Plans are to close Tank 17, a type IV waste tank in the F-area Tank Farm, by filling it with pumpable backfills. Most of the waste was removed from the tank in the late 1980s, and the remainder of the waste was removed in a short spray washing campaign that began on 11 April 1997. More details on the planned closure can be found in the Closure Plan for the High-Level Waste (HLW) Tanks and the specific closure module for Tank 17. To show that closure of the tank is environmentally sound, a performance evaluation has been performed for Tank 17. The performance evaluation projected the concentration of contaminants at various locations and times after closure. This report documents the basis for the inventories of contaminants that were used in the Tank 17 performance evaluation.

In May of 1996, the US Department of Energy implemented a four-year demonstration project identified as the Hanford Tanks Initiative (HTI). The HTI mission is to minimize technical uncertainties and programmatic risks by conducting demonstrations to characterize and remove tank waste using technologies and methods that will be needed in the future to carry out tank waste remediation and tank farm closure at the Hanford Site. Included in the HTI scope is the development of retrieval performance evaluation criteria supporting readiness to close single-shell tanks in the future. A path forward that includes evaluation of closure basis alternatives has been outlined to support the development of retrieval performance evaluation criteria for the AX Farm, and eventual preparation of the SEIS for AX Farm closure. This report documents the results of the Task 4, Waste Inventory study performed to establish the best-basis inventory of waste contaminants for the AX Farm, provides a means of estimating future soil inventories, and provides data for estimating the nature and extent of contamination (radionuclide and chemical) resulting from residual tank waste subsequent to retrieval. Included in the report are a best-basis estimate of the existing radionuclide and chemical inventory in the AX Farm Tanks, an …

The purpose of this acceptance test report was to verify the assembly is correct and complete and meets all the specification and performance requirements. On May 15--16, 1996, the LLW Supercompactor functional demonstrations and performance tests were carried out. These tests were carried out in accordance with the Acceptance Test Procedure, submittal 565, dated 5/3/96. The tests were performed by Herman Miller and Gene Rice of INET Corporation and Richard Lawrence and other PCL personnel. The VIHC representative on May 15, 1996 was Doug Dunlap and on May 16, 1996 the representative was Ken Leist.

The Hanford Seismic Monitoring Network consists of two designs of equipment and sites: seismometer sites and strong motion accelerometer (SMA) sites. Seismometer sites are designed to locate earthquakes on and near the Hanford Site and determine their magnitude and hypocenter location. The US Department of Energy (DOE) Order 5480.28, Natural Phenomena Hazards (DOE 1993) requires that facilities or sites that have structures or components in Performance Category 2 with hazardous material, and all Performance Category 3 and 4 facilities shall have instrumentation or other means to detect and record the occurrence and severity of seismic events. In order to comply with DOE Order 5480.28, the Hanford Seismic Monitoring Network seismometer sites needed to be complemented with strong motion accelerometers to record the ground motion at specific sites. The combined seismometer sites and strong motion accelerometer sites provide the Hanford Site with earthquake information to comply with DOE Order 5480.28. The data from these instruments will be used by the PHMC staff to assess the damage to facilities following a significant earthquake.

This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (Table 1). A notification was made to East Tank Farms Operations concerning low hydroxide in the tank and a hydroxide (caustic) demand analysis was requested. The request for sample analysis (RSA) (Attachment 2) received for AP-107 indicated that the samples were polychlorinated biphenyl (PCB) suspects. Therefore, prior to performing the requested analyses, aliquots were made to perform PCB analysis in accordance with the 222-S Laboratory administrative procedure, LAP-101-100. The results of this analysis indicated that no PCBs were present at 50 ppm and analysis proceeded as non-PCB samples. The results and raw data for the PCB analysis will be included in a revision to this document. The sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer …

Three nonstandard Waste Encapsulation and Storage Facility (WESF) cesium chloride capsules are being shipped from WESF (225B building) to the 324 building. They would normally be shipped in the Beneficial Uses Shipping System (BUSS) cask under its US Department of Energy (DOE) license (DOE 1996), but these capsules are nonstandard: one has a damaged or defective weld in the outer layer of encapsulation, and two have the outer encapsulation removed. The 3 capsules, along with 13 other capsules, will be overpacked in the 324 building to meet the requirements for storage in WESF`s pool.

This report contains the contents of a web page related to research on the development of quantum chemistry methods for computational thermochemistry and the application of quantum chemistry methods to problems in material chemistry and chemical sciences. Research programs highlighted include: Gaussian-2 theory; Density functional theory; Molecular sieve materials; Diamond thin-film growth from buckyball precursors; Electronic structure calculations on lithium polymer electrolytes; Long-distance electronic coupling in donor/acceptor molecules; and Computational studies of NOx reactions in radioactive waste storage.

This Quality Assurance Program Plan (QAPP) provides an overview of the quality assurance program for Building 327. The program applies to the facility safety structures, systems, and components and to activities that could affect safety structures, systems, and components. Adherence to the quality assurance program ensures the following: US Department of Energy missions and objectives are effectively accomplished; Products and services are safe, reliable, and meet or exceed the requirements and expectations of the user; Hazards to the public, to Hanford Site and facility workers, and to the environment are minimized. The format of this Quality Assurance Program Plan is structured to parallel that of 10 CFR 83 0.120, Quality Assurance Requirements. This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the 324 Building B-Cell Safety Cleanout Project (BCCP). This QAPP is responsive to the Westinghouse Hanford Company Quality Assurance Program and Implementation Plan, WHC-SP 113 1, for 10 CFR 830.120, Nuclear Safety Management, Quality Assurance Requirements; and DOE Order 5700.6C, Quality Assurance. This QAPP supersedes PNNL PNL-MA-70 QAP Quality Assurance Plan No. WTC-050 Rev. 2, issue date May 3, 1996.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AP-105. This report supports the requirements of the Tri-Party Agreement Milestone M 44-05.

The purpose of this document is to provide a single referenceable document that provides the X/Qs for the solid waste facilities in the 200 Area, that is to provide the X/Qs for the Solid Waste Dispersal Facilities Master Safety Analysis Report (WHC-SD-WM-MSAR-001, REV. 0, 1996). The X/Qs will be used for the radiological dose estimates in the accident safety analyses. Thus, this document is also to provide the information necessary to perform bounding estimates of the radiological consequences for hypothetical accidents for various solid waste facilities. This document is to examine the variations in the plume dispersion factors associated with the various solid waste facilities. Specifically examined are X/Qs associated with different receptors located in different sectors and at different distances. Examination of one facility included a large area X/Q, while examination of another facility included an elevated release. Generally, the X/Qs are determined for ground releases with and without building wake. In addition, sensitivity of how plume characteristics were affected by using different meteorological data was examined. Each receptor described in this document was evaluated for both 99.5% and 50% meteorological data. Attributes such as plume meander, plume rise, settling and wash-out are not considered in this document.

Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in …

This Quality Assurance Program Plan (QAPP) provides an overview of the quality assurance program for Building 324. This plan supersedes the PNNL Nuclear Facilities Quality Management System Description, PNL-NF-QMSD, Revision 2, dated March 1996. The program applies to the facility safety structures, systems, and components and to activities that could affect safety structures, systems, and components. Adherence to the quality assurance program ensures the following: US Department of Energy missions and objectives are effectively accomplished; Products and services are safe, reliable, and meet or exceed the requirements and expectations of the user; Hazards to the public, to Hanford Site and facility workers, and to the environment are minimized. The format of this Quality Assurance Program Plan is structured to parallel that of 10 CFR 83 0.120, Quality Assurance Requirements.

This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the 324 Building B-Cell Safety Cleanout Project (BCCP). This QAPP is responsive to the Westinghouse Hanford Company Quality Assurance Program and Implementation Plan, WHC-SP-1131, for 10 CFR 830.120, Nuclear Safety Management, Quality Assurance Requirements; and DOE Order 5700.6C, Quality Assurance. This QAPP supersedes PNNL PNL-MA-70 QAP Quality Assurance Plan No. WTC-050 Rev. 2, issue date May 3, 1996. This QAPP has been developed specifically for the BCCP. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of decontaminating B-Cell and project related operations within the 324 Building as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations) are covered in the Building 324 QAPP. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping, and HSRCM-1, Hanford Site Radiological Control Manual, The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. …

This report provides a comprehensive analysis of the Mississippi interior salt basin and to transfer the results effectively.

The objective is to provide a comprehensive geologic analysis of the Mississippi Interior Salt Basin.

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This report provides an independent evaluation of information for a Windows based Human Machine Interface (HMI) to replace the existing DOS based Iconics HMI currently used in the Data Acquisition and Control System (DACS) used at Tank 241-SY-101. A fundamental reason for this evaluation is because of the difficulty of maintaining the system with obsolete, unsupported software. The DACS uses a software operator interface (Genesis for DOS HMI) that is no longer supported by its manufacturer, Iconics. In addition to its obsolescence, it is complex and difficult to train additional personnel on. The FY 1997 budget allocated $40K for phase 1 of a software/hardware upgrade that would have allowed the old DOS based system to be replaced by a current Windows based system. Unfortunately, budget constraints during FY 1997 has prompted deferral of the upgrade. The upgrade needs to be performed at the earliest possible time, before other failures render the system useless. Once completed, the upgrade could alleviate other concerns: spare pump software may be able to be incorporated into the same software as the existing pump, thereby eliminating the parallel path dilemma; and the newer, less complex software should expedite training of future personnel, and in the process, …

Pollution Prevention/Waste Minimization (P2/WMin) is the Department of Energy`s preferred approach to environmental management. The P2/WMin mission is to eliminate or minimize waste generation, pollutant releases to the environment, use of toxic substances, and to conserve resources by implementing cost-effective pollution prevention technologies, practices, and polices. Technical objectives are to: Coordinate the Hanford Site Pollution Prevention and Waste Minimization Program in support of Fluor Daniel Hanford (FDH) and the Department of Energy, Richland Operations office in the development and implementation of the Sitewide Program; Develop site-specific guidance for implementing P2 activities established by the US Department of Energy Headquarters in the 1996 P2 Program Plan and for ensuring consistent generator programs; Provide leadership to promote a Sitewide program to reduce both the volume and toxicity of radioactive, mixed, hazardous and sanitary waste types, to promote recycling, and resource conservation to reduce future risks and costs associated with managing wastes and pollutants; Maintain a program that complies with federal, state and DOE directives; Compile reports on Site P2 progress, including compliance reporting; Establish site-specific goals to minimize the generation of wastes and pollutants, including hazardous, radioactive, mixed, and sanitary from site operations; Establish performance measures to track P2/WMin progress against established …

This report concerns the packaging configurations being tested by the U.S. DOE and its contractors, and according to U.S. DOT specification 7A Type A (DOT-7A) requirements. The objective of this Test Plan is to describe the testing for the qualification of the M-100 Container, Model M-101/7A/12/90 as a DOT-7A Type A packaging. This packaging system is designed to ship Type A solid radioactive materials, normal form, Form Number 1, Form Number 2, and Form Number 3.

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Second Quarter 1997 survey results and the status of actions required are summarized below: All of the routine environmental radiological surveys scheduled during April, May, and June 1997, were performed as planned with the exception of UN-216-E-9. This site was not surveyed as stabilization activities were in progress. The sites scheduled for the Environmental Restorations Contractor (ERC) team were switched with those identified for the third quarter as there was a conflict with vegetation management activities.

Between 8 and 50 metric tonnes of excess plutonium are currently planned to be immobilized in a glass or ceramic waste form in the US. The immobilized Pu would then be encased in HLW glass (the can-in-canister alternative), which would provide a radiation barrier to enhance the proliferation resistance of the material. Associated with the plutonium are about 15 metric tonnes of uranium primarily {sup 238}U and a variety of other impurities (primarily Ga, Mo, Al, Mg, Si, and Cl) totaling about 1 metric tonne or less. Immobilization of this material is complicated by the fact that the uranium content in the various feed streams varies widely, from 0 to about 95%. The proposed ceramic form is composed of about 90% zirconolite (CaZrTi{sub 2}O{sub 7}) and/or pyrochlore (CaPuTi{sub 2}O{sub 7}) with about 10% other phases, typically hollandite (BaAl{sub 2}Ti{sub 6}O{sub 16}) and rutile (TiO{sub 2}). The form is a variation of Synroc-C, which contains nominally 30% zirconolite, 30% perovskite, 30% hollandite, and 10% rutile and noble metal alloys. Zirconolite and perovskite are the actinide host phases in Synroc-C with zirconolite being the more durable phase. The pyrochlore structure is closely related to zirconolite and forms at higher actinide loadings. Thus, …

Recycled Type 304 stainless steel from both Carolina Metals Inc. (CMI) and Manufacturing Science Corporation (MSC) met all the requirements of ASTM A-240 required by Procurement Specification G-SPP-K-00005 Rev. 4. Mechanical strength and corrosion resistance of the material are adequate for service as burial boxes, overpacks, and drums. Inclusion content of both manufacturer`s material was high, resulting in a corresponding decrease in the corrosion resistance. Therefore, an evaluation of the service conditions should be performed before this material is approved for other applications. These heats of stainless steel are not suitable for fabricating DWPF glass canisters because the inclusion and carbon contents are high. However, MSC has recently installed a vacuum induction furnace capable of producing L grade material with a low inclusion content. Material produced from this furnace should be suitable for canister material if appropriate care is taken during the melting/casting process.

The In-situ Vitrification (ISV) process potentially offers the most stable waste-form for containment of radiologically contaminated soils while minimizing personnel contamination. This is a problem that is extensive, and at the same time unique, to the US Department of Energy`s (DOE) Weapons Complex. An earlier ISV process utilized joule heating of the soil to generate the subsurface molten glass product. However previous test work has indicated that the Savannah river Site soils (SRS) may not be entirely suitable for vitrification by joule heating due to their highly refractory nature. The concept of utilizing a plasma torch for soil remediation by in-situ vitrification has recently been developed, and laboratory test work on a 100 kW unit has indicated a potentially successful application with SRS soils. The Environmental Restoration Division (ERD) of Westinghouse Savannah River Company (WSRC) conducted the first field scale demonstration of this process at the (904-65G) K-Reactor Seepage Basin in October 1996 with the intention of determining the applicability and economics of the process for remediation of a SRS radioactive seepage basin. The demonstration was successful in completing three vitrification runs, including two consecutive runs that fused together adjacent columns of glass to form a continuous monolith. This report …