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Requirements for Diluting & Flushing Double Shell Tank (DST) Systems

Description: This document identifies requirements and their applicability to the design and operation of the Double-Shell Tank Diluent and Flush Subsystem. The requirements are described here to justify their use in the Double-Shell Tank Diluent and Flush Subsystem Specification (HNF-4163).
Date: August 1, 2000
Creator: FASSETT, D.P.
Partner: UNT Libraries Government Documents Department

Requirements Analysis Study for Master Pump Shutdown System Project Development Specification [SEC 1 and 2]

Description: This document has been updated during the definitive design portion of the first phase of the W-314 Project to capture additional software requirements and is planned to be updated during the second phase of the W-314 Project to cover the second phase of the Project's scope. The objective is to provide requirement traceability by recording the analysis/basis for the functional descriptions of the master pump shutdown system. This document identifies the sources of the requirements and/or how these were derived. Each requirement is validated either by quoting the source or an analysis process involving the required functionality, performance characteristics, operations input or engineering judgment.
Date: March 24, 2000
Creator: BEVINS, R.R.
Partner: UNT Libraries Government Documents Department

Requirements Verification Report AN Farm to 200E Waste Transfer System for Project W-314 Tank Farm Restoration and Safe Operations

Description: This Requirements Verification Report (RVR) for Project W-314 ''AN Farm to 200E Waste Transfer System'' package provides documented verification of design compliance to all the applicable Project Development Specification (PDS) requirements. Additional PDS requirements verification will be performed during the project's procurement, construction, and testing phases, and the RVR will be updated to reflect this information as appropriate.
Date: September 28, 1999
Creator: MCGREW, D.L.
Partner: UNT Libraries Government Documents Department

Risk Management Plan for Tank Farm Restoration and Safe Operations Project W-314

Description: The Risk Management Plan for Project W-314 describes the systems, processes and procedures for implementation of applicable risk management practices described in HNF-0842, Volume IV, Section 2.6, ''Risk Management''. This plan is tailored specifically for use by Project W-314.
Date: April 19, 2000
Creator: MCGREW, D.L.
Partner: UNT Libraries Government Documents Department

Hanford science and technology needs statements, 2000

Description: In the aftermath of the Cold War, the United States has begun addressing the environmental consequences of five decades of nuclear weapons production. In November 1989, DOE established the Office of Environmental Restoration and Waste Management (EM) as the central authority for cleaning up the DOE weapons complex legacy of pollution, for preventing further environmental contamination, and for instituting responsible environmental management. While performing its tasks, EM found that many aspects of its large and complex mission could not be achieved using existing science and technology or without incurring unreasonable costs, risks, or schedule impacts. Consequently, a process was developed to solicit needs from around the DOE complex and focus the science and technology resources of EM-50, the National Laboratories, private industry, and colleges and universities on those needs. This document describes those needs that the Hanford Site has identified as requiring additional science or technology to complete.
Date: July 16, 1999
Creator: BERLIN, G.T.
Partner: UNT Libraries Government Documents Department

Impact of Aluminum on Anticipated Corrosion in a Flooded SNF Multi Canister Overpack (MCO)

Description: Corrosion reactions in a flooded MCO are examined to determine the impact of aluminum corrosion products (from aluminum basket grids and spacers) on bound water estimates and subsequent fuel/environment reactions during storage. The mass and impact of corrosion products were determined to be insignificant, validating the choice of aluminum as an MCO component and confirming expectations that no changes to the Technical Databook or particulate mass or water content are necessary.
Date: July 6, 1999
Creator: DUNCAN, D.R.
Partner: UNT Libraries Government Documents Department

HANSF 1.3 Users Manual FAI/98-40-R2 Hanford Spent Nuclear Fuel (SNF) Safety Analysis Model [SEC 1 and 2]

Description: The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.
Date: October 7, 1999
Creator: DUNCAN, D.R.
Partner: UNT Libraries Government Documents Department

Installation Instructions (ETN-98-0005) S-farm Overground Transfer (ogt) System Valve Pit 241-S-B to Valve Pit 241-S-D

Description: Lockheed Martin Hanford Corporation (LMHC) is providing an overground transfer (OGT) system for use in saltwell pumping of the 241-S-Tank Farm. Fluor Daniel Northwest (FDNW) was requested to support the effort by completing the design of the OGT system and completing the construction of the encasement pipe and encasement pipe support system. FDNW will also install the concrete shielding blocks for the OGT system. The shielding block system will provide a vehicle barrier for protection of the OGT line and will provide a radiation barrier for operations personnel. LMHC is responsible for the regulatory compliance of the entire transfer system. This installation instruction covers the encasement piping, pipe supports, heat tracing, thermal insulation, leak detectors, temperature indicators, and the shielding blocks. Installation of the primary (inner) pipe and associated equipment was completed at a previous time and the integrity of the primary piping will be confirmed by LMHC prior to operation of the system.
Date: August 25, 1999
Creator: HICKS, D.F.
Partner: UNT Libraries Government Documents Department

Interface Control Document between the Double Shell Tanks (DST) System and T Plant

Description: This Interface Control Document (ICD) describes the interface between the Double-Shell Tank (DST) System and T Plant. T Plant generates waste during decontamination activities. These facilities do not have a direct physical interface since the waste will be moved by tank trailer to the 204-AR waste unloading facility. The purpose of the ICD process is to formalize working agreements between the River Protection Project (WP) DST System and organization/companies internal and external to RPP. This ICD has been developed as part of the requirements basis for design of the DST System to support the Phase I Privatization effort.
Date: November 5, 1999
Creator: MAY, T.H.
Partner: UNT Libraries Government Documents Department

IWTS metal-water reaction rate evaluation (Fauske and Associates report 99-26)

Description: The report presents a thermal stability analysis of partially metallic particulate in two IWTS components, the knock out pot and settlers. Particulate in the knock out pot is thermally stable for combinations of average particle size and metal mass fraction which appear realistic. Particulate in the settlers is thermally stable when a realistic account of particle reactions over time, metal fraction, and size distribution is considered.
Date: July 29, 1999
Creator: DUNCAN, D.R.
Partner: UNT Libraries Government Documents Department

Letter Report (ETN-98-0005) S-farm Overground Transfer (OGT) Line Design Comparison and BIO Evaluation

Description: This document provides an evaluation of the detailed design for the 2414 Overground Transfer (OGT) line between S-Farm valve pits 241-S-B and 2414-0. The evaluation compares the design calculations to the design features, the important assumptions, and the required controls for TWRS BIO representative accident scenarios.
Date: August 25, 1999
Creator: HICKS, D.F.
Partner: UNT Libraries Government Documents Department

Alternatives Generation Analysis Long Length Contaminated Equipment Removal System Storage

Description: The long length contaminated equipment was designed and built to aid in the remote removal and transport of highly radioactive, contaminated equipment from various locations in the tank farms to disposal. The equipment has been stored in an open lay-down yard area, exposed to the elements for the past year and a half. The possible alternatives available to provide shelter for the equipment are investigated.
Date: August 13, 1999
Creator: Boger, R. M.
Partner: UNT Libraries Government Documents Department

Alternatives Generation and Analysis for Heat Removal from High Level Waste Tanks

Description: This document addresses the preferred combination of design and operational configurations to provide heat removal from high-level waste tanks during Phase 1 waste feed delivery to prevent the waste temperature from exceeding tank safety requirement limits. An interim decision for the preferred method to remove the heat from the high-level waste tanks during waste feed delivery operations is presented herein.
Date: June 15, 2000
Creator: WILLIS, W.L.
Partner: UNT Libraries Government Documents Department

Analysis of Bracket Assembly for Diversion Box Leak Detector

Description: This Supporting Document Presents Structural and Stress Analysis of a Bracket Assembly for the diversion box leak detectors related to the Cross Site Transfer Project. The results show that the assembly meets the requirements for dead load and natural phenomena hazards loads (seismic and wind).
Date: August 19, 1999
Creator: ZIADA, H.H.
Partner: UNT Libraries Government Documents Department

Application of Seismic Design Requirements to Cold Vacuum Drying (CVD) Facility Structures and Systems and Components

Description: The methodology followed in assignment of Performance Class (PC) for Natural Phenomena Hazards (NPH) seismic loads for Cold Vacuum Drying Facility (CVDF) Structures, Systems and Components is defined. The loading definition associated with each PC and structure, system and component is then defined.
Date: November 15, 1999
Creator: CREA, B.A.
Partner: UNT Libraries Government Documents Department

Estimates of Particulate Mass in Multi Canister Overpacks (MCO)

Description: High, best estimate, and low values are developed for particulate inventories within MCO baskets that have been loaded with freshly cleaned fuel assemblies and scrap. These per-basket estimates are then applied to all anticipated MCO payload configurations to identify which configurations are bounding for each type of particulate. Finally the resulting bounding and nominal values for residual particulates are combined with corresponding values [from other documents] for particulates that may be generated by corrosion of exposed uranium after the fuel has been cleaned. The resulting rounded nominal estimate for a typical MCO after 40 years of storage is 8 kg. The estimate for a bounding total particulate case MCO is that it may contain up to 64 kg of particulate after 40 years of storage.
Date: February 16, 2000
Creator: Sloughter, J. P.
Partner: UNT Libraries Government Documents Department

Evaluation of Flygt Propeller Xixers for Double Shell Tank (DST) High Level Waste Auxiliary Solids Mobilization

Description: The River Protection Project (RPP) is planning to retrieve radioactive waste from the single-shell tanks (SST) and double-shell tanks (DST) underground at the Hanford Site. This waste will then be transferred to a waste treatment plant to be immobilized (vitrified) in a stable glass form. Over the years, the waste solids in many of the tanks have settled to form a layer of sludge at the bottom. The thickness of the sludge layer varies from tank to tank, from no sludge or a few inches of sludge to about 15 ft of sludge. The purpose of this technology and engineering case study is to evaluate the Flygt{trademark} submersible propeller mixer as a potential technology for auxiliary mobilization of DST HLW solids. Considering the usage and development to date by other sites in the development of this technology, this study also has the objective of expanding the knowledge base of the Flygt{trademark} mixer concept with the broader perspective of Hanford Site tank waste retrieval. More specifically, the objectives of this study delineated from the work plan are described.
Date: July 20, 2000
Creator: PACQUET, E.A.
Partner: UNT Libraries Government Documents Department

Evaluation of helium impurity impacts on Spent Nuclear Fuel project processes (OCRWM)

Description: This document identifies the types and quantities of impurities that may be present within helium that is introduced into multi-canister overpacks (MCO)s by various SNF Project facilities, including, but not limited to the Cold Vacuum Drying (CVD) Facility (CVDF). It then evaluates possible impacts of worst case impurity inventories on MCO drying, transportation, and storage processes. Based on the evaluation results, this document: (1) concludes that the SNF Project helium procurement specification can be a factor-of-ten less restrictive than a typical vendor's standard offering (99.96% pure versus the vendor's 99.997% pure standard offering); (2) concludes that the CVDF's current 99.5% purity requirement is adequate to control the quality of the helium that is delivered to the MCO by the plant's helium distribution system; and (3) recommends specific impurity limits for both of the above cases.
Date: September 21, 1999
Creator: SHERRELL, D.L.
Partner: UNT Libraries Government Documents Department

105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

Description: 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.
Date: November 4, 1999
Creator: Packer, M. J.
Partner: UNT Libraries Government Documents Department