2,102 Matching Results

Search Results

Advanced search parameters have been applied.

Chemical modeling of backfill composed of quartz sand, lime and an Fe-phase

Description: The area adjacent to the waste package is an important component of the engineered barrier system in a high level radioactive waste repository. The combination of lime, quartz sand, and a phase containing reduced iron is investigated whether it can achieve reduction of oxygen in the waste emplacement drift (thereby reducin corrosion rates) and increase the pH. The simulations conducted to date have examined the following backfill options: Fe metal only, Fe metal and lime, and iron metal/lime/quartz sand in equal volume ratios. Each option was simulated under two environments: limited and unlimited air exchange with the atmosphere. Results suggest that the most important variable during the process of chemical conditioning is the amount of air exchange that occurs in the emplacement drift. The desired chemical conditioing (both oxidation potential and pH) will be far less effective in an emplacement that experiences an unlimited exchange of air with the atmosphere.
Date: January 1, 1997
Creator: Meike, A. & Glassley, W.E.
Partner: UNT Libraries Government Documents Department

The Sort on Radioactive Waste Type Model: A method to sort single-shell tanks into characteristics groups

Description: The Sort on Radioactive Waste Type (SORWT) Model is a method to categorize Hanford Site single-shell tanks (SSTS) into groups of tanks expected to exhibit similar chemical and physical characteristics based on their major waste types and processing histories. The model has identified 24 different waste-type groups encompassing 133 of the 149 SSTs and 93% of the total waste volume in SSTS. The remaining 16 SSTs and associated wastes could not be grouped. according to the established criteria and were placed in an ungrouped category. A detailed statistical verification study has been conducted that employs analysis of variance (ANOVA) and the core sample analysis data collected since 1989. These data cover eight tanks and five SORWT groups. The verification study showed that these five SORWT groups are highly statistically significant; they represent approximately 10% of the total waste volume and 26% of the total sludge volume in SSTS. Future sampling recommendations based on the SORWT Model results include 32 core samples from 16 tanks and 18 auger samples from six tanks. Combining these data with the existing body of information will form the basis for characterizing 98 SSTs (66%). These 98 SSTs represent 78% of the total waste volume, 61% of the total sludge volume, and 88 % of the salt cake volume.
Date: February 1, 1995
Creator: Hill, J.G.; Anderson, G.S. & Simpson, B.C.
Partner: UNT Libraries Government Documents Department

Tank characterization report for single-shell tank 241-T-102

Description: A major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-T-102. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-T-102 waste; and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendixes. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. The most recent core sampling of tank 241-T-102 (March 1993) predated the existence of data quality objectives (DQOs). An assessment of the technical issues from the currently applicable DQOs was made using data from the 1993 push mode core sampling event, a July 1994 grab sampling event, and a May 1996 vapor flammability measurement. Historical information for tank 241-T-102, provided in Appendix A, includes surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge model. Appendix B contains further sampling and analysis data from the March 1993 push mode core sampling event and data from the grab sampling event in August 1994 and May 1996 vapor flammability measurement. Of the two push mode cores taken in March of 1993, cores ...
Date: June 24, 1997
Creator: Baldwin, J.H.
Partner: UNT Libraries Government Documents Department

Tank 241-C-106 sluicing project W-320 integrity assessment report

Description: This Integrity Assessment Report is prepared by ICF Kaiser Hanford Co. (ICFKH) for Westinqhouse Hanford Company (WHC), operations contractor and the Department of Energy (DOE), the system owner. It is a revision of the original report dated 10/26/94 (ICFKH Transmittal TR-W-320-295). The original project scope has been modified, necessitating with WAC-173-303-640.
Date: February 11, 1997
Creator: Symons, G.A., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Tank farm restoration and safe operation, project W-314, upgrade scope summary report

Description: This revision of the Project W-314 Upgrade Scope Summary Report (USSR) represents a refinement of the project scope and supporting justification from which the Conceptual Design Report (CDR) was developed. It defines the actual upgrades and provides traceability to the requirement or driver for the activity.
Date: January 8, 1997
Creator: Jacobson, R. W.
Partner: UNT Libraries Government Documents Department

Tank waste remediation system baseline tank waste inventory estimates for fiscal year 1995

Description: A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available.
Date: December 6, 1996
Creator: Shelton, L. W.
Partner: UNT Libraries Government Documents Department

Tank waste remediation system characterization project quality policies

Description: This quality plan describes the system used by Characterization Project management to achieve quality. This plan is comprised of eleven quality policies which, when taken together, form a management system deployed to achieve quality. This quality management system is based on the customer`s quality requirements known as the `RULE`, 10 CFR 830.120, Quality Assurance.
Date: September 24, 1997
Creator: Board, D. C.
Partner: UNT Libraries Government Documents Department

Tank 241-BY-107, Cores 151 and 161, Analytical Results for the 45 day report

Description: This document is the 45-day laboratory report for tank 241-BY-107. Push mode core segments were removed from risers 8 and 9B between June 5, 1996, and July 26, 1996. Segments were received and extruded at the 222-S Analytical Laboratory. Analyses were performed in accordance with Tank 241-BY-107 Push Mode Core Sampling and analysis Plan (TSAP) and the Safety Screening Data Quality Objective (DQO). None of the subsamples submitted for Total Alpha Activity (AT) analysis or Differential Scanning Calorimetry (DSC) exceeded the notification limits as stated in the DQO. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Primary safety screening results are included in the data summary table. The raw data from DSC and TGA analyses are included in this report.
Date: September 9, 1996
Creator: Fritts, L.L.
Partner: UNT Libraries Government Documents Department

Preliminary tank characterization report for single-shell tank 241-TX-101: best-basis inventory

Description: This document is a preliminary Tank Characterization Report (TCR). It only contains the current best-basis inventory (Appendix D) for single-shell tank 241-TX-101. No TCRs have been previously issued for this tank, and current core sample analyses are not available. The best-basis inventory, therefore, is based on an engineering assessment of waste type, process flowsheet data, early sample data, and/or other available information. The Standard Inventories of Chemicals and Radionuclides in Hanford Site Tank Wastes describes standard methodology used to derive the tank-by-tank best-basis inventories. This preliminary TCR will be updated using this same methodology when additional data on tank contents become available.
Date: September 2, 1997
Creator: Kupfer, M.J.
Partner: UNT Libraries Government Documents Department

Assessment groundwater monitoring plan for single shell tank waste management area B-BX-BY

Description: Single Shell Tank Waste Management Area B-BX-BY has been placed into groundwater quality assessment monitoring under interim-status regulations. This document presents background and an assessment groundwater monitoring plan to evaluate any impacts of risks/spills from these Single Shell Tanks in WMA B-BX-BY on groundwater quality.
Date: September 27, 1996
Creator: Caggiano, J.A.
Partner: UNT Libraries Government Documents Department

Tank characterization report for single-shell tank 241-C-110. Revision 1

Description: One of the major functions of the Tank Waste Remediation System (IWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-C-110. The objectives of this report are to use characterization data in response to technical issues associated with 241-C-110 waste and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Supporting data and information are contained in the appendixes. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. While only the results from recent sample events will be used to fulfill the requirements of the data quality objectives (DQOs), other information can be used to support or question conclusions derived from these results. Historical information for tank 241-C-110 are provided included surveillance information, records pertaining to waste transfers and tank operations, and1124 expected tank contents derived from a process knowledge model. The sampling events are listed, as well as sample data obtained before 1989. The results of the 1992 sampling events are also reported in the data package. The statistical analysis and numerical manipulation of data used in issue resolution are reported in Appendix C. Appendix D contains the evaluation to establish the best basis for the inventory estimate and the statistical analysis performed for this evaluation. A bibliography that resulted from an in-depth literature search of all known information sources applicable to tank 241-C-110 and its respective waste types is contained in Appendix E. The reports listed ...
Date: June 14, 1997
Creator: Benar, C.J.
Partner: UNT Libraries Government Documents Department

Flammable gas tank waste level reconciliation for 241-S-111

Description: Fluor Daniel Northwest (FDNW) was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 241-S-111. The trapped gas evaluation document states that Tank S-111 exceeds the 25% of the lower flammable-limit criterion, based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the Welty Report is the basis for this letter report. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unaccounted for surface level rise. From 1973 through 1980, the Welty Report tracked Tank S-111 transfers. This surface level increase is from an unknown source or is unaccounted for. Duke Engineering and Services Hanford and Lockheed Martin Hanford Corporation are interested in determining the validity of the unexplained surface level changes reported in the Welty Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unaccounted for surface level changes as shown in the Welty Report from 1973 through 1980. Tank S-111 initially received waste from REDOX in 1952, and after April 1974, primarily received processed waste slurry from the 242-S Evaporator/Crystallizer and transferred supernatant waste to Tank S-102. From the FDNW review and comparisons of the Welty Report versus other daily records for Tank S-111, FDNW determined that the majority of the time, the Welty Report is consistent with daily records. Surface level decreases that occurred following saltwell pumping were identified as unaccounted for decreases in the Welty Report, however they were probably a continued settlement caused by saltwell pumping of the interstitial liquids. Because the ...
Date: June 23, 1997
Creator: Brevick, C.H. & Gaddis, L.A.
Partner: UNT Libraries Government Documents Department

High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment corrective actions/compliance schedule approval report

Description: This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Corrective Actions/Compliance Schedule Approval Report for the subject facility, contains the corrective actions required to bring the facility into compliance as a result of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. These actions are delineated in the Compliance Schedule Approvals which also contain; noncompliances, risks, compensatory measures, schedules for corrective actions, justifications for approval, and resource impacts.
Date: September 30, 1996
Creator: Biebesheimer, E.
Partner: UNT Libraries Government Documents Department

High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment report

Description: This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Report for the subject facility, represents the results of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. It contains; compliance status, remedial actions, and an implementing manuals report linking S/RID elements to requirement source to implementing manual and section.
Date: September 30, 1996
Creator: Biebesheimer, E., Westinghouse Hanford Co.
Partner: UNT Libraries Government Documents Department

High level waste storage tanks 242-A evaporator S/RID phase II assessment report

Description: This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.
Date: September 27, 1996
Creator: Biebesheimer, E.
Partner: UNT Libraries Government Documents Department

Preliminary tank characterization report for single-shell tank 241-TX-108: best-basis inventory

Description: This document is a preliminary Tank Characterization Report (TCR). It only contains the current best-basis inventory (Appendix D) for single-shell tank 241-TX-108. No TCR has been previously issued for this tank, and current core sample analyses are not available. The best-basis inventory, therefore, is based on an engineering assessment of waste type, process flowsheet data, and/or other available information. The Standard Inventories of Chemicals and Radionuclides in Hanford Site Tank Wastes describes standard methodology used to derive the tank-by-tank best-basis inventories. This preliminary TCR will be updated using this same methodology when additional data on tank contents become available.
Date: August 26, 1997
Creator: Jo, J.
Partner: UNT Libraries Government Documents Department

Preliminary tank characterization report for single-shell tank 241-TX-113: best-basis inventory

Description: This document is a preliminary Tank Characterization Report (TCR). It only contains the current best-basis inventory (Appendix D) for single-shell tank 241-TX-113. No TCRs have been previously issued for this tank, and current core sample analyses are not available. The best-basis inventory, therefore, is based on an engineering assessment of waste type, process flowsheet data, early sample data, and/or other available information. The Standard Inventories of Chemicals and Radionuclides in Hanford Site Tank Wastes describes standard methodology used to derive the tank-by-tank best-basis inventories. This preliminary TCR will be updated using this same methodology when additional data on tank contents become available.
Date: August 26, 1997
Creator: Place, D.E.
Partner: UNT Libraries Government Documents Department

Calculation notes that support accident scenario and consequence determination of a waste tank criticality

Description: The purpose of this calculation note is to provide the basis for criticality consequences for the Tank Farm Safety Analysis Report (FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
Date: September 27, 1996
Creator: Crowe, R.D.
Partner: UNT Libraries Government Documents Department