This document addresses the characterization needs of tanks as set forth in the Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for High-Level Waste Feed Batch X (Crawford et al. 1998). The primary purpose of this document is to collect existing data and identify the data needed to determine whether or not the feed source(s) are appropriate for a specific batch. To answer these questions, the existing tank data must be collected and a detailed review performed. If the existing data are insufficient to complete a full comparison, additional data must be obtained from the feed source(s). Additional information requirements need to be identified and formally documented, then the source tank waste must be sampled or resampled and analyzed. Once the additional data are obtained, the data shall be incorporated into the existing database for the source tank and a reevaluation of the data against the Data Quality Objective (DQO) must be made.

This document addresses the characterization needs of tanks as set forth in the ''Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X'' Data Quality Objective (DQO) (Certa and Jo 1998). The primary purpose of this document is to collect existing data and identify the data needed to determine whether or not the feed source(s) are appropriate for a specific batch before transfer is made to the feed staging tanks. To answer these questions, the existing tank data must be collected and a detailed review performed. If the existing data are insufficient to complete a full comparison, additional data must be obtained from the feed source(s). Additional information requirements need to be identified and formally documented, then the source tank waste must be sampled or resampled and analyzed. Once the additional data are obtained, the data shall be incorporated into the existing database for the source tank and a reevaluation of the data against the DQO must be made.

This Authorization Basis document is one of three documents that constitute the Authorization Basis for the 209-E Building. Per the U.S. Department of Energy, Richland Operations Office (RL) letter 98-WSD-074, this document, the 209-E Building Preliminary Hazards Analysis (WHC-SD-WM-TI-789), and the 209-E Building Safety Evaluation Report (97-WSD-074) constitute the Authorization Basis for the 209-E Building. This Authorization Basis and the associated controls and safety programs will remain in place until safety documentation addressing deactivation of the 209-E Building is developed by the contractor and approved by RL.

Essential and supporting engineering drawings for the Central Waste Complex (CWC) are identified in this document. The purpose of the document is to describe the criteria used to identify drawings and the plan for updating and maintaining their accuracy. This document supports HNF-PRO-242 and HNF-PRO-440.

The Cold Vacuum Drying Facility Project is preparing a document that verifies the design meets the requirements. This document provides the Plan to complete this scope of work.

Document describes first year of operation of 241-AN-107 electrochemical noise based corrosion monitoring system. Data and system status are presented.

Glovebox HC-21A is an enclosure where cans containing plutonium metal buttons or other plutonium bearing materials are prepared for thermal stabilization in the muffle furnaces. The Inert Atmosphere Confinement (IAC), a new feature added to Glovebox HC-21A, allows the opening of containers suspected of containing hydrided plutonium metal. The argon atmosphere in the IAC prevents an adverse reaction between oxygen and the hydride. The hydride is then stabilized in a controlled manner to prevent glovebox over pressurization. After removal from the containers, the plutonium metal buttons or plutonium bearing materials will be placed into muffle furnace boats and then be sent to one of the muffle furnace gloveboxes for stabilization. The materials allowed to be brought into GloveboxHC-21 A are limited to those with a hydrogen to fissile atom ratio (H/X) {le} 20. Glovebox HC-21A is classified as a DRY glovebox, meaning it has no internal liquid lines, and no free liquids or solutions are allowed to be introduced. The double contingency principle states that designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible. This criticality safety evaluation report (CSER) shows that the …

Proposed actions tend to evolve over time. Once National Environmental Policy Act (NEPA) documentation is completed, agencies are at risk that subsequent changes may not be adequately covered or that existing NEPA documentation maybe completely invalidated. Neither NEPA nor its subsequent regulations provide sufficient direction for determining the degree to which a proposed action may change before preparation of new or supplemental documentation is necessary. Yet, decisionmakers are routinely involved in determining if a change to a proposed action departs, to such an extent, from the description presented in the NEPA document that additional documentation is necessary. Experience demonstrates that no two decisionmakers will completely agree, one decisionmaker might believe that a particular change would not require additional documentation, while the other concludes the exact opposite. Lacking definitive direction, decisionmakers and critics alike may point to a universe of potential considerations as the basis for defending their claim that a change in an action does or does not require new or additional NEPA documentation. Assertions are often based on equivocal opinions that can be neither proved nor disproved. Moreover, decisionmakers are frequently placed in an arduous dilemma of justifying a decision, for which there is no generally accepted methodology on …

A Discussion of SY-101 Crust Gas Retention and Release Mechanisms

The flammable gas hazard in Hanford waste tanks was made an issue by the behavior of double-shell Tank (DST) 241-SY-101 (SY-101). Shortly after SY-101 was filled in 1980, the waste level began rising periodically, due to the generation and retention of gases within the slurry, and then suddenly dropping as the gases were released. An intensive study of the tank's behavior revealed that these episodic releases posed a safety hazard because the released gas was flammable, and, in some cases, the volume of gas released was sufficient to exceed the lower flammability limit (LFL) in the tank headspace (Allemann et al. 1993). A mixer pump was installed in SY-101 in late 1993 to prevent gases from building up in the settled solids layer, and the large episodic gas releases have since ceased (Allemann et al. 1994; Stewart et al. 1994; Brewster et al. 1995). However, the surface level of SY-101 has been increasing since at least 1995, and in recent months the level growth has shown significant and unexpected acceleration. Based on a number of observations and measurements, including data from the void fraction instrument (VFI), we have concluded that the level growth is caused largely by increased gas retention …

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This plan outlines the steps to be taken to modify existing neutron/gamma probe designs to allow insertion of these probes into the multifunction instrument trees (MITs) at tank 241-SY-101. The objective is to locate and track this tank's Interstitial Liquid Level (ILL). This plan provides scope, schedule, and cost estimates to achieve this objective, and assigns individual organizational responsibilities to carry out this task.

The Materials Consultation Group of SRTC has completed an external corrosion analysis of the Model 9975 packaging container for storage in K Reactor under ambient conditions for a period of 12 years. The 12-year storage period includes two years for shipping and ten years for storage. Based on review of existing literature and stated building storage conditions, corrosion degradation of the 304L Stainless Steel (SS) packaging container (drum and vessels) should be minimal during the 12 year time period. There may be visible corrosion on the galvanized carbon steel pallet due to initial drum handling. The visible corrosion will not be sufficient to cause significant degradation during the 12-year storage period. The Materials Consultation Group concludes that there are sufficient data to establish the technical basis for safe storage of the Model 9975 container in the 105-K building for up to 10 years following the 2-year shipping period. The data are sufficient to allow the 304L SS containers to be stored for a total period of 15 years.

A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards.

The demonstration of the IGRS approach conducted at SWMU 143 on the White Sands Missile Range has provided information needed to complete a technical performance assessment and cost analysis of the technology. At least 70% of the Cr(VI) present in contaminated sediment at the site was reduced, thus verifying the effectiveness of the approach. Most of the treatment occurred in a zone located from {approximately}4 to 10 ft below ground surface, which appears to be a higher permeability interval. A deeper zone from {approximately}10 to 16 ft that contains lower levels of contamination was essentially unaffected. The deeper zone is somewhat finer grained and has a higher clay content and is, thus, less permeable. It appears that most of the treatment gas was channeled through the higher, more-permeable zone and the lower zone was bypassed. Treatment of the lower zone could probably be accomplished, however, if a second injection well were installed and screened across the zone so that treatment gas could be forced into this interval. The amount of H{sub 2}S consumed during the test exceeded the amount predicted by the laboratory treatability study. In addition, the levels of H{sub 2}S observed at the extraction wells were relatively low, …

Interfacial effects play an important role in governing multiphase fluid behavior in porous media. Strongly hydrophobic organic dyes, used in many experimental studies to facilitate visual observation of the phase distributions, have generally been implicitly assumed to have no influence on the interfacial properties of the various phases in porous media. Sudan IV is the most commonly used dye for non-aqueous phase liquids (NAPLs) in laboratory experiments. It has also been used in at least one field experiment. The effects of this dye on the tetrachloroethylene (PCE)-water-glass system were investigated to test the assumption that the dye does not effect the interfacial properties and therefore PCE mobility. The results indicate that the dye does indeed change the interfacial relationships.The effect of the dye on the interfacial relationships is a complex function of the dye concentration, the solid phase composition, and the dynamic rate of new interface formation. The dye caused a slight (<10 percent) increase in interfacial tension at low concentrations (<0.1 g/L) and high rates of new interface formation. The dye reduced interfacial tension between PCE and water at low rates of new interface formation for all dye concentrations tested (0.00508 to 5.08 g/L). At the highest dye concentration, …

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The purpose of this project was to develop tools for understanding the influence of crystal quality and crystal mounting on harmonic-generation efficiency at high irradiance. Measuring the homogeneity of crystals interferometrically, making detailed physics calculations of conversion efficiency, performing finite- element modeling of mounted crystals, and designing a new optical metrology tool were key elements in obtaining that understanding. For this work, we used the following frequency-tripling scheme: type I second- harmonic generation followed by type II sum-frequency mixing of the residual fundamental and the second harmonic light. The doubler was potassium dihydrogen phosphate (KDP), and the tripler was deuterated KDP (KD*P). With this scheme, near-infrared light (1053 nm) can be frequency tripled (to 351 nm) at high efficiency (theoretically >90%) for high irradiance (>3 GW/cm²). Spatial variations in the birefringence of the large crystals studied here (37 to 41 cm square by about 1 cm thick) imply that the ideal phase-matching orientation of the crystal with respect to the incident laser beam varies across the crystal. We have shown that phase-measuring interferometry can be used to measure these spatial variations. We observed transmitted wavefront differences between orthogonally polarized interferograms of {lambda}/50 to {lambda}/100, which correspond to index variations of …

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descnies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S chn' and SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added …

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descnies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S `chn' and `SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added …

This Software Configuration Management Plan (SCMP) provides the instructions for change control of the W-211 Project, Retrieval Control System (RCS) software after initial approval/release but prior to the transfer of custody to the waste tank operations contractor. This plan applies to the W-211 system software developed by the project, consisting of the computer human-machine interface (HMI) and programmable logic controller (PLC) software source and executable code, for production use by the waste tank operations contractor. The plan encompasses that portion of the W-211 RCS software represented on project-specific AUTOCAD drawings that are released as part of the C1 definitive design package (these drawings are identified on the drawing list associated with each C-1 package), and the associated software code. Implementation of the plan is required for formal acceptance testing and production release. The software configuration management plan does not apply to reports and data generated by the software except where specifically identified. Control of information produced by the software once it has been transferred for operation is the responsibility of the receiving organization.

A program has been initiated to assess, renovate, document and certify tank farm field equipment for year 2000 compliance. The program is necessary to assure no adverse effects occur in tank farm operations as a result of equipment malfunction due to what is widely known as the ''millennium bug''. This document elaborates the protocols for reviewing field equipment lists and tank farm drawings for the purpose of identifying and resolving year 2000 compliance problems in tank farm equipment.

We have demonstrated an all solid state Ti:Sapphire laser system consisting of a power oscillator and single pass amplifier. The electrical-to-optical efficiency far exceeds that of the current CW systems. The pump lasers have lower capital and operating costs than the Argon-ion laser. In the future, we plan to scale the output power to higher levels by adding a fourth pump laser and improving the output power of the current pump lasers. Modeling results suggest that a large increase in efficiency can be realized by improving the beam quality of the pump lasers, even at the cost of reduced output power. We will explore this option by adding apertures to the cavity and/or reducing the rod diameter along with optimizing the resonator design. Other improvements in efficiency which will be investigated include double passing the amplifier for better extraction. To complete this work, the laser system will be converted into a two-stage amplifier. A narrow band, lower power oscillator currently under development will be injected in to the amplifier to study the extraction and efficiency characteristics of the amplifier throughout the tuning range of Ti:Sapphire. Detailed beam quality measurements will also be made. Other work will include doubling the narrow …

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).