injection zone, through other formations such as the Salado, and onto adjacent property has long been recognized. In 1980, the DOE intended to prohibit secondary recovery by waterflooding in one mile buffer surrounding the WIPP Site. However, the DOE relinquished the right to restrict waterflooding based on a natural resources report which maintained that there was a minimal amount of crude oil likely to exist at the WIPP site, hence waterflooding adjacent to the WIPP would be unlikely. This document presents the workshop presentations and analyses for the fluid injection for salt water disposal and enhanced oil recovery utilizing fluid injection and their potential effects on the WIPP facility

  10. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2002-01-01

    This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable

  11. New Payload Initiatives for Shipments to WIPP Will Expand DoE's Ability to Dispose of Transuranic Waste

    International Nuclear Information System (INIS)

    Nelson, R.A.; White, D.S.

    2009-01-01

    The Waste Isolation Pilot Plant (WIPP) shipping and disposal operations currently employ two different disposal methods: one for Contact Handled (CH) waste and another for Remote Handled (RH) waste. CH waste is emplaced in a variety of payload container configurations on the floor of each disposal room. In contrast, RH waste is packaged into a single type of canister and emplaced in pre-drilled holes in the walls of disposal rooms. CH waste containers are shipped to WIPP in unshielded Type B packages licensed by the Nuclear Regulatory Commission (NRC), whereas RH waste is shipped in similarly licensed shielded packages that also include lead to attenuate higher energy gamma photons to meet transportation dose limits. Because the lead employed in the existing shipping packages (called the RH-72B) does not attenuate neutrons, this transportation and disposal system is not able to accommodate neutron emitting waste streams. Recently, DOE proposed the use of gamma-shielded containers that would allow packaging of gamma-emitting RH waste in a configuration that could be shipped in a CH shipping package and emplaced on the floor of WIPP disposal rooms, while still being counted against repository capacity limits as RH waste. The gamma-shielded containers can be handled by contact. The NRC reviewed the license application for these gamma-shielded containers and the approval is pending, but expected at the end of 2008. Concurrent with the submission to NRC, DOE submitted a planned change request to the U.S. Environmental Protection Agency to allow the placement of the gamma shielded containers in the repository with other CH waste. This paper presents an update of the status of DoE's gamma-shielded container initiative. In addition to the gamma-shielded container, to increase the versatility of the RH shipping process, the Department of Energy (DOE) is considering the development of a new method to shield neutron-emitting waste, which would be shipped and emplaced using

  12. Review comments on Environmental Analysis Cost Reduction Proposals (WIPP-DOE-136), July 1982

    International Nuclear Information System (INIS)

    Channell, J.K.

    1982-11-01

    The cost reduction proposals have the laudable goal of significantly reducing the total capital And operating cost connected with WIPP. Furthermore, since the proposed changes would reduce the size and operating rate of the project, they would be expected to have decreased environmental And socioeconomic impacts. However, some of these cost reduction proposals do decrease factors of safety in various components of the project or trade off one type of environmental detriment for another. The report does not contain sufficient detail to justify all of the conclusions reached; more discussion and quantitative information (including costs) is necessary in some cases. Also, there are places where the report is unclear or contradictory. Without a more detailed evaluation, EEG is unable to conclude that each of these cost reduction proposals either has a net environmental/health and safety benefit or a cost savings that justifies a net detriment. A revised Environmental Analysis (EA) should either include additional information or specifically reference backup documents where these conclusions have been justified. In addition, the EA needs to be revised to include the effect of the recently announced (11/18/82) decision by DOE to relocate the underground waste storage areas of the repository to the south

  13. Background radiation measurements at the Waste Isolation Pilot Plant (WIPP) Site, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Minnema, D.M.; Brewer, L.W.

    1983-09-01

    A series of background radiation measurements was performed at the Waste Isolation Pilot Plant (WIPP) Site, Carlsbad, New Mexico. The survey consisted of gross gamma and gamma spectral measurements of the radiation fields, soil and salt grab sample gamma analysis, and radon and working level measurements. The survey included locations at the surface and also within the mine itself. Background radiation levels on the surface were measured to average 7.65 microR/hour, and 0.7 microR/hour within the mine. Radon and working levels were at or below detection levels at all locations, and the radon concentration was estimated to be about 0.01 pCi/liter on the surface based on spectral measurements. The spectral measurements were performed using an intrinsic germanium spectrometer, and calculations from the spectra indicated that potassium-40 contributed about 28% to the surface level dose rates, natural uranium daughters contributed about 64%, and cesium-137 from weapons testing fallout contributed about 8%. In the mine potassium-40 was the only identifiable contributor to the dose rate

  14. Basic data report for drillholes at the H-11 complex (Waste Isolation Pilot Plant-WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Mercer, J.W. (Sandia National Labs., Albuquerque, NM (USA)); Snyder, R.P. (Geological Survey, Denver, CO (USA))

    1990-05-01

    Drillholes H-11b1, H-11b2, and H-11b3 were drilled from August to December 1983 for site characterization and hydrologic studies of the Culebra Dolomite Member of the Upper Permian Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. In October 1984, the three wells were subjected to a series of pumping tests designed to develop the wells, provide information on hydraulic communication between the wells, provide hydraulic properties information, and to obtain water samples for quality of water measurements. Based on these tests, it was determined that this location would provide an excellent pad to conduct a convergent-flow non-sorbing tracer test in the Culebra dolomite. In 1988, a fourth hole (H-11b4) was drilled at this complex to provide a tracer-injection hole for the H-11 convergent-flow tracer test and to provide an additional point at which the hydraulic response of the Culebra H-11 multipad pumping test could be monitored. A suite of geophysical logs was run on the drillholes and was used to identify different lithologies and aided in interpretation of the hydraulic tests. 4 refs., 6 figs., 6 tabs.

  15. Basic data report for drillholes at the H-11 complex (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    Mercer, J.W.; Snyder, R.P.

    1990-05-01

    Drillholes H-11b1, H-11b2, and H-11b3 were drilled from August to December 1983 for site characterization and hydrologic studies of the Culebra Dolomite Member of the Upper Permian Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. In October 1984, the three wells were subjected to a series of pumping tests designed to develop the wells, provide information on hydraulic communication between the wells, provide hydraulic properties information, and to obtain water samples for quality of water measurements. Based on these tests, it was determined that this location would provide an excellent pad to conduct a convergent-flow non-sorbing tracer test in the Culebra dolomite. In 1988, a fourth hole (H-11b4) was drilled at this complex to provide a tracer-injection hole for the H-11 convergent-flow tracer test and to provide an additional point at which the hydraulic response of the Culebra H-11 multipad pumping test could be monitored. A suite of geophysical logs was run on the drillholes and was used to identify different lithologies and aided in interpretation of the hydraulic tests. 4 refs., 6 figs., 6 tabs

  16. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  17. The Rustler Formation at the WIPP [Waste Isolations Pilot Plant] site: Report of a workshop on the geology and hydrology of the Rustler Formation as it relates to the WIPP Project

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1987-02-01

    This workshop contained eight papers characterizing the Rustler Formation at the WIPP site in New Mexico. Four of these reports were processed separately for the data bases. Information contained in the four remaining papers is available in journal articles or in the reports of other conferences and included discussions of ground water flow through the Rustler Formation, the potential migration of leached radionuclides in this rock, the effects of mineral dissolution on the removal of underlying salt deposits, and a possible pathway for radionuclide migration into the biosphere

  18. Densities and species composition of the avifauna of the Los Medanos WIPP site, southeastern New Mexico

    International Nuclear Information System (INIS)

    Ligon, J.D.; Haydock, J.

    1981-01-01

    Data were gathered in various habitat types to determine annual fluctuations in species diversity and relative abundance, breeding densities, reproductive success of White-necked Ravens and Harris Hawks, fall and spring migrant species and to collect voucher specimens for the site. Four Emlen transects were surveyed in four habitat types during the summer of 1980. These transects were used monthly in May, June and July to determine densities of breeding and non-breeding birds. Active White-necked Raven and Harris Hawk nests were located by checking all conspicuous nests. The nests were checked several times during the nesting stage to determine nest success. During 1980, eleven new species and two new families were added to the list of birds seen on or near the WIPP site. The list now totals 133 species representing 38 families. White-necked Raven nesting success was slightly lower in 1980 than in 1979. Average clutch size in 1980 was 5.5, which is 3.5% less than in 1979 and 19% greater than in 1978. The average number of birds fledged per nest was surprisingly similar over the past three years despite fairly large climatic differences. Success of Harris Hawk nesting was very low in the autumn of 1980 due principally to bad weather. The overall density of breeding birds was lower in 1980 than in 1979 in all habitat types. The overall density was also lower in 1980 than in 1978 in all habitat types except mesquite-grassland. Many species showed larger year-to-year fluctuations in numbers. Mourning Dove density, for example, dropped from 76.9 to 11.2 individuals per square kilometer in the hummock-mesquite habitat. Voucher specimens have been collected for 69 of the 133 species seen on the Los Medanos site

  19. Simultaneous Thermal Analysis of WIPP and LANL Waste Drum Samples: A Preliminary Report

    Energy Technology Data Exchange (ETDEWEB)

    Wayne, David M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-19

    On Friday, February 14, 2014, an incident in P7R7 of the WIPP underground repository released radioactive material into the environment. The direct cause of the event was a breached transuranic (TRU) waste container, subsequently identified as Drum 68660. Photographic and other evidence indicates that the breach of 68660 was caused by an exothermic event. Subsequent investigations (Britt, 2015; Clark and Funk, 2015; Wilson et al., 2015; Clark, 2015) indicate that the combination of nitrate salts, pH neutralizing chemicals, and organic-based adsorbent represented a potentially energetic mixture. The materials inside the breached steel drum consisted of remediated, 30- to 40-year old, Pu processing wastes from LANL. The contents were processed and repackaged in 2014. Processing activities at LANL included: 1) neutralization of acidic liquid contents, 2) sorption of the neutralized liquid, and 3) mixing of acidic nitrate salts with an absorber to meet waste acceptance criteria. The contents of 68660 and its sibling, 68685, were derived from the same parent drum, S855793. Drum S855793 originally contained ten plastic bags of acidic nitrate salts, and four bags of mixed nitrate and oxalate salts generated in 1985 by Pu recovery operations. These salts were predominantly oxalic acid, hydrated nitrate salts of Mg, Ca, and Fe, anhydrous Na(NO3), and minor amounts of anhydrous and hydrous nitrate salts of Pb, Al, K, Cr, and Ni. Other major components include sorbed water, nitric acid, dissolved nitrates, an absorbent (Swheat Scoop®) and a neutralizer (KolorSafe®). The contents of 68660 are described in greater detail in Appendix E of Wilson et al. (2015)

  20. Scientific studies in support of the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Chu, M.S.Y.; Weart, W.D.

    1996-01-01

    The DOE submitted a Compliance Certification Application for WIPP in october, 1996. A critical part of this application was a Performance Assessment which predicts the cumulative radioactive release to the accessible environment over a time period of 10,000 years. Comparison of this predicted release to the EPA standard shows a comfortable margin of compliance. The scientific understanding that was critical to developing this assessment spans a broad range of geotechnical disciplines, and required a thorough understanding of the site's geology and hydrology. Evaluation of the geologic processes which are active in the site region establishes that there will be no natural breach of site integrity for millions of years, far longer than the 10,000 year regulatory period. Inadvertent human intrusion is, therefore, the only credible scenario to lead to potential radioactive release to the accessible environment. To substantiate this conclusion and to quantify these potential releases from human intrusion, it has been necessary to develop an understanding of the following processes: salt creep and shaft seal efficacy; gas generation from organic decomposition of waste materials and anoxic corrosion of metals in the waste and waste packages; solubilities for actinides in brine; fluid flow in Salado formation rocks, and hydrologic transport of actinides in the overlying dolomite aquifers. Other issues which had to be evaluated to allow definition of breach scenarios were brine reservoir occurrences and their associated reservoir parameters, consequences of mining over the repository, and drilling for natural resources in the vicinity of the repository. Results of all these studies will be briefly summarized in this paper

  1. A conceptual performance assessment model of the dissolved actinide source term for the WIPP

    International Nuclear Information System (INIS)

    Weiner, R.F.; Stockman, C.T.; Wang, Y.; Novak, C.F.

    1996-01-01

    This paper presents a performance assessment model of dissolved actinide concentrations for the Waste Isolation Pilot Plant (WIPP). The model assesses the concentration of each actinide oxidation state and combines these concentrations with an oxidation state distribution. The chemical behavior of actinides in the same oxidation state is presumed to be very similar for almost all situations, but exceptions arising from experimental evidence are accommodated. The code BRAGFLO calculates the gas pressure, brine mass, gas volume, and mass of remaining Fe and cellulosics for each time step and computational cell. The total CO 2 in the repository and dissolved Ca(OH) 2 is estimated. Lookup tables are constructed for pmH and f(CO 2 ) as a function of brine type and volume, moles of CO 2 , and Ca(OH) 2 . Amounts of five soluble complexants are considered. A model based on the formulation of Harvie et al. produces tables of solubilities for each actinide oxidation state as a function of pmH, f(CO 2 ), brine composition, and complexant. Experimental data yield lookup tables of fractions of Th, U, Np, Pu, and Am in each oxidation state as a function of f(CO 2 ) and complexant. The tables are then used to provide a concentration of a particular actinide at particular values of pmH and f(CO 2 ). Under steady-state conditions, the oxidation state of each actinide that is most stable in the particular chemical environment controls the concentration of that actinide in solution. In the absence of steady-state conditions, the oxidation state distribution of interest is that of the dissolved actinide, and the oxidation states may be treated as if they were separate compounds

  2. Report of biological investigations at the Los Medanos Waste Isolation Pilot Plant (WIPP) area of New Mexico during FY 1978

    International Nuclear Information System (INIS)

    Best, T.L.; Neuhauser, S.

    1980-03-01

    The US Department of Energy is considering the construction of a Waste Isolation Pilot Plant (WIPP) in Eddy County, NM. This location is approximately 40 km east of Carlsbad, NM. Biological studies during FY 1978 were concentrated within a 5-mi radius of drill hole ERDA 9. Additional study areas have been established at other sites in the vicinity, e.g., the Gnome site, the salt lakes and several stations along the Pecos River southward from Carlsbad, NM, to the dam at Red Bluff Reservoir in Texas. The precise locations of all study areas are presented and their biology discussed

  3. Rustler Formation in the waste handling and exhaust shafts, Waste Isolation Pilot Plant (WIPP) site, southeastern New Mexico

    International Nuclear Information System (INIS)

    Holt, R.M.; Powers, D.W.

    1987-01-01

    The Permian Rustler Formation was recently examined in detail in two shafts at the WIPP site: the waste handling shaft (waste shaft) and the exhaust shaft. Fresh exposures of the Rustler in the shafts exhibited abundant primary sedimentary structures. The abundance of primary sedimentary structures observed in the shafts is unequaled in previously described sections. Data are reported here in their stratigraphic context as an initial basis for evaluation of depositional environments of the Rustler and reevaluating the role of dissolution in the formation of the Rustler. 10 refs

  4. Report of biological investigations at the Los Medanos Waste Isolation Pilot Plant (WIPP) area of New Mexico during FY 1978

    Energy Technology Data Exchange (ETDEWEB)

    Best, T.L.; Neuhauser, S. (eds.)

    1980-03-01

    The US Department of Energy is considering the construction of a Waste Isolation Pilot Plant (WIPP) in Eddy County, NM. This location is approximately 40 km east of Carlsbad, NM. Biological studies during FY 1978 were concentrated within a 5-mi radius of drill hole ERDA 9. Additional study areas have been established at other sites in the vicinity, e.g., the Gnome site, the salt lakes and several stations along the Pecos River southward from Carlsbad, NM, to the dam at Red Bluff Reservoir in Texas. The precise locations of all study areas are presented and their biology discussed.

  5. The development of WIPPVENT, a windows based interactive mine ventilation simulation software program at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    McDaniel, K.H.

    1995-01-01

    An interactive mine ventilation simulation software program (WIPPVENT) was developed at the Waste Isolation Pilot Plant (WIPP). The WIPP is a US Department of Energy (DOE) research and development project located near Carlsbad, New Mexico. The facility is designed to provide a permanent, safe underground disposal of US defense generated transuranic waste in bedded salt. In addition to it's regular functions, the underground ventilation system is engineered to prevent the uncontrolled spread of radioactive materials in the unlikely event of a release. To enhance the operability system, Westinghouse Electric Corporation has developed an interactive mine ventilation simulation software program (WIPPVENT). While WIPPVENT includes most of the functions of the commercially available simulation program VNETPC (copyright 1991 Mine Ventilation Services, Inc.), the user interface has been completely rewritten as a Windows reg-sign application and screen graphics have been added. WIPPVENT is designed to interact with the WIPP ventilation monitoring systems through the site wide Central Monitoring System

  6. Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

    International Nuclear Information System (INIS)

    Martell, M.A.; Hansen, F.; Weiner, R.

    1998-01-01

    Use of nature's laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia

  7. Solubility and sorption characteristics of uranium(VI) associated with rock samples and brines/groundwaters from WIPP and NTS

    International Nuclear Information System (INIS)

    Dosch, R.G.

    1981-01-01

    Solubility measurements for U(VI) in WIPP-related brines/groundwaters were made using initial U(VI) concentrations in the range of 1 to 50 μg/ml. Distribution coefficients (Kd) for U(VI) were determined for Culebra and Magenta dolomites using four different brine/groundwater compositions and for argillaceous shale and hornfels samples from the Eleana and Calico Hills Formation on NTS using a groundwater simulant typical of that area. The Kd's were evaluated as functions of: (1) U(VI) concentration (1.4 x 10 -4 to 1.4 μg/ml); (2) solution volume-to-rock mass ratios used in the measurements (5 to 100 ml/g), and for WIPP material only; (3) water composition (0 to 100% brine in groundwater); and (4) sample location in the Culebra and Magenta dolomite members of the Rustler Formation. The results indicate that if groundwater intrudes into a repository and leaches a waste form, significant concentrations of dissolved or colloidal U(VI) could be maintained in the liquid phase. Should these solutions enter an aquifer system, there are reasonable sets of conditions which could lead to subsequent migration of U(VI) away from the repository site

  8. Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

    Energy Technology Data Exchange (ETDEWEB)

    Martell, M.A.; Hansen, F.; Weiner, R.

    1998-10-01

    Use of nature`s laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia.

  9. Stochastic analysis of radionuclides travel times at the waste isolation pilot plant (WIPP), in New Mexico (U.S.A.)

    International Nuclear Information System (INIS)

    Capilla Roma, J. E.; Gomez-Hernandez, J. J.; Sahuquillo Herraiz, A.

    1999-01-01

    Multiple equally likely transmissivity fields that honor piezo metric head measurements are generated as input to a Monte-Carlo exercise, for the stochastic analysis of travel times in the Culebra dolomite overlaying the Waste Isolation Pilot Plant (WIPP) in New Mexico, USA. Results of the analysis show the importance of modeling variable-density flow as accurately as possible, and of including as much information as possible in the simulations of alternative scenarios. Results also unveil a channel of high transmissivity when transmissivity fields are conditioned to piezo metric data. This channel leads to important reductions of travel time from the WIPP area to the south boundary. The uncertainty of the boundary conditions is analyzed searching for alternative boundary conditions can be obtained that improve the reproduction of piezo metric data and yield a reduction of the minimum travel times to the south boundary. Results of the Monte-Carlo exercise are compared with those from a deterministic analysis showing the limitations of the latter method when trying to estimate extreme values or characterizing the uncertainty of their predictions. The report ends with a brief study on the impact of the small transmissivity measurements at location P-18, showing that its value is not consistent with the model of spatial variability inferred from the data and that it has an important effect on model predictions. (Author)

  10. Permeability of natural rock salt from the Waste Isolation Pilot Plant (WIPP) during damage evolution and healing

    International Nuclear Information System (INIS)

    Pfeifle, T.W.; Hurtado, L.D.

    1998-06-01

    The US Department of Energy has developed the Waste Isolation Pilot Plant (WIPP) in the bedded salt of southeastern New Mexico to demonstrate the safe disposal of radioactive transuranic wastes. Four vertical shafts provide access to the underground workings located at a depth of about 660 meters. These shafts connect the underground facility to the surface and potentially provide communication between lithologic units, so they will be sealed to limit both the release of hazardous waste from and fluid flow into the repository. The seal design must consider the potential for fluid flow through a disturbed rock zone (DRZ) that develops in the salt near the shafts. The DRZ, which forms initially during excavation and then evolves with time, is expected to have higher permeability than the native salt. The closure of the shaft openings (i.e., through salt creep) will compress the seals, thereby inducing a compressive back-stress on the DRZ. This back-stress is expected to arrest the evolution of the DRZ, and with time will promote healing of damage. This paper presents laboratory data from tertiary creep and hydrostatic compression tests designed to characterize damage evolution and healing in WIPP salt. Healing is quantified in terms of permanent reduction in permeability, and the data are used to estimate healing times based on considerations of first-order kinetics

  11. A review of WIPP [Waste Isolation Pilot Plant] repository clays and their relationship to clays of adjacent strata

    International Nuclear Information System (INIS)

    Krumhansl, J.L.; Kimball, K.M.; Stein, C.L.

    1990-12-01

    The Salado Formation is a thick evaporite sequence located in the Permian Delaware Basin of southeastern New Mexico. This study focuses on the intense diagenetic alteration that has affected the small amounts of clay, feldspar, and quartz washed into the basin during salt deposition. These changes are of more than academic interest since this formation also houses the WIPP (Waste Isolation Pilot Plant). Site characterization concerns warrant compiling a detailed data base describing the clays in and around the facility horizon. An extensive sampling effort was undertaken to address these programmatic issues as well as to provide additional insight regarding diagenetic mechanisms in the Salado. Seventy-five samples were collected from argillaceous partings in halite at the stratigraphic level of the Waste Isolation Pilot Plant (WIPP). These were compared with twenty-eight samples from cores of the Vaca Triste member of the Salado, a thin clastic unit at the top of the McNutt potash zone, and with a clay-rich sample from the lower contact of the Culebra Dolomite (in the overlying Rustler Formation). These settings were compared to assess the influence of differences in brine chemistry (i.e., halite and potash facies, normal to hypersaline marine conditions) and sediment composition (clays, sandy silt, dolomitized limestone) on diagenetic processes. 44 refs., 11 figs., 5 tabs

  12. Stochastic analysis of radionuclides travel times at the waste isolation pilot plant (WIPP), in New Mexico (U. S. A. )

    Energy Technology Data Exchange (ETDEWEB)

    Capilla Roma, J. E.; Gomez-Hernandez, J. J.; Sahuquillo Herraiz, A. (Universidad Politecnia de Valencia (Spain))

    1999-12-15

    Multiple equally likely transmissivity fields that honor piezo metric head measurements are generated as input to a Monte-Carlo exercise, for the stochastic analysis of travel times in the Culebra dolomite overlaying the Waste Isolation Pilot Plant (WIPP) in New Mexico, USA. Results of the analysis show the importance of modeling variable-density flow as accurately as possible, and of including as much information as possible in the simulations of alternative scenarios. Results also unveil a channel of high transmissivity when transmissivity fields are conditioned to piezo metric data. This channel leads to important reductions of travel time from the WIPP area to the south boundary. The uncertainty of the boundary conditions is analyzed searching for alternative boundary conditions can be obtained that improve the reproduction of piezo metric data and yield a reduction of the minimum travel times to the south boundary. Results of the Monte-Carlo exercise are compared with those from a deterministic analysis showing the limitations of the latter method when trying to estimate extreme values or characterizing the uncertainty of their predictions. The report ends with a brief study on the impact of the small transmissivity measurements at location P-18, showing that its value is not consistent with the model of spatial variability inferred from the data and that it has an important effect on model predictions. (Author)

  13. A comparison of geostatistically-based inverse techniques for use in performance assessment analyses at the WIPP site results from the Test Case No. 1

    International Nuclear Information System (INIS)

    Zimmerman, D.A.; Gallegos, D.P.

    1992-01-01

    The groundwater flow pathway in the Culebra Dolomite aquifer at the Waste Isolation Pilot Plant (WIPP) has been identified a potentially important pathway for radionuclide migration to the accessible environment. Consequently, uncertainties in the models used to describe flow and transport in the Culebra need to be addressed. A ''Geostatistics Test Problem'' is being developed to evaluate a number of inverse techniques that may be used for Dow calculations in the WIPP performance assessment (PA). The Test Problem is actually a series of test cases, each being developed as a highly complex synthetic data sct; the intent is for the ensemble of these data sets span the range of possible conceptual models of groundwater now at the WIPP site. This paper describes the results from Test Case No. 1. Of the five techniques compared, those based on the linearized form of the groundwater flow equation exhibited less bias and less spread in their GWTT distribution functions; the semi-analytical method had the least bias. While the results are not sufficient to make generalizations about which techniques may be better suited for the WIPP PA (only one test case has been exercised), analyses of the data from this test case provides some indication about the relative importance of other aspects of the flow modeling (besides inverse method or geostatistical approach) in PA. Then ancillary analyses examine the effect of gridding an the effect of boundary conditions on the groundwater travel time estimates

  14. Development and application of an analysis methodology for interpreting ambiguous historical pressure data in the WIPP gas-generation experiments.

    Energy Technology Data Exchange (ETDEWEB)

    Felicione, F. S.

    2006-01-23

    The potential for generation of gases in transuranic (TRU) waste by microbial activity, chemical interactions, corrosion, and radiolysis was addressed in the Argonne National Laboratory-West (ANL-West) Gas-Generation Experiments (GGE). Data was collected over several years by simulating the conditions in the Waste Isolation Pilot Plant (WIPP) after the eventual intrusion of brine into the repository. Fourteen test containers with various actual TRU waste immersed in representative brine were inoculated with WIPP-relevant microbes, pressurized with inert gases, and kept in an inert-atmosphere environment for several years to provide estimates of the gas-generation rates that will be used in computer models for future WIPP Performance Assessments. Modest temperature variations occurred during the long-term ANL-West experiments. Although the experiment temperatures always remained well within the experiment specifications, the small temperature variation was observed to affect the test container pressure far more than had been anticipated. In fact, the pressure variations were so large, and seemingly erratic, that it was impossible to discern whether the data was even valid and whether the long-term pressure trend was increasing, decreasing, or constant. The result was that no useful estimates of gas-generation rates could be deduced from the pressure data. Several initial attempts were made to quantify the pressure fluctuations by relating these to the measured temperature variation, but none was successful. The work reported here carefully analyzed the pressure measurements to determine if these were valid or erroneous data. It was found that a thorough consideration of the physical phenomena that were occurring can, in conjunction with suitable gas laws, account quite accurately for the pressure changes that were observed. Failure of the earlier attempts to validate the data was traced to the omission of several phenomena, the most important being the variation in

  15. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    International Nuclear Information System (INIS)

    RECHARD, ROBERT P.

    2000-01-01

    The opening of the Waste Isolation Pilot Plant on March 26, 1999, was the culmination of a regulatory assessment process that had taken 25 years. National policy issues, negotiated agreements, and court settlements during the first 15 years of the project had a strong influence on the amount and type of scientific data collected up to this point. Assessment activities before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to satisfy negotiated agreements with the State of New Mexico, or (3) to develop general understanding of selected natural phenomena associated with nuclear waste disposal. In the last 10 years, federal compliance policy and actual regulations were sketched out, and continued to evolve until 1996. During this period, stochastic simulations were introduced as a tool for the assessment of the WIPP's performance, and four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed

  16. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    International Nuclear Information System (INIS)

    Rechard, R.P.

    1998-04-01

    Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements with the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed

  17. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION & PLANNING FOR REVRIEVAL TREATMENT & EVENTUAL DISPOSAL AT WIPP

    Energy Technology Data Exchange (ETDEWEB)

    KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

    2006-01-18

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP).

  18. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P.

    1998-04-01

    Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements with the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.

  19. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    Energy Technology Data Exchange (ETDEWEB)

    RECHARD,ROBERT P.

    2000-03-01

    The opening of the Waste Isolation Pilot Plant on March 26, 1999, was the culmination of a regulatory assessment process that had taken 25 years. National policy issues, negotiated agreements, and court settlements during the first 15 years of the project had a strong influence on the amount and type of scientific data collected up to this point. Assessment activities before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to satisfy negotiated agreements with the State of New Mexico, or (3) to develop general understanding of selected natural phenomena associated with nuclear waste disposal. In the last 10 years, federal compliance policy and actual regulations were sketched out, and continued to evolve until 1996. During this period, stochastic simulations were introduced as a tool for the assessment of the WIPP's performance, and four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.

  20. Hydrologic analyses of two brine encounters in the vicinity of the Waste Isolation Pilot Plant (WIPP) Site

    International Nuclear Information System (INIS)

    Spiegler, P.

    1982-12-01

    The data from ERDA-6 indicates a naturally fractured reservoir of the two-porosity type. The best estimate of the volume is about 60 thousand to 120 thousand barrels. The data from WIPP-12 also indicates a naturally fractured reservoir of the two-porosity type. The best estimate of the volume is about 5 million to 10 million barrels. The excess pressure above hydrostatic pressure suggests that the reservoirs were formed many millions of years ago. The location of the fractures suggest that their formation may be connected to the tilting of the Delaware Basin as a unit. The effect of the flow testing data on a drilling scenario through the repository many years following its closure is evaluated

  1. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 6, Chapter D, Appendices D4--D13: Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    This report (Vol. 6) for the WIPP facility contains appendices on the following information: Site characterization; general geology; ecological monitoring; and chemical compatibility of waste forms and container materials.

  2. Performance Demonstration Program Plan for Analysis of Simulated Headspace Gases

    International Nuclear Information System (INIS)

    2007-01-01

    The Performance Demonstration Program (PDP) for headspace gases distributes blind audit samples in a gas matrix for analysis of volatile organic compounds (VOCs). Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility's compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document

  3. Performance Demonstration Program Plan for Analysis of Simulated Headspace Gases

    International Nuclear Information System (INIS)

    2006-01-01

    The Performance Demonstration Program (PDP) for headspace gases distributes sample gases of volatile organic compounds (VOCs) for analysis. Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility's compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document. Participating measurement

  4. Performance Demonstration Program Plan for Analysis of Simulated Headspace Gases

    Energy Technology Data Exchange (ETDEWEB)

    Carlsbad Field Office

    2006-04-01

    The Performance Demonstration Program (PDP) for headspace gases distributes sample gases of volatile organic compounds (VOCs) for analysis. Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility’s compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document. Participating measurement

  5. Performance Demonstration Program Plan for Analysis of Simulated Headspace Gases

    Energy Technology Data Exchange (ETDEWEB)

    Carlsbad Field Office

    2007-11-19

    The Performance Demonstration Program (PDP) for headspace gases distributes blind audit samples in a gas matrix for analysis of volatile organic compounds (VOCs). Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility’s compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document

  6. Performance Demonstration Program Plan for Analysis of Simulated Headspace Gases

    Energy Technology Data Exchange (ETDEWEB)

    Carlsbad Field Office

    2007-11-13

    The Performance Demonstration Program (PDP) for headspace gases distributes blind audit samples in a gas matrix for analysis of volatile organic compounds (VOCs). Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility’s compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document

  7. Preoperational environmental programs for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Reith, C.C.; Eastmond, R.J.; Kehrman, R.F.

    1985-01-01

    Since its inception, the Waste Isolation Pilot Plant (WIPP) project has involved a comprehensive series of environmental programs. The first round of field studies began in 1975 to characterize the local environment and to provide data necessary for the projection of potential environmental impacts. These included ecological surveys and experiments, along with measurements of meteorological and radiological parameters in the vicinity of the site. A second round of preoperational field studies is just starting. The current programs monitor construction-related environmental impacts and quantify baseline levels of radiation and radionuclides along possible release pathways. In 1988, when transuranic wastes arrive, these programs will be replaced by operational programs that monitor the same parameters, but with possible adjustments in sampling intensity. Operational monitoring will presist until 2013, with a few components lasting through the two-year decommissioning period and beyond closure of the facility. This paper describes and classifies the preoperational environmental programs for the WIPP project. The paper also provides a chronological context for all programs of environmental data acquisition which have been or will be implemented during the period of active institutional control over the site. A time chart is used to illustrate how past and present activities fit into the overall program for environmental surveillance and protection at the WIPP project

  8. Balancing compliance and cost when implementing a Quality Assurance program

    International Nuclear Information System (INIS)

    Pickering, S.Y.

    1997-12-01

    When implementing a Quality Assurance (QA) program, compliance and cost must be balanced. A QA program must be developed that hits the mark in terms of adequate control and documentation, but does not unnecessarily expand resources. As the Waste Isolation Pilot Plant (WIPP) has moved towards certification, Sandia National Laboratories has learned much about balancing compliance and costs. Some of these lessons are summarized here

  9. Technical requirements for the actinide source-term waste test program

    International Nuclear Information System (INIS)

    Phillips, M.L.F.; Molecke, M.A.

    1993-10-01

    This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency's 40 CFR Part 191B

  10. "Maternal Health and Family Planning Distance Education" experience among physicians: a three-phase study to determine the educational needs, develop education program, and evaluate efficacy of the education administered.

    Science.gov (United States)

    Ciftci, Bestami; Uzel, Nesibe; Ozel, M Onur; Zergeroglu, Sema; Deger, Cetin; Turasan, S Sare; Karakoc, Ayse Gul; Ozbalci, Semra

    2016-01-01

    This study aims to assess the educational needs of family practitioners and evaluate the efficacy of the ongoing "Maternal Health and Family Planning Distance Education" program conducted by the General Directorate of Health Research (SAGEM) of the Turkish Ministry of Health. This study consisted of three phases. In the first phase, an online survey on maternal health and family planning educational needs was sent to 20,611 physicians via e-mail. Of the 20,611 physicians, 4,729 completed the survey. In the second phase, of the 1,061 physicians registered to the education program, 632 physicians with active participation were included. In the third phase, the preeducation expectations of 287 physicians and posteducation satisfaction of 54 physicians were analyzed with a questionnaire. The majority of the physicians were employed in a family health center (97.4%) and practicing for 16-20 years (23.2%) without any prior in-service training (60.9%). High-to-very high educational need was expressed by 56.4% of physicians for pregnancy, delivery, and puerperality. Topics that the physicians, including both those with ≥16 years in practice and without prior in-service training, expressed need for more detailed content were pregnancy, delivery, and puerperality (37.5%); emergency obstetric approach in the primary care setting (33.1%); and gynecological infectious diseases and treatment approach (32.4%). Following the education program, the participants' expectations were fulfilled in terms of refreshing their knowledge, particularly in the field of Maternal Health and Family Planning (87.1% and 75.9%) and the percentage of participants who expressed that they had sufficient high level knowledge increased from 55% to 68.5%. The education on Maternal Health and Family Planning refreshed the knowledge of participants and highly met the preeducation expectations. Determining the educational needs and expectations of the target population prior to the education program seems

  11. “Maternal Health and Family Planning Distance Education” experience among physicians: a three-phase study to determine the educational needs, develop education program, and evaluate efficacy of the education administered

    Science.gov (United States)

    Ciftci, Bestami; Uzel, Nesibe; Ozel, M Onur; Zergeroglu, Sema; Deger, Cetin; Turasan, S Sare; Karakoc, Ayse Gul; Ozbalci, Semra

    2016-01-01

    Aim This study aims to assess the educational needs of family practitioners and evaluate the efficacy of the ongoing “Maternal Health and Family Planning Distance Education” program conducted by the General Directorate of Health Research (SAGEM) of the Turkish Ministry of Health. Methods This study consisted of three phases. In the first phase, an online survey on maternal health and family planning educational needs was sent to 20,611 physicians via e-mail. Of the 20,611 physicians, 4,729 completed the survey. In the second phase, of the 1,061 physicians registered to the education program, 632 physicians with active participation were included. In the third phase, the preeducation expectations of 287 physicians and posteducation satisfaction of 54 physicians were analyzed with a questionnaire. Results The majority of the physicians were employed in a family health center (97.4%) and practicing for 16–20 years (23.2%) without any prior in-service training (60.9%). High-to-very high educational need was expressed by 56.4% of physicians for pregnancy, delivery, and puerperality. Topics that the physicians, including both those with ≥16 years in practice and without prior in-service training, expressed need for more detailed content were pregnancy, delivery, and puerperality (37.5%); emergency obstetric approach in the primary care setting (33.1%); and gynecological infectious diseases and treatment approach (32.4%). Following the education program, the participants’ expectations were fulfilled in terms of refreshing their knowledge, particularly in the field of Maternal Health and Family Planning (87.1% and 75.9%) and the percentage of participants who expressed that they had sufficient high level knowledge increased from 55% to 68.5%. Conclusion The education on Maternal Health and Family Planning refreshed the knowledge of participants and highly met the preeducation expectations. Determining the educational needs and expectations of the target

  12. Report of Class II Survey and Testing of Cultural Resources at the WIPP (Waste Isolation Pilot Plant) Site at Carlsbad, New Mexico,

    Science.gov (United States)

    1987-05-01

    Method Chronometric Sample isolated single Archaeomagnetic , obsidian component sites hydration, thermolumi- nescence, corrected radio- carbon dates ...115 Table 6.2 LA 54388 C-14 Dates , WIPP Assessment Study, ACOE, 1986 117 ,’-4 as... . -. - -, -%.F- , . -. . . % a . N .. ... < < .. <. .’a...from the study area to relatively well- dated archaeological sites which have provided chronological control for local research should be emphasized. The

  13. Computer-Administered Interviews and Rating Scales

    Science.gov (United States)

    Garb, Howard N.

    2007-01-01

    To evaluate the value of computer-administered interviews and rating scales, the following topics are reviewed in the present article: (a) strengths and weaknesses of structured and unstructured assessment instruments, (b) advantages and disadvantages of computer administration, and (c) the validity and utility of computer-administered interviews…

  14. Operations Program Plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1990-09-01

    This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

  15. Radiometric measurements on the fabrication of non-destructive assay standards for WIPP-Performance Demonstration Program

    International Nuclear Information System (INIS)

    Wong, A.S.; Marshall, R.S.

    1997-04-01

    The Inorganic Elemental Analysis Group of LANL has prepared several different sets of working reference materials (WRMs). These WRMs are prepared by blending quantities of nuclear materials (plutonium, americium, and enriched uranium) with diatomaceous earth. The blends are encapsulated in stainless steel cylinders. These WRMs are being measured as blind controls in neutron and gamma based non-destructive assay (NDA) instruments. Radiometric measurements on the blending homogeneity and verification on a set of sixty three plutonium based WRMs are discussed in this paper

  16. Radionuclide release, transport, and consequence modeling for WIPP: a report of a workshop held on September 16-17, 1981

    International Nuclear Information System (INIS)

    1982-02-01

    The purpose of this workshop was to discuss potential mechanisms for release of radionuclides from the WIPP repository years after waste emplacement and termination of institutional controls, and the resultant radiological consequences. Opportunity was also provided for the exchange of information on meaningful release and transport models, and the availability, reliability and significance of data for the parameters applicable to those models. Other than those scenarios provided in draft by the Environmental Evaluation Group (EEG) (Appendix II), there were no new breach scenarios postulated. Also there were no major objections posed to the EEG proposals or the approaches taken in these drafts. Although there were no formal conclusions highlighted by the Conference, the EEG has concluded that the statements below provide a summary of EEG's views concerning the topics covered. These views are based upon the discussions at the Conference, the subsequent comments of the conferees, the information provided in the preceding EEG sponsored geological meeting and field trip, and the information contained in the EEG draft reports

  17. Clinical Pharmacokinetics of Systemically Administered Antileishmanial Drugs

    NARCIS (Netherlands)

    Kip, Anke E; Schellens, Jan H M; Beijnen, Jos H; Dorlo, Thomas P C

    This review describes the pharmacokinetic properties of the systemically administered antileishmanial drugs pentavalent antimony, paromomycin, pentamidine, miltefosine and amphotericin B (AMB), including their absorption, distribution, metabolism and excretion and potential drug-drug interactions.

  18. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    Washington TRU Solutions

    2002-01-01

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP

  19. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2002-09-24

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

  20. 40 CFR 147.1550 - State-administered program.

    Science.gov (United States)

    2010-07-01

    ... Attorney General of New Jersey (by Deputy Attorney General) to Commissioner, Department of Environmental... Injection Control,” April 15, 1983 (six pages); (3) Letter from Attorney General of New Jersey (by Assistant Attorney General) to Commissioner, Department of Environmental Protection, “Re: New Jersey Pollutant...

  1. 40 CFR 282.61 - Hawaii State-Administered Program.

    Science.gov (United States)

    2010-07-01

    ... has taken its own actions, as well as in accordance with other statutory and regulatory provisions. (c..., 919 Ala Moana Boulevard, Suite 212, Honolulu, HI 96814. (1) State statutes and regulations. (i) The...

  2. Performance Demonstration Program Plan for RCRA Constituent Analysis of Solidified Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Carlsbad Field Office

    2006-09-21

    The Performance Demonstration Program (PDP) for Resource Conservation and Recovery Act (RCRA) constituents distributes test samples for analysis of volatile organic compounds (VOCs), semivolatile organic compounds (SVOCs), and metals in solid matrices. Each distribution of test samples is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD; DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department. The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the RCRA PDP. Participating laboratories demonstrate acceptable performance by successfully analyzing single- blind performance evaluation samples (subsequently referred to as PDP samples) according to the criteria established in this plan. PDP samples are used as an independent means to assess laboratory performance regarding compliance with the WAP quality assurance objectives (QAOs). The concentrations of analytes in the PDP samples address levels of regulatory concern and encompass the range of concentrations anticipated in waste characterization samples. The WIPP requires analyses of homogeneous solid wastes to demonstrate compliance with regulatory requirements. These analyses must be performed by laboratories that demonstrate acceptable performance in this PDP. These analyses are referred to as WIPP analyses, and the samples on which they are performed are referred to as WIPP samples. Participating laboratories must analyze PDP samples using the same procedures used for WIPP samples.

  3. Performance Demonstration Program Plan for RCRA Constituent Analysis of Solidified Wastes

    International Nuclear Information System (INIS)

    2006-01-01

    The Performance Demonstration Program (PDP) for Resource Conservation and Recovery Act (RCRA) constituents distributes test samples for analysis of volatile organic compounds (VOCs), semivolatile organic compounds (SVOCs), and metals in solid matrices. Each distribution of test samples is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD; DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department. The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the RCRA PDP. Participating laboratories demonstrate acceptable performance by successfully analyzing single-blind performance evaluation samples (subsequently referred to as PDP samples) according to the criteria established in this plan. PDP samples are used as an independent means to assess laboratory performance regarding compliance with the WAP quality assurance objectives (QAOs). The concentrations of analytes in the PDP samples address levels of regulatory concern and encompass the range of concentrations anticipated in waste characterization samples. The WIPP requires analyses of homogeneous solid wastes to demonstrate compliance with regulatory requirements. These analyses must be performed by laboratories that demonstrate acceptable performance in this PDP. These analyses are referred to as WIPP analyses, and the samples on which they are performed are referred to as WIPP samples. Participating laboratories must analyze PDP samples using the same procedures used for WIPP samples.

  4. Two-well recirculation tracer tests at the H-2 hydropad, Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    1986-10-01

    Two recirculation tracer tests were performed on the Culebra Dolomite Member of the Rustler Formation at the H-2 hydropad at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The first test, which used pentafluorobenzoate (PFB), sodium benzoate, and a suite of halocarbons for tracers, was terminated before breakthrough at the pumping well because of equipment failure. The second test, which used sodium thiocyanate (SCN) and difluorochlorobromomethane (BCF) as tracers, proceeded normally and lasted 270 days. During the second test, the tracer injected during the first test was recovered. Tracer test analyses for the two tests were performed only for the PFB tracer injected during the first test and recovered during the second, and for SCN. Analysis of the PFB recovery was crudely modeled as a one-dimensional pulse-injection test. The SCN tracer used in the second test was analyzed with the homogeneous, isotropic Grove and Beetem one-dimensional porous-medium recirculating flow test model. In general, model predictions are in poor agreement with the field measurements. Discrepancies could be produced by the combined effects of local nonhomogeneities, matrix diffusion, and possible sorption or degradation of the tracer during the test. The best overall match between the SCN breakthrough curve predicted by the semianalytical model and that observed in measurements was achieved using a porosity that ranged from 17% to 19% and a dispersivity of 16 to 18 ft. A match based only on the early part of the breakthrough curve, however, yielded a porosity of 11.5% and a dispersivity of 8 ft. The latter porosity might more closely represent the effective porosity of the Culebra, if the SCN degraded during the test

  5. Dissolution of evaporites and its possible impact on the integrity of the Waste Isolation Pilot Plant (WIPP) New Mexico, USA

    International Nuclear Information System (INIS)

    Zand, S.M.

    1982-01-01

    The radiological consequences of a breach of the WIPP TRU waste repository, as a result of dissolution processes were shown to be in two broad classes. Most of the possible scenarieos that could happen as a result of the deep dissolution processes were shown to be addressed by the scenarios already presented elsewhere or are being investigated at the present. The remaining possible scenarios, except one, showed that the possible release of radionuclides through the geosphere to the biosphere would take periods of time orders-of-magnitude longer than the half-life of Plutonium-239. The one not specifically addressed, a postulated hydralogic pathway with the characteristics of the Salado/Castile interface aquifer, appears unlikely. However, it should be quantified when more data become available. To obtain a better understanding of the radiological health effects of the deep dissolution-caused breach of the repository, emphasis must be placed on better evaluation and refinement of the existing mathematical models and associated parameters. In the majority of the existing scenarios the most significant pathway of the radionuclide through the geosphere to the biosphere is the dolomitic Magenta and Culebra aquifers. Because these formations are fractured, mathematical modeling of radionuclide transport is subject to a large degree of uncertainty. Other uncertainties that relate to this pathway which need further study are: (a) the possibility of having more permeable abandoned mined potash tunnels as a part of the radionuclide flow path and (b) the outcrops of the Magenta and Culebra formations in Nash Draw, 11 km (7 mi) before the outlet to the Pecos River at Malaga Bend. The problems associated with the quantifications of these uncertainties as well as the effects of long-term climatic and hydrologic changes and hydrogeological data requirements of the models should be further addressed

  6. Experimental program plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

  7. Experimental program plan for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

  8. Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

  9. Initial computer modeling of WIPP [Waste Isolation Pilot Plant] underground ventilation system, September 1985--March 1986

    International Nuclear Information System (INIS)

    Sethi, S.

    1986-11-01

    Provision of a good ventilation system has been and continues to be a major priority here of those responsible for its design, management, and operation. As an ongoing effort in this direction, development of computer simulated models for the system was initiated in September, 1985. It was decided to utilize Dravo's 'MINEVENT' computer program for this purpose. Accordingly, initial computer models of the mine's ventilation system have been developed for various modes of operation. Specifically, they include: Simulation of the current ventilation system, and Simulation of the designed ventilation system for modes: mine construction mode/shift, waste storage mode/shift, and air reversal mode. 5 figs

  10. The densities of halite-saturated WIPP-A and NBT-6 brines and their NaCl contents in weight percent, molal, and molar units from 20 to 100 degrees C

    Science.gov (United States)

    Chou, I-Ming; Buizinga, B.; Clynne, M.A.; Potter, R.W.

    1982-01-01

    A series of density measurements has been performed at 30?, 50?, 70?, and 90?C for halite-undersaturated WIPP-A and NBT-6 brines with various NaCl contents approaching saturation. The densities of halite-saturated WIPP-A and NBT-6 brines were obtained by extrapolating these measured densities to halite saturation points. The maximum difference between the densities obtained in this Fashion and those calculated from the model of Potter and Haas is 0.015 g/cm3. The NaCl contents in halite-saturated WIPP-A and NBT-6 brines are reported in wt %, molal, and molar units from 20? to 100?C.

  11. A comparison of geostatistically-based inverse techniques for use in performance assessment analysis at the WIPP site results from test case No. 1

    International Nuclear Information System (INIS)

    Zimmerman, D.A.; Gallegos, D.P.

    1993-01-01

    The groundwater flow pathway in the Culebra Dolomite aquifer at the Waste Isolation Pilot Plant (WIPP) has been identified as a potentially important pathway for radionuclide migration to the accessible environment. Consequently, uncertainties in the models used to described flow and transport in the Culebra need to be addressed. A 'Geostatistics Test Problem' is being developed as a highly complex synthetic data set; the intent is for the ensemble of these data sets span the range of possible conceptual models of groundwater flow at the WIPP site. The Test Problem analysis approach is to use a comparison of the probabilistic groundwater travel time (GWTT) estimates produced by each technique as the basis for the evaluation. Participants are given observations of head and transmissivity and are asked to develop stochastic models of groundwater flow for the synthetic system. Cumulative distribution functions (CDFs) of groundwater flow (computed via particle tracking) are constructed using the head and transmissivity data generated through the application of each technique; one semi-analytical method generates the CDFs of groundwater flow directly. This paper describes the results from Test Case No 1. Of the five techniques compared, those based on the linearized form of the groundwater flow equation exhibited less bias and less spread in their GWTT distribution functions; the semi-analytical method had the least bias. While the results are not sufficient to make generalizations about which techniques may be better suited for the WIPP PA (only one test case has been exercised), analysis of the data from this test case provides some indication about the relative importance of other aspects of the flow modeling (besides inverse method or geostatistical approach) in PA. These ancillary analyses examine the effect of gridding and the effect of boundary conditions on the groundwater travel time estimates

  12. Systems Engineering in the Development and Implementation of the Savannah River Site Transuranic Waste Disposition Program

    International Nuclear Information System (INIS)

    Fayfich, R.R.

    1999-01-01

    The use of systems engineering facilitated the strategic planning and implementation of the Savannah River Site (SRS) transuranic waste disposal program. This application represented the first SRS use of systems engineering in the pre-program planning stages during the development of a comprehensive strategic plan for the disposal of transuranic waste at the Department of Energy Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The use of systems engineering focused the efforts of the technical experts to devise a three initiative plan for the disposal of transuranic waste where previous efforts failed. Continued application of systems engineering facilitated the further development and implementation of the first initiative outlined in the strategic plan, i.e., set-up the program and process to begin to characterize and ship waste to the WIPP.This application of systems engineering to the transuranic waste program represented the first opportunity at the SRS for a comprehensive usage of systems engineering at all program levels. The application was initiated at the earliest possible point in the program development, i.e., strategic planning, and successively was used in detailed development and implementation of the program. Systems engineering successfully focused efforts to produce a comprehensive plan for the disposal of SRS transuranic waste at the WIPP, and facilitated development of the SRS capability and infrastructure to characterize, certify, and ship waste

  13. Wellbore Flow Treatment Used to Predict Radioactive Brine Releases to the Surface from Future Drilling Penetrations into th Waste Isolation Pilot Plant (WIPP), New Mexico, USA

    Energy Technology Data Exchange (ETDEWEB)

    Hadgu, T.; O' Brien, D.G.; Stoelzel, D.M.; Vaughn, P.

    1998-10-15

    The Waste Isolation Pilot Plant (WIPP) is the U.S. Department of Energy's (DOE) mined geologic repository in southeastern New Mexico, USA. This site is designed for the permanent burial of transuranic radioactive waste generated by defense related activities. The waste produces gases when exposed to brine. This gas generation may result in increased pressures over time. Thereforq a future driller that unknowingly penetrates through the site may experience a blowout This paper describes the methodology used to predict the resultant volumes of contaminated brine released to the surface.

  14. Growth Performance of Cockerels Administered Crude Follicular ...

    African Journals Online (AJOL)

    This Study was conducted to assess the performance of cockerels administered crude follicular and testicular fluids. Two hundred (200) day old Hyaline white cockerel chicks were randomly assigned to five different treatments namely control (T1), 0.5mls follicular fluid (T2), 25% testicular fluid (T3), 0.25ml follicular fluid (T4) ...

  15. Training and experience of doctors administering obstetric ...

    African Journals Online (AJOL)

    Background All the published Saving Mothers Reports generated by the National Committee of the Confidential Enquiries into Maternal Deaths in South Africa have associated anaesthesia-related maternal deaths with the lack of skills of the doctors administering the anaesthesia. The Reports have shown the Free State to ...

  16. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 5, Chapter D, Appendix D1 (conclusion), Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Cook, Neville G.W.; Heuze, Francois E.; Miller, Hamish D.S.; Thoms, Robert L.

    1993-03-01

    The reference design for the underground facilities at the Waste Isolation Pilot Plant was developed using the best criteria available at initiation of the detailed design effort. These design criteria are contained in the US Department of Energy document titled Design Criteria, Waste Isolation Pilot Plant (WIPP). Revised Mission Concept-IIA (RMC-IIA), Rev. 4, dated February 1984. The validation process described in the Design Validation Final Report has resulted in validation of the reference design of the underground openings based on these criteria. Future changes may necessitate modification of the Design Criteria document and/or the reference design. Validation of the reference design as presented in this report permits the consideration of future design or design criteria modifications necessitated by these changes or by experience gained at the WIPP. Any future modifications to the design criteria and/or the reference design will be governed by a DOE Standard Operation Procedure (SOP) covering underground design changes. This procedure will explain the process to be followed in describing, evaluating and approving the change.

  17. Administering stuttering modification therapy in school settings.

    Science.gov (United States)

    Williams, Dale F; Dugan, Peter M

    2002-08-01

    Stuttering modification techniques can be used effectively in the school setting. In fact, speech-language pathologists can use this environment to their advantage to address not only disfluency but also the emotional and behavioral aspects of stuttering. Toward this end, stuttering modification goals and techniques are outlined, with a discussion of how to adapt them to school environments. Specific topics include writing clear, measurable IEP goals, taking advantage of the school setting to implement these goals, administering stuttering modification within a group therapy mode, involving parents and teachers, and monitoring progress.

  18. Performance Demonstration Program Management Plan

    International Nuclear Information System (INIS)

    2005-01-01

    To demonstrate compliance with the Waste Isolation Pilot Plant (WIPP) waste characterization program, each testing and analytical facility performing waste characterization activities participates in the Performance Demonstration Program (PDP). The PDP serves as a quality control check against expected results and provides information about the quality of data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed by an independent organization to each of the facilities participating in the PDP. There are three elements within the PDP: analysis of simulated headspace gases, analysis of solids for Resource Conservation and Recovery Act (RCRA) constituents, and analysis for transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques. Because the analysis for TRU radionuclides using NDA techniques involves both the counting of drums and standard waste boxes, four PDP plans are required to describe the activities of the three PDP elements. In accordance with these PDP plans, the reviewing and approving authority for PDP results and for the overall program is the CBFO PDP Appointee. The CBFO PDP Appointee is responsible for ensuring the implementation of each of these plans by concurring with the designation of the Program Coordinator and by providing technical oversight and coordination for the program. The Program Coordinator will designate the PDP Manager, who will coordinate the three elements of the PDP. The purpose of this management plan is to identify how the requirements applicable to the PDP are implemented during the management and coordination of PDP activities. The other participants in the program (organizations that perform site implementation and activities under CBFO contracts or interoffice work orders) are not covered under this management plan. Those activities are governed by the organization's quality assurance (QA) program and procedures or as otherwise directed by CBFO.

  19. Ocular toxicity from systemically administered xenobiotics

    Science.gov (United States)

    Gokulgandhi, Mitan R; Vadlapudi, Aswani Dutt; Mitra, Ashim K

    2015-01-01

    Introduction The eye is considered as the most privileged organ because of the blood–ocular barrier that acts as a barrier to systemically administered xenobiotics. However, there has been a significant increase in the number of reports on systemic drug-induced ocular complications. If such complications are left untreated, then it may cause permanent damage to vision. Hence, knowledge of most recent updates on ever-increasing reports of such toxicities has become imperative to develop better therapy while minimizing toxicities. Areas covered The article is mainly divided into anterior and posterior segment manifestations caused by systemically administered drugs. The anterior segment is further elaborated on corneal complications where as the posterior segment is focused on optic nerve, retinal and vitreous complications. Furthermore, this article includes recent updates on acute and chronic ocular predicaments, in addition to discussing various associated symptoms caused by drugs. Expert opinion Direct correlation of ocular toxicities due to systemic drug therapy is evident from current literature. Therefore, it is necessary to have detailed documentation of these complications to improve understanding and predict toxicities. We made an attempt to ensure that the reader is aware of the characteristic ocular complications, the potential for irreversible drug toxicity and indications for cessation. PMID:22803583

  20. [Improving nursing staff accuracy in administering chemotherapy].

    Science.gov (United States)

    Lin, Chin-Ying; Chu, Yun-Li; Chiou, Yen-Gan; Chiang, Ming-Chu

    2009-12-01

    As most anticancer drugs are cytotoxic, their safe and error-free application is important. We analyzed data from the hematology-oncology ward chemotherapy checklist dated January 13th through February 3rd, 2007 and found accuracy rates for chemotherapy drug usage as low as 68.4%. Possible causes identified for this poor result include incomplete chemotherapy standards protocols, lack of chemotherapy quality control, and insufficient chemotherapy knowledge amongst nursing staff. This project aimed to improve the accuracy of nursing staff in administering chemotherapy and to raise nursing staff knowledge regarding chemotherapy. Our strategies for improvement included completing a chemotherapy standards protocol, establishing a chemotherapy quality-control monitoring system, augmenting chemotherapy training and adding appropriate equipment and staff reminders. After strategies were implemented, accuracy in chemotherapy administration rose to 96.7%. Related knowledge amongst nursing staff also improved from an initial 77.5% to 89.2%. Implementing the recommended measures achieved a significant improvement in the accuracy and quality of chemotherapy administered by nursing personnel.

  1. Metrological aspects in the estimate of the administered activity in nuclear medicine patients

    International Nuclear Information System (INIS)

    Ruzzarin, A.; Iwahara, A.; Tahuata, L.; Xavier, A.M.

    2014-01-01

    In order to investigate the performance quality of routine measurements of Nuclear Medicine Services (NMS), the National Metrology Laboratory of Ionizing Radiation/Institute of Radiation Protection and Dosimetry (LNMRI/IRD) has been conducting, since 1998, a program of comparison for activity measurements of radiopharmaceuticals administered to patients in nuclear medicine. Correction factors are determined from the result of performance analysis in order to determine with better accuracy the activity to be administered to the patients. (author)

  2. System and method for administering radiation

    International Nuclear Information System (INIS)

    Vogel, T.M.

    1975-01-01

    A system and method for metering the quantity of radiation administered a subject by a source of radiation movable along a path relative to the subject is described. The system cumulatively counts the amount of radiation directed toward the subject during each of a succession of increments of motion of the source. When a predetermined amount of radiation is delivered during an increment, the source is disabled until the source passes into the next increment of displacement. The count of radiation is restarted at the instant the source is disabled, to accumulate accurately any added spurious radiation dosage which may occur and to include that dosage in the count of the permitted amount for the next succeeding increment of motion. Several interlocks for disabling the system in response to various malfunctions are included. Means for controlling the speed of movement of the source and/or the dose rate of the source are also included. (auth)

  3. Tumour targeting with systemically administered bacteria.

    LENUS (Irish Health Repository)

    Morrissey, David

    2012-01-31

    Challenges for oncology practitioners and researchers include specific treatment and detection of tumours. The ideal anti-cancer therapy would selectively eradicate tumour cells, whilst minimising side effects to normal tissue. Bacteria have emerged as biological gene vectors with natural tumour specificity, capable of homing to tumours and replicating locally to high levels when systemically administered. This property enables targeting of both the primary tumour and secondary metastases. In the case of invasive pathogenic species, this targeting strategy can be used to deliver genes intracellularly for tumour cell expression, while non-invasive species transformed with plasmids suitable for bacterial expression of heterologous genes can secrete therapeutic proteins locally within the tumour environment (cell therapy approach). Many bacterial genera have been demonstrated to localise to and replicate to high levels within tumour tissue when intravenously (IV) administered in rodent models and reporter gene tagging of bacteria has permitted real-time visualisation of this phenomenon. Live imaging of tumour colonising bacteria also presents diagnostic potential for this approach. The nature of tumour selective bacterial colonisation appears to be tumour origin- and bacterial species- independent. While originally a correlation was drawn between anaerobic bacterial colonisation and the hypoxic nature of solid tumours, it is recently becoming apparent that other elements of the unique microenvironment within solid tumours, including aberrant neovasculature and local immune suppression, may be responsible. Here, we consider the pre-clinical data supporting the use of bacteria as a tumour-targeting tool, recent advances in the area, and future work required to develop it into a beneficial clinical tool.

  4. Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    The US Department of Energy is currently constructing the Waste Isolation Pilot near Carlsbad, New Mexico. The full-scale pilot plant will demonstrate the feasibility of the safe disposal of defense-related nuclear waste in a bedded salt formation at a depth of 2160 feet below the surface. WIPP will provide for the permanent storage of 25,000 cu ft of remote-handled (RH) transuranic waste and 6,000,000 cu ft of contact-handled (CH) transuranic waste. This paper covers the major mechanical/structural design considerations for the waste hoist and its hoist tower structure. The design of the hoist system and safety features incorporates state-of-the-art technology developed in the hoist and mining industry to ensure safe operation for transporting nuclear waste underground. Also included are design specifications for VOC-10 monitoring system.

  5. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION and PLANNING FOR REVRIEVAL TREATMENT and EVENTUAL DISPOSAL AT WIPP

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

    2006-01-01

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP)

  6. Potential microbial impact on transuranic wastes under conditions expected in the Waste Isolation Pilot Plant (WIPP). Annual report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

    Barnhart, B.J.; Campbell, E.W.; Martinez, E.; Caldwell, D.E.; Hallett, R.

    1980-07-01

    Previous results were confirmed showing elevated frequencies of radiation-resistant bacteria in microorganisms isolated from shallow transuranic (TRU) burial soil that exhibits nanocurie levels of beta and gamma radioactivity. Research to determine whether plutonium could be methylated by the microbially produced methyl donor, methylcobalamine, was terminated when literature and consulting radiochemists confirmed that other alkylated transuranic elements are extremely short-lived in the presence of oxygen. Emphasis was placed on investigation of the dissolution of plutonium dioxide by complex formation between plutonium and a polyhydroxamate chelate similar to that produced by microorganisms. New chromatographic and spectrophotometric evidence supports previous results showing enhanced dissolution of alpha radioactivity when 239 Pu dioxide was mixed with the chelate Desferol. Microbial degradation studies of citrate, ethylenediamine tetraacetate (EDTA), and nitrilo triacetate (NTA) chelates of europium are in progress. Current results are summarized. All of the chelates were found to degrade. The average half-life for citrate, NTA, and EDTA was 3.2, 8.0, and 28 years, respectively. Microbial CO 2 generation is also in progress in 72 tests on several waste matrices under potential WIPP isolation conditions. The mean rate of gas generation was 5.97 μg CO 2 /g waste/day. Increasing temperature increased rates of microbial gas generation across treatments of brine, varying water content, nutrient additions, and anaerobic conditions. No microbial growth was detected in experiments to enumerate and identify the microorganisms in rocksalt cores from the proposed WIPP site. This report contains the year's research results and recommendations derived for the design of safe storage of TRU wastes under geologic repository conditions

  7. Ecological Monitoring Program at the Waste Isolation Pilot Plant: Second semiannual report, January 1985--June 1985

    International Nuclear Information System (INIS)

    Fischer, N.T.

    1985-12-01

    This is the second semiannual report of the Ecological Monitoring Program (EMP) at the Waste Isolation Pilot Plant (WIPP) project in southeastern New Mexico. The purpose of the EMP is to quantify and assess the impacts of WIPP construction activities on the surrounding ecosystem. The predicted impacts include: (1) alteration of natural habitat, (2) deposition of salt and dust, and (3) increased human activity and noise. This report describes the data collection activities and presents results, analyses, and discussions for the period of January through June, 1985. Also included are data collected prior to this period which were not available for inclusion in the first EMP semiannual report and data collected after this period which provide a more complete basis for the analyses and discussion. The eight subprograms currently active in the EMP are: environmental photography, soil chemistry, soil microbiology, vegetation, wildlife, meteorology, air quality, and water quality. 16 refs., 37 figs., 17 tabs

  8. 32 CFR 637.11 - Authority to administer oaths.

    Science.gov (United States)

    2010-07-01

    ... ENFORCEMENT AND CRIMINAL INVESTIGATIONS MILITARY POLICE INVESTIGATION Investigations § 637.11 Authority to... administer oaths to military personnel who are subject to the UCMJ. The authority to administer oaths to...

  9. Defense transuranic waste program strategy document

    International Nuclear Information System (INIS)

    1982-07-01

    This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment

  10. Programming

    International Nuclear Information System (INIS)

    Jackson, M.A.

    1982-01-01

    The programmer's task is often taken to be the construction of algorithms, expressed in hierarchical structures of procedures: this view underlies the majority of traditional programming languages, such as Fortran. A different view is appropriate to a wide class of problem, perhaps including some problems in High Energy Physics. The programmer's task is regarded as having three main stages: first, an explicit model is constructed of the reality with which the program is concerned; second, this model is elaborated to produce the required program outputs; third, the resulting program is transformed to run efficiently in the execution environment. The first two stages deal in network structures of sequential processes; only the third is concerned with procedure hierarchies. (orig.)

  11. Programming

    CERN Document Server

    Jackson, M A

    1982-01-01

    The programmer's task is often taken to be the construction of algorithms, expressed in hierarchical structures of procedures: this view underlies the majority of traditional programming languages, such as Fortran. A different view is appropriate to a wide class of problem, perhaps including some problems in High Energy Physics. The programmer's task is regarded as having three main stages: first, an explicit model is constructed of the reality with which the program is concerned; second, this model is elaborated to produce the required program outputs; third, the resulting program is transformed to run efficiently in the execution environment. The first two stages deal in network structures of sequential processes; only the third is concerned with procedure hierarchies.

  12. WIPP site and vicinity geological field trip. A report of a field trip to the proposed Waste Isolation Pilot Plant project in Southeastern New Mexico, June 16 to 18, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chaturvedi, L

    1980-10-01

    The Environmental Evaluation Group is conducting an assessment of the radiological health risks to people from the Waste Isolation Pilot Plant. As a part of this work, EEG is making an effort to improve the understanding of those geological issues concerning the WIPP site which may affect the radiological consequences of the proposed repository. One of the important geological issues to be resolved is the timing and the nature of the dissolution processes which may have affected the WIPP site. EEG organized a two-day conference of geological scientists, on January 17-18, 1980. On the basis of the January conference and the June field trip, EEG has formed the following conclusions: (1) it has not been clearly established that the site or the surrounding area has been attacked by deep dissolution to render it unsuitable for the nuclear waste pilot repository; (2) the existence of an isolated breccia pipe at the site unaccompanied by a deep dissolution wedge, is a very remote possibility; (3) more specific information about the origin and the nature of the brine reservoirs is needed. An important question that should be resolved is whether each encounter with artesian brine represents a separate pocket or whether these occurrences are interconnected; (4) Anderson has postulated a major tectonic fault or a fracture system at the Basin margin along the San Simon Swale; (5) the area in the northern part of the WIPP site, identified from geophysical and bore hole data as the disturbed zone, should be further investigated to cleary understand the nature and significance of this structural anomaly; and (6) a major drawback encountered during the discussions of geological issues related to the WIPP site is the absence of published material that brings together all the known information related to a particular issue.

  13. Product traceability and quality as applied to the united states transuranic and high-level waste repository programs

    International Nuclear Information System (INIS)

    Pickering, S.Y.; Orrell, S.A.

    2000-01-01

    As with any repository program, predictions of the performance of a site over very long time frames may often meet with skepticism from the public and decision-makers, such as regulatory and governmental agencies. Experience at the WIPP and the YMP indicate that demonstrating the defensibility of data, conceptual models, computer codes, and numerical analyses is critical. Five overarching principles have been found to be the basis of a technically and publicly acceptable repository. The principles are traceability, transparency, reproducibility, retrievability, and reviews. - Traceability allows one to understand the source and justification of data and other input that generate conclusions. - Transparency allows one to follow the logic, calculations, and other operations that produce results. - Reproducibility allows one to reconstruct the results without recourse to the originator of the information. - Retrievability allows one to retrieve documentation that demonstrate these overarching principles. - Reviews ensure that the work is technically acceptable, complete, and accurate. This paper discusses how these principles are applied to the WIPP and the YMP. By setting up quality assurance and management controls (e.g., procedures, audits, peer reviews) these principles are implemented. Without successfully applying these principles the WIPP would not have gone from research to industrial maturity. The YMP is ensuring that these are implemented for activities that support licensing. Any repository program concerned with demonstrating defensibility to the public and regulators would do well by incorporating traceability, transparency, reproducibility, retrievability, and reviews into their program. (authors)

  14. Crack closure and healing studies in WIPP [Waste Isolation Pilot Plant] salt using compressional wave velocity and attenuation measurements: Test methods and results

    International Nuclear Information System (INIS)

    Brodsky, N.S.

    1990-11-01

    Compressional wave ultrasonic data were used to qualitatively assess the extent of crack closure during hydrostatic compression of damaged specimens of WIPP salt. Cracks were introduced during constant strain-rate triaxial tests at low confining pressure (0.5 MPa) as specimens were taken to either 0.5, 1.0, or 1.5 percent axial strain. For three specimens taken to 1.0 percent axial strain, the pressure was increased to 5, 10 or 15 MPa. For the remaining specimens, pressure was raised to 15 MPa. Waveforms for compressional waves traveling both parallel and perpendicular to the direction of maximum principal stress were measured in the undamaged state, during constant strain-rate tests, and then monitored as functions of time while the specimens were held at pressure. Both wave velocities and amplitudes increased over time at pressure, indicating that cracks closed and perhaps healed. The recovery of ultrasonic wave characteristics depended upon both pressure and damage level. The higher the pressure, the greater the velocity recovery; however, amplitude recovery showed no clear correlation with pressure. For both amplitudes and velocities, recoveries were greatest in the specimens with the least damage. 13 refs., 15 figs., 1 tab

  15. Quarter-scale modeling of room convergence effects on CH [contact-handled] TRU drum waste emplacements using WIPP [Waste Isolation Pilot Plant] reference design geometries

    International Nuclear Information System (INIS)

    VandeKraats, J.

    1987-11-01

    This study investigates the effect of horizontal room convergence on CH waste packages emplaced in the WIPP Reference Design geometry (rooms 13 feet high by 33 feet wide, with minus 3/8 inch screened backfill emplaced over and around the waste packages) as a function of time. Based on two tests, predictions were made with regard to full-scale 6-packs emplaced in the Reference Design geometry. These are that load will be transmitted completely through the stack within the first five years after waste emplacement and all drums in all 6-packs will be affected; that virtually all drums will show some deformation eight years after emplacement; that some drums may breach before the eighth year after emplacement has elapsed; and that based on criteria developed during testing, it is predicted that 1% of the drums emplaced will be breached after 8 years and, after 15 years, approximately 12% of the drums are predicted to be breached. 8 refs., 41 figs., 3 tabs

  16. Mobile/Modular Deployment Project-Enhancing Efficiencies within the National Transuranic Waste Program

    International Nuclear Information System (INIS)

    Triay, I.R.; Basabilvazo, G.B.; Countiss, S.; Moody, D.C.; Behrens, R.G.; Lott, S.A.

    2002-01-01

    In 1999, the National Transuranic (TRU) Waste Program (NTP) achieved two significant milestones. First, the Waste Isolation Plant (WIPP) opened in March for the permanent disposal of TRU waste generated by, and temporarily stored at, various sites supporting the nation's defense programs. Second, the Hazardous Waste Facility Permit, issued by the New Mexico Environment Department, for WIPP became effective in November. While the opening of WIPP brought to closure a number of scientific, engineering, regulatory, and political challenges, achieving this major milestone led to a new set of challenges-how to achieve the Department of Energy's (DOE's) NTP end-state vision: All TRU waste from DOE sites scheduled for closure is removed All legacy TRU waste from DOE sites with an ongoing nuclear mission is disposed 0 All newly generated TRU waste is disposed as it is generated The goal is to operate the national TRU waste program safely, cost effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. The existing schedule for TRU waste disposition would achieve the NTP vision in 2034 at an estimated life-cycle cost of $16B. The DOE's Carlsbad Field Office (CBFO) seeks to achieve this vision early-by at least 10 years- while saving the nation an estimated $48 to $6B. CBFO's approach is to optimize, or to make as functional as possible, TRU waste disposition. That is, to remove barriers that impede waste disposition, and increase the rate and cost efficiency of waste disposal at WIPP, while maintaining safety. The Mobile/Modular Deployment Project (MMDP) is the principal vehicle for implementing DOE's new commercial model of using best business practices of national authorization basis, standardization, and economies of scale to accelerate the completion of WIPP's mission. The MMDP is one of the cornerstones of the National TRU Waste System Optimization Project (1). The objective of the MMDP is to increase TRU

  17. Effect of orally administered probenecid on the pharmacokinetics of cefoxitin.

    OpenAIRE

    Vlasses, P H; Holbrook, A M; Schrogie, J J; Rogers, J D; Ferguson, R K; Abrams, W B

    1980-01-01

    To characterize the effect of orally administered probenecid on the pharmacokinetics of cefoxitin in healthy male volunteers, we administered to one group of six subjects 2 g of cefoxitin by intravenous (i.v.) bolus either alone, with 1 g of probenecid concomitantly, or when 1 g of probenecid was administered 1 h previously by using a crossover design. Likewise, we administered to a second group of six subjects 2 g of cefoxitin intramuscularly (i.m.) together with 1 and 2 g of probenecid. Pro...

  18. An appointment-based model to systematically assess and administer vaccinations.

    Science.gov (United States)

    Luder, Heidi R; Kunze, Natalie; Heaton, Pamela C; Frede, Stacey M

    2018-03-27

    To incorporate the assessment of vaccination status and administration of vaccines in an appointment-based model (ABM) and measure the impact on vaccinations administered and patient and pharmacist satisfaction with the appointment-based model. An ABM was implemented to systematically assess vaccination status and administer vaccines. Patients made an appointment to pick up synchronized prescriptions, and pharmacists assessed vaccination histories and administered vaccinations during the appointment. In addition, pharmacists could access the statewide immunization information system to objectively determine vaccination histories and document administered vaccines. This project was conducted at 24 Kroger Pharmacies in the Cincinnati-Dayton Area. Any patient filling more than 1 maintenance medication was eligible for the ABM program. Pharmacists were encouraged to target patients at high risk for medication problems and vaccine-preventable diseases, including patients 60 years of age or older with more than 5 medications and high-risk disease states such as diabetes, asthma, and chronic obstructive pulmonary disease. Pharmacies were randomized, and an a priori analysis was conducted to ensure that the 24 intervention and 78 control stores were similar at baseline. Postimplementation data on the mean number of vaccines per store were compared between the intervention stores and the control stores from September 2014 through December 2015. Patient and pharmacist satisfaction with the ABM was assessed via surveys. The pharmacist vaccine assessment as part of the ABM program showed higher overall mean vaccinations per store compared with the control group during the project period (1810.71 ± 500.88 vs. 1455.09 ± 754.43; P = 0.01). Patients and pharmacists felt that the ABM program facilitated vaccine discussions. The ABM program with a focus on vaccinations allowed pharmacists to systematically assess patient vaccination histories and administer vaccines in the

  19. Transuranic waste management program and facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-01-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  20. Environmental baseline study of the Los Medanos Waste Isolation Pilot Plant (WIPP) project area of New Mexico: a progress report

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, H.G. (ed.)

    1977-09-01

    Exploratory drilling operations are being conducted for a Waste Isolation Pilot Program in southeastern New Mexico. Prior to the establishment of such a program, an environmental study was initiated to serve as a baseline for evaluation of the impact of future activities in the Los Medanos area. Much of this area has been influenced by human activities over a long period, and hence the baseline data only reflects the present, relatively disturbed condition of the environment. The study covers air resources, soils, and biotic resources. 23 tables, 6 figs. (DLC)

  1. Methods of administering oral formulations and child acceptability

    NARCIS (Netherlands)

    van Riet-Nales, Diana A; Ferreira, José A; Schobben, Alfred F A M; de Neef, Barbara J; Egberts, Toine C G; Rademaker, Carin M A

    2015-01-01

    INTRODUCTION: Children may be unable or unwilling to swallow medicines. In order to avoid or accommodate any such problems, parents may decide to administer medicines other than intended. The aim of this study was to investigate how parents administered four oral placebo formulations to infants and

  2. Methods of administering oral formulations and child acceptability

    NARCIS (Netherlands)

    Van Riet-Nales, Diana A.; Ferreira, José A.; Schobben, Alfred F A M; De Neef, Barbara J.; Egberts, Toine C G; Rademaker, Carin M A

    2015-01-01

    Abstract Introduction Children may be unable or unwilling to swallow medicines. In order to avoid or accommodate any such problems, parents may decide to administer medicines other than intended. The aim of this study was to investigate how parents administered four oral placebo formulations to

  3. 39 CFR 222.1 - Authority to administer postal affairs.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Authority to administer postal affairs. 222.1 Section 222.1 Postal Service UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION DELEGATIONS OF AUTHORITY § 222.1 Authority to administer postal affairs. (a) The Postmaster General. The postmaster general...

  4. A Computer-Administered Examination in Professional Ethics.

    Science.gov (United States)

    White, Michael J.

    1988-01-01

    Presents rationale and procedure for a computer-administered examination in professional ethics. Discusses advantages and implications of computer-administered testing in professional ethics, noting benefits for instructors and students of professional ethics in counseling and counseling psychology. (Author/NB)

  5. RH Packaging Program Guidance

    International Nuclear Information System (INIS)

    Washington TRU Solutions, LLC

    2003-01-01

    The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M and O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR (section) 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word

  6. Flammability Assessment Methodology Program Phase I: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    C. A. Loehr; S. M. Djordjevic; K. J. Liekhus; M. J. Connolly

    1997-09-01

    The Flammability Assessment Methodology Program (FAMP) was established to investigate the flammability of gas mixtures found in transuranic (TRU) waste containers. The FAMP results provide a basis for increasing the permissible concentrations of flammable volatile organic compounds (VOCs) in TRU waste containers. The FAMP results will be used to modify the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (TRUPACT-II SARP) upon acceptance of the methodology by the Nuclear Regulatory Commission. Implementation of the methodology would substantially increase the number of drums that can be shipped to the Waste Isolation Pilot Plant (WIPP) without repackaging or treatment. Central to the program was experimental testing and modeling to predict the gas mixture lower explosive limit (MLEL) of gases observed in TRU waste containers. The experimental data supported selection of an MLEL model that was used in constructing screening limits for flammable VOC and flammable gas concentrations. The MLEL values predicted by the model for individual drums will be utilized to assess flammability for drums that do not meet the screening criteria. Finally, the predicted MLEL values will be used to derive acceptable gas generation rates, decay heat limits, and aspiration time requirements for drums that do not pass the screening limits. The results of the program demonstrate that an increased number of waste containers can be shipped to WIPP within the flammability safety envelope established in the TRUPACT-II SARP.

  7. Environmental programs for grades K-12 sponsored by the Westinghouse Waste Isolation Division Educational Programs Department

    International Nuclear Information System (INIS)

    Mikel, C.J.

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP) created its educational programs department in 1990 as a result of the Secretary of Energy's focus on education stated in SEN-23-90. This Secretary of Energy Notice reflects the focus for US Department of Energy facilities to enhance education through their resources (both human and financial) with an emphasis on math and science. The mission of the Westinghouse Waste Isolation Division (WID) educational programs department is to enhance education at all levels and to promote educational experiences that give students the opportunity to make decisions and develop skills for productive lives. Programs have been developed around the environmental monitoring department, to give students from different grade levels hands on experiences in the environmental sciences field to stimulate their interest in the natural sciences

  8. Coupled multiphase flow and closure analysis of repository response to waste-generated gas at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Freeze, G.A.; Larson, K.W.; Davies, P.B.

    1995-10-01

    A long-term assessment of the Waste Isolation Pilot Plant (WIPP) repository performance must consider the impact of gas generation resulting from the corrosion and microbial degradation of the emplaced waste. A multiphase fluid flow code, TOUGH2/EOS8, was adapted to model the processes of gas generation, disposal room creep closure, and multiphase (brine and gas) fluid flow, as well as the coupling between the three processes. System response to gas generation was simulated with a single, isolated disposal room surrounded by homogeneous halite containing two anhydrite interbeds, one above and one below the room. The interbeds were assumed to have flow connections to the room through high-permeability, excavation-induced fractures. System behavior was evaluated by tracking four performance measures: (1) peak room pressure; (2) maximum brine volume in the room; (3) total mass of gas expelled from the room; and (4) the maximum gas migration distance in an interbed. Baseline simulations used current best estimates of system parameters, selected through an evaluation of available data, to predict system response to gas generation under best-estimate conditions. Sensitivity simulations quantified the effects of parameter uncertainty by evaluating the change in the performance measures in response to parameter variations. In the sensitivity simulations, a single parameter value was varied to its minimum and maximum values, representative of the extreme expected values, with all other parameters held at best-estimate values. Sensitivity simulations identified the following parameters as important to gas expulsion and migration away from a disposal room: interbed porosity; interbed permeability; gas-generation potential; halite permeability; and interbed threshold pressure. Simulations also showed that the inclusion of interbed fracturing and a disturbed rock zone had a significant impact on system performance

  9. The role of regional groundwater flow in the hydrogeology of the Culebra member of the Rustler formation at the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    Corbet, T.F.; Knupp, P.M.

    1996-12-01

    Numerical simulation has been used to enhance conceptual understanding, of the hydrogeology of the Culebra Dolomite in the context of regional groundwater flow. The hydrogeology is of interest because this unit is a possible pathway for offsite migration of radionuclides from a proposed repository for defense-generated transuranic wastes (the Waste Isolation Pilot Plant). The numerical model used is three-dimensional, extends laterally to topographic features that form the actual boundaries of a regional groundwater system, and uses a free-surface upper boundary condition to simulate the effect of change in the rate of recharge on groundwater flow. Steady-state simulations were performed to examine the sensitivity of simulation results to assumed values for hydraulic conductivity and recharge rate. Transient simulations, covering the time period from 14,000 years in the past to 10,000 years in the future, provided insight into how patterns of groundwater flow respond to changes in climate. Simulation results suggest that rates and directions of Groundwater flow in the Culebra change with time due to interaction between recharge, movement of the water table, and the topography of the land surface. The gentle east-to-west slope of the land surface in the vicinity of the WIPP caused groundwater in the Culebra to flow toward and discharge into Nash Draw, a topographic depression. Modern-day flow directions in the Culebra reflect regional rather than local features of the topography. Changes in Groundwater flow, however, lagged behind changes in the rate of recharge. The present-day position of the water table is still adjusting to the decrease in recharge that ended 8,000 years ago. Contaminants introduced into the Culebra will travel toward the accessible environment along the Culebra rather than by leaking upward or downward into other units. Natural changes in flow over the next 10,000 years will be small and will mainly reflect future short-term wet periods

  10. Coupled multiphase flow and closure analysis of repository response to waste-generated gas at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, G.A.; Larson, K.W. [INTERA Inc., Austin, TX (United States); Davies, P.B. [Sandia National Laboratories, Albuquerque, NM (United States)

    1995-10-01

    A long-term assessment of the Waste Isolation Pilot Plant (WIPP) repository performance must consider the impact of gas generation resulting from the corrosion and microbial degradation of the emplaced waste. A multiphase fluid flow code, TOUGH2/EOS8, was adapted to model the processes of gas generation, disposal room creep closure, and multiphase (brine and gas) fluid flow, as well as the coupling between the three processes. System response to gas generation was simulated with a single, isolated disposal room surrounded by homogeneous halite containing two anhydrite interbeds, one above and one below the room. The interbeds were assumed to have flow connections to the room through high-permeability, excavation-induced fractures. System behavior was evaluated by tracking four performance measures: (1) peak room pressure; (2) maximum brine volume in the room; (3) total mass of gas expelled from the room; and (4) the maximum gas migration distance in an interbed. Baseline simulations used current best estimates of system parameters, selected through an evaluation of available data, to predict system response to gas generation under best-estimate conditions. Sensitivity simulations quantified the effects of parameter uncertainty by evaluating the change in the performance measures in response to parameter variations. In the sensitivity simulations, a single parameter value was varied to its minimum and maximum values, representative of the extreme expected values, with all other parameters held at best-estimate values. Sensitivity simulations identified the following parameters as important to gas expulsion and migration away from a disposal room: interbed porosity; interbed permeability; gas-generation potential; halite permeability; and interbed threshold pressure. Simulations also showed that the inclusion of interbed fracturing and a disturbed rock zone had a significant impact on system performance.

  11. An analysis of the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Greenfield, M.A. [Univ. of California, Los Angeles, CA (United States); Sargent, T.J.

    1995-11-01

    The Environmental Evaluation Group (EEG) previously analyzed the probability of a catastrophic accident in the waste hoist of the Waste Isolation Pilot Plant (WIPP) and published the results in Greenfield (1990; EEG-44) and Greenfield and Sargent (1993; EEG-53). The most significant safety element in the waste hoist is the hydraulic brake system, whose possible failure was identified in these studies as the most important contributor in accident scenarios. Westinghouse Electric Corporation, Waste Isolation Division has calculated the probability of an accident involving the brake system based on studies utilizing extensive fault tree analyses. This analysis conducted for the U.S. Department of Energy (DOE) used point estimates to describe the probability of failure and includes failure rates for the various components comprising the brake system. An additional controlling factor in the DOE calculations is the mode of operation of the brake system. This factor enters for the following reason. The basic failure rate per annum of any individual element is called the Event Probability (EP), and is expressed as the probability of failure per annum. The EP in turn is the product of two factors. One is the {open_quotes}reported{close_quotes} failure rate, usually expressed as the probability of failure per hour and the other is the expected number of hours that the element is in use, called the {open_quotes}mission time{close_quotes}. In many instances the {open_quotes}mission time{close_quotes} will be the number of operating hours of the brake system per annum. However since the operation of the waste hoist system includes regular {open_quotes}reoperational check{close_quotes} tests, the {open_quotes}mission time{close_quotes} for standby components is reduced in accordance with the specifics of the operational time table.

  12. An analysis of the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.

    1995-11-01

    The Environmental Evaluation Group (EEG) previously analyzed the probability of a catastrophic accident in the waste hoist of the Waste Isolation Pilot Plant (WIPP) and published the results in Greenfield (1990; EEG-44) and Greenfield and Sargent (1993; EEG-53). The most significant safety element in the waste hoist is the hydraulic brake system, whose possible failure was identified in these studies as the most important contributor in accident scenarios. Westinghouse Electric Corporation, Waste Isolation Division has calculated the probability of an accident involving the brake system based on studies utilizing extensive fault tree analyses. This analysis conducted for the U.S. Department of Energy (DOE) used point estimates to describe the probability of failure and includes failure rates for the various components comprising the brake system. An additional controlling factor in the DOE calculations is the mode of operation of the brake system. This factor enters for the following reason. The basic failure rate per annum of any individual element is called the Event Probability (EP), and is expressed as the probability of failure per annum. The EP in turn is the product of two factors. One is the open-quotes reportedclose quotes failure rate, usually expressed as the probability of failure per hour and the other is the expected number of hours that the element is in use, called the open-quotes mission timeclose quotes. In many instances the open-quotes mission timeclose quotes will be the number of operating hours of the brake system per annum. However since the operation of the waste hoist system includes regular open-quotes reoperational checkclose quotes tests, the open-quotes mission timeclose quotes for standby components is reduced in accordance with the specifics of the operational time table

  13. Waste Isolation Pilot Plant Salado hydrology program data report {number_sign}3

    Energy Technology Data Exchange (ETDEWEB)

    Chace, D.A.; Roberts, R.M.; Palmer, J.B.; Kloska, M.B.; Fort, M.D.; Martin, G.J.; Stensrud, W.A. [INTERA, Inc., Albuquerque, NM (United States)

    1998-01-01

    WIPP Salado Hydrology Program Data Report {number_sign}3 presents hydrologic data collected during permeability testing, coupled permeability and hydrofracture testing, and gas-threshold-pressure testing of the Salado Formation performed from November 1991 through October 1995. Fluid-pressure monitoring data representing August 1989 through May 1995 are also included. The report presents data from the drilling and testing of three boreholes associated with the permeability testing program, nine boreholes associated with the coupled permeability and hydrofracture testing program, and three boreholes associated with the gas-threshold-pressure testing program. The purpose of the permeability testing program was to provide data with which to interpret the disturbed and undisturbed permeability and pore pressure characteristics of the different Salado Formation lithologies. The purpose of the coupled permeability and hydrofracture testing program was to provide data with which to characterize the occurrence, propagation, and direction of pressure induced fractures in the Salado Formation lithologies, especially MB139. The purpose of the gas-threshold-pressure testing program was to provide data with which to characterize the conditions under which pressurized gas displaces fluid in the brine-saturated Salado Formation lithologies. All of the holes were drilled from the WIPP underground facility 655 m below ground surface in the Salado Formation.

  14. Performance Of Children With Autism In Parent-Administered Cognitive And Language Exercises

    OpenAIRE

    Elgart, Jonah; Vyshedskiy Ph.D., Andrey; Gankin, Yuriy; Khokhlovich, Edward; Faisman, Alexander; Dunn, Rita; Lokshina, Lisa

    2017-01-01

    There is a broad scientific consensus that early and intensive therapy has the greatest chance of positive impact on an individual with autism spectrum disorder (ASD). However, the availability, quality, and general funding for early intervention programs is often lacking, leaving newly diagnosed children without adequate and sufficient therapy during the most critical early period of their development. Parent-administered iPad-assisted therapy has the potential to reduce the gap between the ...

  15. 47 CFR 97.509 - Administering VE requirements.

    Science.gov (United States)

    2010-10-01

    ..., grandchildren, stepchildren, parents, grandparents, stepparents, brothers, sisters, stepbrothers, stepsisters... accommodate an examinee whose physical disabilities require a special examination procedure. The administering VEs may require a physician's certification indicating the nature of the disability before determining...

  16. Findings from Survey Administered to Weatherization Training Centers

    Energy Technology Data Exchange (ETDEWEB)

    Conlon, Brian [Univ. of Tennessee, Knoxville, TN (United States); Tonn, Bruce Edward [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-03-01

    This report summarizes results of a survey administered to directors of weatherization training centers that receive funding from the U.S. Department of Energy. The survey presents results related to questions on training offered and future plans.

  17. Plasma kinetics of intravenously administered lactose- in-saline in ...

    African Journals Online (AJOL)

    USER

    2010-05-17

    ) the rapid sequestration of homologous desialylated erythrocytes from the blood stream of rabbits has been considerably inhibited by intravenously administered lactose (Muller et al., 1981). More recently, infusion of lactose ...

  18. Conceptual plan: Two-Phase Flow Laboratory Program for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Howarth, S.M.

    1993-07-01

    The Salado Two-Phase Flow Laboratory Program was established to address concerns regarding two-phase flow properties and to provide WIPP-specific, geologically consistent experimental data to develop more appropriate correlations for Salado rock to replace those currently used in Performance Assessment models. Researchers in Sandia's Fluid Flow and Transport Department originally identified and emphasized the need for laboratory measurements of Salado threshold pressure and relative permeability. The program expanded to include the measurement of capillary pressure, rock compressibility, porosity, and intrinsic permeability and the assessment of core damage. Sensitivity analyses identified the anhydrite interbed layers as the most likely path for the dissipation of waste-generated gas from waste-storage rooms because of their relatively high permeability. Due to this the program will initially focus on the anhydrite interbed material. The program may expand to include similar rock and flow measurements on other WIPP materials including impure halite, pure halite, and backfill and seal materials. This conceptual plan presents the scope, objectives, and historical documentation of the development of the Salado Two-Phase Flow Program through January 1993. Potential laboratory techniques for assessing core damage and measuring porosity, rock compressibility, capillary and threshold pressure, permeability as a function of stress, and relative permeability are discussed. Details of actual test designs, test procedures, and data analysis are not included in this report, but will be included in the Salado Two-Phase Flow Laboratory Program Test Plan pending the results of experimental and other scoping activities in FY93

  19. Informationally administered reward enhances intrinsic motivation in schizophrenia.

    Science.gov (United States)

    Lee, Hyeon-Seung; Jang, Seon-Kyeong; Lee, Ga-Young; Park, Seon-Cheol; Medalia, Alice; Choi, Kee-Hong

    2017-10-01

    Even when individuals with schizophrenia have an intact ability to enjoy rewarding moments, the means to assist them to translate rewarding experiences into goal-directed behaviors is unclear. The present study sought to determine whether informationally administered rewards enhance intrinsic motivation to foster goal-directed behaviors in individuals with schizophrenia (SZ) and healthy controls (HCs). Eighty-four participants (SZ=43, HCs=41) were randomly assigned to conditions involving either a performance-contingent reward with an informationally administered reward or a task-contingent reward with no feedback. Participants were asked to play two cognitive games of equalized difficulty. Accuracy, self-reported intrinsic motivation, free-choice intrinsic motivation (i.e., game play during a free-choice observation period), and perceived competency were measured. Intrinsic motivation and perceived competency in the cognitive games were similar between the two participant groups. The informationally administered reward significantly enhanced self-reported intrinsic motivation and perceived competency in both the groups. The likelihood that individuals with schizophrenia would play the game during the free-choice observation period was four times greater in the informationally administered reward condition than that in the no-feedback condition. Our findings suggest that, in the context of cognitive remediation, individuals with schizophrenia would benefit from informationally administered rewards. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. The five year report of the Tunnel Sealing Experiment: an international project of AECL, JNC, ANDRA and WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, N.A.; Cournut, A.; Dixon, D. (and others)

    2002-07-01

    of bentonite; concrete heat of hydration; concrete shrinkage; grouting of the both EDZ and the concrete-rock interface; cracking of the concrete and debonding of the concrete-rock interface. The conclusions arising from the TSX are directly applicable to either tunnel or shaft seals constructed in potential host rock environments under consideration for radioactive waste disposal, and the results have direct application to the repository sealing programs of the participating countries. (author)

  1. The five year report of the Tunnel Sealing Experiment: an international project of AECL, JNC, ANDRA and WIPP

    International Nuclear Information System (INIS)

    Chandler, N.A.; Cournut, A.; Dixon, D.

    2002-01-01

    bentonite; concrete heat of hydration; concrete shrinkage; grouting of the both EDZ and the concrete-rock interface; cracking of the concrete and debonding of the concrete-rock interface. The conclusions arising from the TSX are directly applicable to either tunnel or shaft seals constructed in potential host rock environments under consideration for radioactive waste disposal, and the results have direct application to the repository sealing programs of the participating countries. (author)

  2. Comparison of an interviewer-administered with an automated self-administered 24 h (ASA24) dietary recall in adolescents.

    Science.gov (United States)

    Hughes, Ashley R; Summer, Suzanne S; Ollberding, Nicholas J; Benken, Laura A; Kalkwarf, Heidi J

    2017-12-01

    The current pilot study aimed to assess whether reporting quality would decline materially in adolescents completing weekly web-based Automated Self-Administered 24-Hour dietary recalls (ASA24-Kids-2014) and interviewer-administered 24 h dietary recalls for six weeks. We also aimed to assess method preference. We conducted two studies. Study 1 (n 20) randomized participants to complete either one ASA24-Kids-2014 or one interviewer-administered recall weekly, for six weeks. Energy intake and number of foods reported were described for each method over time. Differences between recall methods for each measure were tested using mixed-effects regression. Study 2 (n 10) employed a randomized crossover design to describe method preference. Dietary intake was collected either by telephone (interviewer-administered dietary recalls) or via the Internet (ASA24-Kids-2014 dietary recalls). Adolescents aged 12-17 years with no prior diet recording experience were enrolled. In Study 1, mean (sd) total energy and number of foods reported decreased by 50 (222) kJ (12 (53) kcal) and 0·05 (0·31) items v. 38 (138) kJ (9 (33) kcal) and 0·17 (0·14) items per recall for participants randomized to the ASA24-Kids-2014 v. interviewer-administered recalls, respectively. There was no difference between groups for either measure (P > 0·57). In Study 2, eight of ten participants preferred the interviewer-administered recall over the ASA24-Kids-2014. Overall, seven of twenty participants experienced technical difficulties with the ASA24-Kids-2014. No appreciable decay in reporting quality was seen for either method. However, participants reported a preference for the interviewer-administered recall. Our findings can help inform and support larger studies to further characterize the performance of the ASA24 in adolescents.

  3. Administering chemotherapy in nononcology settings: a case study.

    Science.gov (United States)

    Smith, Nancy

    2011-08-01

    Providing chemotherapy for patients in a variety of settings may be a challenge for oncology nurses. Increased acuity and comorbidities of patients needing chemotherapy have resulted in a greater incidence of administration in nononcology settings, such as intensive care units (ICUs). In addition, patients with conditions other than cancer are receiving chemotherapy. Because of a lack of certified and experienced chemotherapy nurses in the ICU, oncology nurses may be pulled from their unit to administer chemotherapy. Another possibility is that nonchemotherapy-certified nurses may be asked to administer chemotherapy. Caring for patients receiving chemotherapy may be stressful for nononcology nurses because of their lack of knowledge regarding chemotherapy precautions and the management of side effects and toxicities. Not only is coordination and cooperation between nursing personnel vital, certified oncology nurses must be able to assess the situation, provide the necessary information and education, and safely administer the chemotherapy. This article describes a case study and provides suggestions for planning in similar situations.

  4. Effect of lead acetate administered orally at different dosage levels ...

    African Journals Online (AJOL)

    The project was conducted to evaluate the effect of lead administered as lead acetate at different dosage levels via drinking water in broiler chicks. Thirty-five healthy chicks were divided into seven groups (five chicks each) and one group was kept as un-medicated control. Groups A, B, C, D, E and F were medicated with ...

  5. Teaching Auction Strategy Using Experiments Administered Via the Internet

    Science.gov (United States)

    Asker, John; Grosskopf, Brit; McKinney, C. Nicholas; Niederle, Muriel; Roth, Alvin E.; Weizsacker, Georg

    2004-01-01

    The authors present an experimental design used to teach concepts in the economics of auctions and implications for e-Business procurement. The experiment is easily administered and can be adapted to many different treatments. The chief innovation is that it does not require the use of a lab or class time. Instead, the design can be implemented on…

  6. Challenges of Administering Teacher Education Programme in Kenyan Universities

    Science.gov (United States)

    Genvieve, Nasimiyu

    2017-01-01

    Proper management of logistical issues in Teacher education programme tends to promote the quality of preparation of school teachers. The main objective of the study was to investigate challenges of administering teacher education programmes in Kenyan universities. The theoretical framework of the study was adopted as used by Koehler and Mishra's…

  7. Comparison between fish and linseed oils administered orally for ...

    African Journals Online (AJOL)

    The objective of this study was to compare the efficacy of two sources of omega 3 and 6, fish oil (FO) and linseed oil (LO), orally administered, alone or in combination, for treating experimentally induced keratoconjunctivitis sicca (KCS) in rabbits. Twenty-eight New Zealand rabbits were used in this study. Seven animals ...

  8. Potency Studies of live- Attenuated Viral Vaccines Administered in ...

    African Journals Online (AJOL)

    We critically carried out a potency study in 1992 and 1997 on measles and poliovirus vaccines administered at five different vaccination centers in the metropolitan Lagos, Nigeria. using WHO guidelines on titration of live- viral vaccines, our results revealed that only 6 (16.7%) of 36 measles vaccine (MV) vials and 11 ...

  9. Statistical analysis of Japanese Thorotrast-administered autopsy cases

    International Nuclear Information System (INIS)

    Mori, T.; Kato, Y.; Shimamine, T.; Watanabe, S.

    1979-01-01

    The causes of death of 144 Japanese autopsy cases during 1945-1975, who had been intravascularly injected with Thorotrast in life, were compared with those of non-Thorotrast-administered autopsy cases in the same age bracket, recorded in the Annals of Japanese Pathological Autopsy Cases during 1958-1973. This comparison revealed that the incidence of malignant hepatic tumors was more than 10 times higher in the Thorotrast-administered cases. The increase was attributable to an increased incidence of hemangioendothelioma and cholangiocarcinoma of the liver. The only significant increase of liver cirrhosis found to exist in the Thorotrast group occurred in the female cases. Some of the Thorotrast-administered cases were found to have developed myeloid leukemia and erythroleukemia. There was also a significant increase in the number of cases of aplastic anemia in the Thorotrast group, but clinically and pathologically these were atypical. Lymphatic leukemia was not observed. No significant difference was found in the incidence of either malignant lymphomas or osteosarcomas in the Thorotrast group and the controls. Lung cancer, on the other hand, showed a significantly higher incidence among the controls than among the Thorotrast-administered cases

  10. Biochemical effects on the liver and kidney of rats administered ...

    African Journals Online (AJOL)

    The effects of aqueous extract of ximenia Americana stem bark on liver and kidney of albino rats was investigated. Different doses of the crude extract were administered to rats for 30 consecutive days. The levels of serum aspartate aminotransferase (AST) and alanine aminotransferase (ALT) of treated animals significantly ...

  11. Erythrocyte osmotic fragility of pigs administered ascorbic acid and ...

    African Journals Online (AJOL)

    The experiment was carried out with the aim of investigating the effect of an antioxidant ascorbic acid on erythrocyte osmotic fragility of pigs transported by road for 4 h during the harmattan season. 16 pigs administered with ascorbic acid at the dose of 250 mg/kg per os and individually served as experimental animals and ...

  12. The role of intraperitoneally administered vitamin C during ...

    African Journals Online (AJOL)

    The effects of daily intraperitoneally administered doses of 100 mg/kg bd. wt. vitamin C on levels of some endogenous antioxidants as well as hepatic and renal function were investigated in a group of rabbits infected with a strain of Trypanosoma congolense (strain number: BS2/TC /SP28/P4). Values of parameters ...

  13. Impact of Methods of Administering Growth-Stage Deficit Irrigation ...

    African Journals Online (AJOL)

    ABSRACT: Field experiments were conducted in 2009/10 and 2010/11 irrigation seasons at the Institute for. Agricultural Research, Samaru Zaria, to assess the impact of two methods of administering Growth-stage deficit irrigation scheduling (GSDIS) on yield and soil water balance of an early maturing maize variety.

  14. Pharmacokinetics of orally administered tramadol in domestic rabbits (Oryctolagus cuniculus).

    Science.gov (United States)

    Souza, Marcy J; Greenacre, Cheryl B; Cox, Sherry K

    2008-08-01

    To determine the pharmacokinetics of an orally administered dose of tramadol in domestic rabbits (Oryctolagus cuniculus). 6 healthy adult sexually intact female New Zealand White rabbits. Physical examinations and plasma biochemical analyses were performed to ensure rabbits were healthy prior to the experiment. Rabbits were anesthetized with isoflurane, and IV catheters were placed in a medial saphenous or jugular vein for collection of blood samples. One blood sample was collected before treatment with tramadol. Rabbits were allowed to recover from anesthesia a minimum of 1 hour before treatment. Then, tramadol (11 mg/kg, PO) was administered once, and blood samples were collected at various time points up to 360 minutes after administration. Blood samples were analyzed with high-performance liquid chromatography to determine plasma concentrations of tramadol and its major metabolite (O-desmethyltramadol). No adverse effects were detected after oral administration of tramadol to rabbits. Mean +/- SD half-life of tramadol after administration was 145.4 +/- 81.0 minutes; mean +/- SD maximum plasma concentration was 135.3 +/- 89.1 ng/mL. Although the dose of tramadol required to provide analgesia in rabbits is unknown, the dose administered in the study reported here did not reach a plasma concentration of tramadol or O-desmethyltramadol that would provide sufficient analgesia in humans for clinically acceptable periods. Many factors may influence absorption of orally administered tramadol in rabbits.

  15. Brine Sampling and Evaluation Program: 1988 report

    International Nuclear Information System (INIS)

    Deal, D.E.; Abitz, R.J.; Case, J.B.; Crawley, M.E.; Deshler, R.M.; Drez, P.E.; Givens, C.A.; King, R.B.; Myers, J.; Pietz, J.M.; Roggenthen, W.M.; Tyburski, J.R.; Belski, D.S.; Niou, S.; Wallace, M.G.

    1989-12-01

    The data presented in this report are the result of Brine Sampling and Evaluation Program (BSEP) activities at the Waste Isolation Pilot Plant (WIPP) during 1988. These activities, which are a continuation and update of studies that began in 1982 as part of the Site Validation Program, were formalized as the BSEP in 1985 to document and investigate the origins, hydraulic characteristics, extent, and composition of brine occurrences in the Permian Salado Formation, and seepage of that brine into the excavations at the WIPP. Previous BSEP reports (Deal and Case, 1987; Deal and others, 1987) described the results of ongoing activities that monitor brine inflow into boreholes in the facility, moisture content of the Salado Formation, brine geochemistry, and brine weeps and crusts. The information provided in this report updates past work and describes progress made during the calendar year 1988. During 1988, BSEP activities focused on four major areas to describe and quantify brine activity: (1) monitoring of brine inflow parameters, e.g., measuring brines recovered from holes drilled upward from the underground drifts (upholes), downward from the underground drifts (downholes), and near-horizontal holes; (2) characterizing the brine, e.g., the geochemistry of the brine and the presence of bacteria and their possible interactions with experiments and operations; (3) characterizing formation properties associated with the occurrence of brine; e.g., determining the water content of various geologic units, examining these units in boreholes using a video camera system, and measuring their resistivity (conductivity); and (4) modeling to examine the interaction of salt deformation near the workings and brine seepage through the deforming salt. 77 refs., 48 figs., 32 tabs

  16. Protocol compliance of administering parenteral medication in Dutch hospitals: an evaluation and cost-estimation of the implementation.

    NARCIS (Netherlands)

    Schilp, J.; Boot, S.; Blok, C. de; Spreeuwenberg, P.; Wagner, C.

    2014-01-01

    Objectives: Preventable adverse drug events (ADEs) are closely related to administration processes of parenteral medication. The Dutch Patient Safety Program provided a protocol for administering parenteral medication to reduce the amount of ADEs. The execution of the protocol was evaluated and a

  17. Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

    International Nuclear Information System (INIS)

    DOE Carlsbad Field Office

    2001-01-01

    The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to

  18. Chesapeake Bay Program Grant Guidance

    Science.gov (United States)

    Grant Guidance and appendices for the Chesapeake Bay Program that describes how the U.S. Environmental Protection Agency’s (EPA) Region 3’s Chesapeake Bay Program Office (CBPO) administers grant and cooperative agreement funds.

  19. Efficacy and safety of intravenous fentanyl administered by ambulance personnel

    DEFF Research Database (Denmark)

    Friesgaard, Kristian Dahl; Nikolajsen, Lone; Giebner, Matthias

    2016-01-01

    BACKGROUND: Management of pain in the pre-hospital setting is often inadequate. In 2011, ambulance personnel were authorized to administer intravenous fentanyl in the Central Denmark Region. The aim of this study was to evaluate the efficacy and safety of intravenous fentanyl administered...... by ambulance personnel. METHODS: Pre-hospital medical charts from 2348 adults treated with intravenous fentanyl by ambulance personnel during a 6-month period were reviewed. The primary outcome was the change in pain intensity on a numeric rating scale (NRS) from before fentanyl treatment to hospital arrival....... Secondary outcomes included the number of patients with reduction in pain intensity during transport (NRS ≥ 2), the number of patients with NRS > 3 at hospital arrival, and potential fentanyl-related side effects. RESULTS: Fentanyl reduced pain from before treatment (8, IQR 7-9) to hospital arrival (4, IQR...

  20. Techniques to administer oral, inhalational, and IV sedation in dentistry

    OpenAIRE

    Diana Krystyna Harbuz; Michael O’Halloran

    2016-01-01

    Background Sedation in dentistry is a controversial topic given the variety of opinions regarding its safe practice. Aims This article evaluates the various techniques used to administer sedation in dentistry and specific methods practiced to form a recommendation for clinicians. Methods An extensive literature search was performed using PubMed, Medline, Google Scholar, Google, and local library resources. Results Most of the literature revealed a consensus that li...

  1. Challenging situations when administering palliative chemotherapy - a nursing perspective.

    Science.gov (United States)

    Näppä, Ulla; Rasmussen, Birgit H; Axelsson, Bertil; Lindqvist, Olav

    2014-12-01

    Palliative chemotherapy treatments (PCT) are becoming more common for patients with incurable cancer; a basic challenge is to optimize tumour response while minimizing side-effects and harm. As registered nurses most often administer PCT, they are most likely to be confronted with difficult situations during PCT administration. This study explores challenging situations experienced by nurses when administering PCT to patients with incurable cancer. Registered nurses experienced in administering PCT were asked in interviews to recall PCT situations they found challenging. Inspired by the narrative tradition, stories were elicited and analysed using a structural and thematic narrative analysis. A total of twenty-eight stories were narrated by seventeen nurses. Twenty of these were dilemmas that could be sorted into three storylines containing one to three dilemmatic situations each. The six dilemmatic situations broadly related to three interwoven areas: the uncertainty of the outcome when giving potent drugs to vulnerable patients; the difficulty of resisting giving PCT to patients who want it; and insufficient communication between nurses and physician. Nurses who administer PCT are engaged in a complex task that can give rise to a number of dilemmatic situations. The findings may be interpreted as meaning that at least some situations might be preventable if the knowledge and insight of all team members - nurses, physicians, patients, and relatives - are jointly communicated and taken into account when deciding whether or not to give PCT. Forming palliative care teams early in the PCT trajectory, could be beneficial for staff and patients. Copyright © 2014 Elsevier Ltd. All rights reserved.

  2. The School Breakfast Program

    Science.gov (United States)

    US Department of Agriculture, 2009

    2009-01-01

    The School Breakfast Program is a federally assisted meal program operating in public and nonprofit private schools and residential child care institutions. It began as a pilot project in 1966, and was made permanent in 1975. The School Breakfast Program is administered at the Federal level by the Food and Nutrition Service. At the State level,…

  3. Absorption sites of orally administered drugs in the small intestine.

    Science.gov (United States)

    Murakami, Teruo

    2017-12-01

    In pharmacotherapy, drugs are mostly taken orally to be absorbed systemically from the small intestine, and some drugs are known to have preferential absorption sites in the small intestine. It would therefore be valuable to know the absorption sites of orally administered drugs and the influencing factors. Areas covered:In this review, the author summarizes the reported absorption sites of orally administered drugs, as well as, influencing factors and experimental techniques. Information on the main absorption sites and influencing factors can help to develop ideal drug delivery systems and more effective pharmacotherapies. Expert opinion: Various factors including: the solubility, lipophilicity, luminal concentration, pKa value, transporter substrate specificity, transporter expression, luminal fluid pH, gastrointestinal transit time, and intestinal metabolism determine the site-dependent intestinal absorption. However, most of the dissolved fraction of orally administered drugs including substrates for ABC and SLC transporters, except for some weakly basic drugs with higher pKa values, are considered to be absorbed sequentially from the proximal small intestine. Securing the solubility and stability of drugs prior to reaching to the main absorption sites and appropriate delivery rates of drugs at absorption sites are important goals for achieving effective pharmacotherapy.

  4. A prequalifying program for evaluating the analytical performance of commercial laboratories

    International Nuclear Information System (INIS)

    Reith, C.C.; Bishop, C.T.

    1987-01-01

    Soil and water samples were spiked with known activities of radionuclides and sent to seven commercial laboratories that had expressed an interest in analyzing environmental samples for the Waste Isolation Pilot Plant (WIPP). This Prequalifying Program was part of the selection process for an analytical subcontractor for a three-year program of baseline radiological surveillance around the WIPP site. Both media were spiked at three different activity levels with several transuranic radionuclides, as well as tritium, fission products, and activation products. Laboratory performance was evaluated by calculating relative error for each radionuclide in each sample, assigning grade values, and compiling grades into report cards for each candidate. Results for the five laboratories completing the Prequalifying Program were pooled to reveal differing degrees of difficulty among the treatments and radionuclides. Interlaboratory comparisons revealed systematic errors in the performance of one candidate. The final report cards contained clear differences among overall grades for the five laboratories, enabling analytical performance to be used as a quantitative criterion in the selection of an analytical subcontractor. (author)

  5. Filling a niche market: administering drugs by injection or infusion.

    Science.gov (United States)

    Kaldy, Joanne

    2015-05-01

    There is greater incentive than ever to keep individuals requiring injectable or infusion therapy in the nursing facility-and not transfer them to a hospital-to receive those services. There is a demand for pharmacists with the skills, knowledge, and training to provide these services. To make that possible, pharmacies and pharmacists with the proper equipment, supplies, knowledge, training, and expertise are needed to work closely with physicians and nurses to provide sterile, properly compounded products and ensure that drugs are administered appropriately and in the right doses. These pharmacists also can work with facilities and practitioners to assess, improve, and document quality.

  6. Biologic effects of orally administered deuterium oxide on rat liver.

    Science.gov (United States)

    Kanwar, K C; Verma, R

    1977-01-01

    Rats were made to drink D2O mixed water (30: 70) for 6 weeks in order to study the biological effects of orally administered D2O on the liver. Heavy water administration results in gradual decrease in the body weight whereas the liver showed marginal increase in weight throughout the experimental period. Phosphatases and dehydrogenases were analyzed biochemically. Acid phosphatase, glucose-6-phosphatase and adenosine triphosphatase registered fall in contrast to alkaline phosphatase, SDH and LDH, all of which showed a definite increase. Lipids, nucleic acids and proteins, estimated biochemically, gradually decreased throughout the experimental period in response to D2O feeding.

  7. Motivation and satisfaction among community health workers administering rapid diagnostic tests for malaria in Western Kenya.

    Science.gov (United States)

    Winn, Laura K; Lesser, Adriane; Menya, Diana; Baumgartner, Joy N; Kipkoech Kirui, Joseph; Saran, Indrani; Prudhomme-O'Meara, Wendy

    2018-06-01

    The continued success of community case management (CCM) programs in low-resource settings depends on the ability of these programs to retain the community health workers (CHWs), many of whom are volunteers, and maintain their high-quality performance. This study aims to identify factors related to the motivation and satisfaction of CHWs working in a malaria CCM program in two sub-counties in Western Kenya. We interviewed 70 CHWs who were trained to administer malaria rapid diagnostic tests as part of a broader study evaluating a malaria CCM program. We identified factors related to CHWs' motivation and their satisfaction with participation in the program, as well as the feasibility of program scale-up. We used principal components analysis to develop an overall CHW satisfaction score and assessed associations between this score and individual CHW characteristics as well as their experiences in the program. The majority of CHWs reported that they were motivated to perform their role in this malaria CCM program by a personal desire to help their community (69%). The most common challenge CHWs reported was a lack of community understanding about malaria diagnostic testing and CHWs' role in the program (39%). Most CHWs (89%) reported that their involvement in the diagnostic testing intervention had either a neutral or a net positive effect on their other CHW activities, including improving skills applicable to other tasks. CHWs who said they strongly agreed with the statement that their work with the malaria program was appreciated by the community had a 0.76 standard deviation (SD) increase in their overall satisfaction score (95% confidence interval CI = 0.10-1.24, P  = 0.03). Almost all CHWs (99%) strongly agreed that they wanted to continue their role in the malaria program. Overall, CHWs reported high satisfaction with their role in community-based malaria diagnosis, though they faced challenges primarily related to community understanding and

  8. Metabolic fate of orally administered enzymatically synthesized glycogen in rats.

    Science.gov (United States)

    Furuyashiki, Takashi; Takata, Hiroki; Kojima, Iwao; Kuriki, Takashi; Fukuda, Itsuko; Ashida, Hitoshi

    2011-04-01

    We developed a new process for enzymatically synthesized glycogen (ESG), which is equivalent in physicochemical properties to natural-source glycogen (NSG) except its resistant property to degradation by α-amylase in vitro. In this study the metabolic fates of orally administered ESG in rats were investigated by a single oral administration test and a 2 week ingestion test. The glycemic index of ESG was 79. After the 2 week ingestion of ESG, the cecal content and production of short chain fatty acids were significantly increased, the pH value of cecal content was lowered, and the counts of Bifidobacterium and Lactobacillus in feces were significantly increased. Additionally, plasma levels of triacylglycerol and total cholesterol were significantly reduced by ESG. In contrast, NSG did not affect these parameters at all. The results collectively suggest that around 20% of orally administered ESG was transferred to the cecum in the form of polymer and assimilated into short chain fatty acids by microbiota and the polymer affected lipid metabolism.

  9. Metabolism of exogenously administered natural surfactant in the newborn lamb

    Energy Technology Data Exchange (ETDEWEB)

    Glatz, T.; Ikegami, M.; Jobe, A.

    1982-09-01

    (/sup 3/H)-Palmitate labeled natural lamb surfactant and free (/sup 14/C)-choline were mixed with the lung fluid of 11 term lambs at cesarean section, before the first breath. After receiving the isotope, the lambs were delivered, allowed to breathe spontaneously, and were subsequently sacrificed from 5 min to 96 h of age. Alveolar washes, lung homogenates, microsomal and lamellar body fractions of lungs, and pulmonary alveolar macrophages were examined for the presence of labeled phosphatidylcholine. Analysis of the labeled natural surfactant kinetic data revealed an apparent t 1/2 of phosphatidylcholine in the whole lung of 6.0 days. This half-life can be interpreted only as a rough estimate. Appearance of considerable (/sup 3/H) labeled phosphatidylcholine in the lung homogenates demonstrated uptake of phosphatidylcholine from alveoli into lung tissue. The surfactant-associated label in homogenates was localized preferentially to lamellar body fractions. Some of the administered (/sup 14/C)-choline appeared in phosphatidylcholine. Almost all of this labeled phosphatidylcholine was associated with the homogenate. Extremely small % of administered (3H) and (14C) were found in pulmonary alveolar macrophages.

  10. The Carlsbad Environmental Monitoring and Research Center: An independent program for community information

    International Nuclear Information System (INIS)

    Fingleton, Donald J.; Bhada, Ron K.; Derald Morgan, J.; Julien, Howard

    1992-01-01

    The Waste Isolation Pilot Plant (WIPP) was designed and built as a research and development facility to obtain data to demonstrate the safe management, storage, and disposal of defense-related transuranic (TRU) waste. The WIPP facility, near Carlsbad, New Mexico, is scheduled to receive its first shipment of TRU waste in 1992. The citizens of Carlsbad requested the U.S. Department of Energy (DOE) to provide them with an independent organization that would monitor the entire area with state-of-the-art monitoring techniques and publish the data. As a follow-up, the DOE approved a proposal from the Waste-management Education and Research Consortium of New Mexico to develop and implement this program. The purpose of this paper is to (1) describe this innovative program to establish the Carlsbad Environmental Monitoring and Research Center, an independent university based center to study health and environmental impacts associated with technological development; (2) present the Center's mission and objectives; and (3) give an overview of the progress. (author)

  11. US waste management overview, new legislation, and status and plans of the disposal program

    International Nuclear Information System (INIS)

    Isaacs, T.

    1988-01-01

    The Nuclear Waste Policy Act of 1982 provided a comprehensive master plan for the United States to locate a nuclear waste repository. Details of this process, which began with 9 sites, are well known. One repository was to be provided with a 70,000 metric ton limit on capacity. Provisions were to be made for transportation and a proposed MRS facility, and for activities leading to the potential siting of a second repository. A decision analysis technique was used by DOE in nominating three repository sites for characterization. The second repository program, which had become a matter of political controversy, was stopped because the first repository would have enough capacity for all commercial spent fuel for some time to come. A court decision to drop the MRS was later overruled. DOE still wants a vigorous international program along with work concerned with any rock medium that can be of potential value to the US repository effort. WIPP will continue to be of interest and emphasis as a repository project in salt for defense transuranic wastes. High-level wastes will not be permanently isolated at WIPP

  12. Maine Migrant Program: 1997-1998 Program Evaluation.

    Science.gov (United States)

    Bazinet, Suzanne C., Ed.

    The Maine Department of Education contracts with local educational agencies to administer the Maine Migrant Education Program. The program's overall mission is to provide the support necessary for migrant children to achieve Maine's academic standards. In 1997-98, 73 local migrant programs served 9,838 students, and 63 summer programs served 1,769…

  13. Metrological aspects in the estimate of the administered activity in nuclear medicine patients; Aspectos metrologicos na estimativa da atividade administrada em pacientes de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ruzzarin, A.; Iwahara, A.; Tahuata, L., E-mail: anelise@bolsista.ird.gov.br [Instituto de Radioprotecao e Dosimetria, (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil), Lab. Nacional de Metrologia das Radiacoes Ionizantes; Xavier, A.M. [Comissao Nacional de Energia Nuclear (ESPOA/CNEN-RS), Porto Alegre, RS (Brazil). Escritorio de Porto Alegre

    2014-07-01

    In order to investigate the performance quality of routine measurements of Nuclear Medicine Services (NMS), the National Metrology Laboratory of Ionizing Radiation/Institute of Radiation Protection and Dosimetry (LNMRI/IRD) has been conducting, since 1998, a program of comparison for activity measurements of radiopharmaceuticals administered to patients in nuclear medicine. Correction factors are determined from the result of performance analysis in order to determine with better accuracy the activity to be administered to the patients. (author)

  14. Moderate and deep nurse-administered propofol sedation is safe

    DEFF Research Database (Denmark)

    Jensen, Jeppe Thue; Møller, Ann; Hornslet, Pernille

    2015-01-01

    INTRODUCTION: Non-anaesthesiologist-administered propofol sedation (NAPS/NAAP) is increasingly used in many countries. Most regimens aim for light or moderate sedation. Little evidence on safety of deep NAPS sedation is available. The aim of this study was to explore the safety of intermittent deep...... sedation with NAPS in patients undergoing gastroenterologic endoscopic procedures. METHODS: This was a retrospective case-control study. All patients sedated with NAPS for colonoscopies, sigmoidoscopies and oesophagogastroduodenoscopies from May 2007 through December 2012 were included. Cases were defined...... with a higher rate of adverse events. CONCLUSION: Safety during intermittent deep sedation with NAPS was good. Age, ASA class 3 and total propofol dose were correlated with a higher rate of adverse events. Patients aged 60 years or more needed more handling during adverse events. FUNDING: Arvid Nilsson...

  15. Administering truncated receive functions in a parallel messaging interface

    Science.gov (United States)

    Archer, Charles J; Blocksome, Michael A; Ratterman, Joseph D; Smith, Brian E

    2014-12-09

    Administering truncated receive functions in a parallel messaging interface (`PMI`) of a parallel computer comprising a plurality of compute nodes coupled for data communications through the PMI and through a data communications network, including: sending, through the PMI on a source compute node, a quantity of data from the source compute node to a destination compute node; specifying, by an application on the destination compute node, a portion of the quantity of data to be received by the application on the destination compute node and a portion of the quantity of data to be discarded; receiving, by the PMI on the destination compute node, all of the quantity of data; providing, by the PMI on the destination compute node to the application on the destination compute node, only the portion of the quantity of data to be received by the application; and discarding, by the PMI on the destination compute node, the portion of the quantity of data to be discarded.

  16. Moderate and deep nurse-administered propofol sedation is safe

    DEFF Research Database (Denmark)

    Jensen, Jeppe Thue; Møller, Ann; Hornslet, Pernille

    2015-01-01

    sedation with NAPS in patients undergoing gastroenterologic endoscopic procedures. METHODS: This was a retrospective case-control study. All patients sedated with NAPS for colonoscopies, sigmoidoscopies and oesophagogastroduodenoscopies from May 2007 through December 2012 were included. Cases were defined......INTRODUCTION: Non-anaesthesiologist-administered propofol sedation (NAPS/NAAP) is increasingly used in many countries. Most regimens aim for light or moderate sedation. Little evidence on safety of deep NAPS sedation is available. The aim of this study was to explore the safety of intermittent deep......'s Foundation provided funding for this study. The founders did not have any influence on the design or the presentation of the study. TRIAL REGISTRATION: not relevant....

  17. Haematological disorders in Thorotrast-administered patients in Japan

    International Nuclear Information System (INIS)

    Kamiyama, Ryuichi; Hatakeyama, Shigeru

    1989-01-01

    Fifteen haematological disorders including ten leukaemia cases, one primary acquired sideroblastic anaemia and four aplastic anaemia cases were studied clinicopathologically in autopsies from patients who had been administered Thorotrast in Japan. The leukaemia group, the primary acquired sideroblastic anaemia and the aplastic anaemia cases after Thorotrast administration were considered to be mainly atypical, and it was speculated that damage induced by Thorotrast may affect the haemopoietic stem cell level and the haemopoietic microenvironment. Both dose rate and absorbed dose estimated in bone marrow, spleen and liver at autopsy showed no significant difference between the leukaemia group, primary acquired sideroblastic anaemia, aplastic anaemia and non-haematological disorders excluding the malignant hepatic tumours and liver cirrhosis. (author)

  18. Techniques to administer oral, inhalational, and IV sedation in dentistry

    Directory of Open Access Journals (Sweden)

    Diana Krystyna Harbuz

    2016-02-01

    Full Text Available Background Sedation in dentistry is a controversial topic given the variety of opinions regarding its safe practice. Aims This article evaluates the various techniques used to administer sedation in dentistry and specific methods practiced to form a recommendation for clinicians. Methods An extensive literature search was performed using PubMed, Medline, Google Scholar, Google, and local library resources. Results Most of the literature revealed a consensus that light sedation on low-risk American Society of Anesthesiologists (ASA groups, that is ASA I, and possibly II, is the safest method for sedation in a dental outpatient setting. Conclusion Formal training is essential to achieve the safe practice of sedation in dentistry or medicine. The appropriate setting for sedation should be determined as there is an increased risk outside the hospital setting. Patients should be adequately assessed and medication titrated appropriately, based on individual requirements.

  19. Human metabolism of orally administered radioactive cobalt chloride.

    Science.gov (United States)

    Holstein, H; Ranebo, Y; Rääf, C L

    2015-05-01

    This study investigated the human gastrointestinal uptake (f1) and subsequent whole-body retention of orally administered inorganic radioactive cobalt. Of eight adult volunteers aged between 24 and 68 years, seven were given solutions of (57)Co (T1/2 = 272 d) containing a stable cobalt carrier, and six were given carrier-free (58)Co (T1/2 = 71 d). The administered activities ranged between 25 and 103 kBq. The observed mean f1, based on 6 days accumulated urinary excretion sampling and whole-body counting, was 0.028 ± 0.0048 for carrier-free (58)Co, and 0.016 ± 0.0021 for carrier-associated (57)Co. These values were in reasonable agreement with values reported from previous studies involving a single intake of inorganic cobalt. The time pattern of the total retention (including residual cobalt in the GI tract) included a short-term component with a biological half-time of 0.71 ± 0.03 d (average ± 1 standard error of the mean for the two nuclides), an intermediate component with a mean half-time of 32 ± 8.5 d, and a long-term component (observed in two volunteers) with half-times ranging from 80 to 720 d for the two isotopes. From the present data we conclude that for the short-lived (57)Co and (58)Co, more than 95% of the internal absorbed dose was delivered within 7 days following oral intake, with a high individual variation influenced by the transit time of the unabsorbed cobalt through the gastro-intestinal tract. Copyright © 2015 Elsevier Ltd. All rights reserved.

  20. Balanced propofol sedation administered by nonanesthesiologists: The first Italian experience

    Science.gov (United States)

    Repici, Alessandro; Pagano, Nico; Hassan, Cesare; Carlino, Alessandra; Rando, Giacomo; Strangio, Giuseppe; Romeo, Fabio; Zullo, Angelo; Ferrara, Elisa; Vitetta, Eva; Ferreira, Daniel de Paula Pessoa; Danese, Silvio; Arosio, Massimo; Malesci, Alberto

    2011-01-01

    AIM: To assess the efficacy and safety of a balanced approach using midazolam in combination with propofol, administered by non-anesthesiologists, in a large series of diagnostic colonoscopies. METHODS: Consecutive patients undergoing diagnostic colonoscopy were sedated with a single dose of midazolam (0.05 mg/kg) and low-dose propofol (starter bolus of 0.5 mg/kg and repeated boluses of 10 to 20 mg). Induction time and deepest level of sedation, adverse and serious adverse events, as well as recovery times, were prospectively assessed. Cecal intubation and adenoma detection rates were also collected. RESULTS: Overall, 1593 eligible patients were included. The median dose of propofol administered was 70 mg (range: 40-120 mg), and the median dose of midazolam was 2.3 mg (range: 2-4 mg). Median induction time of sedation was 3 min (range: 1-4 min), and median recovery time was 23 min (range: 10-40 min). A moderate level of sedation was achieved in 1561 (98%) patients, whilst a deep sedation occurred in 32 (2%) cases. Transient oxygen desaturation requiring further oxygen supplementation occurred in 8 (0.46%; 95% CI: 0.2%-0.8%) patients. No serious adverse event was observed. Cecal intubation and adenoma detection rates were 93.5% and 23.4% (27.8% for male and 18.5% for female, subjects), respectively. CONCLUSION: A balanced sedation protocol provided a minimalization of the dose of propofol needed to target a moderate sedation for colonoscopy, resulting in a high safety profile for non-anesthesiologist propofol sedation. PMID:21987624

  1. Orally administered nicotine induces urothelial hyperplasia in rats and mice

    International Nuclear Information System (INIS)

    Dodmane, Puttappa R.; Arnold, Lora L.; Pennington, Karen L.; Cohen, Samuel M.

    2014-01-01

    Highlights: • Rats and mice orally administered with nicotine tartrate for total of 4 weeks. • No treatment-related death or whole body toxicity observed in any of the groups. • Urothelium showed simple hyperplasia in treated rats and mice. • No significant change in BrdU labeling index or SEM classification of urothelium. - Abstract: Tobacco smoking is a major risk factor for multiple human cancers including urinary bladder carcinoma. Tobacco smoke is a complex mixture containing chemicals that are known carcinogens in humans and/or animals. Aromatic amines a major class of DNA-reactive carcinogens in cigarette smoke, are not present at sufficiently high levels to fully explain the incidence of bladder cancer in cigarette smokers. Other agents in tobacco smoke could be excreted in urine and enhance the carcinogenic process by increasing urothelial cell proliferation. Nicotine is one such major component, as it has been shown to induce cell proliferation in multiple cell types in vitro. However, in vivo evidence specifically for the urothelium is lacking. We previously showed that cigarette smoke induces increased urothelial cell proliferation in mice. In the present study, urothelial proliferative and cytotoxic effects were examined after nicotine treatment in mice and rats. Nicotine hydrogen tartrate was administered in drinking water to rats (52 ppm nicotine) and mice (514 ppm nicotine) for 4 weeks and urothelial changes were evaluated. Histopathologically, 7/10 rats and 4/10 mice showed simple hyperplasia following nicotine treatment compared to none in the controls. Rats had an increased mean BrdU labeling index compared to controls, although it was not statistically significantly elevated in either species. Scanning electron microscopic visualization of the urothelium did not reveal significant cytotoxicity. These findings suggest that oral nicotine administration induced urothelial hyperplasia (increased cell proliferation), possibly due to a

  2. Safety of florfenicol administered in feed to tilapia (Oreochromis sp.)

    Science.gov (United States)

    Gaikowski, Mark P.; Wolf, Jeffrey C.; Schleis, Susan M.; Tuomari, Darrell; Endris, Richard G.

    2013-01-01

    The safety of Aquaflor® (50% w/w florfenicol [FFC]) incorporated in feed then administered to tilapia for 20 days (2x the recommended duration) at 0, 15, 45, or 75 mg/kg body weight/day (0, 1, 3, or 5x the recommended dose of 15 mg FFC/kg BW/d) was investigated. Mortality, behavioral change, feed consumption, body size, and gross and microscopic lesions were determined. Estimated delivered doses were >96.9% of target. Three unscheduled mortalities occurred but were considered incidental since FFC-related findings were not identified. Feed consumption was only affected during the last 10 dosing days when the 45 and 75 mg/kg groups consumed only 62.5% and 55.3% of the feed offered, respectively. There were significant, dose-dependent reductions in body size in the FFC-dose groups relative to the controls. Treatment-related histopathological findings included increased severity of lamellar epithelial hyperplasia, increased incidence of lamellar adhesions, decreased incidence of lamellar telangiectasis in the gills, increased glycogen-type and lipid-type hepatocellular vacuolation in the liver, decreased lymphocytes, increased blast cells, and increased individual cell necrosis in the anterior kidney, and tubular epithelial degeneration and mineralization in the posterior kidney. These changes are likely to be of minimal clinical relevance, given the lack of mortality or morbidity observed. This study has shown that FFC, when administered in feed to tilapia at the recommended dose (15 mg FFC/kg BW/day) for 10 days would be well tolerated.

  3. 40 CFR 131.8 - Requirements for Indian Tribes to administer a water quality standards program.

    Science.gov (United States)

    2010-07-01

    ..., taxation, and the exercise of the power of eminent domain; and (iii) Identify the source of the Tribal... determined based on OMB Circular A-105, may accept and approve a tribal application for purposes of...

  4. 76 FR 20699 - Fellowship Placement Pilot Program Requests for Expressions of Interest To Administer Pilot

    Science.gov (United States)

    2011-04-13

    ... secure additional funding support from other philanthropic organizations to fulfill the scope of work for...: 1. Take on high-level responsibilities and be immersed in the core operations of the host city; 2... private philanthropic organization, which HUD is authorized to accept under section 7(k) of the Department...

  5. 78 FR 730 - State Program Requirements; Approval of Application To Administer Partial National Pollutant...

    Science.gov (United States)

    2013-01-04

    ... biological pesticides or chemical pesticides that leave a residue, discharges from silviculture activities... feeding operations (``CAFO''), discharges from the application of biological pesticides or chemical pesticides that leave a residue, discharges from silviculture activities, and discharges of storm water from...

  6. A Comprehensive Theory of Cost-Effectiveness. Administering for Change Program. Technical Paper.

    Science.gov (United States)

    Temkin, Sanford

    This monograph provides a theoretical substantiation for benefit-cost analysis and cost-effectiveness analysis in school system planning. Nine examples of decision-making situations are presented. A simple case of a single objective to be attained with one plan being selected from a set of proposed plans with no resource constraints evolves into a…

  7. How to Finance and Administer Rural Development Programs. Resources for Rural Development Series: Handbook No. 3.

    Science.gov (United States)

    National Area Development Inst., Rockport, TX.

    One of a series, this handbook is designed to assist individuals involved in area development to gain knowledge and understanding of the public and private sources of funds for support of various area development activities. National, regional, and local private sector sources of development capital are examined to give an overview of business…

  8. 40 CFR 272.1351 - Montana State-Administered Program: Final Authorization.

    Science.gov (United States)

    2010-07-01

    ... Annotated (MCA) 2005, Title 25, “Civil Procedure”: Chapter 20, “Rules of Civil Procedure”, Rule 24(a). (iii) Montana Code Annotated (MCA) 2005, Title 27, “Civil Liability, Remedies, and Limitations”: Chapter 30...

  9. A Self-Administered Parent Training Program Based upon the Principles of Applied Behavior Analysis

    Science.gov (United States)

    Maguire, Heather M.

    2012-01-01

    Parents often respond to challenging behavior exhibited by their children in such a way that unintentionally strengthens it. Applied behavior analysis (ABA) is a research-based science that has been proven effective in remediating challenging behavior in children. Although many parents could benefit from using strategies from the field of ABA with…

  10. 77 FR 58830 - State Program Requirements; Application To Administer Partial National Pollutant Discharge...

    Science.gov (United States)

    2012-09-24

    ... Department of Agriculture, Food and Forestry (ODAFF) has submitted to the Environmental Protection Agency... management, log transport and log storage, and other activities, except those related to wood preservation... chemicals; manufacturing of food and kindred products, tobacco, paper, lumber, wood, textile mill and other...

  11. 40 CFR 272.651 - Idaho State-Administered Program: Final Authorization.

    Science.gov (United States)

    2010-07-01

    ..., “Hazardous Waste Management”, published in 2002 by the Michie Company, Law Publishers: sections 39-4404; 39... by the Michie Company, Law Publishers: sections 39-5804; 39-5809; 39-5810; 39-5813(2); 39-5814; 39..., Volume 2, Title 9, Chapter 3, “Public Writings”, published in 1990 by the Michie Company, Law Publishers...

  12. 22 CFR 196.2 - How is the Fellowship Program administered?

    Science.gov (United States)

    2010-04-01

    ... grant funds, fellows are required to complete prescribed coursework and maintain a satisfactory grade point average as determined by the Department of State. Fellows are also required to accept employment...

  13. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

  14. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2002-03-04

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

  15. State Energy Program Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Office of Building Technology, State and Community Programs

    1999-03-17

    The State Energy Program Operations Manual is a reference tool for the states and the program officials at the U.S. Department of Energy's Office of Building Technology, State and Community Programs and Regional Support Offices as well as State Energy Offices. The Manual contains information needed to apply for and administer the State Energy Program, including program history, application rules and requirements, and program administration and monitoring requirements.

  16. U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.

  17. Macroscopic and microscopic biodistribution of intravenously administered iron oxide nanoparticles

    Science.gov (United States)

    Misra, Adwiteeya; Petryk, Alicia A.; Strawbridge, Rendall R.; Hoopes, P. Jack

    2015-03-01

    Iron oxide nanoparticles (IONP) are being developed for use as a cancer treatment. They have demonstrated efficacy when used either as a monotherapy or in conjunction with conventional chemotherapy and radiation. The success of IONP as a therapeutic tool depends on the delivery of a safe and controlled cytotoxic thermal dose to tumor tissue following activation with an alternating magnetic field (AMF). Prior to clinical approval, knowledge of IONP toxicity, biodistribution and physiological clearance is essential. This preliminary time-course study determines the acute toxicity and biodistribution of 110 nm dextran-coated IONP (iron) in mice, 7 days post systemic, at doses of 0.4, 0.6, and 1.0 mg Fe/ g mouse bodyweight. Acute toxicity, manifested as changes in the behavior of mice, was only observed temporarily at 1.0 mg Fe/ g mouse bodyweight, the highest dose administered. Regardless of dose, mass spectrometry and histological analysis demonstrated over 3 mg Fe/g tissue in organs within the reticuloendotheilial system (i.e. liver, spleen, and lymph nodes). Other organs (brain, heart, lungs, and kidney) had less than 0.5 mg Fe/g tissue with iron predominantly confined to the organ vasculature.

  18. Developmental toxicity of orally administered pineapple leaf extract in rats.

    Science.gov (United States)

    Hu, Jun; Lin, Han; Shen, Jia; Lan, Jiaqi; Ma, Chao; Zhao, Yunan; Lei, Fan; Xing, Dongming; Du, Lijun

    2011-06-01

    The extract of pineapple leaves (EPL) has anti-diabetic and anti-dyslipidemic effects and can be developed into a promising natural medicine. This study was conducted to evaluate EPL's effects on developmental parameters in order to provide evidence of its safety before potential medical use. Five groups were included: a negative control that was given distilled water daily, a positive control that was dosed 7 mg/kg cyclophosphamide (CP) every two days, and three groups that were respectively dosed 2.0, 1.0, and 0.5 g/kg EPL daily. Female rats were dosed during the organogenesis period of gestation days (GD) 7-17 and terminated on GD 20. A series of parameters were examined. Data revealed that CP significantly reduced maternal body weight gains, caused maternal organ weight alterations, reduced female fertility, disturbed fetal growth and development, and caused marked teratogenic effects on fetal appearances, skeleton and internal organs. Distilled water and the three high doses of EPL did not cause any of the aforementioned effects. This study concluded that orally administered EPL is safe to rats during embryonic development. Copyright © 2011 Elsevier Ltd. All rights reserved.

  19. Toxicity and biodistribution of orally administered casein nanoparticles.

    Science.gov (United States)

    Gil, Ana Gloria; Irache, Juan Manuel; Peñuelas, Iván; González Navarro, Carlos Javier; López de Cerain, Adela

    2017-08-01

    In the last years, casein nanoparticles have been proposed as carriers for the oral delivery of biologically active compounds. However, till now, no information about their possible specific hazards in vivo was available. The aim of this work was to assess the safety of casein nanoparticles when administered orally to animals through a 90 days dose-repeated toxicity study (OECD guideline 408), that was performed in Wistar rats under GLP conditions. After 90 days, no evidences of significant alterations in animals treated daily with 50, 150 or 500 mg/kg bw of nanoparticles were found. This safety agrees well with the fact that nanoparticles were not absorbed and remained within the gut as observed by radiolabelling in the biodistribution study. After 28 days, there was a generalized hyperchloremia in males and females treated with the highest dose of 500 mg/kg bw, that was coupled with hypernatremia in the females. These effects were related to the presence of mannitol which was used as excipient in the formulation of casein nanoparticles. According to these results, the No Observed Adverse Effect Level (NOAEL) could be established in 150 mg/kg bw/day and the Lowest Observed Effect Level (LOEL) could be established in 500 mg/kg bw/day. Copyright © 2017. Published by Elsevier Ltd.

  20. Administering and Detecting Protein Marks on Arthropods for Dispersal Research.

    Science.gov (United States)

    Hagler, James R; Machtley, Scott A

    2016-01-28

    Monitoring arthropod movement is often required to better understand associated population dynamics, dispersal patterns, host plant preferences, and other ecological interactions. Arthropods are usually tracked in nature by tagging them with a unique mark and then re-collecting them over time and space to determine their dispersal capabilities. In addition to actual physical tags, such as colored dust or paint, various types of proteins have proven very effective for marking arthropods for ecological research. Proteins can be administered internally and/or externally. The proteins can then be detected on recaptured arthropods with a protein-specific enzyme-linked immunosorbent assay (ELISA). Here we describe protocols for externally and internally tagging arthropods with protein. Two simple experimental examples are demonstrated: (1) an internal protein mark introduced to an insect by providing a protein-enriched diet and (2) an external protein mark topically applied to an insect using a medical nebulizer. We then relate a step-by-step guide of the sandwich and indirect ELISA methods used to detect protein marks on the insects. In this demonstration, various aspects of the acquisition and detection of protein markers on arthropods for mark-release-recapture, mark-capture, and self-mark-capture types of research are discussed, along with the various ways that the immunomarking procedure has been adapted to suit a wide variety of research objectives.

  1. Barriers for administering primary health care services to battered ...

    African Journals Online (AJOL)

    Eman H. Alsabhan

    2011-09-15

    Sep 15, 2011 ... of specific programs to improve both the knowledge and skills of the medical staff to deal with vio- lence among women. Also ... that the lifetime prevalence of physical or sexual partner vio- lence, or both, varied ... and sexually transmitted infections); maternal health (e.g. in- creased risk for high blood ...

  2. Review of the integrity of a Self Administered Motivational Instrument.

    Science.gov (United States)

    Duffy, Tim; McCaig, Marie; McGrandles, Amanda; Rimmer, Russell; Martin, Colin R

    2014-04-01

    Motivational interviewing (MI) was developed by Miller and Rollnick as an evidence-based counselling approach for use in supporting people with alcohol problems. Over the years the principles and spirit of MI have been reviewed and fine-tuned and the approach has been embraced by practitioners worldwide and across fields. Since 2001 a number of instruments have been designed to evaluate the fidelity of MI practice. For the purposes of this study, one such instrument is used to assess a self-administered motivational instrument, known as the SAMI, which takes the interviewer role. The SAMI is evaluated against the MITI 3.1.1, which is designed to assess the extent to which MI interventions perform on five global dimensions. These are evocation, collaboration, autonomy/support, direction and empathy. The SAMI was assembled based on the principles and spirit of MI, problem solving and goal-setting. The targeted behaviour changes were student learning styles and approaches to study. The SAMI was distributed, completed and submitted electronically via the university virtual learning environment. Thirty three mature students of a university which delivered online nursing programme were invited to complete the SAMI. Of these, 25 submitted completed transcripts. Transcripts of a sample of six completed SAMIs were assessed by a group of teachers and researchers with experience in the use and evaluation of MI, using five-point Likert scales to assess the SAMI on the five dimensions. Overall, an average score exceeding 4.5 was attained across the five dimensions. Conventionally, such a score is recognised as competency in MI. However, on one dimension (empathy), the rating was three. This current research confirms that global principles have been observed in the online delivery of MI using the SAMI to probe approaches to study. Copyright © 2013 Elsevier Ltd. All rights reserved.

  3. Behavioral effects of urotensin-II centrally administered in mice.

    Science.gov (United States)

    Do-Rego, Jean-Claude; Chatenet, David; Orta, Marie-Hélène; Naudin, Bertrand; Le Cudennec, Camille; Leprince, Jérôme; Scalbert, Elizabeth; Vaudry, Hubert; Costentin, Jean

    2005-11-01

    Urotensin-II (U-II) receptors are widely distributed in the central nervous system. Intracerebroventricular (i.c.v.) injection of U-II causes hypertension and bradycardia and stimulates prolactin and thyrotropin secretion. However, the behavioral effects of centrally administered U-II have received little attention. In the present study, we tested the effects of i.c.v. injections of U-II on behavioral, metabolic, and endocrine responses in mice. Administration of graded doses of U-II (1-10,000 ng/mouse) provoked: (1) a dose-dependent reduction in the number of head dips in the hole-board test; (2) a dose-dependent reduction in the number of entries in the white chamber in the black-and-white compartment test, and in the number of entries in the central platform and open arms in the plus-maze test; and (3) a dose-dependent increase in the duration of immobility in the forced-swimming test and tail suspension test. Intracerebroventricular injection of U-II also caused an increase in: food intake at doses of 100 and 1,000 ng/mouse, water intake at doses of 100-10,000 ng/mouse, and horizontal locomotion activity at a dose of 10,000 ng/mouse. Whatever was the dose, the central administration of U-II had no effect on body temperature, nociception, apomorphine-induced penile erection and climbing behavior, and stress-induced plasma corticosterone level. Taken together, the present study demonstrates that the central injection of U-II at doses of 1-10,000 ng/mouse induces anxiogenic- and depressant-like effects in mouse. These data suggest that U-II may be involved in some aspects of psychiatric disorders.

  4. Overlay field application program, Pennsylvania US-119.

    Science.gov (United States)

    2010-11-01

    The Concrete Overly Filed Application program is administered by FHWA and the National Concrete Pavement Technology Center (CP Tech Center). The overall objective of this program is to increase the awareness and knowledge of concrete overlay applicat...

  5. An aqueous thermodynamic model for the Pb 2+-Na +-K +-Ca 2+-Mg 2+-H +-Cl --SO 42--H 2O system to high concentration: application to WIPP brines

    Science.gov (United States)

    Felmy, Andrew R.; Onishi, Lisa M.; Foster, Nancy S.; Rustad, James R.; Rai, Dhanpat; Mason, Marvin J.

    2000-11-01

    The development of an aqueous thermodynamic model for the Pb 2+-Na +-K +-Ca 2+-Mg 2+-Cl --SO 42--H 2O system is presented, which is valid to high ionic strengths at 25°C. The model is based on the equations of Pitzer and has been parameterized from existing solubility, osmotic, electromotive force (emf), and spectroscopic data. To accurately represent the aqueous thermodynamics of Pb 2+ in concentrated chloride containing solutions required the inclusion of four Pb chloride species (i.e., PbCl +, PbCl 2(aq), PbCl 3-, and PbCl 42-) along with the necessary Pitzer ion interaction parameters for these species with the major electrolyte ions. The reliability of the final equilibrium model is tested against experimental solubility data on PbCl 2(c) and PbSO 4(c) in high ionic strength Waste Isolation Pilot Plant (WIPP) brines obtained as part of this study. On an overall basis the model accurately predicted the aqueous speciation, based on comparisons with our UV-Vis spectroscopy measurements, as well as the observed solubility. The model also proved satisfactory in predicting the observed solid phase assemblages, with the possible exception of those found in solutions high in KCl.

  6. Evaluation of Summer Bridge Programs

    Science.gov (United States)

    Garcia, Lisa D.; Paz, Chiara C.

    2009-01-01

    Many colleges and universities in the United States offer summer programs for their incoming students. While programs are structured and administered in a variety of ways and target various student populations, the most common type of summer bridge program aims to serve historically underrepresented students and students of low socioeconomic…

  7. Exam 70-411 administering Windows Server 2012

    CERN Document Server

    Course, Microsoft Official Academic

    2014-01-01

    Microsoft Windows Server is a multi-purpose server designed to increase reliability and flexibility of  a network infrastructure. Windows Server is the paramount tool used by enterprises in their datacenter and desktop strategy. The most recent versions of Windows Server also provide both server and client virtualization. Its ubiquity in the enterprise results in the need for networking professionals who know how to plan, design, implement, operate, and troubleshoot networks relying on Windows Server. Microsoft Learning is preparing the next round of its Windows Server Certification program

  8. Authority of Pharmacists to Administer Human Papillomavirus Vaccine: Alignment of State Laws With Age-Level Recommendations.

    Science.gov (United States)

    Dingman, Deirdre A; Schmit, Cason D

    One strategy to increase the uptake of human papillomavirus (HPV) vaccine among adolescents is through the use of pharmacists. Our objectives were to (1) use a publicly available database to describe the statutory and regulatory authority of pharmacists to administer the HPV vaccine in the United States and (2) discuss how the current status of laws may influence achievement of the Healthy People 2020 goal of 80% HPV vaccination rate for teenagers aged 13-15. Using information from the Centers for Disease Control and Prevention's (CDC's) Public Health Law Program database, we identified state laws in effect as of January 1, 2016, giving pharmacists authority to administer vaccines. We used a standardized analysis algorithm to determine whether states' laws (1) authorized pharmacists to administer HPV vaccine, (2) required third-party authorization for pharmacist administration, and (3) restricted HPV vaccine administration by pharmacists to certain patient age groups. Of 50 states and the District of Columbia, 40 had laws expressly granting pharmacists authority to administer HPV vaccine to patients, but only 22 had laws that authorized pharmacists to vaccinate preadolescents aged 11 or 12 (ie, the CDC-recommended age group). Pharmacists were granted prescriptive authority by 5 states, and they were given authority pursuant to general (non-patient-specific) third-party authorization (eg, a licensed health care provider) by 32 states or patient-specific third-party authorization by 3 states. Most states permitted pharmacists to administer HPV vaccines only to boys and girls older than 11 or 12, which may hinder achievement of the Healthy People 2020 goal for HPV vaccination. Efforts should be made to strengthen the role of pharmacists in addressing this public health issue.

  9. Environmental baseline study of the Los Medanos Waste Isolation Pilot Plant (WIPP) project area of New Mexico: a progress report. An addendum

    International Nuclear Information System (INIS)

    Wolfe, H.G.

    1977-09-01

    Sandia Laboratories, Albuquerque, New Mexico, has been conducting exploratory drilling operations for a Waste Isolation Pilot Program Eddy and Lea counties in southeast New Mexico for almost two years. Prior to the establishment of such a program, an environmental study has been carried out as a baseline for evaluation of the impact of future activities in the Los Medanos area. Data are presented on the geology; topography; climate; vegetation; and population density, diet, and seasonal movements of mammals, lizards, snakes, birds, insects, and ground-dwelling arthropods of the study area

  10. RH Packaging Program Guidance

    International Nuclear Information System (INIS)

    2008-01-01

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the 'RH-TRU 72-B cask') and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' It further states: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M and O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8, 'Deliberate Misconduct.' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, 'Packaging and Transportation of Radioactive Material,' certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, 'Reporting of Defects and Noncompliance,' regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous

  11. RH Packaging Program Guidance

    International Nuclear Information System (INIS)

    2006-01-01

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' It further states: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M and O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) 1.8, 'Deliberate Misconduct.' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, 'Packaging and Transportation of Radioactive Material,' certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, 'Reporting of Defects and Noncompliance,' regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these

  12. RH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2008-01-12

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a

  13. RH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2006-11-07

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to

  14. Are self-administered or minimal therapist contact psychotherapies an effective treatment for irritable bowel syndrome (IBS): a systematic review.

    Science.gov (United States)

    Ahl, Alyce; Mikocka-Walus, Antonina; Gordon, Andrea; Andrews, Jane M

    2013-08-01

    Irritable bowel syndrome is a highly prevalent gastrointestinal condition that is known to be associated with maladaptive psychological coping and is extremely costly to the health-care system. Psychotherapy has been found to improve both physical and psychological symptoms in IBS. However, it is unknown whether 'no therapist' or 'minimal therapist' contact self-help psychotherapy programs are effective treatments for IBS. Thus, this paper aims to determine whether 'no therapist' or 'minimal therapist' contact self-help psychotherapy programs are effective treatments for IBS. A search of PubMed, SCOPUS, Cochrane Library, and Ebscohost research databases was conducted without language or date restriction in July 2012. Nine relevant publications were included in the final review, all of which were randomized controlled trials (RCTs) and included an intervention that was primarily self-administered. It was found that 'no therapist' contact self-help programs are likely to have poor results due to lack of engagement in the program, whilst 'minimal therapist' contact programs appear to produce positive results in terms of symptom relief. Trends towards 'minimal therapist' contact self-help programs having a positive impact on quality of life (QOL) and psychological outcomes were evident. 'Minimal therapist' contact psychotherapy programs have the potential to reduce healthcare seeking behaviour and potentially reduce healthcare costs. However, further studies need to be conducted to confirm this effect as there is poor standardisation in the measurements of the available studies. Copyright © 2013 Elsevier Inc. All rights reserved.

  15. 34 CFR 460.2 - What programs are authorized by the Adult Education Act?

    Science.gov (United States)

    2010-07-01

    ...-administered Workplace Literacy Program (34 CFR part 433). (c) State-administered English Literacy Program (34 CFR part 434). (d) State Literacy Resource Centers Program (34 CFR part 464). (e) National Workplace... Program (34 CFR part 489). (l) Life Skills for State and Local Prisoners Program (34 CFR part 490...

  16. Integrated modeling and experimental programs to predict brine and gas flow at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Howarth, S.M.; Vaughn, P.; Webb, S.W.; Larson, K.W.

    1995-01-01

    Evaluation of the performance of the WIPP repository involves modeling of brine and gas flow in the host rocks of the Salado Formation, which consist of halite and anhydrite interbeds. Numerous physical, chemical, and structural processes, must be understood to perform this modeling. Gas generation within the repository is strongly coupled to the amount of brine inflow to the repository because brine aids in the corrosion of metals and associated generation of hydrogen gas. Increasing gas pressure in the repository decreases the rate of brine inflow. Ultimately, the gas pressure may exceed the brine pressure and gas may flow out of the repository. Relative-permeability curves and a correlation between threshold pressure and permeability taken from studies reported in the literature were used in PA models prior to being experimentally verified as appropriate for WIPP. In addition, interbed permeabilities were treated as constant and independent of effective stress in early models. Subsequently, the process of interbed fracturing (or fracture dilation) was recognized to limit gas pressures in the repository to values below lithostatic, and assumed (and unverified) relationships between porosity, permeability, and pore pressure were employed. Parameter-sensitivity studies performed using the simplified models identified important parameters for which site-specific data were needed. Unrealistic modeling results, such as room pressures substantially above lithostatic, showed the need to include additional processes in the models. Field and laboratory experimental programs have been initiated in conjunction with continued model development to provide information on important processes and parameters

  17. Open-label, multicenter study of self-administered icatibant for attacks of hereditary angioedema

    DEFF Research Database (Denmark)

    Aberer, W; Maurer, M; Reshef, A

    2014-01-01

    Historically, treatment for hereditary angioedema (HAE) attacks has been administered by healthcare professionals (HCPs). Patient self-administration could reduce delays between symptom onset and treatment, and attack burden. The primary objective was to assess the safety of self-administered ica......Historically, treatment for hereditary angioedema (HAE) attacks has been administered by healthcare professionals (HCPs). Patient self-administration could reduce delays between symptom onset and treatment, and attack burden. The primary objective was to assess the safety of self...

  18. 49 CFR 384.201 - Testing program.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 5 2010-10-01 2010-10-01 false Testing program. 384.201 Section 384.201... COMMERCIAL DRIVER'S LICENSE PROGRAM Minimum Standards for Substantial Compliance by States § 384.201 Testing program. The State shall adopt and administer a program for testing and ensuring the fitness of persons to...

  19. Phlebotomine mortality effect of systemic insecticides administered to dogs.

    Science.gov (United States)

    Gomez, Sonia Ares; Curdi, Javier Lucientes; Hernandez, Juan Antonio Castillo; Peris, Paz Peris; Gil, Adriana Esteban; Velasquez, Ronald Vladimir Oropeza; Hernandez, Paula Ortega; Picado, Albert

    2018-04-05

    Zoonotic visceral leishmaniasis (ZVL) caused by Leishmania (Leishmania) infantum is an important disease in humans and dogs. Different mammal species are reservoirs but dogs are considered to be the main one. Phlebotomine sand flies are the proven vector. Four systemic insecticides approved for their use in dogs were previously selected based on their potential to be used in endemic countries as part of the control programs of ZVL. These insecticides are proved to be safe and effective against the on-label insects and parasites, but there is no information about their activity against phlebotomine sand flies. The phlebotomine mortality of four systemic insecticides in dogs was evaluated using two randomized clinical trials. For the first trial, thirty dogs were randomly allocated into five groups: four treatments and one control, of equal size. The treatments evaluated were: Guardian®SR, Elanco (moxidectin); Comfortis®, Elanco (spinosad); Bravecto®, Merck Animal Health (fluralaner); and NexGard®, Merial (afoxolaner). Blood from dogs was taken at days 2, 4, 21 and 31 post-treatment (trial 1). The compound that showed the highest efficacy was selected for a second trial (trial 2) with 20 dogs sampled at days 0, 2, 4, 7, 14, 18, 32, 39, 51 and 84 post-treatment. Membrane feeding bioassays with Phlebotomus papatasi were used to evaluate the phlebotomine mortality efficacy of the different treatments. Phlebotomine mortality was observed every 24 h following the membrane feeding during 5 days. A mixed model for a negative binomial logistic regression, and a Cox proportional hazard mixed model were used to estimate phlebotomine mortality due to different treatments. Fluralaner was the only compound that showed significant phlebotomine mortality. Fluralaner maintained the phlebotomine mortality between 60-80% for 30 days after treatment. In trial 1 we found that fluralaner increased the risk of death by 1.9 times (95% CI: 1.02-3.6) and 1.7 times (95% CI: 1.09-2.6) at

  20. Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program

    International Nuclear Information System (INIS)

    2001-01-01

    The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWB's will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components

  1. Comparison of the analgesic properties of transdermally administered fentanyl and intramuscularly administered buprenorphine during and following experimental orthopedic surgery in sheep.

    Science.gov (United States)

    Ahern, Benjamin J; Soma, Lawrance R; Boston, Raymond C; Schaer, Thomas P

    2009-03-01

    To evaluate the analgesic properties of transdermally administered fentanyl and IM administered buprenorphine in sheep undergoing unilateral tibial osteotomy. 20 mature sheep. Fentanyl patches (n = 15 sheep) or placebo patches (5 sheep) were applied 12 hours before sheep underwent general anesthesia and a unilateral tibial osteotomy. Buprenorphine was administered to the placebo group every 6 hours commencing at time of induction. Signs of pain were assessed every 12 hours after surgery by 2 independent observers unaware of treatment groups. There were no differences in preoperative and intraoperative physiologic data between the 2 groups. Sheep treated with fentanyl required less preoperative administration of diazepam for sedation and had significantly lower postoperative pain scores, compared with those treated with buprenorphine. No complications associated with the antebrachium at the site of patch application were detected. Under the conditions of this study, transdermally administered fentanyl was a superior option to IM administered buprenorphine for alleviation of postoperative orthopedic pain in sheep. This information can be used to assist clinicians in the development of a rational analgesic regimen for research and clinical patients.

  2. State Energy Program in Hawaii

    Energy Technology Data Exchange (ETDEWEB)

    2003-05-01

    The Hawaii Strategic Industry Division administers DOE's State Energy Program in Hawaii. The division's current accomplishments include establishing a Model Energy Code for the state, instituting a successful solar program, and making energy performance contracts available for government facilities.

  3. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2009-06-01

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  4. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2007-12-13

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  5. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2008-09-11

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the pplication." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  6. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    2006-01-01

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' They further state: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant| (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations(CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations

  7. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    2009-01-01

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' They further state: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations

  8. Nurse administered propofol sedation for pulmonary endoscopies requires a specific protocol

    DEFF Research Database (Denmark)

    Jensen, Jeppe Thue; Banning, Anne-Marie; Clementsen, Paul

    2012-01-01

    This study provides an evaluation and risk analysis of propofol sedation for endoscopic pulmonary procedures according to our unit's "gastroenterologic nurse-administered propofol sedation (NAPS) guideline".......This study provides an evaluation and risk analysis of propofol sedation for endoscopic pulmonary procedures according to our unit's "gastroenterologic nurse-administered propofol sedation (NAPS) guideline"....

  9. 30 CFR 250.1508 - What must I do when MMS administers written or oral tests?

    Science.gov (United States)

    2010-07-01

    ... Production Safety Training § 250.1508 What must I do when MMS administers written or oral tests? MMS or its... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must I do when MMS administers written or... written or oral tests; and (b) Identify personnel by current position, years of experience in present...

  10. 42 CFR 2a.5 - Contents of application; research projects in which drugs will be administered.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Contents of application; research projects in which... application; research projects in which drugs will be administered. (a) In addition to the information... for an authorization of confidentiality for a research project which involves the administering of a...

  11. Intravenously administered lidocaine in therapeutic doses increases the intraspinal release of acetylcholine in rats

    DEFF Research Database (Denmark)

    Abelson, Klas S P; Höglund, A Urban

    2002-01-01

    The local anesthetic lidocaine suppresses different pain conditions when administered systemically. Part of the antinociceptive effect appears to be mediated via receptor mechanisms. We have previously shown that muscarinic and nicotinic agonists that produce antinociception increase...... by systemically administered lidocaine is mediated through an action on muscarinic and nicotinic receptors....

  12. 39 CFR 222.2 - Authority to administer oaths or function as notaries public.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Authority to administer oaths or function as notaries public. 222.2 Section 222.2 Postal Service UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION DELEGATIONS OF AUTHORITY § 222.2 Authority to administer oaths or function as notaries public. (a...

  13. Microbial characterization for the Source-Term Waste Test Program (STTP) at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Leonard, P.A.; Strietelmeier, B.A.; Pansoy-Hjelvik, M.E.; Villarreal, R.

    1999-04-01

    The effects of microbial activity on the performance of the proposed underground nuclear waste repository, the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico are being studied at Los Alamos National Laboratory (LANL) as part of an ex situ large-scale experiment. Actual actinide-containing waste is being used to predict the effect of potential brine inundation in the repository in the distant future. The study conditions are meant to simulate what might exist should the underground repository be flooded hundreds of years after closure as a result of inadvertent drilling into brine pockets below the repository. The Department of Energy (DOE) selected LANL to conduct the Actinide Source-Term Waste Test Program (STTP) to confirm the predictive capability of computer models being developed at Sandia National Laboratory.

  14. Microbial characterization for the Source-Term Waste Test Program (STTP) at Los Alamos

    International Nuclear Information System (INIS)

    Leonard, P.A.; Strietelmeier, B.A.; Pansoy-Hjelvik, M.E.; Villarreal, R.

    1999-01-01

    The effects of microbial activity on the performance of the proposed underground nuclear waste repository, the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico are being studied at Los Alamos National Laboratory (LANL) as part of an ex situ large-scale experiment. Actual actinide-containing waste is being used to predict the effect of potential brine inundation in the repository in the distant future. The study conditions are meant to simulate what might exist should the underground repository be flooded hundreds of years after closure as a result of inadvertent drilling into brine pockets below the repository. The Department of Energy (DOE) selected LANL to conduct the Actinide Source-Term Waste Test Program (STTP) to confirm the predictive capability of computer models being developed at Sandia National Laboratory

  15. Distribution of rare earths in liver of mice administered with chloride compounds of 12 rare earths

    International Nuclear Information System (INIS)

    Shinohara, A.; Chiba, M.; Inaba, Y.

    1998-01-01

    Full text: Rare earths are used in high technology field, however, the information on their biological effects are not sufficient. The behaviour of rare earths in biology is of interest in connection with their toxicity. In the present study, the distribution of rare earths in liver of mice administered with these elements was investigated. The effects on Ca and other biological essential elements were also determined. Male mice (5 weeks old) were injected with one of 12 kinds of rare earths (chlorides of Y, La, Ce, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er and Yb) at the dose of 25 mg/KXg body weight. After 20 hours of administration, mice were sacrificed, then liver and other organs were taken out. Liver was homogenized and separated by centrifugation. The concentrations of rare earths administered were measured by microwave-induced plasma-mass spectrometry (MIP-MS) after acid digestion. The concentrations of administered elements in whole liver were about 100μg/g (wet weight), where the difference between elements was few. Distribution amounts of elements administered in four fractions were following order; 700μg precipitate > mitocondrial fraction > microsomal fraction > cytosol. The relative contents in these fractions, however, was different depending on the element administered. Calcium concentrations in liver of administered mice were higher than those of control mice. Increase of Ca concentrations were observed in all four fractions and the increase ratio was also dependent on the elements administered

  16. Depression screening using the Patient Health Questionnaire-9 administered on a touch screen computer.

    Science.gov (United States)

    Fann, Jesse R; Berry, Donna L; Wolpin, Seth; Austin-Seymour, Mary; Bush, Nigel; Halpenny, Barbara; Lober, William B; McCorkle, Ruth

    2009-01-01

    To (1) evaluate the feasibility of touch screen depression screening in cancer patients using the Patient Health Questionnaire-9 (PHQ-9), (2) evaluate the construct validity of the PHQ-9 using the touch screen modality, and (3) examine the prevalence and severity of depression using this screening modality. The PHQ-9 was placed in a web-based survey within a study of the clinical impact of computerized symptom and quality of life screening. Patients in medical oncology, radiation oncology, and hematopoietic stem cell transplantation (HSCT) clinics used the program on a touch screen computer in waiting rooms prior to therapy (T1) and during therapy (T2). Responses of depressed mood or anhedonia (PHQ-2 cardinal depression symptoms) triggered additional items. PHQ-9 scores were provided to the oncology team in real time. Among 342 patients enrolled, 33 (9.6%) at T1 and 69 (20.2%) at T2 triggered the full PHQ-9 by endorsing at least one cardinal symptom. Feasibility was high, with at least 97% completing the PHQ-2 and at least 96% completing the PHQ-9 when triggered and a mean completion time of about 2 min. The PHQ-9 had good construct validity. Medical oncology patients had the highest percent of positive screens (12.9%) at T1, while HSCT patients had the highest percent (30.5%) at T2. Using this method, 21 (6.1%) at T1 and 54 (15.8%) at T2 of the total sample had moderate to severe depression. The PHQ-9 administered on a touch screen computer is feasible and provides valid depression data in a diverse cancer population. (c) 2008 John Wiley & Sons, Ltd.

  17. Can the BASNEF Model Help to Develop Self-Administered Healthy Behavior in Iranian Youth?

    Science.gov (United States)

    Shahnazi, Hossein; Bee Koon, Poh; Abd Talib, Ruzita; Lubis, Syarif Husin; Ganjali Dashti, Marjan; Khatooni, Elham; Bahreini Esfahani, Nimah

    2016-01-01

    Background: The stage of youth is critical for human development in several ways. On the one hand, it can lead people towards the adoption of a healthy lifestyle during adulthood based on these earlier practices. On the other hand, it can comprise the development of healthy living practices later on in live, an outcome which is often caused by the youth adopting a risky lifestyle early on. Objectives: The primary objective of this study was to determine the effectiveness of implementing an educational intervention program based on the BASNEF Model (a simplified approach to understanding behavior), designed to cultivate self-administered lifestyle control skills in youths. Materials and Methods: This was a quasi-experimental intervention study, implemented during 2010 - 2011. A total of 288 randomly selected high-school students between the ages of 15 and 17 participated in this study. These students were later divided into experimental and control groups. Subjects completed a BASNEF questionnaire at the baseline (pre-test), one month later (post-test) and three months after the educational intervention (follow-up). Four educational sessions were held, each of a 120 - 150 minute duration. After the data had been collected, the ANOVA test was used to compare trends in changes. The Pearson correlation coefficient was then used to analyze the correlation between components of the BASNEF model. Finally, regression analysis was used to determine the predictive power of the study. Results: Results from the intervention study reveal that the beliefs and attitudes about nutrition of the intervention group, calculated in terms of scores, improved significantly for both male and female subjects (P eating habits and more active lifestyles at an early age in order to foster long-term health and well-being. PMID:27231582

  18. Evaluation of the first pharmacist-administered vaccinations in Western Australia: a mixed-methods study.

    Science.gov (United States)

    Hattingh, H Laetitia; Sim, T Fei; Parsons, R; Czarniak, P; Vickery, A; Ayadurai, S

    2016-09-20

    This study evaluated the uptake of Western Australian (WA) pharmacist vaccination services, the profiles of consumers being vaccinated and the facilitators and challenges experienced by pharmacy staff in the preparation, implementation and delivery of services. Mixed-methods methodology with both quantitative and qualitative data through surveys, pharmacy computer records and immuniser pharmacist interviews. Community pharmacies in WA that provided pharmacist vaccination services between March and October 2015. Immuniser pharmacists from 86 pharmacies completed baseline surveys and 78 completed exit surveys; computer records from 57 pharmacies; 25 immuniser pharmacists were interviewed. Pharmacy and immuniser pharmacist profiles; pharmacist vaccination services provided and consumer profiles who accessed services. 15 621 influenza vaccinations were administered by immuniser pharmacists at 76 WA community pharmacies between March and October 2015. There were no major adverse events, and vaccinations under the National Immunisation Program but chose to have it at a pharmacy. A high percentage of vaccinations was delivered in rural and regional areas indicating that provision of pharmacist vaccination services facilitated access for rural and remote consumers. Immuniser pharmacists reported feeling confident in providing vaccination services and were of the opinion that services should be expanded to other vaccinations. Pharmacists also reported significant professional satisfaction in providing the service. All participating pharmacies intended to continue providing influenza vaccinations in 2016. This initial evaluation of WA pharmacist vaccination services showed that vaccine delivery was safe. Convenience and accessibility were important aspects in usage of services. There is scope to expand pharmacist vaccination services to other vaccines and younger children; however, government funding to pharmacists needs to be considered. Published by the BMJ Publishing

  19. Learn About the Water Pollution Control (Section 106) Grant Program

    Science.gov (United States)

    Under CWA Section 106, EPA is authorized to provide grants to states, eligible interstate agencies, and eligible tribes to establish and administer programs, including enforcement programs,for the prevention, reduction, and elimination of water pollution.

  20. Self-Administered Computer Therapy for Apraxia of Speech: Two-Period Randomized Control Trial With Crossover.

    Science.gov (United States)

    Varley, Rosemary; Cowell, Patricia E; Dyson, Lucy; Inglis, Lesley; Roper, Abigail; Whiteside, Sandra P

    2016-03-01

    There is currently little evidence on effective interventions for poststroke apraxia of speech. We report outcomes of a trial of self-administered computer therapy for apraxia of speech. Effects of speech intervention on naming and repetition of treated and untreated words were compared with those of a visuospatial sham program. The study used a parallel-group, 2-period, crossover design, with participants receiving 2 interventions. Fifty participants with chronic and stable apraxia of speech were randomly allocated to 1 of 2 order conditions: speech-first condition versus sham-first condition. Period 1 design was equivalent to a randomized controlled trial. We report results for this period and profile the effect of the period 2 crossover. Period 1 results revealed significant improvement in naming and repetition only in the speech-first group. The sham-first group displayed improvement in speech production after speech intervention in period 2. Significant improvement of treated words was found in both naming and repetition, with little generalization to structurally similar and dissimilar untreated words. Speech gains were largely maintained after withdrawal of intervention. There was a significant relationship between treatment dose and response. However, average self-administered dose was modest for both groups. Future software design would benefit from incorporation of social and gaming components to boost motivation. Single-word production can be improved in chronic apraxia of speech with behavioral intervention. Self-administered computerized therapy is a promising method for delivering high-intensity speech/language rehabilitation. URL: http://orcid.org/0000-0002-1278-0601. Unique identifier: ISRCTN88245643. © 2016 American Heart Association, Inc.