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The X/Q values unit doses for spent nuclear fuel projects

Description: The purpose of this document is to provide a single referenceable document that provides the X/Qs for all the facilities in the spent nuclear fuel projects, and includes the bases for the X/Q calculations. The X/Q values for the nuclear fuel projects were calculated over the past several years. The values currently used in the nuclear fuel project were documented in letter reports and as attached to various PSEs and Safety Analysis documents. Therefore, there is a need to consolidate these docu… more
Date: May 14, 1997
Creator: Huang, C. H.
Partner: UNT Libraries Government Documents Department
open access

Tank characterization report for single-shell tank 241-C-104

Description: A major function of the Tank Waste Remediation System 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 appendices serve as the TCR for single-shell tank 241-C-104. The objectives of this report are: (1) to use characterization data in response to technical iss… more
Date: May 21, 1997
Creator: Baldwin, J. H.
Partner: UNT Libraries Government Documents Department
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Tank 241-BY-112, cores 174 and 177 analytical results for the final report

Description: Results from bulk density tests ranged from 1.03 g/mL to 1.86 g/mL. The highest bulk density result of 1.86 g/mL was used to calculate the solid total alpha activity notification limit for this tank (33.1 uCi/g), Total Alpha (AT) Analysis. Attachment 2 contains the Data Verification and Deliverable (DVD) Summary Report for AT analyses. This report summarizes results from AT analyses and provides data qualifiers and total propagated uncertainty (TPU) values for results. The TPU values are based … more
Date: May 6, 1997
Creator: Nuzum, J. L.
Partner: UNT Libraries Government Documents Department
open access

Structural evaluation of W-211 flexible receiver platforms and tank pit walls

Description: This document is a structural analysis of the Flexible Receiver Platforms and the tank-pit wall during removal of equipment and during a accidental drop of that equipment. The platform and the pit walls must withstand a accidental drop of a mixer and transfer pumps in specific pits in tanks 102-AP and 104-AP. A mixer pump will be removed from riser 11 in pit 2A on tank 241-AP-102. A transfer pump will be removed from riser 13 in pit 2D on tank 241-AP-102 and another transfer pump will be remove… more
Date: November 3, 1997
Creator: Shrivastava, H. P.
Partner: UNT Libraries Government Documents Department
open access

Effects of spray leak inside the 204-AR Waste Unloading Facility

Description: The purpose of this document is to investigate the effects of a spray leak inside the 204-AR Waste Unloading Facility. This analysis will provide information to be used in the revision of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The scope of work is to assess the impacts of the radiological and toxicological consequences if the 204-AR Waste Unloading Facility door remains open during a spray leak accident. The dimensions of the roll-up door on the Unloading … more
Date: May 19, 1997
Creator: Huang, C.
Partner: UNT Libraries Government Documents Department
open access

Historical basis for analog input setpoints, 241-AY and 241-AZ tank farm MICON automation system

Description: This document describes the original basis for selection of the analog input setpoints for the MICON Automation System. In most cases the setpoints were based on vendor supplied information and design requirements. However, some setpoints were also established based on engineering judgment. These setpoints are subject to change as more experience with operation of the ventilation system is obtained. Revision 1 incorporates minor changes to ensure the document setpoints accurately reflect limits… more
Date: December 8, 1997
Creator: Bragg, D. A.
Partner: UNT Libraries Government Documents Department
open access

Tank 241-AP-107, grab samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 analytical results for the final report

Description: This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (T… more
Date: December 22, 1997
Creator: Steen, F. H.
Partner: UNT Libraries Government Documents Department
open access

Tank 241-Z-361 process and characterization history

Description: 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 20 plus years ago. Records of transfers into the tank, past characterization efforts, and speculation will be used to estimate the current condition of Tank 241-Z-361 and its contents.
Date: December 23, 1997
Creator: Jones, S. A.
Partner: UNT Libraries Government Documents Department
open access

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

Description: The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to charac… more
Date: October 7, 1997
Creator: Hladek, K. L.
Partner: UNT Libraries Government Documents Department
open access

Postirradiation Testing Laboratory (327 Building)

Description: A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revi… more
Date: May 28, 1997
Creator: Kammenzind, D. E.
Partner: UNT Libraries Government Documents Department
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Safety evaluation for packaging (onsite) SERF cask

Description: This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-… more
Date: October 24, 1997
Creator: Edwards, W. S.
Partner: UNT Libraries Government Documents Department
open access

Thermocouple module halt failure acceptance test procedure for Tank 241-SY-101 DACS-1

Description: The readiness of the Tank 241-SY-101 Data Acquisition and Control System (DACS-1) to provide monitoring and alarms for a halt failure of any thermocouple module will be tested during the performance of this procedure. Updated DACS-1 ``1/0 MODULE HEALTH STATUS``, ``MININ1``, and ``MININ2`` screens, which now provide indication of thermocouple module failure, will also be tested as part of this procedure.
Date: December 9, 1997
Creator: Ermi, A. M.
Partner: UNT Libraries Government Documents Department
open access

Design review report for the Hanford K East and K West Basins MCO loading system

Description: This design report presents the final design of the MCO Loading System. The report includes final design drawings, a system description, failure modes and recovery plans, a system operational description, and stress analysis. Design comments from the final design review have been incorporated.
Date: October 28, 1997
Creator: Brisbin, S. A.
Partner: UNT Libraries Government Documents Department
open access

Tank 241-AX-101 grab samples 1AX-97-1 through 1AX-97-3 analytical results for the final report

Description: This document is the final report for tank 241-AX-101 grab samples. Four grab samples were collected from riser 5B on July 29, 1997. Analyses were performed on samples 1AX-97-1, 1AX-97-2 and 1AX-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Miller, 1997). The analytical results are presented in Table 1. No notification limits were exceeded… more
Date: November 13, 1997
Creator: Esch, R. A.
Partner: UNT Libraries Government Documents Department
open access

WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

Description: On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table… more
Date: November 24, 1997
Creator: Leist, K. J.
Partner: UNT Libraries Government Documents Department
open access

Waste Certification Program Plan for Oak Ridge National Laboratory. Revision 1

Description: This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of… more
Date: May 1, 1997
Creator: Orrin, R. C.
Partner: UNT Libraries Government Documents Department
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200-Area plateau inactive miscellaneous underground storage tanks locations

Description: Fluor Daniel Northwest (FDNW) has been tasked by Lockheed Martin Hanford Corporation (LMHC) to incorporate current location data for 64 of the 200-Area plateau inactive miscellaneous underground storage tanks (IMUST) into the centralized mapping computer database for the Hanford facilities. The IMUST coordinate locations and tank names for the tanks currently assigned to the Hanford Site contractors are listed in Appendix A. The IMUST are inactive tanks installed in underground vaults or buried… more
Date: December 1, 1997
Creator: Brevick, C. H.
Partner: UNT Libraries Government Documents Department
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Technical safety requirements (TSR) for waste receiving and processing (WRAP) facility

Description: The scope of this TSR document is based on the WRAP Final Safety Analysis Report (HNF-SD-W026-SAR-002) and supporting documents. The administrative controls set forth in this TSR document are derived from the WRAP Final Safety Analysis Report.
Date: November 18, 1997
Creator: Weidert, J. R.
Partner: UNT Libraries Government Documents Department
open access

Calculation of dose rates during replacement of the 3CL seal tube in the FFTF IEM cell

Description: In September 1996, the seal tube at the 3CL window of the Interim Examination and Maintenance (IEM) Cell at the Fast Flux Test Facility (FFTF) failed. Replacement of the seal tube required removing the 3CL master slave manipulator (MSM) and shielding creating a streaming path for radiation from irradiated fuel and activated hardware in the IEM Cell. As a part of the preparation for the seal tube replacement, expected dose rates in the IEM Cell gallery outside the open 3CL penetration during the… more
Date: November 12, 1997
Creator: Nelson, J. V.
Partner: UNT Libraries Government Documents Department
open access

DMS test summary report for the WRAP facility

Description: This report documents the functional and integration testing process performed to verify functionality of the Release 1.1, Release 2.0, Release 3.0 and Release 3.1 software for the Waste Receiving and Processing Facility (WRAP) Data Management Systems (DMS) Release 2.
Date: November 4, 1997
Creator: Weidert, J. R.
Partner: UNT Libraries Government Documents Department
open access

Cold vacuum drying residual free water test description

Description: Residual free water expected to remain in a Multi-Canister Overpack (MCO) after processing in the Cold Vacuum Drying (CVD) Facility is investigated based on three alternative models of fuel crevices. Tests and operating conditions for the CVD process are defined based on the analysis of these models. The models consider water pockets constrained by cladding defects, water constrained in a pore or crack by flow through a porous bed, and water constrained in pores by diffusion. An analysis of com… more
Date: December 23, 1997
Creator: Pajunen, A. L.
Partner: UNT Libraries Government Documents Department
open access

Safety evaluation for packaging (onsite) singly encapsulated cesium chloride capsules

Description: Three nonstandard Waste Encapsulation and Storage Facility (WESF) cesium chloride capsules are being shipped from WESF (225B building) to the 324 building. They would normally be shipped in the Beneficial Uses Shipping System (BUSS) cask under its US Department of Energy (DOE) license (DOE 1996), but these capsules are nonstandard: one has a damaged or defective weld in the outer layer of encapsulation, and two have the outer encapsulation removed. The 3 capsules, along with 13 other capsules, … more
Date: May 22, 1997
Creator: Smyth, W. W.
Partner: UNT Libraries Government Documents Department
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