Published January 27, 2010 | Version v1
Report

Results For The Fourth Quarter Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminant Results

Description

The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, the DDA (Deliquification, Dissolution, and Adjustment) process, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are listed in the current Saltstone WAC. SRS Liquid Waste Operations (LWO) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2009 Fourth Quarter samples collected from Tank 50 on October 2, 2009 and discusses those results in further detail than the previously issued results report. This report details the chemical and radionuclide contaminant results for the characterization of the 2009 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (3) The reported detection limits for 59Ni and 94Nb are above the requested limits from Reference 4. However, they are each below the limits established in Reference 3. (4) The reported detection limit for isopropanol is greater than the requested limit from Table 4 of the WAC. (5) The reported detection limits for 247Cm and 249Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 3. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50.

Availability note (English)

Available from http://sti.srs.gov/fulltext/SRNL-STI-2009-00828.pdf; PURL: https://www.osti.gov/servlets/purl/973591-NJbljQ/

Additional details

Publishing Information

Imprint Pagination
20 p.
Report number
SRNL-STI--2009-00828

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
41064363
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CHEMICAL COMPOSITION; LIQUID WASTES; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE MANAGEMENT; RADIOCHEMICAL ANALYSIS; RADIOISOTOPES
Descriptors DEC
CHEMICAL ANALYSIS; ISOTOPES; MANAGEMENT; MATERIALS; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTE MANAGEMENT; WASTES

Optional Information

Contract/Grant/Project number
AC09-08SR22470
Notes
doi 10.2172/973591
Funding organization
US Department of Energy (United States)