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  Partner: UNT Libraries Government Documents Department
 Decade: 1990-1999
101-SY Dome pressure issues surrounding mitigation pump decontamination during removal
This document addresses issues related to use of the spraywands and ring used to decontaminate the mitigation pump installed in 101-SY. It has been determined that use of the wands will influence tank dome pressures as a function of ventilation system configuration, spray drop size, rinse water temperature, and rate at which spraywand flows are established. digital.library.unt.edu/ark:/67531/metadc685082/
105-DR Large Sodium Fire Facility closure activities evaluation report
This report evaluates the closure activities at the 105-DR Large Sodium Fire Facility. The closure activities discussed include: the closure activities for the structures, equipment, soil, and gravel scrubber; decontamination methods; materials made available for recycling or reuse; and waste management. The evaluation compares these activities to the regulatory requirements and closure plan requirements. The report concludes that the areas identified in the closure plan can be clean closed. digital.library.unt.edu/ark:/67531/metadc688077/
105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan
This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act. digital.library.unt.edu/ark:/67531/metadc793733/
105-DR Large sodium fire facility soil sampling data evaluation report
This report evaluates the soil sampling activities, soil sample analysis, and soil sample data associated with the closure activities at the 105-DR Large Sodium Fire Facility. The evaluation compares these activities to the regulatory requirements for meeting clean closure. The report concludes that there is no soil contamination from the waste treatment activities. digital.library.unt.edu/ark:/67531/metadc674679/
105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel
Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations. digital.library.unt.edu/ark:/67531/metadc737276/
105 K East and 105 K West fuel transfer bay crane use strategy for spent nuclear fuel path-forward
The purpose of this document is to outline the K Basins 30 ton crane qualification strategy for use in the Spent Nuclear Fuel Project fuel relocation campaign. digital.library.unt.edu/ark:/67531/metadc687833/
105 K east ion exchange and cartridge filter restart computer software configuration management plan
Configuration Management Plan for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc687530/
105 K east ion exchange and cartridge filter restart computer software design description
Computer Software Design Description for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc678232/
105 K East ion exchange and cartridge filter restart computer software documentation
Computer Software Documentation for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc686352/
105 K east ion exchange and cartridge filter restart computer software requirements specification
Computer Software Requirements Specification for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc685564/
105 K east ion exchange and cartridge filter restart computer software user documentation
Computer software user documentation for the cartridge filter restart project. digital.library.unt.edu/ark:/67531/metadc674835/
105 K east ion exchange and cartridge filter restart instrumentation acceptance test report
Acceptance Test Report following the completion of ATP-012 for the 105KE CP-A and CP-A Computer and PLC Panels. The test was conducted from 11/13/95 to 12/11/95. Three test discrepancies were generated during the ATP and all were dispositioned and closed. All sections were completed except Section 5.9 which was deleted per ECN 190556. digital.library.unt.edu/ark:/67531/metadc687199/
105 K East isolation barrier acceptance analysis report
The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit. digital.library.unt.edu/ark:/67531/metadc791918/
105-K East sandfilter backwash line sample analysis report: first campaign
This document summarizes the sandfilter backwash for 105-K East. digital.library.unt.edu/ark:/67531/metadc687323/
105-K east sandfilter backwash line sample analysis report. Second campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin Operations must not exceed a certain total inventory in order to be within a criticality specification. The second campaign of this project consisted of three samples, numbered by the customer 208KEB, 209KEB, and 210KEB. digital.library.unt.edu/ark:/67531/metadc679910/
105-K east sandfilter backwash line sample analysis report: Third campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin operations must not exceed a certain total inventory in order to be within a criticality specification. The third campaign of this project consisted of three samples, numbered by the customer 245KEB, 246KEB, and 247KEB. A revised letter of instruction controlled their processing. digital.library.unt.edu/ark:/67531/metadc684251/
105 K-West isolation barrier leak recovery plan
Leak testing is being performed in 105 KW to verify the performance of the isolation barriers which have been recently installed. When an 11 inch differential head is established between the main basin and the discharge chute, a leak-rate of approximately 30 - 35 gpm is observed. The leak-rate would be achieved by a 1.65`` - 2`` diameter hole (or equivalent). Analyses suggest that the flow is turbulent/laminar transitional (dominantly turbulent), which would be indicative of a single point leak, typical of a pipe or large opening. However, local vortex rotation is observed in the entry to the West transfer chute while no observable motion was seen in the East transfer chute: this may be an indication of seal leakage in the East isolation barrier. The potential for leakage had been considered during the design and field work planning stages. Review of potential leak detection technologies had been made; at the planning stage it was determined that location specific leak detection could be established relatively quickly, applying existing K Basins technology (dye or ultrasonics). The decision was made not to pre-stage leak detection since the equipment development is highly dependent on the nature and location of the leak, and the characteristics of the leak rate provides data which guides leak characterization technology. The expense could be deferred and potentially avoided without risk to critical path activity. Consistent with the above, a systematic recovery plan has been developed utilizing phased activities to provide for management discipline combined with timely diagnosis and correction. Because this activity is not critical path at this time, activities will be coordinated with other plant activity to optimize overall plant work. Particular care will be exercised in assuring that information gained from this recovery can be utilized in the more critical work in 105 KE. digital.library.unt.edu/ark:/67531/metadc678918/
105-KE Basin isolation barrier leak rate test analytical development. Revision 1
This document provides an analytical development in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used to determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under postulated accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage: viscous laminar and turbulent flow. An analytical development is presented for each flow regime. The basic geometry and nomenclature of the postulated leak paths are denoted. digital.library.unt.edu/ark:/67531/metadc793772/
105-KE Isolation Barrier Leak Rate Acceptance Test Report
This Acceptance Test Report (ATR) contains the completed and signed Acceptance Procedure (ATP) for the 105-KE Isolations Barrier Leak Rate Test. The Test Engineer`s log, the completed sections of the ATP in the Appendix for Repeat Testing (Appendix K), the approved WHC J-7s (Appendix H), the data logger files (Appendices T and U), and the post test calibration checks (Appendix V) are included. digital.library.unt.edu/ark:/67531/metadc793988/
105-KW Sandfilter Backwash Pit sludge volume calculation
The volume of sludge contained in the 100-KW Sandfilter Backwash Pit (SFBWP) was calculated from depth measurements of the sludge, pit dimension measurements and analysis of video tape recordings taken by an underwater camera. The term sludge as used in this report is any combination of sand, sediment, or corrosion products visible in the SFBWP area. This work was performed to determine baseline volume for use in determination of quantities of uranium and plutonium deposited in the pit from sandfilter backwashes. The SFBWP has three areas where sludge is deposited: (1) the main pit floor, (2) the transfer channel floor, and (3) the surfaces and structures in the SFBWP. The depths of sludge and the uniformity of deposition varies significantly between these three areas. As a result, each of the areas was evaluated separately. The total volume of sludge determined was 3.75 M{sup 3} (132.2 ft{sup 3}). digital.library.unt.edu/ark:/67531/metadc667682/
105-N basin sediment disposition phase-two sampling and analysis plan
The sampling and analysis plan for Phase 2 of the 105-N Basin sediment disposition task defines the sampling and analytical activities that will be performed to support characterization of the sediment and selection of an appropriate sediment disposal option. digital.library.unt.edu/ark:/67531/metadc623439/
The 110 GHz ECH installation on DII-D: Status and initial experimental results
Two 110 GHz gyrotrons with nominal output power of 1 MW each have been installed on the DIII-D tokamak. The gyrotrons, produced by Gycom and Communications and Power Industries, are connected to the tokamak by windowless evacuated transmission lines using circular corrugated waveguide carrying the HE{sub 11} mode. Initial experiments with the Gycom gyrotron showed good central heating efficiency at the second harmonic resonance with record central electron temperatures for DIII-D in excess of 10 keV achieved. The beam spot in the DIII-D vacuum vessel was well focused, with a diameter of approximately 8 cm, and it could be steered poloidally by a remotely adjustable mirror. The injection was at 19 deg off-perpendicular for current drive and the beams could be modulated for studies of energy transport and power deposition. The system will be described and the initial physics results will be presented. A third gyrotron, also at 110 GHz, will be installed later this year. Progress with this CPI tube will be discussed and future plans for the ECH installation and physics experiments using it will be presented. digital.library.unt.edu/ark:/67531/metadc679160/
The 110 GHz Gyrotron System on DIII-D: Gyrotron Tests and Physics Results
The DIII-D tokamak has installed a system with three gyrotrons at the 1 MW level operating at 110 GHz. Physics experiments on electron cyclotron current drive, heating, and transport have been performed. Good efficiency has been achieved both for on-axis and off-axis current drive with relevance for control of the current density profile leading to advanced regimes of tokamak operation, although there is a difference between off-axis ECCD efficiency inside and outside the magnetic axis. Heating efficiency is excellent and electron temperatures up to 10 keV have been achieved. The gyrotron system is versatile, with poloidal scan and control of the polarization of the injected rf beam. Phase correcting mirrors form a Gaussian beam and focus it into the waveguide. Both perpendicular and oblique launch into the tokamak have been used. Three different gyrotron designs are installed and therefore unique problems specific to each have been encountered, including parasitic oscillations, mode hops during modulation and polarization control problems. Two of the gyrotrons suffered damage during operations, one due to filament failure and one due to a vacuum leak. The repairs and subsequent testing will be described. The transmission system uses evacuated, windowless waveguide and the three gyrotrons have output windows of three different materials. One gyrotron uses a diamond window and generates a Gaussian beam directly. The development of the system and specific tests and results from each of the gyrotrons will be presented. The DIII-D project has committed to an upgrade of the system, which will add three gyrotrons in the 1 MW class, all using diamond output windows, to permit operation at up to ten seconds per pulse at one megawatt output for each gyrotron. digital.library.unt.edu/ark:/67531/metadc722415/
120-D-1 (100-D) ponds training plan
This is the Environmental Restoration Contractor Team training plan for the 100-D Ponds treatment, storage, and disposal unit. This plan is intended to meet the requirements of WAC 173-303-330 and the Hanford Dangerous Waste Permit. The WAC 173-303-330(1)(d)(ii, v, vi) requires that personnel be familiar, where applicable, with waste feed cut-off systems, proper responses to groundwater contamination incidents, shutdown of operations, response to fire or explosion, and other process operation activities. digital.library.unt.edu/ark:/67531/metadc627901/
125 TON MPC WASTE PACKAGE SHIELDING ANALYSIS/2-D DORT (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the dose rates from the MPC waste packages to be used by the EBS and other repository systems to incorporate ALARA practices in the overall repository design in compliance with the goals of the Waste Package Implementation Plan for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives. The objectives of this evaluation are (1) to show the dose rate as a function of distance from the waste package surface and (2) to provide the shielding thicknesses required for the waste package transporter to meet a 10 mrem/hr target dose rate at 2 meters from the transporter surface. digital.library.unt.edu/ark:/67531/metadc792895/
(129)Xe NMR of Mesoporous Silicas
The porosities of three mesoporous silica materials were characterized with {sup 129}Xe NMR spectroscopy. The materials were synthesized by a sol-gel process with r = 0, 25, and 70% methanol by weight in an aqueous cetyltrimethylammonium bromide solution. Temperature dependent chemical shifts and spin lattice relaxation times reveal that xenon does not penetrate the pores of the largely disordered (r= 70%) silica. For both r = 0 and 25%, temperature dependent resonances corresponding to physisorbed xenon were observed. An additional resonance for the r = 25% sample was attributed to xenon between the disordered cylindrical pores. 2D NMR exchange experiments corroborate the spin lattice relaxation data which show that xenon is in rapid exchange between the adsorbed and the gas phase. digital.library.unt.edu/ark:/67531/metadc691458/
150-MW S-band klystron program at the Stanford Linear Accelerator Center
Two S-Band klystrons operating at 150 MW have been designed, fabricated and tested at the Stanford Linear Accelerator Center (SLAC) during the past two years for use in an experimental accelerator at Deutsches Elektronen-Synchrotron (DESY) in Hamburg, Germany. Both klystrons operate at the design power, 60 Hz repetition rate, 3 {micro}s pulsewidth, with an efficiency {gt} 40%, and agreement between the experimental results and simulations is excellent. The 535 kV, 700 A electron gun was tested by constructing a solenoidal focused beam stick which identified a source of oscillation, subsequently engineered out of the klystron guns. Design of the beam stick and the two klystrons is discussed, along with observation and suppression of spurious oscillations. Differences in design and the resulting performance of the Klystrons is emphasized. digital.library.unt.edu/ark:/67531/metadc694313/
183-H Basin Mixed Waste Analysis and Testing Report
The purpose of this sampling and analysis report is to provide data necessary to support treatment and disposal options for the low-level mixed waste from the 183-H solar evaporation ponds. In 1973, four of the 16 flocculation and sedimentation basins were designated for use as solar evaporation basins to provide waste reduction by natural evaporation of liquid chemical wastes from the 300 Area fuel fabrication facilities. The primary purpose of this effort is to gather chemical and bulk property data for the waste in the drums/boxes of sediment removed from the basin at Central Waste Complex. digital.library.unt.edu/ark:/67531/metadc675714/
183-H Basin sludge treatability test report
This document presents the results from the treatability testing of a 1-kg sample of 183-H Basin sludge. Compressive strength measurements, Toxic Characteristic Leach Procedure, and a modified ANSI 16.1 leach test were conducted digital.library.unt.edu/ark:/67531/metadc667016/
183-H Solar Evaporation Basins PostClosure Plan
The 183-H Solar Evaporation Basins (183-H) have certified closure under a modified closure option available in the Hanford Facility Dangerous Waste Permit under Condition II.K.3. The following information contains a description of the unit, past closure actions, and postclosure care requirements subject to compliance under the Permit. Corrective actions required for dangerous waste constituents remaining at 183-H will occur in conjunction with Comprehensive Environmental Response, Compensation, and Liability Act remedial actions for the 100-HR-1 Source Operable Unit and the 100-HR-3 Groundwater Operable Unit digital.library.unt.edu/ark:/67531/metadc626607/
183 KE Potable water system analysis plan
Sampling analysis plans (SAP) are a recognized manner of providing applicable requirements for conducting media sampling and analysis in a manner consistent with prescirbed objectives. This SAP has been prepared to satisfy the data quality objectives listed in this SAP with respect to the operation of the 183 KE potable water for K Area. digital.library.unt.edu/ark:/67531/metadc669450/
183 KE Potable Water System Quality Assurance Project Plan
This Quality Assurance Project Plan (QAPP) describes the quality assurance (QA) requirements for sampling, analysis, equipment, and data reporting for the 183 KE Potable Water Facility. digital.library.unt.edu/ark:/67531/metadc670771/
A 200-A, 500-Hz, triangle current-wave modulator and magnet used for particle beam rastering
This paper describes a simple 2D beam-rastering system to uniformly spread a 100-mA 6.7-MeV cw proton beam over a 50-cm by 50-cm beam stop. The basic circuit uses a 20-mF capacitor bank, a IGBT (insulated gate bipolar transistor) full-wave inverter, and a 1-mH ferrite dipole magnet to produce a {+-} 500-Gauss peak triangular-waveform deflection field at 500 Hz. A dc input voltage of 200 volts at 2.6 amps (520 watts) produces a 160-ampere peak-to-peak triangular current waveform in the ferrite magnet at 500 Hz. For dual-axis rastering, two ferrite dipoles are used, one at 500 Hz, and the other at 575 Hz, to produce a uniform 2D beam distribution at the beam stop. The paper will discuss the IGBT modulator and ferrite deflector in detail, including current and voltage waveforms, and the ferrite magnet B-dot (dB/dt) signal. digital.library.unt.edu/ark:/67531/metadc696828/
200 area effluent treatment facilities configuration management plan
Provides facility specific configuration management guidance and references. Describes methods used at Liquid Effluent Facilities for configuration control in accordance with upper tier requirements digital.library.unt.edu/ark:/67531/metadc681588/
200 area effluent treatment facility basic support systems operational test specification
This document identifies the test requirements for the 200 Area Effluent Treatment Facility Basic Support Systems digital.library.unt.edu/ark:/67531/metadc674926/
200 area effluent treatment facility opertaional test report
This document reports the results of the 200 Area Effluent Treatment Facility (200 Area ETF) operational testing activities. These Operational testing activities demonstrated that the functional, operational and design requirements of the 200 Area ETF have been met and identified open items which require retesting. digital.library.unt.edu/ark:/67531/metadc679677/
200 Area effluent treatment facility process control plan 95-001
Provides initial run plan guidance for the 200 Area Effluent Treatment Facility in the treatment of Liquid Effluent Retention Facility waste during Phase III testing digital.library.unt.edu/ark:/67531/metadc678674/
200 Area effluent treatment facility process control plan 98-02
This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). digital.library.unt.edu/ark:/67531/metadc681991/
200 Area Effluent Treatment Facility set-values selection basis
This document identifies the set-values and selection basis to support operation of the 200 Area ETF and 200 Area TEDF. digital.library.unt.edu/ark:/67531/metadc706448/
200 Area Liquid Effluent Facilities -- Quality assurance program plan
This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements. digital.library.unt.edu/ark:/67531/metadc685263/
200 area liquid effluent facility quality assurance program plan. Revision 1
Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities digital.library.unt.edu/ark:/67531/metadc688741/
200 Area population weighted X/Q for the public within 10 miles of the site boundary
An overall population weighted atmospheric dispersion coefficient (X/Q) has been calculated for the public within 10 miles of the Hanford Site boundary. The Columbia river was assumed as the Hanford site boundary to the north and the east. The GXQ code was used for the calculation. The value calculated is 1.88 x 10-8 s/m 3. digital.library.unt.edu/ark:/67531/metadc707382/
200 Area TEDF effluent sampling and analysis plan
This sampling analysis sets forth the effluent sampling requirements, analytical methods, statistical analyses, and reporting requirements to satisfy the State Waste Discharge Permit No. ST4502 for the Treated Effluent Disposal Facility. These requirements are listed below: Determine the variability in the effluent of all constituents for which enforcement limits, early warning values and monitoring requirements; demonstrate compliance with the permit; and verify that BAT/AKART (Best Available Technology/All know and Reasonable Treatment) source, treatment, and technology controls are being met. digital.library.unt.edu/ark:/67531/metadc625691/
200 Area treated effluent disposal facility operational test report
This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met. digital.library.unt.edu/ark:/67531/metadc675375/
200 Area Treated Effluent Disposal Facility operational test specification. Revision 2
This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met. The technical requirements for operational testing of the 200 Area TEDF are defined by the test requirements presented in Appendix A. These test requirements demonstrate the following: pump station No.1 and associated support equipment operate both automatically and manually; pump station No. 2 and associated support equipment operate both automatically and manually; water is transported through the collection and transfer lines to the disposal ponds with no detectable leakage; the disposal ponds accept flow from the transfer lines with all support equipment operating as designed; and the control systems operate and status the 200 Area TEDF including monitoring of appropriate generator discharge parameters. digital.library.unt.edu/ark:/67531/metadc675881/
200-BP-5 operable unit treatability test report
The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites. digital.library.unt.edu/ark:/67531/metadc664341/
T-200 series tank concentration predictions
Of the 177 tanks containing nuclear waste at the Hanford site, 68 have not been characterized based on sampling information. It may be possible to characterize 34 of the 68 unsampled tanks by using information from other sources, such as the Tank Characterization Database (TCD) and the Historical Tank Content Estimates (HTCE). This report lists predicted concentrations of 17 analytes along with the associated estimates of uncertainty for the T-200 series tanks (T-201, T-202, T-203, T-204), based on historical data and sample results from tanks other than the T-200 tanks. The main benefits of reduced sampling are reduced cost, reduced time to achieve acceptable characterization, and reduced exposure of sampling personnel. However, in order to characterize a tank on the basis of reducing sampling, the predicted tank averages and the associated uncertainties must be technically credible and useful. The objective of this report is to describe the approach to predict (without a sample) or estimate (from a single sample) the concentrations of the 17 analytes for the T-200 tanks. Sampling of these tanks and laboratory analysis of the samples is currently under way (sampling is scheduled for 03/27/97 through 04/21/97). This report briefly describes the statistical prediction techniques. digital.library.unt.edu/ark:/67531/metadc698731/
204-AR facility rail accident analysis
This is a probabilistic analysis of the rail car accidents at the 204- AR Waste Unloading Facility. digital.library.unt.edu/ark:/67531/metadc710057/
209-E Building -- Response to ventilation failure evaluation
This document provides an evaluation and recommendations for radiological workplace air monitoring and response to ventilation failure for the Critical Mass Laboratory, 209-E Building. The Critical Mass Laboratory, part of the 209-E Building, was designed to provide a heavily shielded room where plutonium and uranium liquid solutions could be brought into various critical configurations under readily controlled and monitored conditions. The facility is contained within a one-story L-shaped concrete block and reinforced concrete building. One wing houses offices, a control room, shops, and a common area while the other wing includes an equipment room, the change room, work areas, and the two-story Critical Assembly Room (CAR). Three of the rooms contain radiologically contaminated equipment and materials. digital.library.unt.edu/ark:/67531/metadc685690/
216-Day report for Tank 241-C-111, cores 58 and 59
Three core samples from tank C-111, and a field blank, were received by the 222-S laboratories. Cores 58, 59, and the field blank were analyzed in accordance with plans. A hot cell blank was analyzed at the direction of the hot cell chemist. No sample results exceeded the notification limits. Core 60 was not analyzed. digital.library.unt.edu/ark:/67531/metadc684570/