In May of 1994, racks of corrosion samples were installed along the Oregon coast. The aluminum alloy 3105 samples were mounted on utility poles in Astoria, Manzanita, Lincoln City, Gold Beach, Brookings, Portland, and Albany. At each coastal location, samples were placed on four different poles at various distances from the coast (from as near as 50 feet to as far as 5 miles). The inland sites (Portland and Albany) have only one pole per site and are used as control sites. Besides the 3105 alloys, 5052 and 6061 aluminum alloys were placed at all sites. Since installation, one rack was lost due to the pole being taken down by the phone company (in Lincoln City), but the rest of the poles and racks are still in place.<br> <br> In August of 1995, the aluminum samples were visually inspected, and the remaining six 3105 aluminum samples in Lincoln City were removed for laboratory examination. Non-destructive x-ray analysis was used on the Lincoln City samples to obtain information a bout the nature of the corrosion products. Because the analysis was performed while the corrosion products remained on the surface, aluminum peaks dominated the diffraction pattern, and relative peak-heights were different from …

Augmentation of the internal software of a commercial x-ray fluorescence gauge is shown to enable the instrument to extend its continuous on-line real-time measurements of a galvanneal coating's total elemental content to encompass similar measurements of the relative thickness of the coating's three principal metallurgical phases. The mathematical structure of this software augmentation is derived from the theory of neural networks. The empirical basis for the numerics embedded in the software's decision logic is presented. The performance of the augmented gauge is validated by comparing the gauge-implied real-time phase distribution with the phase distribution independently measured off-line on time-tagged samples drawn from the galvanneal production line where the measurement gauge had been installed. The performance validation is shown to demonstrate good agreement between the gauge and laboratory measurements and to suggest preferred approaches to be followed in future applications of the augmented gauge.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) in response to a request received via a QAP-3-12 Design Input Data Request (Reference 5.1) from Waste Acceptance, Storage, & Transportation (WAST) Design (formerly MRSMPC Design). This design analysis is an answer to the Design Input Data Request to provide: Specific requirements for long-term criticality control. The time period for long-term criticality control requirements encompass the time phases of operations (pre-closure), containment (first 1,000 years post-closure), and isolation (the time period beyond the containment phase, at least to 10,000 years post-closure). The purpose and objective of this analysis is to provide specific long-term disposal criticality control requirements for the Multi-Purpose Canister (MPC) Subsystem Design Procurement Specification (DPS), so as to not preclude MPC compatibility with disposal in the MGDS.(References 5.2, 5.3, and 5.4) The response is stated in Section 8 herein and will be available for transmittal as an attachment to a QAP-3-12 Design Input Data Transmittal.

The purpose of this analysis is to determine if the permanent portions of the configuration item BABEAA000 that will be constructed for the Exploratory Studies Facility (ESF) (i.e., Starter Tunnel for the North Portal and the headwall at the South Portal) are quality-affecting items. The objective is to establish the appropriate Quality Assurance (QA) classification based on these determinations. This analysis does not address the remaining scope of the Portals configuration item.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) in response to a request received via a QAP-3-12 Design Input Data Request from Waste Acceptance, Storage & Transportation (WAST) Design (formerly MRS/MPC Design). The request is to provide: Specific material requirements for the various MPC components (shell, basket, closure lids, shield plug, neutron absorber, and flux traps, if used ). The objective of this analysis is to provide the requested requirements. The purpose of this analysis is to provide a documented record of the basis for the requested requirements. The response is stated in Section 8 herein. The analysis is based upon requirements from an MGDS perspective.

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This report and its appendices present a general overview of congressional office procedures associated with handling casework and the assistance by a Member of Congress to help constituents in their dealings with federal agencies.

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This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The First Quarter 1996 survey results and the status of actions required from current and past reports are summarized: All the routine environmental radiological surveys scheduled during January, February, and March 1996 were completed. One hundred four environmental radiological surveys were performed during the first quarter of 1996, thirty at the active waste sites and seventy four at the inactive waste sites. Contamination above background levels was found at six of the active waste sites and eight of the inactive waste sites. Contamination levels as high as > 1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys, all were in Underground Radioactive Material (URM) areas. The contamination found within eleven of the URH areas was immediately cleaned up and no further action was required. In the remaining three sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR`s) were issued and the sites were turned over to the landlord for further action if required.

This data package satisfies the requirement for a format IV, final report. It is a follow-up to the 45-day safety screen report for tank AP-104. Evaporator candidate feed from tank 241-AP-104 (hereafter referred to as AP-104) was characterized for physical, inorganic, organic and radiochemical parameters by the Westinghouse Hanford Company, 222-S Laboratory, and by the Battelle Pacific Northwest National Laboratory (PNNL), Analytical Chemistry Laboratory (ACL) as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Laboratory analyses at ACL Laboratory was performed according to the TSAP. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory`s Quality Assurance Plan, References 5 and 6. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation. SAMPLING The TSAP, section 2, provided sampling information for waste samples collected from tank AP-104. The bottle-on-a-string method was used to collect liquid grab samples from the tank. Each glass sample bottle was …