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Initial single-shell tank retrieval system tank selection

Description: The Hanford Federal Facility Agreement and Consent Order (also known as the Tri-Party Agreement), established several milestones associated with the Initial Single-Shell Tank Retrieval System (ISSTRS). It also established that the scope of ISSTRS is the retrieval of a complete tank farm or an equivalent number of tanks. This study selected the single- shell tanks to be included in the ISSTRS work scope. This study determined that the ISSTRS work scope should consist of four tanks located in the A, AX, and C, tank farms. One of the tanks (Tank 241-AX-103) will be a salt cake retrieval demonstration tank. The other three (Tanks 241 -A-1 02, 241 -C-1 03, and 241-C-105) are 100-series tanks containing high interim storage risk, high long-term hazard waste and are assumed not to be leaking.
Date: October 24, 1996
Creator: Grenard, C.E.
Partner: UNT Libraries Government Documents Department

Demonstration of retrieval methods for Westinghouse Hanford Corporation October 20, 1995

Description: Westinghouse Hanford Corporation has been pursuing strategies to break up and retrieve the radioactive waste material in single shell storage tanks at the Hanford Nuclear Reservation, by working with non-radioactive ``saltcake`` and sludge material that simulate the actual waste. It has been suggested that the use of higher volumes of water than used in the past (10 gpm nozzles at 10,000 psi) might be successful in breaking down the hard waste simulants. Additionally, the application of these higher volumes of water might successfully be applied through commercially available tooling using methods similar to those used in the deslagging of large utility boilers. NMW Industrial Services, Inc., has proposed a trial consisting of three approaches each to dislodging both the solid (saltcake) simulant and the sludge simulant.
Date: October 1, 1996
Partner: UNT Libraries Government Documents Department

Issues associated with manipulator-based waste retrieval from Hanford underground storage tanks with a preliminary review of commercial concepts

Description: Westinghouse Hanford Company (WHC) is exploring commercial methods for retrieving waste from the underground storage tanks at the Hanford site in south central Washington state. WHC needs data on commercial retrieval systems equipment in order to make programmatic decisions for waste retrieval. Full system testing of retrieval processes is to be demonstrated in phases through September 1997 in support of programs aimed to Acquire Commercial Technology for Retrieval (ACTR) and at the Hanford Tanks Initiative (HTI). One of the important parts of the integrated testing will be the deployment of retrieval tools using manipulator-based systems. WHC requires an assessment of a number of commercial deployment systems that have been identified by the ACTR program as good candidates to be included in an integrated testing effort. Included in this assessment should be an independent evaluation of manipulator tests performed to date, so that WHC can construct an integrated test based on these systems. The objectives of this document are to provide a description of the need, requirements, and constraints for a manipulator-based retrieval system; to evaluate manipulator-based concepts and testing performed to date by a number of commercial organizations; and to identify issues to be resolved through testing and/or analysis for each concept.
Date: September 17, 1996
Creator: Berglin, E.J.
Partner: UNT Libraries Government Documents Department

Demonstration of retrieval methods for Westinghouse Hanford Corporation by EPW Industrial Services Incorporated, trial number 2, April 30, 1996

Description: Westinghouse Hanford Company has been pursuing strategies to break up and retrieve the radioactive waste material in single shell storage tanks at the Hanford Nuclear Reservation, by working with non-radioactive ``saltcake`` and sludge material that simulate the actual waste. Previous trials run by MPW for Westinghouse Hanford Company (report dated October 20, 1995) resulted in difficulty breaking up the simulant using three approaches, with pressures to I 0,000 psi and flow rates to 56 gpm. The saltcake sirnulant was extremely hard, with a tensile strength similar to concrete. Westinghouse Hanford proposed a second set of trials utilizing a range of four sirnulants to attempt to bracket the capability of the I 0,000 psi waterblast stream. This set of trials had one simulant similar to the soft sludge previously trialed, two similar to the hard saltcake but with a lower strength, and one with a coarse rock-salt in a saltcake matrix, which is quite low in strength. Under this proposal, MPW would attempt to dislodge the four different simulants us@@ng two methods, for a total of eight pans. Each pan would be 4-foot square x I- 1/2-foot deep. The approaches would be as follows: A. Rotary tooling approaching straight down, with two triangle nozzles, each at a nominal 12.5 gpm at I 0,000 psi, at a 45-degree angle. B. Straight in to the exposed edge of the material with an articulated ``water cannon`` -with a triangle nozzle rated at approximately 25 gpm.
Date: October 1, 1996
Partner: UNT Libraries Government Documents Department

A risk evaluation for the fuel retrieval sub-project

Description: This study reviews the technical, schedule and budget baselines of the sub-project to assure all significant issues have been identified on the sub-project issues management list. The issue resolution dates are identified and resolution plans established. Those issues that could adversely impact procurement activities have been uniquely identified on the list and a risk assessment completed.
Date: October 11, 1996
Creator: Carlisle, B.S.
Partner: UNT Libraries Government Documents Department

Hanford tanks initiative test facility functions and requirements

Description: This document presents the functions and requirements for a test facility for testing single-shell tank waste retrieval equipment and systems for the Hanford Tanks Initiative (HTI) project. This effort includes review of previous test facility functions and requirements and conducting a workshop to develop specific functions and requirements for HTI testing needs. Functions and requirements for testing future retrieval systems that follow HTI are also identified.
Date: March 1, 1997
Creator: Krieg, S.A., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Tank 241-C-106 waste retrieval sluicing system (WRSS) sluicer assembly test reports

Description: The sluicer test report documents the results of the Project W-320 factory testing conducted at the Olympic Tool and Engineering facility. Included are background information, test goals, a brief discussion on the sluicer hose problem, and conclusions.
Date: August 26, 1996
Creator: May, T.H., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

TANK SPACE OPTIONS REPORT

Description: Since this report was originally issued in 2001, several options proposed for increasing double-shell tank (DST) storage space were implemented or are in the process of implementation. Changes to the single-shell tank (SST) waste retrieval schedule, completion of DST space saving options, and the DST space saving options in progress have delayed the projected shortfall of DST storage space from the 2007-2011 to the 2018-2025 timeframe (ORP-11242, River Protection Project System Plan). This report reevaluates options from Rev. 0 and includes evaluations of new options for alleviating projected restrictions on SST waste retrieval beginning in 2018 because of the lack of DST storage space.
Date: August 11, 2009
Creator: WL, WILLIS & MR, AHRENDT
Partner: UNT Libraries Government Documents Department

Improving sample recovery

Description: This Engineering Task Plan (ETP) describes the tasks, i.e., tests, studies, external support and modifications planned to increase the recovery of the recovery of the waste tank contents using combinations of improved techniques, equipment, knowledge, experience and testing to better the recovery rates presently being experienced.
Date: September 1995
Creator: Blanchard, R. J.
Partner: UNT Libraries Government Documents Department

Project W-320, 241-C-106 sluicing: Piping calculations. Volume 2

Description: This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable. The objectives of this calculation are (1) To perform static and Safety Class 2 dynamic stress analysis of the Slurry and Supernate Process (inner) piping connecting Tanks 241-C-106 and 241-AY-102 in order to be in compliance with the Code requirements; (2) To assure the thermal expansion of the process pipe not be strained by the outer encasement pipe; and (3) To furnish process pipe support to the Civil Engineering group.
Date: July 25, 1998
Creator: Bailey, J.W.
Partner: UNT Libraries Government Documents Department

Characterization of Hanford K basin spent nuclear fuel and sludge

Description: A characterization plan was prepared to support the Integrated Process Strategy (IPS) for resolution of the safety and environmental concerns associated with the deteriorating Spent Nuclear Fuel (SNF) stored in the Hanford Site K Basins. This plan provides the structure and logic and identifies the information needs to be supported by the characterization activities. The IPS involves removal of the fuel elements from the storage canister and placing them in a container, i.e., Multiple Canister Overpack (MCO) capable of holding multiple tiers of baskets full of fuel. The MCOs will be vacuum dried to remove free water and shipped to the Container Storage Building (CSB) where they will be staged waiting for hot vacuum conditioning. The MCO will be placed in interim storage in the CSB following conditioning and disposition.
Date: March 13, 1996
Creator: Lawrence, L.A.
Partner: UNT Libraries Government Documents Department

Sampling and analysis of sludge from the Hanford K East basin

Description: Sludge samples from the floor of the Hanford K East Basin fuel storage pool has been retrieved and analyzed. Both chemical and physical properties have been determined. The results are to be used to determine the disposition of the bulk of the sludge and possibly assess the impact of residual sludge on dry storage of the associated intact metallic uranium fuel elements.
Date: March 13, 1996
Creator: Makenas, B. J.
Partner: UNT Libraries Government Documents Department

Project W-320, 241-C-106 sluicing HVAC calculations, Volume 1

Description: This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following calculations: Exhaust airflow sizing for Tank 241-C-106; Equipment sizing and selection recirculation fan; Sizing high efficiency mist eliminator; Sizing electric heating coil; Equipment sizing and selection of recirculation condenser; Chiller skid system sizing and selection; High efficiency metal filter shielding input and flushing frequency; and Exhaust skid stack sizing and fan sizing.
Date: August 7, 1998
Creator: Bailey, J.W.
Partner: UNT Libraries Government Documents Department

Single Shell Tank (SST) Retrieval Sequence FY 2000 Update

Description: This document describes the baseline single-shell tank (SST) waste retrieval sequence for the River Protection Project (RPP) updated for Fiscal Year 2000. The SST retrieval sequence identifies the proposed retrieval order (sequence), the tank selection and prioritization rationale, and planned retrieval dates for Hanford SSTs. In addition, the tank selection criteria and reference retrieval method for this sequence are discussed.
Date: September 27, 2000
Creator: Garfield, J. S.
Partner: UNT Libraries Government Documents Department

Tank waste remediation system retrieval and disposal mission waste feed delivery plan

Description: This document is a plan presenting the objectives, organization, and management and technical approaches for the Waste Feed Delivery (WFD) Program. This WFD Plan focuses on the Tank Waste Remediation System (TWRS) Project`s Waste Retrieval and Disposal Mission.
Date: January 8, 1998
Creator: Potter, R.D.
Partner: UNT Libraries Government Documents Department

Development of design basis capacity for SNF project systems

Description: An estimate of the design capacity for Spent Nuclear Fuel Project systems producing Multi-Canister Overpacks is developed based on completing fuel processing in a two year period. The design basis capacity for systems relates the desired annual processing rate to potential operating inefficiencies which may be actually experienced to project a design capacity for systems. The basis for estimating operating efficiency factors is described. Estimates of the design basis capacity were limited to systems actually producing the Multi-Canister Overpack. These systems include Fuel Retrieval, K Basin SNF Vacuum Drying, Canister Storage Building support for Staging and Storage, and Hot Vacuum conditioning. The capacity of other systems are assumed to be derived from these system capacities such that systems producing a Multi-Canister Overpack are not constrained.
Date: February 27, 1996
Creator: Pajunen, A.L.
Partner: UNT Libraries Government Documents Department

Project W-320, 241-C-106 sluicing HVAC calculations, Volume 4

Description: This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following design calculations: Cooling load in pump pit 241-AY-102; Pressure relief seal loop design; Process building piping stress analysis; Exhaust skid maximum allowable leakage criteria; and Recirculation heat, N509 duct requirements.
Date: July 30, 1998
Creator: Bailey, J.W.
Partner: UNT Libraries Government Documents Department

Spent Nuclear Fuel Project operational staffing plan

Description: Using the Spent Nuclear Fuel (SNF) Project`s current process flow concepts and knowledge from cognizant engineering and operational personnel, an initial assessment of the SNF Project radiological exposure and resource requirements was completed. A small project team completed a step by step analysis of fuel movement in the K Basins to the new interim storage location, the Canister Storage Building (CSB). This analysis looked at fuel retrieval, conditioning of the fuel, and transportation of the fuel. This plan describes the staffing structure for fuel processing, fuel movement, and the maintenance and operation (M&O) staffing requirements of the facilities. This initial draft does not identify the support function resources required for M&O, i.e., administrative and engineering (technical support). These will be included in future revisions to the plan. This plan looks at the resource requirements for the SNF subprojects, specifically, the operations of the facilities, balances resources where applicable, rotates crews where applicable, and attempts to use individuals in multi-task assignments. This plan does not apply to the construction phase of planned projects that affect staffing levels of K Basins.
Date: March 1, 1996
Creator: Debban, B.L.
Partner: UNT Libraries Government Documents Department

Operational tank leak detection and minimization during retrieval

Description: This report evaluates the activities associated with the retrieval of wastes from the single-shell tanks proposed under the initial Single-Shell Tank Retrieval System. This report focuses on minimizing leakage during retrieval by using effective leak detection and mitigating actions. After reviewing the historical data available on single-shell leakage, and evaluating current leak detection technology, this report concludes that the only currently available leak detection method which can function within the most probable leakage range is the mass balance system. If utilized after each sluicing campaign, this method should allow detection at a leakage value well below the leakage value where significant health effects occur which is calculated for each tank. Furthermore, this report concludes that the planned sequence or sluicing activities will serve to further minimize the probability and volume of leaks by keeping liquid away from areas with the greatest potential for leaking. Finally, this report identifies a series of operational responses which when used in conjunction with the recommended sluicing sequence and leak detection methods will minimize worker exposure and environmental safety health risks.
Date: March 1, 1996
Creator: Hertzel, J.S.
Partner: UNT Libraries Government Documents Department

60-day waste compatibility safety issue and final results for 244-TX DCRT, grab samples TX-95-1, TX-95-2, and TX-95-3

Description: Three grab samples (TX-95-1, TX-95-2, and TX-95-3) were taken from tank 241- TX-244 riser 8 on November 7, 1995 and received by the 222-S Laboratory on that same day. Samples TX-95-1 and TX-95-2 were designated as supernate liquids, and sample TX-95-3 was designated as a supernate/sludge. These samples were analyzed to support the waste compatibility safety program. Accuracy and precision criteria were met for all analyses. No notifications were required based on sample results. This document provides the analysis to support the waste compatibility safety program.
Date: January 1, 1996
Creator: Esch, R.A.
Partner: UNT Libraries Government Documents Department