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Title: DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization

Abstract

This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.

Authors:
Publication Date:
Research Org.:
Washington Closure Hanford (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
972718
Report Number(s):
WCH-059
TRN: US201006%%501
DOE Contract Number:
DE-AC06-05RL14655
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; AIR; CONTAMINATION; DOSE RATES; DUCTS; HOT CELLS; TANKS; WASTES; 324 building, 327 building, DQO, hot cells

Citation Formats

T.A. Lee. DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization. United States: N. p., 2006. Web. doi:10.2172/972718.
T.A. Lee. DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization. United States. doi:10.2172/972718.
T.A. Lee. Mon . "DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization". United States. doi:10.2172/972718. https://www.osti.gov/servlets/purl/972718.
@article{osti_972718,
title = {DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization},
author = {T.A. Lee},
abstractNote = {This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.},
doi = {10.2172/972718},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Feb 06 00:00:00 EST 2006},
month = {Mon Feb 06 00:00:00 EST 2006}
}

Technical Report:

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  • The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.
  • An instrument pod has been designed and constructed to estimate the quantity of TRU isotopes present in hot cells in Hanfords 327 Building. This estimate is required to assign the proper waste classification for ultimate disposal of the hot cell. The instrument pod consists of a cylindrical polyethylene moderator containing three neutron detectors. The pod diameter was chosen to allow the pod to be deployed through a 7-inch port in the hot cell wall. A polyethylene traverse pipe, long enough to extend through the interior of the cell, was designed for insertion through the hot cell port, allowing the podmore » to be positioned inside the cell. The neutron detectors chosen for the pod were fission chambers, which provides acceptable sensitivity to neutrons with excellent rejection of gammas even in high-contamination cells. The neutron pod was tested and calibrated in PNNLs Low Scatter Room (LSR), using a 252Cf source in both unmoderated and D2O-moderated configurations. The calibration configurations were then modeled using MCNP to arrive at a calibration constant that relates the neutron flux incident on the pod to neutron count rate. The neutron pod was used in the G and H hot cells in the 327 Building. These hot cells had been decommissioned and are slated for disposal. For each hot cell, the neutron pod was positioned at about 10 locations inside the cell and count rates were recorded. The recorded count rates were all very close to background levels, since substantial cleanup effort had been expended in each cell. MCNP modeling was then performed, with plutonium distributed inside the cell in several likely distributions. The models produced values of neutron count rate per gram Pu in the cell. These values were then applied to the measured count rates to determine the quantity of Pu that is in the cell. The best estimate for the contents of G cell is 1.18 g Pu, with an uncertainty bound ranging from 0 g to 2.75 g Pu. For H Cell, the best estimate is 1.03 g Pu, with an uncertainty bound ranging from 0 g to 2.80 g Pu. The best estimates of the TRU activity as a function of waste mass in the entire cell is 2.34 nCi/g for G cell and 3.87 nCi/g for H cell.« less
  • This report evaluates the modification options for handling radiological liquid waste (RLW) generated during decontamination and cleanout of the 327 Building. The overall objective of the 327 Facility Stabilization Project is to establish a passively safe and environmentally secure configuration of the 327 Facility. The issue of handling of RLW from the 327 Facility (assuming the 34O Facility is not available to accept the RLW) has been conceptually examined in at least two earlier engineering studies (Parsons 1997a and Hobart l997). Each study identified a similar preferred alternative that included modifying the 327 Facility RLWS handling systems to provide amore » truck load-out station, either within the confines of the facility or exterior to the facility. The alternatives also maximized the use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes. An issue discussed in each study involved the anticipated volume of the RLW stream. Estimates ranged between 113,550 and 387,500 liters in the earlier studies. During the development of the 324/327 Building Stabilization/Deactivation Project Management Plan, the lower estimate of approximately 113,550 liters was confirmed and has been adopted as the baseline for the 327 Facility RLW stream. The goal of this engineering study is to reevaluate the existing preferred alternative and select a new preferred alternative, if appropriate. Based on the new or confirmed preferred alternative, this study will also provide a conceptual design and cost estimate for required modifications to the 327 Facility to allow removal of RLWS and treatment of the RLW generated during deactivation.« less
  • This report evaluates the modification options for handling radiological liquid waste generated during decontamination and cleanout of the 324 Building. Recent discussions indicate that the Hanford site railroad system will be closed by the end of FY 1998 necessitating the need for an alternate transfer method. The issue of handling of Radioactive Liquid Waste (RLW) from the 324 Building (assuming the 340 Facility is not available to accept the RLW) has been examined in at least two earlier engineering studies (Parsons 1997a and Hobart 1997). Each study identified a similar preferred alternative that included modifying the 324 Building RLWS tomore » allow load-out of wastewater to a truck tanker, while making maximum use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes to the building. This alternative is accepted as the basis for further discussion presented in this study. The goal of this engineering study is to verify the path forward presented in the previous studies and assure that the selected alternative satisfies the 324 Building deactivation goals and objectives as currently described in the project management plan. This study will also evaluate options available to implement the preferred alternative and select the preferred option for implementation of the entire system. Items requiring further examination will also be identified. Finally, the study will provide a conceptual design, schedule and cost estimate for the required modifications to the 324 Building to allow removal of RLW. Attachment 5 is an excerpt from the project baseline schedule found in the Project Management Plan.« less
  • Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05 requires US Department of Energy, Richland Operations Office to complete a 324 Building Special Case Waste Assessment in Support of the 324 Building Closure. This document has been prepared with the intent of meeting this regulatory commitment. Alternatives for the Special Case Wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in themore » recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.« less