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CSER 97-001 Criticality safety limits for PFP 26-inch vacuum lineremoval

Description: As part of the plutonium stabilization operations in the 234-5Z Building, several runs of 26-inch (26 inches of Hg) process vacuum header, along with associated smaller piping is to be cut into sections and disposed of. This criticality safety evaluation report (CSER) requested by Nirider (1996) addresses the removal of several hundred feet of abandoned 3 and 4 inch nominal diameter vacuum header and associated smaller diameter piping runs located in the duct level of the 234-5Z Building in rooms 262, 263, and 264 as shown in the two attached drawings.
Date: February 14, 1997
Creator: Himes, D. A.
Partner: UNT Libraries Government Documents Department

Testing of sludge coating adhesiveness on fuel elements in 105-K west basin

Description: This report summarizes the results from the first sludge adherence tests performed in the 105-K West Basin on N Reactor fuel. The outside surface of the outer fuel elements were brushed, using stainless steel wire brushes, to test the adhesiveness of various types of sludge coatings to the cladding`s surface. The majority of the sludge was removed by the wire brushes in this test but different types of sludge were more adhesive than others. Particularly, an orange rust-like sludge coating that was just slightly more adherent to the fuel`s cladding than the majority of the sludge coatings and a thick white vertical strip sludge coating that was much more difficult to remove. The test demonstrated that all of the sludge could be removed from the outer fuel elements` surfaces if the need arises.
Date: March 11, 1997
Creator: Maassen, D.P., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Engineering report (conceptual design) PFP solution stabilization

Description: This Engineering Report (Conceptual Design) addresses remediation of the plutonium-bearing solutions currently in inventory at the Plutonium Finishing Plant (PFP). The recommendation from the Environmental Impact Statement (EIS) is that the solutions be treated thermally and stabilized as a solid for long term storage. For solutions which are not discardable, the baseline plan is to utilize a denitration process to stabilize the solutions prior to packaging for storage.
Date: July 17, 1997
Creator: Witt, J. B.
Partner: UNT Libraries Government Documents Department

High priority tank sampling and analysis report

Description: In July 1993, the Defense Nuclear Facilities Board issued Recommendation 93-5 (Conway 1993) which noted that there was insufficient tank waste technical information and the pace to obtain it was too slow to ensure that Hanford Site wastes could be safely stored, that associated operations could be conducted safely, and that future disposal data requirements could be met. In response, the US Department of Energy, in May 1996, issued Revision 1 of the Recommendation 93-5 Implementation Plan (DOE-RL 1996). The Implementation Plan presented a modified approach to achieve the original plan`s objectives, concentrating on actions necessary to ensure that wastes can be safely stored, that operations can be safely conducted, and that timely characterization information for the tank waste Disposal Program could be obtained. The Implementation Plan proposed 28 High Priority tanks for near term core sampling and analysis, which along with sampling and analysis of other non-High Priority tanks, could provide the scientific and technical data to confirm assumptions, calibrate models, and.measure safety related phenomenology of the waste. When the analysis results of the High Priority and other-tank sampling were reviewed, it was expected that a series of 12 questions, 9 related to safety issues and 3 related to planning for the disposal process, should be answered allowing key decisions to be made. This report discusses the execution of the Implementation Plan and the results achieved in addressing the questions. Through sampling and analysis, all nine safety related questions have been answered and extensive data for the three disposal planning related questions have been collected, allowing for key decision making. Many more tanks than the original 28 High Priority tanks identified in the Implementation Plan were sampled and analyzed. Twenty-one High Priority tanks and 85 other tanks were core sampled and used to address the questions. Thirty-eight additional tanks ...
Date: March 24, 1998
Creator: Brown, T.M.
Partner: UNT Libraries Government Documents Department

Tank 241-Z-361 process and characterization history

Description: An Unreviewed Safety Question (Wagoner, 1997) was declared based on lack of adequate authorization basis for Tank 241-Z-361 in the 200W Area at Hanford. This document is a summary of the history of Tank 241-Z-361 through December 1997. Documents reviewed include engineering files, laboratory notebooks from characterization efforts, waste facility process procedures, supporting documents and interviews of people`s recollections of over twenty years ago. Records of transfers into the tank, past characterization efforts, and speculation were used to estimate the current condition of Tank 241-Z-361 and its contents. Information about the overall waste system as related to the settling tank was included to help in understanding the numbering system and process relationships. The Plutonium Finishing Plant was built in 1948 and began processing plutonium in mid-1949. The Incinerator (232-Z) operated from December 1961 until May 1973. The Plutonium Reclamation Facility (PRF, 236-Z) began operation in May 1964. The Waste Treatment Facility (242-Z) operated from August 1964 until August 1976. Waste from some processes went through transfer lines to 241-Z sump tanks. High salt and organic waste under normal operation were sent to Z-9 or Z-18 cribs. Water from the retention basin may have also passed through this tank. The transfer lines to 241-Z were numbered D-4 to D-6. The 241-Z sump tanks were numbered D-4 through D-8. The D-4, 5, and 8 drains went to the D-6 sump tank. When D-6 tank was full it was transferred to D-7 tank. Prior to transfer to cribs, the D-7 tank contents was sampled. If the plutonium content was analyzed to be more than 10 g per batch, the material was (generally) reprocessed. Below the discard limit, caustic was added and the material was sent to the cribs via the 241-Z-361 settling tank where solids settled out and the liquid overflowed by gravity ...
Date: August 6, 1998
Creator: Jones, S.A.
Partner: UNT Libraries Government Documents Department

Tank characterization report for single-shell tank 241-BY-112

Description: This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-112. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated a Ferrocyanide Watch List tank.)
Date: August 22, 1997
Creator: Baldwin, J.H.
Partner: UNT Libraries Government Documents Department

System maintenance verification and validation plan for the TWRS controlled baseline database system

Description: TWRS Controlled Baseline Database, formally known as the Performance Measurement Control System, is used to track and monitor TWRS project management baseline information. This document contains the verification and validation approach for system documentation changes within the database system.
Date: September 23, 1998
Creator: Spencer, S.G.
Partner: UNT Libraries Government Documents Department

Scoping assessment on medical isotope production at the Fast Flux Test Facility

Description: The Scoping Assessment addresses the need for medical isotope production and the capability of the Fast Flux Test Facility to provide such isotopes. Included in the discussion are types of isotopes used in radiopharmaceuticals, which types of cancers are targets, and in what way isotopes provide treatment and/or pain relief for patients.
Date: August 29, 1997
Creator: Scott, S.W.
Partner: UNT Libraries Government Documents Department

Acceptance test report for the Tank 241-C-106 in-tank imaging system

Description: This document presents the results of Acceptance Testing of the 241-C-106 in-tank video camera imaging system. The purpose of this imaging system is to monitor the Project W-320 sluicing of Tank 241-C-106. The objective of acceptance testing of the 241-C-106 video camera system was to verify that all equipment and components function in accordance with procurement specification requirements and original equipment manufacturer`s (OEM) specifications. This document reports the results of the testing.
Date: May 22, 1998
Creator: Pedersen, L.T.
Partner: UNT Libraries Government Documents Department

Vapor and gas sampling of single-shell tank 241-U-104 using the in situ vapor sampling system

Description: The Vapor Issue.Resolution Program tasked the Vapor Team (VT) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-U-104. This document presents In Situ Vapor Sampling System (ISVS) data resulting from the July 16, 1996 sampling of SST 241-U-104. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory (PNNL) which supplied and analyzed the sample media.
Date: August 5, 1997
Creator: Lockrem, L.L.
Partner: UNT Libraries Government Documents Department

Sampling and analysis plan (SAP) for WESF drains and TK-100 sump

Description: The intent of this project is to determine whether the Waste Encapsulation and Storage Facility (WESF) floor drain piping and the TK-100 sump are free from contamination. TK-100 is currently used as a catch tank to transfer low level liquid waste from WESF to Tank Farms via B Plant. This system is being modified as part of the WESF decoupling since B Plant is being deactivated. As a result of the 1,1,1-trichloroethane (TCA) discovery in TK-100, the associated WESF floor drains and the pit sump need to be sampled. Breakdown constituents have been reviewed and found to be non-hazardous. There are 29 floor drains that tie into a common header leading into the tank. To prevent high exposure during sampling of the drains, TK-100 will be removed into the B Plant canyon and a new tank will be placed in the pit before any floor drain samples are taken. The sump will be sampled prior to TK-100 removal. A sample of the sludge and any liquid in the sump will be taken and analyzed for TCA and polychlorinated biphenyl (PCB). After the sump has been sampled, the vault floor will be flushed. The flush will be transferred from the sump into TK-100. TK-100 will be moved into B Plant. The vault will then be cleaned of debris and visually inspected. If there is no visual indication of TCA or PCB staining, the vault will be painted and a new tank installed. If there is an indication of TCA or PCB from laboratory analysis or staining, further negotiations will be required to determine a path forward. A total of 8 sets of three 40ml samples will be required for all of the floor drains and sump. The sump set will include one 125ml solid sample. The only analysis required will be ...
Date: May 14, 1998
Creator: Simmons, F.M.
Partner: UNT Libraries Government Documents Department

Hanford site tank waste remediation system programmatic environmental review report

Description: The US Department of Energy (DOE) committed in the Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS) Record of Decision (ROD) to perform future National Environmental Policy Act (NEPA) analysis at key points in the Program. Each review will address the potential impacts that new information may have on the environmental impacts presented in the TWRS EIS and support an assessment of whether DOE`s plans for remediating the tank waste are still pursuing the appropriate plan for remediation or whether adjustments to the program are needed. In response to this commitment, DOE prepared a Supplement Analysis (SA) to support the first of these reevaluations. Subsequent to the completion of the SA, the Phase IB negotiations process with private contractors resulted in several changes to the planned approach. These changes along with other new information regarding the TWRS Program have potential implications for Phase 1 and Phase 2 of tank waste retrieval and waste storage and/or disposal that may influence the environmental impacts of the Phased Implementation alternative. This report focuses on identifying those potential environmental impacts that may require NEPA analysis prior to authorization to begin facility construction and operations.
Date: September 3, 1998
Creator: Haass, C.C.
Partner: UNT Libraries Government Documents Department

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

Description: This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.
Date: December 30, 1997
Creator: Pickett, W.W.
Partner: UNT Libraries Government Documents Department

Tank 241-AP-108 grab sampling and analysis plan

Description: This Sampling and Analysis Plan (SAP) will identify characterization objectives for sample collection, laboratory analytical evaluation, and reporting requirements for tank 241-AP-108 (AP 108). It is written in accordance with the Tank 241-AP-108 Tank Characterization Plan, the Tank Safety Screening Data Quality Objective, the 242-A Evaporator Liquid Effluent Retention Facility Data Quality Objectives, and the Data Quality Objectives for Tank Farms Waste Compatibility Program.
Date: February 7, 1997
Creator: Baldwin, J.H., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Life-cycle cost and impacts: alternatives for managing KE basin sludge

Description: This document presents the results of a life-cycle cost and impacts evaluation of alternatives for managing sludge that will be removed from the K Basins. The two basins are located in the 100-K Area of the Hanford Site. This evaluation was conducted by Fluor Daniel Hanford, Inc. (FDH) and its subcontractors to support decisions regarding the ultimate disposition of the sludge. The long-range plan for the Hanford Site calls for spent nuclear fuel (SNF), sludge, debris, and water to be removed from the K East (KE) and K West (KW) Basins. This activity will be conducted as a removal action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The scope of the CERCLA action will be limited to removing the SNF, sludge, debris, and water from the basins and transferring them to authorized facilities for interim storage and/or treatment and disposal. The scope includes treating the sludge and water in the 100-K Area prior to the transfer. Alternatives for the removal action are evaluated in a CERCLA engineering evaluation/cost analysis (EE/CA) and include different methods for managing sludge from the KE Basins. The scope of the removal action does not include storing, treating, or disposing of the sludge once it is transferred to the receiving facility and the EE/CA does not evaluate those downstream activities. This life-cycle evaluation goes beyond the EE/CA and considers the full life-cycle costs and impacts of dispositioning sludge.
Date: June 27, 1997
Creator: Alderman, C.J.
Partner: UNT Libraries Government Documents Department

Design requirements document for the phase 1 privatization electrical power system

Description: The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV distribution system inside the privatization facilities site boundaries is the responsibility of the privatization contract.
Date: October 29, 1997
Creator: Singh, G.
Partner: UNT Libraries Government Documents Department

High heat program, thermal hydraulic computer models

Description: The purpose of this report is to describe the thermal hydraulic computer models, the computer model benchmarking and methodology to be used in performing the analysis necessary for the resolution of the high heat safety issue for Tank 241-C, -106.
Date: March 5, 1998
Creator: Ogden, D.M.
Partner: UNT Libraries Government Documents Department

Management self assessment plan

Description: Duke Engineering and Services Hanford Inc., Spent Nuclear Fuel Project is responsible for the operation of fuel storage facilities. The SNF project mission includes the safe removal, processing and transportation of Spent Nuclear Fuel from 100 K Area fuel storage basins to a new Storage facility in the Hanford 200 East Area. Its mission is the modification of the 100 K area fuel storage facilities and the construction of two new facilities: the 100 K Area Cold Vacuum Drying Facility, and the 200 East Area Canister Storage Building. The management self assessment plan described in this document is scheduled to begin in April of 1999 and be complete in May of 1999. The management self assessment plan describes line management preparations for declaring that line management is ready to commence operations.
Date: January 30, 1998
Creator: Debban, B. L.
Partner: UNT Libraries Government Documents Department

Grouting guidelines for Hanford Tanks Initiative cone penetrometer borings

Description: Grouting of an open cone penetrometer (CP) borehole is done to construct a barrier that prevents the vertical migration of fluids and contaminants between geologic units and aquifers intersected by the boring. Whether to grout, the types of grout, and the method of deployment are functions of the site-specific conditions. This report recommends the strategy that should be followed both before and during HTI [Hanford Tanks Initiative] CP deployment to decide specific borehole grouting needs at Hanford SST farms. Topics discussed in this report that bear on this strategy include: Regulatory guidance, hydrogeologic conditions, operational factors, specific CP grouting deployment recommendations.
Date: May 18, 1998
Creator: Iwatate, D.F.
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

ENRAF gauge reference level calculations

Description: This document describes the method for calculating reference levels for Enraf Series 854 Level Detectors as installed in the tank farms. The reference level calculation for each installed level gauge is contained herein.
Date: February 6, 1997
Creator: Huber, J.H., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

221-U Facility concrete and reinforcing steel evaluations specification for the canyon disposition initiative (CDI)

Description: This describes a test program to establish the in-situ material properties of the reinforced concrete in Building 221-U for comparison to the original design specifications. Field sampling and laboratory testing of concrete and reinforcing steel structural materials in Building 221-U for design verification will be undertaken. Forty seven samples are to be taken from radiologically clean exterior walls of the canyon. Laboratory testing program includes unconfined compressive strength of concrete cores, tensile strength of reinforcing steel, and petrographic examinations of concrete cores taken from walls below existing grade.
Date: May 28, 1998
Creator: Baxter, J.T.
Partner: UNT Libraries Government Documents Department

Historical tank content estimate for the southeast quadrant of the Hanford 200 area

Description: The Historical Tank Content Estimate for the Quadrant provides historical information on a tank-by-tank basis of the radioactive mixed wastes stored in the underground single-shell tanks for the Hanford 200 Areas. This report summarized historical information such as waste history, level history, temperature history, riser configuration, tank integrity, and inventory estimates on a tank- by-tank basis. Tank farm aerial photographs and interior tank montages are also provided for each tank. A description of the development of data for the document of the inventory estimates provided by Los Alamos National Laboratory are also given in this report.
Date: March 14, 1997
Creator: Brevick, C.H.; Stroup, J.L. & Funk, J.W., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department