ornlOAK RIDGENATIONALLABORATORY

LOCKHEED MMR

ORNL/TM-13351

Statistical Description of LiquidLow-Level Waste System

Transuranic Wastesat Oak Ridge National Laboratory,

Oak Ridge, Tennessee

C. K. BayneS. M. DePaoli

J. R. DeVore (ed.)D. J. Downing

J. M. Keller

MA:F TH!3 DOCUMENT IS UNLIMITED

MANAGED AND OPERATED BY

LOCKHEED MARTIN ENERGY RESEARCH CORPORATION

FOR THE UNITED STATES

DEPARTMENT OF ENERGY

ORNL-27 (3-86)

This docxmient has been approved by theORNL Technical Information Office ifor release to the public. Date: l a M 2 . /

ORNL/TM-13351

STATISTICAL DESCRIPTION OF LIQUD3LOW-LEVEL WASTE SYSTEM

TRANSURANIC WASTESAT OAK RIDGE NATIONAL LABORATORY,

OAK RIDGE, TENNESSEE

C. K. BayneS. M. DePaoli

J. R. DeVore (ed.)D. J. Downing

J. M. Keller

Date Published—December 1996

Prepared forU.S. Department of Energy

Waste Management Technology Divisionunder budget and reporting number EW 3120043

Prepared byOAK RIDGE NATIONAL LABORATORY

Oak Ridge, Tennessee 37831operated by

Lockheed Martin Energy Systems, Inc.for the

U.S. DEPARTMENT OF ENERGYunder contract No. DE-AC05-84OR21400

CONTENTS

FIGURES v

TABLES vii

ABBREVIATIONS ix

EXECUTIVE SUMMARY xi

1. INTRODUCTION 1-1

2. THE LLLW SYSTEM AT ORNL 2-1

2.1 GUNITE AND ASSOCIATED TANKS (GAAT) 2-12.2 OLD HYDROFRACTURE FACILITY (OHF) 2-32.3 BETHEL VALLEY EVAPORATOR SERVICE TANKS (BVEST) 2-6

2.3.1 Waste Storage Tanks C-l and C-2 2-62.3.2 Waste Evaporator System 2-8

2.4 MELTON VALLEY STORAGE TANKS (MVST) 2-82.5 ANTICIPATED CHANGES TO ORNL LLLW 2-10

2.5.1 MVST-CIP 2-112.5.2 Cesium Removal 2-112.5.3 Additional Evaporation 2-112.5.4 Source Treatment 2-12

3. DISCUSSION OF DATA FROM PREVIOUS SAMPLING CAMPAIGNS 3-13.1 PREVIOUS REPORTS, SAMPLING METHODS, AND LIMITATIONS 3-1

3.1.1 Peretz Report (ORNL/TM-10218, 1986) 3-13.1.2 Autrey Reports (ORNL/ER-13, 1990 and ORNL/ER-19, 1992) 3-33.1.3 Sears Report (ORNL/TM-11652, 1990) 3-33.1.4 GAAT Reports (ORNL/ER/Sub/87-99053/74, 1995

and ORNL/ER/Sub/87-99053/79, 1996) 3-63.1.5 1996 OHF Report and Recent MVST and BVEST Data 3-8

3.2 PREVIOUS REPORTS, ANALYTICAL METHODS, AND LIMITATIONS 3-83.2.1 Peretz Report (ORNL/TM-10218, 1986) 3-93.2.2 Autrey Reports (ORNL/ER-13, 1990 and ORNL/ER-19, 1992) 3-93.2.3 Sears Report (ORNL/TM-11652, 1990) 3-113.2.4 GAAT Data (ORNL/ER/Sub/87-99053/74, 1995

and ORNL/ER/Sub/87-99053/79, 1996) 3-133.2.5 OHF Data (1996) \ 3-173.2.6 Recent Data for MVST and BVEST (ORNL/TM-13234, 1996

and ORNL/TM-13248, 1996) 3-173.2.7 Summary of Data Limitations and Data Qualifications . . 3-18

3.3 DATA USED FOR THE EVALUATION 3-193.4 MASS OF TANK SLUDGE 3-243.5 DATA SUMMARY 3-26

in

CONTENTS (continued)

4. ESTIMATING PROPERTY BOUNDS 4-14.1 ASSUMPTIONS FOR STATISTICALLY CORRECT

CHARACTERIZATION 4-14.2 AN OVERVIEW OF STATISTICAL INTERVALS 4-24.3 DEFINITIONS AND EXAMPLES 4-3

4.3.1 Confidence Interval for the Population Mean 4-54.3.2 Confidence Interval for the Probability of Being .

less than a Specified Value 4-64.3.3 Tolerance Intervals to Contain a Specified Population Proportion 4-64.3.4 One-sided and Two-sided Prediction Bounds to Contain All of M Future

Observations 4-84.3.5 Log Transformations . 4 4-9

4.4 PREDICTION INTERVALS WHEN THE DATA IS EXPONENTIALLYDISTRIBUTED 4-10

5. REFERENCES 5-1

APPENDIX A. A HISTORY OF TANK WASTE AT ORNL A-lAPPENDK B. TANK SAMPLING DATA B-l

IV

FIGURES

2.1 Diagram of ORNL Tank Farm System 2-22.2 North Tank Farm 2-32.3 South Tank Farm 2-42.4 Old Hydrofracture Facility site 2-52.5 Layout of BVEST and Evaporator Facility 2-72.6 Melton Valley Storage Tanks 2-93.1 Soft sludge sampler 3-53.2 Frequency of measurements for the physical variables 3-233.3 Frequency of measurements for the chemical measurements 3-243.4 Frequency of measurements for the radiological measurements 3-243.5 Percentage of sludge mass for each tank farm 3-26

DISCLAIMER

Portions of this document may be illegiblein electronic image products. Images areproduced from the best available originaldocument

TABLES

3.1 Summary of ORNL LLLW system tank sampling campaigns 3-13.2 Categorization of waste by similar chemical properties 3-93.3 Summary of data limitations and additional needs 3-193.4 Sludge data obtained from referenced reports that was restricted

from statistical analysis 3-203.5 Number of measurements on sludge samples from 1985 to 1996 : 3-223.6 Average number of variables measures on sludge samples for each year 3-233.7 Sludge mass and volume for each tank 3-253.8 Sludge mass and volume for each tank farm 3-263.9 Definition of summary statistics 3-273.10 Summary statistics for physical measurements on sludge samples 3-283.11 Summary statistics for chemical measurements (mg/kg) on sludge samples 3-313.12 Summary statistics for radiological measurements (Bq/g) on sludge samples . . . . 3-393.13 Weighted summary statistics for physical measurements on sludge samples 3-473.14 Weighted summary statistics for chemical measurements on sludge samples 3-493.15 Weighted summary statistics for radiological measurements on sludge samples . . . 3-544.1 Selected percentiles of the student's ^-distribution 4-144.2 The factor g(o.95,P)n) f° r calculating two-sided 95% tolerance intervals

and the factor r(095mn) for calculating two-sided 95% prediction intervalsfor m future observations 4-15

4.3 The factor g(0.95,Pfn) f° r calculating two-sided 99% tolerance intervals,and the factor r(0 95 p n) for calculating two-sided 99% prediction intervalsfor m future observations 4-15

4.4 Factors g'(i^_Pin) for calculating normal distribution one-sided 100 (l-a)%tolerance bounds 4-16

4.5 Factors r'(1^mn) for calculating normal distribution one-sided 100(l-a)%prediction bounds for m future observations using the results of a previoussample of n observations 4-17

4.6 Factors B (.95; m,n) for calculating exponential distribution two-sided 95%prediction intervals for m future observations using the results of a previoussample of n observations 4-18

B.I Physical variable measurements on sludge samples from 1985 to 1996 B-5B.2 Chemical variable measurements (mg/kg) on sludge samples from 1985 to 1996 . B-7B.3 Radiological variable measurements (bq/g) on sludge samples

from 1985 to 1996 B-llB.4 Physical variable measurements on liquid samples from 1985 to 1986 B-19B.5 Chemical variable measurements (mg/kg) on liquid samples from 1985 to 1996 . . B-21B.6 Radiological variable measurements (bq/g) on liquid samples

from 1985 to 1996 B-29B.7 Sludge organic concentrations (|ig/kg) reported in Sears' report B-37B.8 Sludge organic concentrations (p.g/kg) reported in Autrey's report B-38B.9 Sludge Arochlor concentrations (ng/kg) reported for GAAT tanks B-39B.10 Sludge organic concentrations (mg/kg) reported in GAAT Phase 2 report

and Keller's report B-40

Vll

B.l l Sludge semi-volatile organic concentrations (mg/kg) reported in GAATPhase 2 report and Keller's report B-41

B.12 Tenatively identified volatile and semi-volatile concentrations (mg/kg) reported inKeller's report ; . . . • . B-42

B.13 Liquid organic concentrations ((i.g/1) reported in Sears' report B-43B.14 Liquid organic concentrations (ug/1) measured by direct aqueous injection gas

chromatograph reported in Autrey's report B-43B.I5 Liquid organic concentrations (ug/1) measured by gas chromatograph\mass

spectrometry reported in Autrey's report B-45B.I6 Liquid semi-volatile organic concentrations (ng/1) reported in Autrey's report . . . B-47B.I7 Liquid organic concentrations (mg/1) reported in GAAT Phase 2 report

and Keller's report ' B-48

vni

ABBREVIATIONS

AA atomic absorptionALARA as low as reasonably achievableASME American Society of Mechanical EngineersASTM American Society for Testing MaterialsBVEST Bethel Valley Evaporator Service TankCFR Code of Federal RegulationsDAIGC direct aqueous injection gas chromatographyDOE U.S. Department of EnergyDSOL dissolved solidsEASC Emergency Avoidance Solidification CampaignEPA U.S. Environmental Protection AgencyFFA Federal Facility AgreementFY fiscal yearGAAT Gunite and Associated TanksGC/MS gas chromatography/mass spectrometryGFAA graphic furnace atomic absorptionIC Ion chromatographyICAR inorganic carbonICP-AES Inductively Coupled Plasma Atomic Emission SpectroscopyITE in-tank evaporationLLLW liquid low-level wasteLLW low-level wasteLWSP Liquid Waste Solidification ProjectMVST Melton Valley Storage TanksMVST-CIP MVST Capacity Increase TanksNHVOA nonhalogenated volatile organic analysisNTF North Tank FarmOHF Old Hydrofracture FacilityORNL Oak Ridge National LaboratoryOTE Out of Tank EvaporationRCRA Resource Conservation and Recovery ActREDC Radiochemical Engineering Development CenterRFP Request for ProposalRMAL Radioactive Materials Analytical LaboratorySSMS spark source mass spectrometrySSOL suspended solidsSTF South Tank FarmSVOA Semivolatile Organic Compound AnalysisSVOC semivolatile organic compoundTCAR total carbonTCS tank characterization systemTIMS thermal ionization mass spectrometryTOC total organic carbonTRU transuranicTSOL total solids

IX

TWCP Transuranic Waste Characterization ProgramVOA volatile organics analysisWAC waste acceptance criteriaWAG Waste Area GroupingWIPP Waste Isolation Pilot Plant

EXECUTIVE SUMMARY

The U.S. Department of Energy (DOE) has presented plans for processing transuraniclow-level liquid wastes located at Oak Ridge National Laboratory (ORNL). The TennesseeDepartment of Health and Environment has mandated that the processing of these wastes mustbegin by the year 2002 and that the goal should be permanent disposal at a site located off theOak Ridge Reservation. To meet this schedule, DOE will solicit bids from various privatesector companies for the construction of a processing facility to be operated by the privatesector on a contract basis. This report will support the Request for Proposal process by givingpotential vendors information about the wastes contained in the ORNL tank farm system. Thereport consolidates all current data about the properties and the waste composition and presentsmethods to calculate the error bounds of the data in the best technically defensible mannerpossible.

Liquid low-level wastes (LLLW) have been generated since ORNL began operations.Before 1984 the waste was discharged to settling basins for dilution, disposed of in seepagepits after decay, or disposed of on-site by the hydrofracture process. From 1984 to the presenttime, these wastes have been concentrated and stored in the Bethel Valley Evaporator ServiceTanks (BVESTs) and Melton Valley Storage Tanks (MVSTs). When storage space in the tanksbecomes limited, the liquid portion has been solidified into concrete monoliths. The ORNLLLLW tank system is described in Chap. 2. An operating history of tank waste at ORNL,including Gunite and Associated Tanks (GAAT) operations, Old Hydrofracture Facility (OHF)operations, GAAT sluicing operations, Building 2531 evaporator operations, evaporationoperations at the MVST facility, and waste composition changes as a result of evaporation, isgiven in Appendix A.

Future changes to ORNL LLLW are certain given the many different programs already inprogress and planned to deal with ORNL's liquid waste problems. Legacy wastes will behandled by consolidation of all sludges into MVSTs before solidification by the private sectorvendor. Generation of wastes by ongoing programs at ORNL will add newly generated waste,which must also be treated, to the system. These wastes could be different than the wastesbeing generated today. To assure that adequate storage capacity is always available, closemanagement of the waste movements will be required. How and in what sequence these occurwill greatly influence the composition of the wastes the private sector will see. The order inwhich the sludges are transferred and the degree of mixing performed could be handled inseveral different ways. The schedule for these operations as well as the order of the operationswill be developed over a period of time and cannot be discerned at the present time.

Sludges from GAAT, OHF, and BVEST will be consolidated in MVSTs whereassupernates (containing no sludges) will be consolidated in the new MVST-Capacity IncreaseTanks.

Demonstration of cesium removal activities will continue in fiscal year 1997 for removalof cesium from up to 25,000 gallons of MVST supernate. Future superaate cesium removalmay also occur. Additional evaporation will be initiated in the future to further reduce thevolumes of supernates to gain storage space within the tanks for additional storage of newlygenerated wastes. A combination of the Out of Tank Evaporator and the Building 2518

xi

evaporator facilities will be used for this. The expected supernate NaNO3 concentration shouldbe ~8Af when this is complete. The Radiochemical Engineering Development Center (REDC)is presently the largest contributor of radionuclides to the ORNL waste stream. REDC issupposed to start treating their waste to remove 137Cs and reduce the transuranic content tonontransuranic in the 1998-99 time frame.

The ORNL tank system has been sampled on numerous occasions. The results of theprevious sampling campaigns are summarized in this report. A general principle to use is thatthe later data is generally more accurate because the analytical laboratory had more practice atdoing the analysis as well as better equipment. The BVEST and MVST systems are part of theactive waste systems, and the composition of the wastes reported for them have changedduring since the sampling occurred. This is particularly true for the supernates, which aretransferred and treated on a regular basis. •

The analytical methodology and data limitations for radioactive waste tank samplescollected from 1985 to present are also summarized. The full scope of analytical datadiscussed in this summary was not taken as part of a comprehensive characterization of theLLLW system. The waste tank data collection represents many different projects with differentneeds, analytical requirements, and data quality objectives. In addition, the list of analyticalmeasurements and the quality level varied between projects. The most critical data limitationassociated the characterization of underground storage tanks is the limited access to the tankcontents, which restricts the options available for statistical sampling. Both vertical segregationin the sludge (layering) and concentration gradients were observed in the liquid phase. For theMVST, BVEST, and OHF tanks, the sludge has only been sampled in a single location. ManyGAAT had sludge samples taken at three different locations and large differences inconcentration were observed for most species measured.

For the reasons discussed previously, the data used in the evaluation required closescreening to ensure that the statistical analysis used the best data possible. Some sludgemeasurements were excluded from the analysis for various reasons as was all supernate data(because it is expected to be significantly different by the time the private sector vendor beginsprocessing the sludge). Measurements from the various reports have been standardized so theirunits are consistent throughout this report. Six statistics were calculated to summarize thesludge measurements: the number of measurements, mean, standard deviation, minimum,maximum, and relative error (standard deviation/mean x 100%). These data are included forall included measurements in tabular form.

A correct and valid analysis of data for the purpose of making statistical inference, suchas creating confidence intervals or bounds on some parameter, requires certain assumptions.Three major assumptions allow correct results to follow from an analysis: (1) the assumptionof a specified population, (2) the assumption of a random sample, and (3) the assumption thatthe sampled population is the target population. The first assumes that the data come from aspecific and well-defined population. In our setting, the population consists of the possible setof analytes. The fact that we do not analyze for all possible analytes means that we do nothave a complete description of the population of interest and may be missing importantanalytes that may have important interaction effects with analytes that are measured. Thisinteraction could have serious implications when trying to determine bounds on a givenanalyte. The second assumption is that the sample taken is random. In our situation this is

xii

violated in several respects. The most obvious and serious violation is that the samples selectedcame from one position in the tank because the tank only has one opening from which tosample. The requirement of a random sample is critical in that the statistical intervals reflectonly the variability introduced by the sampling process and do not take into account any biasesthat might be introduced by nonrandom samples. In addition, the core type samples takenshowed definite layers of material, which was composited and analyzed. This results in noestimate of the variability of the analyte in a given tank and yields a mean concentration. Thisnonrandomness can lead to heavily biased observations, the results of which are not amenableto adjustment. Finally, the methods used assume that the population of interest is the same asthat sampled. Because the population of interest is the MVSTs after transfer from the othertanks, we simply are not sampling the population of interest.

Methods of calculating the following intervals are given with examples on how to usethem: Confidence interval for the population mean, confidence interval for the probability ofbeing greater than a specified value, tolerance intervals to contain a population proportion, andprediction bounds to contain all of m future observations. These intervals are appropriate underthe given assumptions.-In addition to the given assumptions, we must also assume for the fourintervals that the sample was drawn from a normally distributed population. Intervals for theprobability of being greater than a specified value, tolerance intervals, and prediction boundscan be calculated if the underlying distribution is assumed to be lognormal. Prediction intervalsfor the case when the underlying distribution is exponential can also be calculated. The usersof the report can calculate their own confidence intervals with these formulas based on theappropriate assumptions.

xm

1. INTRODUCTION

The U.S. Department of Energy (DOE) has presented plans for processing liquid low-level wastes (LLLW) located at Oak Ridge National Laboratory (ORNL) in the LLLW tanksystem. These wastes are among the most hazardous on the Oak Ridge Reservation andexhibit both Resource Conservation and Recovery Act (RCRA) toxic and radiologicalhazards.The Tennessee Department of Health and Environment has mandated that theprocessing of these wastes must begin by the year 2002 and that the goal should be1 permanentdisposal at a site located off the Oak Ridge Reservation. To meet this schedule, DOE willsolicit bids from various private sector companies for the construction of a processing facilityon land located near the ORNL Melton Valley Storage Tanks (MVSTs) to be operated by theprivate sector on a contract basis.

Four tank farms (a total of 26 tanks) contain these wastes: the Gunite and AssociatedTanks (GAAT), the Old Hydrofracture Facility (OHF) tanks, the Bethel Valley EvaporatorService Tanks (BVESTs) and MVST. The present plans are to transfer the wastes now in theGAAT, OHF tanks, and BVEST as well as newly generated wastes to the eight MVSTs forstorage before treatment by a private sector waste processor. Presently, it has not beendetermined which MVST will be the destination for waste in any individual BVEST, GAAT,or OHF tank, nor has it been determined which MVST will have waste removed or modifiedto make room for the transferred wastes.

This report will support of the Request for Proposal (RFP) process and will give potentialvendors information about the wastes contained in the ORNL tank farm system. The reportconsolidates current data about the properties and composition of these wastes and presentsmethods to calculate the error bounds of the data in the best technically defensible mannerpossible. The report includes information for only the tank waste that is to be included in theRFP.

1-1

2-1

2. THE LLLW SYSTEM AT ORNL

LLLW wastes have been generated at ORNL since operations began. Before 1966, thewaste was discharged to settling basins for dilution or disposed of in seepage pits after decay.From 1966 to 1984, much of this waste was disposed of on-site by the hydrofracture process.The OHF tanks and MVSTs described herein are actually service tanks for the twohydrofracture facilities. From 1984 to present, these wastes have been concentrated and storedin BVESTs and MVSTs. When storage space in the tanks becomes limited, the liquid portionhas been solidified into concrete monoliths. The ORNL LLLW tank system is illustrated inFig. 2.11. The following is a description of the ORNL LLLW tank system. An operatinghistory of tank waste at ORNL, including GAAT operations, OHF operations, GAAT sluicingoperations, Building 2531 evaporator operations,.evaporation operations at the MVST facility,and waste composition changes as a result of evaporation, is given in Appendix A.

2.1 GUNITE AND ASSOCIATED TANKS (GAAT)

GAAT2 include eight tanks in the North Tank Farm, six tanks in the South Tank Farm,and tanks W-l 1 and TH-4. The latter two tanks will not be discussed because they will not beincluded in the RFP. In addition, only tanks W-3 and W-4 in the North Tank Farm are part ofthe RFP; therefore the other six will not be discussed. The North Tank Farm and South TankFarm are in the approximate center of ORNL (on both sides of Central Avenue). CentralAvenue is the main east-west thoroughfare for ORNL. The North Tank Farm, shown inFig. 2.2, is a 45.7-m x 54.9-m (150-ft x 180-ft) lot near the intersection of Third Street andCentral Avenue. It is bordered on the north by the Surface Science Laboratory(Building 3137), on the east by a lot where the Solid State Research Facility will beconstructed, on the south by Central Avenue, and on the west by Third Street.

The South Tank Farm is located across Central Avenue, south of the North Tank Farm(Fig. 2.3). It is bordered on the north by Central Avenue, on the east by Fourth Street, on thesouth by the Metal Recovery Facility (Building 3505), and on the west by Third Street.Tank W-ll is southeast of the South Tank Farm.

The two RFP tanks in the North Tank Farm (W-3 and W-4) are constructed of gunite(sprayed cement slurry). Tanks W-3 and W-4, which have capacities of 160,860 L(42,500 gal) each, are in the southeastern part of the farm. Each tank has an array of inlet andoutlet lines that lead to valve boxes where waste transfers are controlled. Each tank also has anassociated dry well that drains the immediate area around a tank which is intended to controlpotential leaks.

The South Tank Farm contains six gunite tanks (W-5 through W-10). Tanks W-5 throughW-10 are 643,450-L (170,000-gal) tanks arranged in two rows of three with a 18.3-m (60-ft)center-to-center distance. The domed waste storage tanks are 15.2 m (50 ft) in diameter with avertical height of 5.5 m (18 ft) at the center and 4.6 m (15 ft) at the walls. Each tank has anassociated dry well and an array of pipes and valve boxes.

ORNL-DWG 96M-7806

BETHEL VALLEY COLLECTION TANKS

MELTON VALLEY COLLECTION TANKS

PROCESS WASTE TREATMENTPLANT EVAPORATOR

TO PROCESS WASTE TREATMENT PLANT

LOW-LEVEL WASTEEVAPORATOR

OHF TANKSGUNITE & ASSOCIATED TANKS

to

MELTON VALLEY STORAGE TANKS

Fig. 2.1. Diagram of ORNL Tank Farm System.

2-3

FROM BLDG. 3019

4500 AREA

£ TANK

N222S2.6

INSPECVON HOLE

INSPECVON HOLE«o SAMPLED ANNUALLY

FOR NTF LEAKAGE

N221B0

DRAINS•/HAC77&AREA

Fig. 2.2. North Tank Farm.

2.2 OLD HYDROFRACTURE FACBLITYCOHF)

The OHF Facility3'4 was built in 1963 and operated from 1964 until it was shut down in1980. The purpose of this facility was to dispose of liquid waste by the hydrofracture process,which consisted of mixing the waste with grout and injecting the mixture into a shaleformation located -305 m (1000 ft) below ground surface. In 1966, after test injections in1964-65, the facility became operational for the routine disposal of concentratedintermediate-level waste solutions. Improvements and modifications were made to the processand the facility throughout this series of injections, which ended in 1979. The hydrofractureprocess was operated as a large-scale batch process. However, each injection was a continuousoperation. Each injection disposed of an annual accumulation of waste solution of about378,500 L (100,000 gal). During an. injection, waste solution was pumped to the mixer and

2-4

mixed with a stream of dry solids. The resulting grout was pumped down the injection welland out into the shale formation at an injection pressure of about 3000 psi.

• CArrtD iron n rr car-no* rtm wc-t

HMXJKW caKxerz-rvomc * rex (nrj

fx tmiicoMr-iot-t-oor-o

-stt mime f-tour-A-asr-0sttr i-i rat conmo>rm

Fig. 23. South Tank Farm.

The OHF Facility is located in Melton Valley, approximately 1.1 mi south of the ORNLmain plant area within the secured area of Waste Area Grouping (WAG) 5. Figure 2.4 showsthe site layout and all pertinent structures. The OHF underground waste storage tanks are,buried less than 110 yd west of Building 7852 and approximately 131 yd east of White OakCreek.

2-5

NOTE- 2" CS. UNE TO BECOME INACTIVEAND REUOVED mOU THE PUUPHOUSE TO THE VAL\£ BOX AT THEBEGINNING OT THE OHF TANKDECOMMISSIONING.

j^TO EMERGENCY WASTE PIT

IS' Y.CP. DRAM

•FROU BUILDING 7852

KOKVU7KN UC

mOOSS VASTFtJKS

X 3" X 8" 1HOC CCNCHOE PAO

PLAN VIEWAPPROXIMATE SCALE: / * - TO'

Fig. 2.4 Old Hydrofracture Facility site.

Five underground storage tanks ranging in size from 13,000 to 25,000 gal capacity arelocated at the OHF Facility (T-l, T-2, T-3, T-4, and T-9). The five tanks are buried beneathrelatively shallow earth backfill near Building 7852. The tanks were installed in two phases,

2-6

with tanks T- I, T-2, and T-9 being installed initially and tanks T-3 and T-4 installed later.Tanks T-l, T-2, and T-9 were surplus carbon steel tanks from the Oak Ridge Y- 12 Plant andwere installed circa 1963 at the OHF site to store LLLW. These tanks were refitted to includeadditional internals for mixing and sludge retrieval. In 1966, two additional storage tanks (T-3and T-4) were added to the system. They were surplus rubber-lined carbon steel tanks andwere installed in a pit next to the existing three tanks.

Tanks T-l and T-2 are 8 ft in diameter and 44.1 ft long with nominal capacities of15,000 gal. Nominal wall thickness is 1 in. (Weeren 1995). Tank T-9 is 10 ft in diameter and23.8 ft long with a nominal capacity of 13,000 gal. The internal piping is similar to that ofT-l and T-2 except that only; two airlift pumps were installed . Tanks T-3 and T-4 are 10.5ft in diameter and 42.1 ft long. Each of these tanks has 5/8-in.-thick walls with a nominalcapacity of 25,000 gal. Each has a rubber lining on the inside. Fittings of each tank include an18-in. (nominal) manway in the middle of each tank, which contains a pneumatic levelindicator (Fig. 2.4), three airlift pumps, a 2-in. inlet near one end of the tank, and a 4-in.suction line" near the same end. The suction line extends to near the bottom of the tank.

2.3 BETHEL VALLEY EVAPORATOR SERVICE TANKS (BVEST)

The three Evaporator Service Tanks1 (W-21, W-22, and W-23) are essentially identical inconstruction. Each of the 12' diameter, 61 '-4 3/8" long all-welded vessels is fabricated of 1/2"thick American Society of Mechanical Engineers (ASME) SA-240, type 304L stainless steel inaccordance with ASME Code Section VK. The tanks operate at atmospheric pressure orslightly less (-1" wg), but are designed for 15 psig and 150°F; the test pressure is 22.5 psig.A diagram of the Evaporator Service Tank is shown in Fig. 2.5.

Two of the tanks, W-21 and W-22, are located in a single reinforced concrete vault 31 'wide, 65'-4" long, by 16'-2" high; the floor elevation is 779'-10". These tanks receive the rawlow-level waste (LLW) by gravity from, the Waste Collection Header. Tank W-23 is locatedin a separate vault 19' wide, 65'-4" long, by 16'-8" high; the floor elevation is 788'-6". TankW-23 is used to receive the concentrated waste from the evaporators; however, the three tanksare interconnected by piping, which is so arranged that their contents may be interchanged.

The tanks and vaults are designed in accordance with the philosophy for containment ofradioactive liquids and provide double containment. The reinforced concrete walls of the vaultsvary in thickness from 2' to 3 ' and both vaults are located below grade level. The concreteroof slabs are 3 ' thick and are provided with removable stepped plugs to permit access to thevault. The vault floors and the walls to a height of 7'-2" are lined with 16 gauge, type 304Lstainless steel sheet. Sumps and sump pumps are provided in each vault to permit leakage tobe returned to the Service Tanks. The entire installation is constructed in accordance with theUniform Building Code, 1970, for Seismic Zone 2.

2.3.1 Waste Storage Tanks C-l and C-21

It was originally estimated that the six gunite storage tanks, which contain no specialprovisions for cooling, could handle a maximum heat load of about 17,000 BTU/h (5 KW).Thus, the radionuclid concentration in the LLLW had to be restricted to 5-10 Ci/gal, whichcorresponds to a heat generation rate of about 0.1 BTU/gal. It was anticipated that someprocesses at ORNL could produce liquid waste with a considerably higher concentration than

NEVAPORATOR

SERVICETANK

- V A U L T - *

CONTROLHOUSE

W-23

PUMPAREA

W-22

ALPIT

L

ORNL-DWG 96M-7805

W-21

COLLECTION HEADER

COLLECTION HEADER VALVE PIT

HLW TANK VAULT

SERVICE TUNNEL

C-2

C-1

iPi^fl

•EAST VALVE PIT

to

Fig. 2.5. Layout of BVEST and Evaporator Facility.

2-8

this and, thus, a substantially higher heat generation rate. Consequently, in 1964 two internallyand externally cooled 50,000-gal tanks were installed to handle this liquid waste. These tanksare located in an underground, reinforced-concrete vault located adjacent to and directly northof the Evaporator Building (2531) (Fig. 2.5).

The two storage tanks are of all-welded construction, fabricated of American Society forTesting Materials (ASTM) A240-6IT Type 304L stainless steel 1/2" thick. The 61 ' long by 12'diameter horizontal tanks were designed to meet the requirements of ASME Code SectionVIE. The design pressure is 30 psig at a temperature of 200°F. The tanks were hydrostatictested at 50 psig. The tanks are capable of storing acidic wastes with activities up to 2,800Ci/gal, which will generate about 32 BTU/h gallon, if produced from 6 months' cooledhigh-burnup uranium. However, the tanks were never used for materials of this concentration.

In recent years Tanks C-l and C-2 have received waste from Tank W-23 for storage andare considered a part of the BVEST tank farm.

2.3.2 Waste Evaporator System1

Dilute LLLW from the liquid collection system is fed to the evaporators forconcentration. Two 600-gallon-per-hour evaporators are available to concentrate the LLLW;both are housed in Building 2531. One evaporator is served by a 4400 gal feed tank (A-l).The other evaporator is fed directly from one of the evaporator service tanks (W-21 or W-22).Aside from this the operations are identical. These facilities are shown in Fig. 2.5.

The evaporator installations each consist of an evaporator vessel in which the volumereduction takes place, a vapor filter, a water cooled condenser, and a condensate catch tank.With the exception of the condensers, the equipment in both systems is identical; however, theinspection, testing, and quality assurance requirements for the new modifications are morerigorous than those applied to the earlier installation.

The evaporators may be operated singly or concurrently and are arranged so that crossconnections between the two facilities allow maximum flexibility. Evaporator concentrate isstored in Tank W-23 before transfer to MVST.

Because the cessation of waste disposal operations brought about by the shutdown onNew Hydrofracture, Tanks W-21 and W-23 have been used to store evaporator concentrate.Tank W-22 is presently used as the evaporator feed tank; Tanks W-21, W-23, C-l, and C :2are being used for concentrate storage.

2.4 MELTON VALLEY STORAGE TANKS (MVST)1

Storage capacity for the concentrated LLW is provided by 8, 50,000 gal storage tanksinstalled in 2 underground vaults located adjacent to the new hydrofracture site in MeltonValley. These tanks were originally used to store concentrated waste before injection into theshale formations below the adjacent New Hydrofracture Facility. Because hydrofracture is nolonger an approved method for waste disposal, these tanks are the final storage point of LLLWat ORNL. A diagram of these tanks is shown in Fig. 2.6.

ORNL-DWG 96M-7804

PLAN VIEW OF TANK VAULTS SHOWING ACCESS PORT LOCATIONS

W-24 W-25 W-26 W-27

AccessPort

W-28

PumpHouse

W-29

_ i J

W-30

IPump & Valve Vault

W-31

N

b

Fig. 2.6. Melton Valley Storage Tanks.

2-10

The eight tanks (W-24 through W-31) and their reinforced concrete vaults are designed inaccordance with current philosophy for containment safeguards for radioactive liquids; thevaults provide secondary containment. The 1/2" thick, 61 ' 4 7/8" long, 12' diameter all-weldedhorizontal vessels are fabricated of ASME SA 240 Type 304L stainless steel. They arevirtually identical to the evaporator service tanks W-21, W-22, and W-23. Although theyoperate at atmospheric pressure they are designed for 15 psig at 150°F and are hydrostatictested to 22.5 psig. The applicable codes and standards may be found in reference 4 of Sect. 2.

Four tanks are located in each of two identical, reinforced-concrete underground vaults.Each vault is 67' long by 64' wide and 19' high. The vaults have reinforced concrete walls 2'6" to 5' thick and are covered with 3' concrete ceilings. They are lined to a height of 7' 2"with 16-gauge stainless steel sheet to prevent leakage. Each vault is provided with a 3 ' square1 ft. deep sump to collect leakage. The vaults are served by a 22' wide by 130', 6'-8" highpipe tunnel located below grade immediately south of the vaults. This tunnel, which containspiping and pumping equipment, is also lined to a height of 3 ' with 16-gauge stainless steel.

The storage tanks are equipped with liquid level indicators, temperature and specificgravity measuring devices, air spargers, and sampling devices. Readouts are available in thelocal Control House. Liquid level alarms warn of potential overfilling. A nonspecific alarm,which indicates the existence of an abnormal condition, is telemetered to the Waste OperationsControl Center (Bldg. 3105). In addition, the tanks are interconnected to minimize theprobability of overfilling.

2.5 ANTICIPATED CHANGES TO ORNL LLLW

Anticipated changes to ORNL LLLW are certain given the many different programs thatare already in progress or are planned to deal with ORNL's liquid waste problems. Legacywastes will be handled with consolidation of all sludges in MVSTs before solidification by aprivate sector vendor. Present generation of wastes by ongoing programs at ORNL will addnewly generated waste to the system, which must also be treated. These wastes could bedifferent than the wastes being generated today. To assure that adequate storage capacity isalways available, close management of the waste movements will be required. Sludges fromGAAT, OHF, and BVEST will be consolidated in MVSTs whereas supernatants (containing nosludges) will be consolidated in the new MVST Capacity Increase Tanks (MVST-CIP)discussed herein.

The OHF tanks will be sluiced with water and the contents pumped to an existing LLLWvalve box located northwest of Building 7852, tying into the main transfer line to the MVSTfacility. The BVEST sludges will be suspended in LLLW concentrate either by a fluidicbased or more conventional mixer pump-sluicer system and pumped to the MVSTs. GAATsludge will be resuspended in water with a series of sluicer/confined sluicer and remote robotictechniques and transferred to MVSTs.

How and in what sequence these occur will greatly influence the composition of thewastes that the waste processer will see. The order in which the sludges will be transferredand the degree of mixing could occur in a number of different ways. The schedule for theseoperations as well as the order of the operations will be developed over a period of time andcannot be discerned at present. In addition to the mixing of the sludges, other programs are in

2-11

place to deal with different aspects of LLLW. Sections 2.5.1 through 2.5.4 briefly describethese programs (some of these programs are contingent upon funding).

2.5.1 MVST-CEP5

The Federal Facilities Agreement (FFA) requires the transfer of wastes fromnoncompliant tanks. The existing MVSTs are at or very near their capacity because of delaysin the concentrated LLLW processing facility. Therefore, to fully comply with the FFA tokeep the LLLW collection and transfer system operational, return to more conservative OSRlimits, contain water used for the sludge transfers, and support other environmental restorationprograms, additional storage capacity was required.

The most cost-effective method of providing this capacity was determined to be theconstruction of 6, 100,000 gal cylindrical tanks adjacent to the existing MVST facility. Thenew facility has the capability to transfer liquids and readily pumpable sludges to the existingMVST facility, to receive liquids and readily pumpable sludges from the existing MVSTfacility and Bethel Valley Evaporator Facility, and to transfer liquids to the Bethel ValleyEvaporator Facility for treatment. In addition, a line to the existing Liquid WasteSolidification Project (LWSP) facility will be provided; these tanks are presently underconstruction and are scheduled for comissioning in July 1998. At this time, all supernatantwill be removed from MVSTs and transferred here, and sludges contained in the OHF tanks,GAAT, and BVEST will be moved into MVSTs and turned over to the waste processer fortreatment.

2.5.2 Cesium Removal6

The cesium concentration of MVST supernatant will continue to increase to much greaterlevels than those encountered previously. This will continue until the RadiochemicalEngineering Development Center (REDC) implements source treatment activities in 1998.Cesium removal will be required for future LWSP campaigns to reduce radiation exposure andshielding and shipping costs for transport of the solidified supernatant to the Nevada Test Site.

Demonstration operations activities will be continued to evaluate the ability to processradioactive waste through the use of mobile, modular systems (compact processing units orCPUs) available for deployment near the site on an "as needed" basis. Operability of afull-scale treatment system for an extended duration is required before routine deployment.

In fiscal year (FY) 1996, the demonstration system was fabricated, cold testing wasperformed with the selected ion exchanger, the demonstration system was installed, and hotoperations initiated. In FY 1997, operation of the system will be continued for removal ofcesium from/ up to 25,000 gal of MVST supernatant. WMRAD anticipates future use of thesystem (subject to available funding) to remove cesium from MVST supernatant to reduce theradiation exposure and costs associated with processing of the supernatant into a grouted wasteform.

2.5.3 Additional Evaporation

Additional evaporation will be initiated in the future to further reduce the volumes ofsupernatants to gain storage space within the tanks for additional storage of newly generatedwastes. Evaporation will also be used to remove the water used to transport sludges from the

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GAAT and OHF facilities in addition to using settling and pump-back of sluicing liquids. Acombination of Out of Tank Evaporation (OTE, Appendix A) and the Building 2518evaporator facilities will be used for this. Future In-Tank Evaporation (Appendix A) is notpresently planned because OTE is faster and more efficient. The best present estimate is toevaporate the supernatants and sluice waters in MVST, BVEST, OHF, and GAAT almost tothe point of saturation as the legacy waste is consolidated in MVST and MVST-CIP. Theexpected supernatant NaNO3 concentration should be approximately 8M when this is complete.

2.5.4 Source Treatment

Currently, REDC is the largest contributor of radionuclides to the ORNL waste stream.They produce approximately 15,000 gal of dilute LLLW per year, containing approximately10,000 Ci of radionuclides. ORNL's dilute generation, including REDC's contribution, isabout 590,000 gal/year of dilute LLLW containing about 15,000 Ci of radionuclides. REDCwaste is expected to start pretreating their LLLW to remove 137Cs and other fission productsand reduce the transuranic (TRU) content to non-TRU. The pretreatment will consist of anion exchange system, evaporator, and pot dryer, which will produce a very small volume ofconcentrated 137Cs, other fission products, and TRU as a solid waste, but will remove >99% ofthe activity now entering the LLLW system.

3-1

3. DISCUSSION OF DATA FROM PREVIOUS SAMPLING CAMPAIGNS

The ORNL tank system has been sampled on numerous occasions for different reasons.This section summarizes results of the previous sampling campaigns, as compiled from thereferenced reports. For more detailed information the reader is referred to the individualcampaign reports. A general principle to use here is that the later data is generally moreaccurate, mostly because the analytical laboratory had more practice at doing the analyses aswell as better equipment. The BVEST and MVST systems are part of the active wastesystems, and the composition of the wastes reported for them have changed since the samplingoccurred. This is particularly true for the supernatants, which are transferred and treated on aregular basis. Table 3.1 below summarizes the reports, sampling dates, and tanks sampled.

Table 3.1 Summary of ORNL LLLW system tank sampling campaigns '

Report number

ORNL/TM-10218

ORNL/ER-13

ORNL/TM-11652

ORNL/ER/Sub/87-99053/74ORNL/ER/Sub/87-99053/79

Letter report

ORNL/TM-13248

ORNL/TM-13234

Sampling dates

July 1985November 1985

July 1988

December 1989January 1990

November 1994

August 1995

March 1996

November 1993 toFebruary 1996

Fall 1994

Tanks sampled

W-24 to W-28W-24to W-31

T-1, T-2, T-3, T-4, T-9, W-3,W-4, W-5, W-6, W-7, W-8,W-9, W-10

W-24 to W-28, W-31W-21, W-23

W-3, W-4, W-5, W-6,1 W-7, W-8, W-9, W-10W-3, W-4, W-5, W-6,W-7, W-8, W-9, W-10

T-1, T-2, T-3, T-4, T-9

W-21, W-23, W-24, W-25W-26, W-27, W-28, W-31

W-22

Reference

7

8

10

11

12

13

14

15

3.1. PREVIOUS REPORTS, SAMPLING METHODS, AND LIMITATIONS

3.1.1 Peretz Report (ORNL/TM-10218,1986)

The samples analyzed and reported in the Peretz report7 were not taken as part of aplanned comprehensive characterization of the LLW system. Rather, the samples werecollected at different tunes to answer specific questions. Thus, procedures and responsiblepersonnel were different for various samplings. In nearly all cases, the Waste ManagementSection of the ORNL Operations Division was responsible for actually collecting the samples.Because of the radioactivity of the samples, they were submitted to the Radioactive MaterialsAnalytical Laboratory (Bldg. 2026). From this laboratory, samples were distributed to othergroups in the Analytical Chemistry Division. Request numbers were originally assigned to thesamples at Building 2026, and in some cases, these numbers carried onto analyses performedat other locations. The major laboratory groups involved in the analyses are the Radioactive

3-2

Materials Analytical Laboratory, the Transuranium Analytical Laboratory, the Chemical andPhysical Analysis Laboratory, the Mass Spectrometry Laboratory, and the Organic AnalysisLaboratory.

3.1.1.1 Melton Valley Storage Tanks

Data on the contents of MVSTs were generated from two sampling campaigns in July andNovember 1985. During the July sampling, liquid samples were taken through a single nozzlepenetration (designated the "G3" nozzle) in five of the 50,000 gal tanks. Samples werecollected by inserting a hose from the suction side of a sampling pump into the tanks througha shield plug above the nozzle. Samples were drawn from near the top, the middle, and thebottom of the liquid layer in each tank. A sample of liquid was also taken from the sludgeregion at the bottom of each tank. Whatever solids were drawn up with the liquid became partof the sample. Tanks W-24 through W-28 were only sampled in the July sampling phase.

The second sampling phase was conducted in November 1985. All eight tanks weresampled through the same nozzle penetration. A liquid sample and a solids sample were takenfrom each tank. The liquid sample was collected by suspending an open sample bottle into themiddle of the liquid phase. Although stated as a mid-tank sample, the bottles were filledimmediately upon entering the liquid contents and were then mixed somewhat at the middlelevel. Solid samples were taken by pushing a hollow rod into the sludge phase until the bottomof the tank was reached. Cores of sludge were then removed from the rod. Because the sludgein Tank W-31 was particularly hard, extra force was required to reach the tank bottom.External circulation of the tanks, a standard practice at the time the samples were taken, wasstopped to allow the liquid and sludge phases to more fully separate for the Novembersampling. Aeration was continued, however, to maintain mixing in the liquid phase.

Physical observations were recorded during the second sampling. Concerns focused on thequantity and physical characteristics of the sludge layer. An estimate of the depth of sludgepresent in each tank was made by noting at what point the sampling rod seemed to encounterthe sludge phase. The depth estimates obtained in this manner were rough (plus or minus sixinches), and led to approximate estimates of the volume of sludge present in each tank.

3.1.1.2 Evaporator Service Tanks

Tanks W-21, W-22, and W-23 were sampled in November 1985, after thesecondsampling at MVST. Sludge samples were taken from all three of these tanks, and a liquidsample was taken from Tank W-23. Procedures were similar to those used at MVST. Coreswere taken from the sludge near the tank centers, and a bottle was suspended into Tank W-23for the liquid sample. No access points exist on tanks C-l and C-2, so these tanks were notsampled.

3.1.1.3 Gunite storage tanks

Sampling of the Gunite tanks was always difficult because only one penetration wasavailable, and the solids were stratified into different layers characteristic of wastes generatedby ORNL in different years. The data available on the sludge removed from GAAT appears inthe operations reports that document sampling and other activities conducted during eachsluicing campaign. A summary of these sludge removal and injection activities is given inAppendix A of reference 11. Samples taken from MVST before each injection are also given.

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The sampling technique was not detailed but could be presumed to be as described above forMVST.

Data in the Peretz report probably do not well represent the residual contents now presentin GAAT. This residual material was found to be too hard to be sluiced and removed andincludes minor heels of suspended sludge, which could not be pumped out. Hard residualsludge is probably highly inhomogeneous. One of the more intriguing observations of thisresidual material is the presence of well-shaped octahedral crystals, as large as 6 in. on a side.Some of these crystals were removed and found to be formed primarily of sodium phosphate.Any definitive characterization of this residual material would be extremely difficult.

Qualitative descriptions of the sampled material are listed in Appendix B.

3.1.2 Autrey Reports (ORNL/ER-13,1990 and ORNL/ER-19,1992)

The Autrey reports8-9 present the results of a 2-year effort to sample and analyze thecontents of 30 inactive radioactive waste storage tanks, including GAAT. This sectiondescribes the sample collection activities associated with the eight GAAT tanks that will becontributing sludges to MVST. The primary purpose for sampling the inactive waste tanks wasto determine whether these tanks contain hazardous wastes as defined by RCRA regulations(40 CFR Pt. 261, Subparts C and D). In addition, the tank contents needed to be characterizedsufficiently to select viable treatment strategies and meet final waste-form criteria.

From the outset of this project, it was realized that sample analyses would provide only arelative quantification of the tank liquid and sludge contents and were not meant to bestatistically defensible according to U.S. Environmental Protection Agency (EPA) SW-846protocol. Because of the physical design of most of the tanks, sample collection could takeplace only from within a very limited area inside the tank. Sample quantities were also limitedto minimize radiation exposure to the field personnel collecting the samples. The tank liquidswere expected to be fairly homogeneous given the length of time for the solids to settle.

Most liquid samples were collected with a small vacuum pump, as described inSect. 3.1.3. Although this procedure could volatilize the lighter organics in the liquid, thisapproach minimized radiation exposure to personnel and was quite simple to operate. Liquidsamples were usually collected near the top at the midpoint and at the bottom of the tank.Otherwise, samples were collected from the top and bottom of the tank.

Liquid/sludge interfaces in the tanks were found by using a Markland Model 10 sludgegun. Because earlier reports indicated that both soft and hard sludges could be found, twodifferent sludge collectors were prepared. These collectors were updated versions of thecollectors used for the Sears study. Attempts to collect sludge were made first with thesoft-sludge collector. Hard sludges were encountered in only 4 of the 12 concrete tankssampled.

103.1.3 Sears Report (ORNL/TM-11652,1990)

This section describes the sample collection techniques used to collect data for the Searsreport. Detailed, task-specific procedures are given in Appendixes E and F of ref. 10; theseinclude general sampling procedures, instructions for the different types of samplers,precleaning and decontamination of equipment, sample custody, and field log records.

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Sampling was conducted for six MVST (tanks W-24 through W-28 and tank W-31) and twoof concentrate storage tanks (tanks W-21 and W-23) at the evaporator complex in BethelValley. Samples were drawn through the penetration (the "G3" nozzle) used to house theliquid level instrumentation.This access is a 3-in.-diam. pipe that penetrates the tank from thevault ropf. Samples were collected at MVST from September to December 1989, and fromtanks W-21 and W-23 at the evaporator service facility in January 1990.

Liquid samples were taken at three levels: one-third, one-half, and two-thirds depth of theaqueous supernatant. The air-liquid and the liquid-sludge interfaces were located through theuse of the Markland Model 10 sludge gun, thus establishing the depth of the supernatant liquidin the tank. The air-liquid interface was checked for the presence of any immiscible (e.g.,organic) layer; no immiscible or stratified liquid layers were detected in the tanks with theMarkland instrument. Samples representative of a vertical "core" of sludge were collected topick up layering in the waste. Because only sludge directly under the access port can besampled, the samples may not be representative of other locations in the tank and should beconsidered merely an indicator of the tank contents. Samples of the aqueous supernatants intanks W-29 and W-30 were collected by using the pump module (Isolock) sampler. There isno access to sample the sludge in these tanks. No waste additions or transfers took place atMVST while sampling was in progress. The air spargers for MVST had been off since beforethe 1988 Emergency Avoidance Solidification Campaign, except when tanks W-25 and W-26were sparged for about 24 h to mix the liquid contents after the August 1989 waste transfers.

Samples of the supernatant liquid were collected from tanks W-21, W-23 to W-28, andW-31 by using a vacuum pump sampling system. Samples were taken as described previously,except in Tank W-21, where the liquid layer was only 8-in. deep and only one sample wastaken. The sample was pulled by vacuum from the specified level in the tank through Teflontubing into the sample jar. The depth of the liquid phase and sampling locations weredetermined from the Markland measurements. Teflon tubing was cut to length, premeasured,and marked with tape to indicate when the end of the tubing had been lowered below theaccess pipe flange to the appropriate level in the tank liquid. A stainless steel weight wasattached to the lower end to keep the tubing vertical. The upper end of the tubing was pluggedwhile the tubing was lowered to restrict entry of liquid until the desired depth was reached.After the sample was taken, the liquid remaining in the tubing was drained back into the tank,and the tubing was removed. New tubing was used at each sampling location to avoid crosscontamination of the samples.

The air-liquid interface was checked for the possible presence of an organic layer floatingon the aqueous supernatant. The bottom-opening soft sludge sampler (Fig. 3.1) was used tocollect a column of liquid at the interface. The location of this interface was determined withthe Markland detector during the presampling survey. Before sampling, the appropriate lengthwas measured on the handle of the sampling device, and the handle was marked with tape toshow how deep to lower the sampler into the tank. The sample was pulled and examinedvisually in the field for the possible presence of immiscible liquid layers. Samples from theair-liquid interface were drawn from the following tanks: W-21, W-23 through W-28, andW-31. Tanks W-29 and W-30 were not sampled because the "G3" nozzle in these tanks isbeing used to support supernatant solidification activities, and the equipment could not bereadily removed for sampling. The interface was clear in all the samples with no immisciblephases. No organic layer was observed in any of these tanks. The interface sample wasreturned to the tank, and the sampler was then used to collect a soft sludge sample.

3-5ORNL DWG 90-146

CLEAR PVC TUBE-

T SPRING RELEASE

BOTTOM CLOSUREWITH NEOPRENEGASKET

CAP PLUG

CAP

VENT HOLEV ALLEN SCREW

LOCKING PIN

jji/-CLOSURE ROD

/-SPRING

CD

_3

3-6

A bottom-opening, soft sludge sampler was used to collect a core of sludge up to 20-in.deep. The device consists of a detachable handle assembly and a hollow probe of clearpolyvinylchloride (PVC) pipe with a bottom closure that can be controlled from above. Thesludge was usually more than 20-in. deep in the tanks. Samples were collected at successivelylower layers to obtain a vertical profile. Because the sample collector is a clear material, visualmeasurements of sludge depth can be made and other properties observed. This examinationwas performed in a hot cell at the High Radiation Level Analytical Laboratory. If this samplecould not be obtained with the soft-sludge sampler, a "hard" sludge sampler was used.

The earlier work by Peretz et al.7 indicated the presence of a hard crusty layer inTank W-27 that might require cutting blades to take a sample. A commercial hard sludgesampler with an auger-type bit was used for this layer. This sampler consists of a stainlesssteel pipe (barrel) about 1.4-in. in diameter by lO-in.-long, sharpened blades at the bottom, agate valve to hold the sample in place, a vented cap, and handle sections. A cross handle wasused to apply a turning pressure to cut the sludge. Two tanks, W-27 and W-31, containedlayers of "hard" sludge.

The locations (depths) for collecting the sludge samples were developed from theMarkland data on the location of the liquid sludge interface and from the available informationon the distance from the access point to the bottom of the tank. Specific depths were definedfor collecting the upper samples. Before sampling, the appropriate lengths were measured onthe handle and marked with tape to show when the sampler had been lowered to the specifieddepth in the tank. The bottom sample was collected by pushing the sampler to the bottom ofthe tank. The depth to the tank bottom was recorded on the log sheet. In sampling lowerlayers, the sampler was closed until the bottom tip of the sampler was approximately 1 in.above the lowest point previously sampled. The sampler was then opened, lowered to thespecified depth, and the sludge sample collected.

Qualitative descriptions of the sampled material are listed in Appendix B.

3.1.4 GAAT Reports (ORNL/ER/Sub/87-99053/74,1995 andORNL/ER/Sub/87-99053/79,1996)

The characterization of the heel of material left in the gunite tanks was a well organized,extensively managed effort11'12. The August-November 1994 sampling and analysis (Phase I)of 12 underground radioactive waste tanks is documented in ref. 12. The sampling plan forthe 1995 characterization of the eight GAAT tanks is documented in ORNL Inactive WasteTanks Sampling and Analysis Plan, ORNL/RAP/LTR-88/24, April 1988. The sampling planwas amended by "Addendum 1: ORNL Inactive Tanks Sampling and Analysis Plan" in August1994 (Phase I) and again by "Addendum 1, Revision 2: ORNL Inactive Tanks Sampling andAnalysis Plan," DOE/OR/02-1354/D2, February 1995 (Phase II). Field team instructions arefound in ORNL Remedial Investigation/Feasibility Study Project Field Work Guides01-WG-20, Field Work Guide for Sampling of Gunite and Associated Tanks and 01-WG-21,Field Work Guide for Tank Characterization System Operations at ORNL. The field effortswere conducted under the programmatic and procedural umbrella of the ORNL RemedialInvestigation/Feasibility Study Program.

Tanks sampled during the Phase I campaign were W-l, W-2, W-3, and W-4 in the NorthTank Farm (NTF); W-5, W-6, W-7, W-8, W-9, W-10, and W-ll in the South Tank Farm(STF); and TH-4. Both liquid and sludge (when present) samples were collected. Preliminary

3-7

analysis results were reported in December 1994. The campaign was intended to provide datafor criticality safety, engineering design, and waste management as they apply to the GAATtreatability study and remediation.

Phase I samples were collected through existing tank risers. By using a peristaltic pump,two liquid samples were taken from tanks containing 6 ft or more of liquid-one at 1/4 and oneat 3/4 of the total depth. Otherwise, tanks were sampled at the middle of the liquid depth.Initially, 250-mL samples were taken, but because low activity in the liquids resulted in highdetection limits, the sample volume was changed to 500 mL.

Phase I sludge samples were collected in a l-in.-diam. tube lowered vertically into thesludge. Clear Lexan tubes were used for soft sludges so that any layering could be observed.Stainless steel tubes with a honed edge were driven by hand into the sludge bed in an attemptto collect any hardpan sludge on the tank floor. Before each sample was taken, the depth ofthe liquid and sludge was measured by using the top-of-riser elevation as a reference. Theliquid level was measured by a standard water level meter designed for use in wells. Thesludge was measured by a sludge probe based on a photoelectric eye. The water-level meter isvery accurate, but the sludge probe is less so. On the basis of some trial-and-error andduplicate measurements, the sludge probe was discovered to be accurate to approximately±1 in.

Eight tanks (W-3 and W-4 in NTF and W-5 through W-10 in STF) were sampled again(Phase II) from May through August 1995. Analyses of the samples began immediately uponreceipt, and data validation and data base preparation were completed in December 1995.

Access to the tanks was again through existing risers. Two methods were used to collectinformation inside the tanks: pole samplers, as in Phase I, and a newly developed tankcharacterization system (TCS). TCS was developed because the tube sampler could onlycollect samples directly beneath existing tank risers. TCS is a floating system that uses theexisting water in a tank as a platform and support for instruments and samplers. A floatingboom is fed into the tank through the riser, and its position within the tank is controlled byrotation and insertion/withdrawal. An instrument or sampler is mounted at the end of theboom. TCS is an inexpensive system assembled from off-the-shelf components that allowsaccess to all parts of a tank. The major components of TCS are the boom system (supportstructure and floating boom) video camera and lights, sludge grab sampler, wall chip sampler,and sonar depth finder. The boom system consists of a plastic chain with added flotation and alazy-susan support structure that rests,on top of the tank riser. Positioning of the TCS boom isrecorded in polar coordinates: distance and angle. Mock-up testing showed positioning to berepeatable within a few inches.

The video camera was intended for above- and below-water inspections of tank contents;however, underwater inspections were not successful because of unexpected optical propertiesof the wastewater (the camera could not focus, although it worked well in a swimming pooland a mock-up tank).

The sludge grab sampler was used to retrieve samples from the tanks. The sampler is aclamshell device that is lowered from the TCS boom (by a motorized reel) to the bottom ofthe tank. The sampler is then closed by a hydraulic actuator and retrieved. Because it islowered from a floating system, the clamshell must be lightweight. Though the hydraulic

3-8

actuator is quite strong, the clamshell does not have enough weight to sink into denser sludges.This is.likely to bias the samples somewhat toward lighter materials in the tanks.

The sonar depth finder consisted of a commercially available depth finder mounted on thefloating boom. By varying the sensitivity of the system, the operator can discriminate betweenthe sludge surface and the bottom of the tank. High sensitivity settings return the sludgesurface position, and low sensitivity settings return the denser concrete bottom.

TCS was used to characterize tanks W-3, W-4, W-5, W-6, W-8, W-9, and W-10.Tank W-7 contained almost no standing water; therefore, sludge samples were collected inl-in.-diam tubes lowered vertically into the sludge directly beneath the risers. Clear plastictubes were used for soft sludges so that any layering could be observed. Stainless steel tubeswith honed edges were hand-driven into the sludge bed to collect hardpan sludge that may reston the tank floor. Four samples were collected from Tank W-7: two in Lexan tubes and two insteel tubes.

Sludge mapping was used for more accurate calculation of the quantities of materialpresent. The maps were created from data collected by TCS. Testing at the GAAT test tank atthe New Hydrofracture Facility showed the measurements to be accurate to +0.1 ft, which wasconfirmed by duplicate field measurements and by an optical sludge probe directly below thetank risers. Sludge maps were generated by using "Surfer for Windows" software.Questionable sonar measurement points (where the field team noted objects or strange sonarsignal characteristics) were removed from the database before plotting. The readings are basedon operator interpretation because density variations in both the sludge and the "bottom" cancause variation in the results, particularly if the bottom of a tank is covered with hard sludgeor sand and gravel. Detailed maps are shown in Appendix B of ref. 12. Appendix B presents asummary of qualitative field observations.

3.1.5 1996 OHF Report and Recent MVST and BVEST Data

Tank sampling methods used for the 1996 sampling13 of the OHF tanks were identical tothose used for the Sears study, as were tank sampling methods used for the 1996 sampling14'15

of BVEST and MVST. Qualitative descriptions of the samples are found in Appendix B.

3.2 PREVIOUS REPORTS, ANALYTICAL METHODS, AND LIMITATIONS

This section summarizes the analytical methodology and data limitations for radioactivewaste tank'samples collected from 1985 to present. The full scope of analytical data discussedin this summary was not taken as part of a comprehensive characterization of the LLLWsystem. The waste tank data collection represents many different projects with different needs,analytical requirements, and data quality objectives. In addition, the list of analyticalmeasurements and the quality level varied between projects. The scope of this data reviewincludes MVST, the BVEST, the OHF tanks in WAG.5, and the inactive GAAT located inNTF and STF. On the basis of major chemical characteristics, these waste tanks can begrouped into three categories. The characteristics of these four groups of radioactive waste arelisted in Table 3.2.

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Table 3.2. Categorization of waste by similar chemical properties

Category Tanks" Chemical characteristics

Group 1

Group 2

Group 3

BVEST + MVSTW-21, W-22, W-23, W-24, W-25,W-26, W-27, W-28, and W-31

GAATW-3, W-4, W-5, W-6, W-7, W-8, W-9,and W-10

OHFT-l, T-2, T-3, T-4,T-9

High Na or K nitrate contentModerate levels of depleted uraniumSludge both RCRA and TRU

Water washedLow Na and K nitrate content

, Moderate levels of normal uraniumSludge both RCRA and TRU.

Low Na and K nitrate contentElevated nitrite and tributyl phosphate contentModerate levels of enriched uraniumHigh thorium contentHigh radioactive Sr contentSludge both RCRA and TRU

Tanks C-l and C-2 are not on this list because there is no access for sampling. These tanks have never beensampled. Tanks W-29 and W-30 were not sampled because access to the sample ports are blocked withpipelines to the LWSP solidification equipment.

3.2.1 Peretz Report (ORNL/TM-10218,1986)

The earliest data considered for this summary are those in the the Peretz7 et. al report,which discusses data collected in from 1985 to 1986. The Peretz report is a good source forradiochemical and physical data for the MVST and BVEST systems, but the inorganic datahave limited value because large sample dilutions were required before measurements onanalytical instruments not designed for radioactive work. Inorganic data was not provided forsludge samples. Some elemental data were measured by spark source mass spectrometry(SSMS) provided for liquid samples from MVST and a few small waste collection tanks.Measurements by SSMS are semi-quantitative at best, with typical error ranges of 300-500%.The only organic data provided were for the LLW Collection System (WC-10, WC-13,WC-14, 2026, 3019, REDC, Oak Ridge Reservation, and High Flux Isotope Reactor), whichincludes small tanks located at several ORNL facilities. The Peretz report is the only reliablesource of radiochemical data for tanks W-29 and W-30 sludge inventory.

3.2.2 Autrey Reports (ORNL/ER-13,1990 and ORNL/ER-19,1992)

The Autrey8-9 et. al reports discuss the first "systematic ORNL effort to determine the EPAhazard classifications for the radioactive supernatant liquids and sludge contained in theinactive waste tanks. The two reports on this project involved the inspection, sampling, andanalysis of 30 out of 33 radioactive waste tanks located throughout the ORNL complex. Thescope of this project included the GAAT and OHF tanks listed in Table 3.1 plus severalmiscellaneous inactive tanks. The primary goal of this project was to identify inorganic andorganic waste classifications for each tank by RCRA regulations (40 CFR Pt. 261, Subparts Cand D). Limited funding was available for the additional radiochemical, process metal, andphysical measurements, which explains the short list of metals (uranium and silicon) outsidethe regulatory envelope and the cursory summary provided for the anion data. Theradiochemical data consisted of gross alpha/beta measurements, gamma spectrometry for the

3-10

major emitters, total radioactive strontium (89Sr + 90Sr), and an inexpensive identification ofalpha emitters by alpha spectrometry with no prior chemical separations or sample clean-up.Strontium-89 is analyzed for but is not normally found because it has decayed. There was nofunding for analyzing the uranium or plutonium isotopics by mass spectrometry to addresscriticality concerns.

The data collected for the Autrey report was one of the early attempts to apply the EPASW-84616 analytical methodology for inorganic and organic measurements to radioactivesamples. The application of SW-846 to radioactive samples was a considerable learningexperience for the laboratory, and the techniques and data quality have improved significantlysince these data were collected. Some of the problems with the application of regulatorymethods to radioactive samples included addressing as low as reasonably achievable (ALARA)concerns (both dose and contamination control), meeting holding times with the additionalsample handling requirements, and the chemical complexity of the samples, which resulted ininterference problems not addressed by the regulatory methods. Also, expectations for qualitycontrol acceptance criteria for matrix spike recoveries and duplicate reproducibility wereunrealistic. The performance of these quality control measurements were degraded because ofthe complex chemical matrix effects and the sample handling constraints required because ofthe radioactivity.

The metal data for the Autrey report- was significantly better than previous projectsbecause new analytical instrumentation designed for containment of radioactivity was installedin the laboratory for this project. The new instrumentation included an inductively coupledplasma-atomic emission spectrometer (ICP-AES) and a graphite furnace atomic absorption(GFAA) system with a mercury cold vapor attachment. Both of these instruments wereconfigured in radiochemical hoods with filtered ventilation for contamination control andpersonnel safety. The anion data for this project have limited value because an ionchromatograph for radioactive samples was not available and large dilutions were requiredbefore analysis of the samples in a conventional laboratory not designed to handle radioactivematerials. The analytical error for these inorganic measurements are within the range ofcurrent performance standards of approximately ±10%, but the data user should be aware thatthe ICP-AES measurement errors increase significantly for the Autrey data if highconcentrations of iron or uranium were present.

No analytical instruments were in place for organic analysis on radioactive samples duringthe time period of the Autrey project, but the lack of this equipment had little impact on thedata quality for some of the organic measurements. The sample preparation methods for thevolatile organic analysis (VOA) and the semivolatile organic analysis (SVOA) involvesextraction into organic solvents. The extractions separate^most of the radioactivity from theorganic compounds of interest allowing measurements by gas chromatography/massspectrometry (GC/MS), performed in a "cold" laboratory. The luxury of removing theradioactivity was not available for the category of water soluble organic compounds measuredby nonhalogeriated volatile organic analysis (NHVOA) methods such as direct aqueousinjection gas chromatography (DAIGC). DAIGC measurements for this project required largedilutions to reduce the radioactivity before measurements. PCB measurements were notperformed for the Autrey project.

The quality of the radiochemical data for the Autrey reports was sufficient for wasteclassification, but the data user needs to realize that the activities reported for the actinideelements are based on gross screening measurements by alpha spectrometry with no sample

3-11

preparation to improve the alpha spectra. There was insufficient funding for radiochemicalseparations to reduce the dissolved solids and spectral interferences for alpha spectrometry.Radiochemical separations were performed for the tritium, 14C, and total radioactive strontiummeasurements because there were no less-expensive alternatives. The gross alpha activitiesreported for the Autrey project may be biased low if the sample matrix had high dissolvedsolids present. The radionuclides measured by gamma spectrometry—which mostly consists ofthe Cs, Co, and Eu isotopes—meet current quality standards with a typical error range of±10%.

Based on recent data, two obvious typographical errors occurred in the data tables fromthe first Autrey report. The first error is in Table 4.4 of ref. 8, for sample T3/S4 involving thesludge density, which was reported as 1.930 g/mL but should have been 1.390 g/mL. Thesecond error also involved transposing results between two data fields and effects the activitiesreported for 252Cf and244Cm for sample T2/S40 in Table 4.6 of ref. 8. Based on recent dataand the pattern observed for the other OHF sludge samples reported in ref. 8, the 252Cf activityis <200 Bq/g and the 244Cm activity is 1.8e+05 Bq/g. Based on data collected since 1985, therehas never been any 252Cf activity identified in the LLLW processing systems including GAAT,OHF tanks, MVST, and BVEST.

3.2.3 Sears Report (ORNL/TM-11652,1990)

The purpose of the Sears10 study was to determine the characteristics of the supernatantand sludge contained in the active LLLW system, which includes both the MVST and BVESTsystems as listed in Table 3.1. The objective of the Sears study was to provide wastecharacterization data to satisfy the following needs:

• determination of TRU classification,• determination of RCRA classification,

support the LWSP, and• support research and development activities for waste management alternatives.

Samples of the supernatant liquid and sludge were collected from MVST and two of theBVEST (W-21 and W-23). These samples were analyzed for major chemical constituents,radionuclides, RCRA metals, total organic carbon, and physical properties. The project alsoincluded a scoping survey for VOA and SVOA constituents in liquid and sludge from tanksW-24, W-25, and W-31. To support the liquid waste solidification project, the liquid fromtwo of MVST (W-29 and W-30) were also characterized for the organic compounds.

The quality of the analytical data for the metal and organic measurements on the MVSTand BVEST samples is comparable to the data set for the Autrey report, and the discussionson the analytical error also apply to the Sears data set. Overall data quality improved somebecause the laboratory staff gained experience by working on the Autrey project. A significantdifference observed with the MVST and BVEST samples was a much higher sodium andpotassium nitrate content in both the supernatant liquid and sludge. This high nitrate saltcontent did cause measurement problems with the GFAA and ICP-AES methods. Thealkali-nitrate matrix was very corrosive to the graphite furnaces used for GFAA measurementsand very few samples (<10) could be processed without replacing the furnace tube. Thesupernatant liquids had a high dissolved solids content and required a large dilution beforemeasurement by ICP-AES to avoid problems with the sample introduction system into the

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plasma. The list of metals determined was extended to include nine more common metals ofinterest to the developmental staff working on waste management options.

The level of chloride present in the MVST and BVEST liquid and sludge samples weresufficient to cause the loss of silver as insoluble silver chloride, which resulted in low spikerecoveries for silver. No attempt was made to improve the silver spike recoveries because mostof the samples exceeded the regulatory limits for several other RCRA metals. Also, the methodfor improving silver recovery uses high levels of chloride, which is very corrosive to stainlesssteel. Stainless steel is used extensively in radiochemical laboratories for laboratory bench tops,hoods, and glove boxes.

The soluble silicon listed for the liquid samples in the Sears report have limited valuebecause the samples were acidified before measurement, which results in the loss of insolubleforms of silicon. Total silicon in the sludge was not measured for this project. The quality ofthe remaining metal data in the Sears report is sufficient to meet most waste managementdecisions.

The measurement of inorganic anions in the supernatant liquid samples required largedilutions to handle the high nitrate levels, and only the chloride and nitrate results areacceptable. Anion data were not provided for the sludge samples in the Sears report.

The quality of the radiochemical data in the Sears report is sufficient for most wasteclassification requirements with the exception of the235U activities reported for the sludgesamples. Waste management requested that the 235U activity be reported after the project wascompleted and the report was in preparation. Funding was not available to re-analyze thesamples for ^ U , and the laboratory was requested to provide estimates based on existinggamma, spectrometry data. Because of the sample dilutions used to optimize the counting forthe major gamma emitters, the detection limits for 235U were so high that the calculatedactivity limit gave a result that was physically impossible. The 235U data was listed in thereport as less than values with unit of activity, and it was not apparent, unless the activitieswere converted to mass, that the results were implying a 235U mass that exceeded 100% of thesample weight. Therefore, the ^ U data in the Sears report should not be used.

There may be a low bias for the gross beta data because of the loss of radioactive cesiumas a volatile chloride salt when the counting plates were prepared for counting on a gas-flowproportional counter. Current studies indicate that some of the cesium chloride is lost attemperatures in excess of 400°C, which is typical when preparing counting plates. For the lastseveral years, the Radioactive Materials Analytical Laboratory (RMAL) has used liquidscintillation counting for all gross beta measurements to avoid this problem. The cesiumactivities determined by gamma spectrometry are not effected by this temperature problembecause the sample preparation does not use high temperatures.

The alpha activity data show some improvement for the Sears report when compared withearlier data because the high dissolved solids content was reduced with a ferric hydroxideprecipitation to separate the actinides from the high sodium/potassium nitrate. This technique isdiscussed in the Sears report along with some performance data for the technique. In general,most of the radiochemical measurements have an analytical error in the range of ±10%.

The quality of the organic data for the Sears report is similar to previous organic dataprovided for waste tanks, and the discussions for the Autrey organic data applies to the Sears

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data. The VOA and SVOA compounds were extracted into organic solvents, and theextractions with low levels of radioactivity were transported'to conventional laboratories forGC/MS measurements. The water soluble organics were determined by DAIGC after a largedilution to reduce the radioactivity. PCB measurements were not performed for the Searsproject.

3.2.4 GAAT Data (ORNL/ER/Sub/87-99053/74,1995 andORNL/ER/Sub/87-99053/79,1996)

Twelve GAAT underground radioactive waste tanks were sampled and characterized fromAugust to November 1994. Both liquid and sludge (when present) were collected from tanksW-01, W-02, W-03, and W-04 in NTF; tanks W-05, W-06, W-07, W-08, W-09, W-10, andW-l 1 in STF; and tank TH-4, located east of STF. A summary11 of the Phase I GAAT datawas published in June 1995. Then 8 of the 12 GAAT tanks (W-03 through W-10) wereresampled for sludge in different locations during the summer of 1995 to determine the degreeof heterogeneity for the selected waste tanks. A summary12 of the Phase II GAAT data waspublished in February 1996. An evaluation17 of the Phase I and II data was published inMarch 1996. The Phase I and II GAAT projects generated the most extensive collection ofanalytical data for ORNL waste tanks available at the time the project was completed. Thequality assurance level for this data set is sufficient to meet current waste acceptance criteria(WAC) and regulatory requirements for most waste storage sites. The transuranic sludge fromthe Phase II samples (tanks W-06 through W-10) was characterized under a DOE/CAOapproved quality assurance project plan for Waste Isolation Pilot Plant (WIPP)characterization, which should classify the data as acceptable knowledge for the WIPP WAC.The sludge collected in Phase II provides the only set of ORNL tank data available to evaluatethe horizontal distribution of chemical and radiochemical species throughout the tanks.

Most of the analytical methodology for the GAAT projects employed the current RMALanalytical protocols for characterization of liquid and sludge from ORNL waste tanks. Allsamples were digested with microwave techniques before analysis. The liquids were eitherfiltered to remove suspended particles through Whatman 20 micron ashless filter paper orclarified by centrifugation. Forty milliliters of the clarified sample was then transferred to aTeflon™ microwave vessel, and 5 mL of concentrated nitric acid (15.8M) was added for thedigestion. The digestion followed the SW-846 Method 3015, Microwave Assisted Digestion ofAqueous Samples and Extracts. Sludge samples were prepared by weighing about 0.5 g (wetweight) of sample into a Teflon microwave vessel and by adding 10 mL of concentrated nitricacid. After digestion any remaining residue (mostly insoluble silicates) was removed bycentrifugation. The sludge digestion followed SW-846 Method 3051, Microwave AssistedDigestion of Sediments, Sludges, Soils, and Oils. The digested samples were then distributedfor metal and radiochemical analysis. Studies have been performed to verify that thesedigestion techniques are sufficient to give the total content for all analytes except silver andsilicon. The silicon content was not requested for this project; silver data is discussed in thissection.

A total of 26 metals were determined by either ICP-AES or GFAA, including 9 RCRAmetals and 17 metals of interest for process development, waste treatment options, andcriticality safety. Mercury was determined by cold vapor atomic absorption; arsenic, lead,selenium, and thallium were determined by GFAA; all remaining metals were determined byICP-AES.

. 3-14

All of the metals measurements followed protocols established in SW-846 methods, whichincluded the following protocols:

• Method 6010A: Inductively Coupled Plasma - Atomic Emission Spectroscopy;• Method 6020: Inductively Coupled Plasma - Mass Spectrometry;• Method 7000A: Atomic Absorption Methods,

7060A: Arsenic (AA, Furnace Technique),7421: Lead (AA, Furnace Technique),7740: Selenium (AA, Furnace Technique), and7841: Thallium (AA, Furnace Technique);

Method 7470A: Mercury in Liquid Waste (Manual Cold Vapor Method); and• Method 7471A: Mercury in Solid or Semisolid Waste (Manual Cold Vapor Method).

The sample preparation method listed in Method 7471A was replaced with Method 3051to improve contamination control and improve the recovery of mercury from sludge samples.A collaborative study18 involving ORNL, RMAL, and Argonne National Laboratory wasperfomed to demonstrate equivalency with the SW-846 method. EPA requested that the resultsof this study be included in the next update of SW-846.

Sludge samples that contained high levels of uranium (>1000 mg/L) resulted in excessivespectral interferences in the measurement of several metals (aluminum, antimony, beryllium,copper, magnesium, silver, and vanadium). The uranium was removed by techniques19

developed by RMAL using extraction chromatography, specifically the use of a commerciallyavailable ElChrom TRU-Spec™ resin developed by Argonne National Laboratory. The sludgedigest was passed through a TRU-Spec column followed by a 4 M nitric acid wash. Allactinides, including the uranium, were removed from the sample solution. The acid solutionfrom the initial loading plus the acid wash was combined, diluted to a known volume, andanalyzed by ICP-AES.

The silver data for the GAAT project has limited value as a result of poor spikerecoveries, which resulted from the precipitation of silver chloride. No attempt was made toimprove the silver recovery for the reasons discussed previously. The soluble silicon in thesupernatant liquid samples and the total silicon in the sludge samples were not determined forthe GAAT project. All metal, anion, and radiochemical data for the sludge samples were •reported on a wet weight basis. The water content for each sludge sample was reported so thedata can be converted to a dry weight result if needed.

The uranium and plutonium isotopics were determined after radiochemical separation bythermal ionization mass spectrometry.(TIMS). The uranium and plutonium isotopic ratios,along with the total uranium and thorium by ICP-AES, are needed for the evaluation ofcriticality safety. For liquid samples with a high pH, only the uranium isotopic ratios weremeasured by TIMS; the plutonium concentration in basic samples were too low for TIMSmeasurements and a conservative lower boundary for the isotopic dilution of the fissileplutonium was estimated from the radiochemical data. The isotopic ratios for both the uraniumand plutonium in the sludge samples were measured by TIMS. The mass spectrometry data foruranium and plutonium was used to calculate the activity for all the uranium and plutoniumisotopes observed. For long lived radionuclides, the mass spectrometry measurements aremore accurate and sensitive than conventional counting techniques.

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The inorganic anions in the supernatant liquid samples were measured directly by ionchromatography (IC) after a dilution with water. The sludge samples were prepared byweighing 1 g of wet sludge into 10 mL of water which was agitated for 10 min. The slurrywas centrifuged, and the supernatant was analyzed for water soluble anions. The ICmeasurements followed SW-846 Method 9056, Determination of Inorganic Anions by IonChromatography. The insoluble anions in the sludge were not determined for the GAATprojects. Mthods used on more recent samples can be used to determine the total halides, totalphosphorous, and total sulfur to estimate the corresponding insoluble anions present in thesludge samples. The insoluble carbonate (mostly calcium carbonate) can be estimated fromthe total inorganic carbon measured after combustion in a carbon analyzer.

The major metal content, along with the anion data, can be used as a quality check bycalculating the mass and charge balance for each sample. All of the liquid and sludge samplesanajyzed for the GAAT projects yielded good agreement for both mass and charge balance.The mass and charge balance results are excellent considering the assumptions required aboutthe chemical form and oxidation states present in the samples.

The sludge in the GAAT tanks had been extensively washed with water during sluicingoperations before sampling. This water wash removed most of the water soluble salts (mostlysodium/potassium nitrate), which significantly lowered the dissolved solids content in theliquid samples and decreased the salt content of the sludge samples. Because of the lower saltcontent in the samples, special sample preparation for alpha measurements was not necessary.The gross alpha measurements were taken by gas-flow proportional counting with the voltageplateau lowered below the level where beta particles would be counted to ensure minimuminterference. The gross beta measurements were performed by liquid scintillation counting toavoid the loss of radioactive cesium observed when high temperatures are used preparingcounting plates. The analytical errors for the alpha activity measurements were in the range of±8-10%. The gross beta activity reported is actually a total activity that included thesummation of counts from the beta particles, alpha particles, and the conversion electrons. Formost samples, the beta counts dominate the total activity. The analytical errors for the totalactivity measurements were in the range of ±8-10%.

The gamma emitters were determined by gamma spectrometry with a n-type high-puritygermanium detector that had a nominal efficiency of 25% relative to the standard sodiumiodide detector. All positively identified gamma-emitting radionuclides were reported alongwith less than values for 60Co, 152Eu, 154Eu, and 155Eu, which are routinely observed in OKNLwaste. The analytical error for the gamma emitting radionuclides was in the range of±10-12%.

Determination of total radioactive strontium (89Sr +90Sr) requires a chemical separation toremove the 90Y in secular equilibrium with the 90Sr. Because of the absence of othershort-lived radionuclides in the waste, no attempt was made to determine the 89Sr(t1/2 = 50.5 days), and the total radioactive strontium was reported as 90Sr activity in the GAATdata reports. The analytical error for the total radioactive strontium was in the range of '±10-15%.

For ORNL waste, Plutonium alpha activity is the primary driver for determination of theTRU waste classification based on the 100 nCi/g (3700 Bq/g) requirement. To ensure anaccurate measurement of plutonium, the plutonium was chemically separated from all otherradioactivity before measurement. After the plutonium separation, the relative isotopic

3-16

distribution was determined by both alpha spectrometry and TIMS. The measurement byalpha spectrometry only provides acceptable data for the 238Pu and the sum of the239Pu and240Pu. The239Pu and240 Pu peaks cannot be resolved because of a similar alpha energy(5.50 MeV). The TIMS measurements give an accurate result for all the plutonium isotopes,including 241Pu, which is a pure beta emitter. The activity for each plutonium isotope can becalculated from the relative atom percent for each isotope and the total plutonium alphaactivity. The analytical error for the plutonium activities were in the range of ±5-8%. The241Am activity can be estimated by subtracting the238 Pu activity, measured after the plutoniumseparation, from the 5.15 MeV alpha peak (238Pu + 24IAm) measured by alpha spectrometry onthe gross alpha counting plate. The 241Am has a 59 KeV gamma ray, but the high backgroundbelow 100 KeV with a n-type germanium detector introduces a large error for the 241Amgamma peak area. Also, none of commercially available gamma peak processing softwaretested to date performs well measuring the peak area for high count rate samples in the energyregion of 59 KeV.

The sludge samples were analyzed for PCBs during Phase I of the project. The sampleswere prepared by SW-846 Method 3550A, Ultrasonic Extraction, and Method 3665, SulfuricAcid/Permanganate Cleanup. The samples were then measured by SW-846 Method 8081,Organochlorine Pesticides and PCBs as Aroclors by Gas Chromatography: Capillary ColumnTechnique. Only Tank W-10 exceeded the internal Lockheed Martin Energy Systems, Inc.,limit of 2 ppm with a total PCB content of 3.4 ppm (Aroclor 1254 + 1260). None of theliquid-phase samples were analyzed for PCBs because of the low solubility of PCBs in water.

In Phase n, sludge samples were taken from two different locations in each tank sampled.The sludge sample from tanks W-06 through W-10, which are all transuranic waste, werecharacterized for VOA, NHVOA, and SVOA by protocols established in SW-846 methods,which included the following protocols:

• Method 8260A: Volatile Organic Compounds by Gas Chromatography/Mass •Spectrometry (GC/MS): Capillary Column Technique.

• Method 8270B: Semivolatile Organic Compounds by Gas Chromatography MassSpectrometry (GC/MS): Capillary Column Technique. Samplepreparation by Method 3550A: Ultrasonic Extraction.

• Method 8015A: Nonhalogenated Volatile Organics by Gas Chromatography.

The organic measurements were done on two samples collected from different locations ineach of the tanks except Tank W-7. Tank W-7 had the organic measurements done on threelocations along a vertical core of the sludge.

The organic analytical methods used for the GAAT sludge samples were the same asthose used for the DOE/CAO Transuranic Waste Characterization Program (TWCP) and, asstated before, were based on SW-846 methods adapted for radioactive samples. Thesemethods were qualified by the method performance demonstration requirements of the TWCPQuality Assurance Program Plan, Revision B. Blanks, matrix spikes, and matrix spikeduplicates were prepared and run with the samples. The VOA and SVOA measurementsincluded surrogate standards.

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3.2.5 OHF Data (1996)

The OHF tanks consist of five tanks located in WAG 5 and include Tl through T4 andT9. OHF supernatant liquid samples were collected in January 1996; sludge samples werecollected in February-March 1996. The OHF data are summarized in a letter report13. Thegamma radiation dose rate from the OHF sludge samples were comparable to the MVST orBVEST sludge samples. However, the beta radiation dose from the OHF sludge was an orderof magnitude worse than any other OKNL sludge samples processed by the RMAL staff. Thisadditional beta dose was caused by the higher levels of 90Sr present in the OHF sludge. Highlevels of RCRA metals (Cr, Hg, and Pb) were observed in all the OHF sludge samples, and allthe sludge samples were determined to be transuranic based on plutonium content. Elevatedlevels of 233U was observed in the OHF sludge samples, and the sum of the,233 U and23SUexceeded the administrative criticality control limits for waste. This will complicate anytransfer of this material to other waste tanks until this concern is addressed. A significantdifference occurred in the uranium isotopic ratios for the OHF supernatant liquid samples andthe OHF tank sludge samples. This difference may indicate that the OHF sludge samples donot represent the overall sludge content for each tank or could indicate that the liquid is not inequilibrium with all of the sludge.

Most of the discussions concerning the GAAT data also apply to the OHF tank data withthe exception of the silver and silicon results. The sample preparation for both the liquid andsludge samples were taken through a nitric-hydrochloric acid digestion to ensure acceptablespike recovery for the silver. The liquid samples were diluted with water and maintained basicfor measurement of the soluble silicon. The sludge samples were digested in thenitric-hydrofluoric acid to ensure acceptable measurement of the total silicon present. Thequality assurance level for the OHF data set was similar to the GAAT project and is sufficientto meet the waste acceptance criteria and regulatory requirements for most waste storage anddisposal sites. All five of the sludge samples from the OHF tanks were characterized under aDOE/CAO approved quality assurance project plann for WIPP characterization, whichclassifies the data as acceptable knowledge for the WIPP WAC.

3.2.6 Recent Data for MVST and BVEST (ORNL/TM-13234,1996 andORNL/TM-13248,1996)

Analytical data for samples collected from several of the active waste tanks fromNovember 1993 through February 1996 are summarized in two ORNL reports. Thesupernatant liquids from MVST tanks and sludge from W-21, W-23, and W-25 werecharacterized by RMAL, and the results are presented and discussed in a recent ORNLreport14. The supernatant and sludge from BVEST Tank W-22 was sampled in the fall of1994 and characterized by RMAL; the data are documented in a recent Sears15 report. Thesamples analyzed and reported in these reports were not taken as part of a plannedcomprehensive characterization of the LLLW system. The samples were collected at differenttimes with different analytical requirements. Therefore, the set of measured parameters mayvary some from tank to tank. The level of quality assurance approximates that required forregulatory measurements with the understanding that sample size requirements are reduced andmodifications to reduce sample handling are required for radiation dose considerations(ALARA). Also, some procedure modifications are required to handle matrix interferenceproblems. Deviations from procedures or other sample problems are documented in the datafiles located in RMAL. The regulatory holding time requirements for mercury and organicanalyses complied with the SW-846 requirements.

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Previous analytical work on the MVST and BVEST liquid and sludge samples did notspecifically address criticality concerns. There was limited radiochemical data on 233U, 235Uand 239Pu; the data reported was taken from gross screening measurements. The past data forfissile actinides in these waste tanks had relatively large analytical errors and should be usedwith caution. The new analytical data for fissile isotopes in this report are based on moreprecise and accurate techniques. The uranium and plutonium were each chemically separatedfrom the waste matrix and isotopic ratios were determined by thermal ionization massspectrometry. The mass spectrometry data gives detailed and accurate information on themajor fissile isotopes present. How.ever, these isotopic ratio measurements for the sludge donot represent the average isotopic ratios for all the sludge present in each tank. The isotopicdata for each liquid sample should be more representative of the overall supernatant presentthan comparable measurements for the sludge. On the basis of physical observations, the tanksludge tends to be segregated into vertical layers, which indicates minimal mixing of thesludge material as it was added to the tank. Because of limited access to the tanks, noanalytical data are available to evaluate segregation horizontally across the tank.

This recent data for MVSTand BVEST samples provides the first accurate data foruranium and plutonium isotopic ratios in the active LLLW system and was needed to addresscriticality safety questions for the these waste tanks. All the uranium isotopic ratiosdetermined for MVST and BVEST samples indicate the fissile isotopes of uranium (233U and^ U ) have been highly diluted with238 U. Some of the first radiochemical data foF Tc2,37 Np,and 24'Pu activities in the active LLLW system are provided in these recent data summaries.Although, we are confident that greater than 99% of the radioactivity has been accounted forin these waste samples, there remains some interest in the measurement of radionuclides fornickel (5?Ni and 63Ni) and samarium (51 Sm). These additional radionuclides need to beconsidered for future waste characterization projects.

The quality assurance level for the MVST and BVEST samples was similar to the OHFproject and is sufficient to meet the waste acceptance criteria and regulatory requirements formost waste storage and disposal sites. The transuranic sludge from the W-21, W-22, W-23BVEST tanks was characterized under a DOE/CAO approved quality assurance project planfor WIPP characterization, which classifies the data as acceptable knowledge for the WTPPWAC.

3.2.7 Summary of Data Limitations and Data Qualifications

Table 3.3 summarizes some of the data limitations and other qualifications associated withthe data available for the waste tanks listed. The most critical data limitation associated thecharacterization of underground storage tanks is the limited access to the tank contents, whichrestricts the options available for statistical sampling. Both vertical segregation in the sludge(layering) and concentration gradients have been observed in the liquid phase. For the MVST,BVEST, and OHF tanks the sludge has only been sampled in a single location. Many of theGAAT tanks had sludge samples taken at three different locations, and large differences inconcentration were observed for most species measured.

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Table 3.3 Summary of data limitations and additional needs

Category Tanks0 Data limitations/qualifications

Group 1 BVEST + MVSTW-21, W-22, W-23, W-24, W-25,W-26, W-27, W-28, and W-31

Group 2

Group 3

GMTW-l, W-2, W-3, W-4, W-5, W-6,W-7, W-8, W-9, and W-10

OHFT-l, T-2, T-3, T-4, T-9

Nonstatistical samplingSemiquantitative alpha dataHeterogenous wasteIncomplete U isotopicsIncomplete Pu isotopicsNo data for tanks Cl and C2Lack for data for W-29 sludgeLack of data for W-30 sludgeLimited PCB dataSludge both RCRA and TRUNo water soluble chelator data

Multiple samples/locationsCriticality concerns addressedHeterogenous wasteNo water soluble chelator data

Non-statistical samplingOne set of U and Pu isotopicsElevated 233U contentCriticality concerns notaddressedHeterogenous wasteSludge both RCRA and TRUNo water soluble chelator data

"Note: Tanks C-l andC72 are not on this list because there is no access for sampling.These tanks have never been sampled. Tanks W-29 and W-30 were not sampledbecause access to the sample ports are blocked with pipelines to the LWSPequipment Depleted uranium is to be added to the wastes in the OHF tanks to achievecompliance with administrative guidelines.

3.3 DATA USED FOR THE EVALUATION

For reasons discussed previously, the data used for the evaluation required close screeningso that the statistical analysis used the best possible data available. Some sludge measurementstaken several years ago were excluded from the analysis for various reasons described inTable 3.4. The supernate data were not included because the supernate content is expected tobe different by the time the private sector vendor begins processing the sludge. The raw dataused in this statistical analysis are reproduced in Appendix B. Measurements were standardizedfrom the various reports so that their units were consistent throught this report. Table 3.4 liststhe various referenced reports that contained the original data and the data from those reportsthat were restricted from this analysis.

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Table 3.4 Sludge data obtained from referenced reportsthat was restricted from statistical analysis

Report Data changes Reason

Peretz et. al(ORNL/TM-10218) 1986

For more details seeSect. 3.1.1 of this report

Autrey et. al(ORNL/ER-13) 1990

Sears et. al(ORNL/TM-11652) 1990

Bechtel(ORNL/ER/Sub/87-99053/74) 1995

Bechtel( O R N L / E R / S u b / 8 7 -99053/751) 1996.

A. Cation/anion data not usedfrom the Peretz reportB.. Samples labeled as "sludge"samples in Peretz report not used(only used samples labeled as"solid")

A. Density of 1.93 for Tank T-3sludge in Autrey report waschanged to 1.39B. 252Cf and244 Cm values for

. sludge sample from Tank T-2were reversed in Autrey report •C. 22lTh,232Th, and233U analysesgiven in the Autrey report wereremoved from this data setD. Anion analyses for sludges inthe Autrey report were not used

A. a s U analyses reported givenin the Sears report were removedfrom this data setB. Used Transuranium AnalyticalLaboratory data over Inorganicand Physical Analysis Group datawhere duplicate analyses weregiven

No changes to data set

No changes to data set.

A. Analyses not deemed reliableB. Li the Peretz report, the "sludge" sampleswere taken as liquid samples in the sludgeregion of the tanks. All other sampling ofsludges in the tanks (other analyses andreports) has been a core sample of the sludgeitself, and was referred to as a "solid" samplein the Peretz report

A. The value given in the report is believedto be wrong. This change is consistent withmore recent sampling of this tankB. Values for ^Cf and244Cm appeared to bereversed in the Autrey document. Thesevalues were switched and are thus consistentwith more recent sampling of this tank andother OHF tank samplesC. These analyses were removed from thisdata set because they were deemed unreliable.The gamma spectra were misinterpretedD. The measurement of the anions is thoughtto be to be inaccurate due to excessivedilution of samples

A. The 233U values were calculated, notmeasured, and the calculated values weredetermined to be inaccurateB. Per advice of J. M. Keller. TransuraniumAnalytical Laboratory data deemed morereliable

3-21

Table 3.4 (continued)

Report Data changes Reason

Keller et. al(ORNL/TM-13248) 1996

Sears, M. B.(ORNL/TM-13234) 1996

Francis et. al(Draft) 1996

A. Data for Tank W-25 sludgefrom the Keller report was notused in this data setB. Excluded the data for sludgesamples treated with HC1, withthe exception of the Ag, Sb, andP analysesC. Only anion analyses from thewater prepared sludge samples inthe Keller report were used inthis data set

No changes to data set

No changes to data set

A. The sludge samples had been stored andtreated differently than other sludge samples.In addition, the analyses were run withdifferent digestions than other analyses forsludgesB. Analyses of Ag and Sb are typically donewith an HNO3/HC1 digestion. P wasdetermined this way alsoC. Other analyses (other than anions) are notaccurate with a water dissolution only

The physical, chemical, and radiological measurements that OKNL has made on tanksludge range in time from 1985 to 1996. The type of measurements as well as the numbervary from tank to tank as well as from year to year. Table 3.5 lists the number ofmeasurements made for each variable for the sludge matrix.

Table 3.6 shows the average number of physical, chemical, and radiological variables foreach tank farm. The number of variables are averaged over the variables measured on thedifferent tanks in each tank farm. We see that there was no year in which all the variableswere measured.

Figures 3.2, 3.3, and 3.4 illustrate the frequency of variables measured for the physical,chemical, and radiological measurements, respectively. These figures show which variableshave the predominate measurement in the data set.

3-22

Table 3.5 Number of measurements on sludge samples from 1985 to 1996

Physicalvariables

Density (g/ml)H2O Fraction

pHTSOL (mg/g)DSOL (mg/g)SSOL (mg/g)TOC (mg/kg)ICAR (mg/kg)TCAR (mg/kg)

TSOL = TotalSolids "

DSOL =Dissolved Solids

SSOL =Suspended

SolidsTOC = Total

Organic CarbonICAR =

Inorganic CarbonTCAR = Total

Carbon

No. ofmeasurements

4237133511

614545

Chemicalvariables(mg/kg)

AgAlAsBBaBeCaCd

• Co

CrCsCuFeHgK

MgMnNaNiPPbSbSeSiSrThTlUVZn

BromidesChloridesFluoridesNitratesNitrites

PhosphatesSulfatesCyanide

No. ofmeasurements

654962486565496539657

39496549.496549657

65396212484962653939353535355

35351

Radiologicalvariables

(bq/g)

H2O FractionGross AlphaGross Beta

Am241Aul98

C14Cf252Cel44Cm243Cm244Co60Csl34Csl37Eul52Eul54Eul55

H3Nb95

Np2372JEPu/M1Am239pu/240pu

Pu238.Pu239Pu240Pu241Pu242Pu244RulO6Sr90Tc99

Th232U233U234U235U236U238

233U/234JJ

Zr95

No. ofmeasurements

378787408151710107174367666686216127

426063442828302610768

39643528284041

3-23

Table 3.6

Measurementvariable(number)

Average

Tankfarm •

number

1985

of variables

1989

measured on sludge samples

Sample year

1990 1994

for each year

1995 1996

Physical(9)

Chemical(38)

Radiological(38)

GAAT

BVEST

MVST

OHF

GAAT

BVEST

MVST

OHF

GAAT

BVEST

MVST

OHF

,0.4

8.8

7.9

2.0

4.9

2.4

13.0

22.0

13.0

13.0

19.0

14.0

5.0

22.0

19.0

5.3

8.0

32.8

27.0

23.2

26.0

4.6

32.0

19.3

5.0

6.0

12.0

37.0

26.0

26.8

O O o. OCO CO COa tn i-

Physical Measurements

Fig. 3.2. Frequency of measurements for the physical variables.

3-24

Chemical Measurements

Fig. 3.3 Frequency of measurements for the chemical measurements.

90-

<D

E70-<D

560-§50-

l°30-(D• | 2 0 -310-

u j g ^ :

nraRadiological Measurements

Fig. 3.4. Frequency of measurements for the radiological measurements.

3.4 MASS OF TANK SLUDGE

ORNL has detennined the mass and volume of the sludges in the 26 tanks considered inthis report. Table 3.7 shows the sludge masses and volumes in terms of kilograms (mass) andgallons (volume). This table also reports the fraction of the total mass 1,011,143 kilograms andthe fraction of the total volume 199,700 gallons.

Table 3.8 summarizes the sludge mass and volume by tank farm. The tank farm massfractions are used to calculate weighted means and weighted standard deviations for thesummary statistics. Figure 3.5 illustrates the percentage of the total mass for each tank farm.

3-25

Table 3.7 Sludge mass and volume for each tank

Rank

1

2

3

4

5

6

' 7

8

9

10

11

12

13

14

15

16

17

18

19

20

21

22

23

24

25

26

Tank

T-9

W-3

T-l

W-4

T-4

T-2

C-1

C-2

T-3

W-9

W-5

W-22

W-6

W-28

W-10

W-31

W-7

W-8

W-24

W-29

W-30

W-21

W-23

W-25

W-27

W-26

Sludge mass(kg)

2195

3206

4027

6359

6465

6544

7949

7949

10413

13282

15500

30113

34129

40605

42241

42922

45477

46056

56275

56624

56624

58997

90628

103921

104315

118327

Fraction oftotal mass

(1,011,143 kg)

. 0.00217

0.00317

0.00398

0.00629

0.00639

0.00647

0.00786

0.00786

0.01030

0.01314

0.01533

0.02978

0.03375

0.04016

0.04178

0.04245

0.04498

0.04555

0.05565 '

0.05600

0.05600

0.05835

0.08963

0.10278

0.10317

0.11703

Sludge volume(gallons)

500

700

800

1400

1400

1300

1500

1500

2100

2900

3500

6800

7100

7200

9300

9000

8900

10400

11800

11000

11000

10900

16400

20800

21200

20300

Fraction oftotal volume(199,700 gal)

0.00250

0.00351

0.00401

0.00701

0.00701

0.00651

0.00751

0.00751

0.01052

0.01452

0.01753

0.03405

0.03555

0.03605

0.04657

0.04507

0.04457

0.05208

0.05909

0.05508

0.05508

0.05458

0.08212

0.10416

0.10616

0.10165

Note: Sludge masses based on most recent data (fall 1996). Values for tanks C-1 and C-2 are estimates.

3-26

Table 3.8 Sludge mass and volume for each tank farm

Tank farm(No. of tanks)

OHF(5)

BVEST (5)

GAAT (8)

MVST (8)

Tanks

T-l,T-2,T-3,T-4,T-9

C-1,C-2,W-21,W-22,W-23

W-3,W-4,W-5,W-6,W-7,W-8,W-9,W-10

W-24,W-25,W-26,W-27,W-28,W-29,W-30,W-31

Sludge mass(kg)

29,644

195,636

206,250

579,613

Fraction oftotal mass

(1,011,143 kg)

0.029317

0.193480

0.203977

0.573226

OHF (5) BVEST (5) GAAT (8) MVST (8)

Tank Farm (Number of Tanks)

Fig. 3.5. Percentage of sludge mass, for each tank farm.

3.5 DATA SUMMARY

Six statistics were calculated to summarize the sludge measurements [i.e., number ofmeasurements, mean, standard deviation, minimum measurement value, maximummeasurement value, and the %relative error = 100% x (standard deviation)/mean]. These •statistics are defined in Table 3.9 below. Tables 3.10 to 3.12 list the summary statistics for alltank measurements for the physical, chemical, and radiological measurements, respectively.These tables included unweighted summary statistics for all tanks, weighted summary statisticsfor all tanks, and unweighted summary statistics for each tank farm. The weighted summarystatistics are based on the mass fraction of the four tank farms (see Table 3.8).

3-27

The detection limit values were used in the summary statistics for measurements reportedas less than the detection limit value. This procedure may cause positive biases (i.e., largerthan the true value) for the summary statistics. However, this procedure was believed to bethe most conservative approach for the data user. Measurements that are reported as zero arealso included in the database. These measurements indicated that no response was detected forthe measured variable. A zero response for a variable is different from not measuring avariable on a sample.

Table 3.9 Definition of summary statistics

Statistic Formula Description

Number ofMeasurements

N Number of measurementsfor a set of samples.

Mean

Weighted Mean

StdDevs = N-l

srt =Weighted Std Dev ^w

Minimum

Maximum

Percent Relative Error

Minimum

Maximum

%R.E. = 100% xStd Dev

Mean

Average of N measurementsrepresented by the symbols

X], X2, ..., XN

Weighted average of N" measurements. The weights are

represented byW,, W 2 , . . . ,W N .

Standard deviation of Nmeasurements. An estimate of

precision.

Weighted standard deviation of Nmeasurements. A weighted estimate

of precision. The weights arerepresented by

W,. W 2 , . . . ,W N .

Smallest value of N measurements.

Largest value of N measurements.

Standard deviation divided by themean and expressed as a

percentage. An estimate ofstandardized precision.

3-28

Table 3.10 Summary statistics for physical measurements on sludge samples

Variable

Density(g/mL)

H20 fraction

pH

TSOL(mg/g)

DSOL(mg/g)

SSOL (mg/g)

TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

Density• (g/mL)

H20 fraction

pH

TSOL(mg/g)

DSOL(mg/g)

SSOL (mg/g)

TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

N

42

37

13

35

1

1

61

45

45

42

37

13

35

1

1

61

45

45

Mean

Unweighted

1.28

0.71

10.21

467.71

25.50

242.00

5499.33

7047.56

10903.33

Std. Dev. Minimum

statistics over all tanks

0.13

0.11

0.69

184.38

•

•

5541.09

7042.96

8696.27

Weighted statistics over

1.30

0.71

10.27

473.52

25.50

242.00

4528.39

6994.18

10599.41

0.06

0.05

0.22

94.30

•

2024.75

3444.79

4306.73

1.07

0.42

9.10

253.00

•25.50

242.00

100.00

1110.00

1820.00

1 all tanks

. 1.07

0.42

9.10

253.00

25.50

242.00

100.00

1110.00

1820.00

Maximum

1.57

0.89

11.50

964.00

25.50

242.00

28000.00

32000.00

32500.00

1.57

0.89

11.50

964.00

25.50

242.00

28000.00

32000.00

32500.00

%R.E.

10.03

15.37

6.80

39.42

•

•

100.76

99.93

79.76

4.95

6.68

2.18

19.92

•

•

44.71

49.25

40.63

3-29

Table 3.10 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

Density(g/mL)

H20 fraction

pH

TSOL

(mg/g)

DSOL(mg/g)

SSOL (mg/g)

. TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

5

3

0

3

1

1

5

5

5

Unweighted statistics over OHF Tank Farm(mass fraction = 0.029317)

Density(g/mL)

H20 fraction

pH

TSOL(mg/g)

DSOL(mg/g)

SSOL (mg/g)

TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

7

5

5

5

0

0

10

5

5

1.28

0.67

10.08

441.00

•

•

9898.00

11620.00

17800.00

0.08

0.05

0.89

271.55

•

•

8239.91

4667.12

6379.66

1.16

0.60

9.30

253.00

•

•

100.00

5200.00

13000.00

1.39

0.72

11.50

921.00

•

•

28000.00

16000.00

29000.00

• 6.36

7.79

8.86

61.58

•

•

83.25

40.16

35.84

Unweighted statistics over BVEST Tank Farm(mass fraction = 0.193480)

1.37 . 0.12

0.55 0.17

441.00 150.73

25.50

242.00

6580.00 9095.50

1.17

0.42

268.00

25.50

1.46 8.81

0.74 29.84

544.00 34.18

25.50

242.00 242.00

100.00 22100.00 138.23

20100.00 9588.01 10400.00 32000.00 47.70

26640.00 6141.91 18500.00 32500.00 23.06

3-30

Table 3.10 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

Density(g/mL)

H20 fraction

PH

TSOL(mg/g)

DSOL(mg/g)

SSOL (mg/g)

TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

23

29

8

11

0

0

38

27

27

Density(g/mL)

H20 fraction

pH

TSOL(mg/g)

DSOL(mg/g)

SSOL (mg/g)

TOC(mg/kg)

ICAR(mg/kg)

TCAR(mg/kg)

7

0

0

16

0

0

8

8

8

Unweighted statistics over GAAT Tank Farm(mass fraction = 0.203977)

1.24 0.13 1.07 1.57

4588.92 4013.78 200.00 14600.00

3374.44 1678.64 1110.00 7900.00

6366.67 3814.22 1900.00 16600.00

Unweighted statistics over MVST Tank Farm(mass fraction = 0.573226)

1.35 0.12 1.26

475.56 146.76 . 342.00

3650.00 2562.99

8428.75 6745.66

12068.75 9203.75

1.54

10.82

0.73

10.29

475.73

0.10

0.59

220.21

0.58

9.10

300.00

0.89

11.10

944.00

13.32

5.77

46.29

87.47

49.75

59.91

8.61

964.00 30.86

410.00 8530.00 70.22

1410.00 21900.00 80.03

1820.00 30400.00 76.26

3-31 . .

Table 3.11 Summary statistics for chemical measurements (mg/kg) on sludge samples

Variable N Mean Std. Dev. Minimum Maximum %R.E.

Unweighted statistics over all tanks

Ag

Al

As

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

U

65

49

62

48

65

65

49

65

39

65

7

39

49

65

49

49

65

49

65

7

• 65

39

62

12

48

49

62

65

6.17

9898.58

9.02

16.74

95.31

3.25

20193.10

8.29

• 4.22

365.48"

6.00

64.22

5273.37

81.35

5378.35

3300.41

135.58

35105.71

86.53

10452.86

519.12

26.35

9.01

4932.08

133.17

13541.87

9.68

51050.97

9.39

10774.17

16.35

19.19

169.88

7.27

20680.91

9.01

4.27

488.75

7.48

50.13

5682.57

101.54

5370.36

4250.37

238.40

24397.88

89.69

3582.83

. 962.93

15.40

17.86

8843.15

230.70

26848.72

13.75

75087.89

0.01

17.50

0.47

1.20

2.94

0.00

301.00

0.52

1.30

10.00

1.43

6.03

195.00

0.82

219.00

47.80

0.00

4040.00

4.60

6940.00

5.00

9.70

0.30

159.00

2.43

94.60

0.30

451.00

50.00

51100.00

69.00

104.00

1300.00

45.40

83900.00

42.00

24.20

2400.00

22.50

293.00

20300.00

585.00

25200.00

16000.00

1510.00

82000.00

452.00

16000.00

7320.00

56.00

86.00

32500.00

992.00

124000.00

75.20

330000.00

152.13

108.85

181.23

114.67

178.25

223.80

102.42

108.66

101.33

133.73

124.69

78.06

107.76

124.83

99.85

128.78

175.85

69.50

103.65

34.28

185.49

58.45

198.13

179.30

173.24

198.26

142.13

147.08

3-32

Table 3.11 (continued)

Variable N Mean Std. Dev. . Minimum Maximum %R.E.

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

Sulfates

Cyanide

Ag

Al

As

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

39

39

35

35

35

35

5

35

35

1

65

49

62

48

65

65

49

65

39

65

7

39

49

65

49

49

65

49

3.33

141.53

448.00

558.02

1252.46

17650.81

1510.80

2396.49

3498.94

5.40

2.01

251.69

993.89

966.72

2181.11

35312.63

1823.68

2227.68

3189.21

0.38

1.50

4.63

5.00

17.50

10.00

219.00

18.50

250.00

5.40

Weighted statistics over all tanks

7.88

8012.46

17.18

12.51

93.65

1.83

24100.46

9.20

3.64

337.40

3.96

53.51

4319.89

65.61

6381.12

4052.20

104.16

43892.46

4.53

4695.30

10.21

8.14

77.30

1.97

10981.66

5.00

1.69

225.02

1.37

13.46

2581.07

37.14

2546.91

2271.74

106.43

11856.67

0.01

17.50

0.47

1.20

2.94

0.00

301.00

0.52

1.30

10.00

1.43

6.03

195.00

0.82

219.00

47.80

0.00

4040.00

7.80

1100.00

3280.00

3760.00

11900.00

,166000.00

4670.00

7900.00

9400.00

5.40

50.00

51100.00

69.00

104.00

1300.00

45.40

83900.00

42.00

24.20

•2400.00

22.50

293.00

20300.00

585.00

25200.00

16000.00

1510.00

82000.00

60.39

177.84

221.85

173.24

174.15

200.06

120.71

92.96

91.15

57.52

58.60

59.42

65.07

82.54

107.45

45.57

54.41

46.37

66.69

34.53

25.15

59.75

56.60

39.91

56.06

102.18

3-33

Table 3.11 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

Sulfates

Cyanide

65

7

65

39

62

12

48

49

62

65

39

39

35

35

35

35

5

35

35

1

63.42

13158.71

462.24

27.30

18.73

2272.82

88.75

5867.64

12.05

48161.88

2.88

133.22

506.63

470.71

1401.09

19501.12

1510.80

2722.96

3816.91

5.40

27.04

925.01

438.00

6.79

11.63

1675.01

52.81

5178.35

6.15

34238.16

0.68

110.87

443.14

364.37

968.46

15375.54

312.25

925.10

1373.99

4.60

6940.00

5.00

9.70

0.30

159.00

2.43

94.60

0.30

451.00

0.38

1.50

4.63

5.00

17.50

10.00

219.00

18.50

250.00

5.40

452.00

16000.00

7320.00

56.00

86.00

32500.00

992.00

124000.00

75.20

330000.00

7.80

1100.00

3280.00

3760.00

11900.00

166000.00

4670.00

7900.00

9400.00

5.40

Unweighted statistics over O H F Tank Farm(mass fraction = 0.029317)

42.63

7.03

94.76

24.87

62.12

73.70

59.50

88.25

51.03

71.09

23.69

83.23

87.47

77.41

69.12

78.84

20.67

33.97

36.00

Ag

Al

As

B

Ba

Be

Ca

10

5

10

5

10

10

5

1.24

20304.00

1.83

42.14

64.36

9.49

31160.00

0.83

9980.74

0.97

6.52

26.87

15.46

7068.45

0.15

9320.00

1.00

31.80

26.50

0.00

20600.00

2.90

34500.00

4.00

49.70

115.00

45.40

37900.00

66.88

49.16

53.05

15.47

41.75

162.90

22.68

Variable

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

N

10

5 •

10

5

5

5

•10

5

5

10

5

10

5

10

5

10

5

5

5

10

10

5

.5

5

5

5

5

5

5

Table

Mean -

11.21

8.90

106.63

7.32

151.26

7704.00

121.58

2600.80

3414.00

166.20

8388.00

204.10

8694.00

513.00

18.00

1 1.35

9734.00

692.40

88620.00

1.25

3245.00

7.04

179.40

32.77

1144.20

215.60

1333.90

1510.80

114.66

3-34

3.11 (continued)

Std. Dev.

3.21

4.06

65.91

8.73

85.86

6021.41

176.88

•2031.82

1214.59

186.71

5967.04

145.98

2249.31

183.77

1.41

0.40

12731.00

352.65

24615.58

0.42

2066.09

0.50

35.18

27.89

1486.96

55.86

1738.22

1823.68

87.42

Minimum

6.60

4.24

10.00

1.43

64.30

3150.00

1.80

974.00

1730.00

0.00

4040.00

50.00

6940.00

229.00

17.00

0.74

3640.00

282.00

56800.00

0.60

1000.00

6.60

149.00

4.63

247.00

140.00

27.90

219.00

18.50

Maximum

16.40

14.20

. 241.00

22.50

293.00

17900.00

585.00

6140.00

5140.00

472.00

18800.00

452.00

12600.00

860.00

20.00

2.00

32500.00

992.00

124000.00

2.00

7870.00

7.80

236.00

70.00

3760.00

272.00

4250.00

4670.00

195.00

%R.E.

28.67

45.62

61.81

119.25

56.76

78.16

145.49

78.12

35.58

112.34

71.14

71.52

25.87

35.82

7.86

29.49

130.79

50.93

27.78

33.44

63.67

7.14

19.61

85.11

129.96

25.91

130.31

120.71

76.24

Variable

Sulfates

Cyanide

N

5

0

Table

Mean

1170.20

3-35

3.11 (continued)

Std. Dev. Minimum

1048.85 339.00

Maximum

2960.00

%R.E.

89.63

Unweighted statistics over BVEST Tank Farm(mass fraction = 0.193480)

Ag

Al

As

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

5

5

5

4

5

• 5

5

5

3

5

2

3

5

5

5

' 5

5

5

5

2

5

3

5

3

4

17.33

1776.40

21.24

7.38

62.98

128

54600.00

27.40

3.02

179.20

2.69

49.67

2464.00

39.95

13054.00

10470.00

114.20

50860.00

84.80

14850.00

352.60

45.67

15.62

2059.67

265.00

21.27

840.66

22.78

2.10

11.69

1.73

18658.91

8.72

1.99

42.01

0.17

24.11

896.18

41.05

8602.88

4946.89

118.89

25256.05

18.32

1626.35

64.91

17.04

15.75

1682.83

44.16

2.03

' 852.00

4.40

5.03

48.40

0.00

33600.00

16.10

1.30

146.00

2.57

33.70

1900.00

8.44

3270.00

3620.00

0.00

15400.00

69.60

13700.00

290.00

26.00

4.40

159.00

200.00

50.00

2800.00

50.00

10.00

78.00

3.66

83900.00

39.00

5.20

248.00

2.81

77.40

4040.00

105.00

25200.00

16000.00

275.00

82000.00

110.00

16000.00

450.00

56.00

39.00

3360.00

295.00

122.74

47.32

107.25

28.48

18.56

134.94

34.17

31.81

66.01

23.45

6.31

48.54

36.37

102.77

65.90

47.25

104.10

49.66

21.61

10.95

18.41

37.31

100.85

81.70

16.66

Variable

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

Sulfates

Cyanide

N

. 5

5

5

3

3

2

2

2

2

0

2

2

1

Table

Mean

10516.00

29.44

29700.00

3.25

951.00

279.50

2145.00

171.00

146000.00

•

205.00

5785.00

5.40

3-36

3.11 (continued)

Std. Dev.

3026.17

26.49

8887.91

2.58

176.55

269.41

1449.57

19.80

28284.27

•

7.07

3174.91

.

Minimum

7460.00

10.00

17000.00

0.38

756.00

89.00

1120.00

157.00

126000.00

•

200.00

3540.00

5.40

Maximum

14000.00

75.20

39700.00

5.37

1100.00

470.00

3170.00

185.00

166000.00

•

210.00

8030.00

5.40

%R.E.

28.78

89.99

29.93

79.33

18.56

96.39

67.58

11.58

19.37

3.45

54.88

Unweighted statistics over GAAT Tank Farm(mass fraction = 0.203977)

Ag

Al

As

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

42

31

39

31

42

42

31

42

31

42

0

31

31

42

4.96 .

10754.79

2.30

16.32

111.65

2.62

7776.19

4.08

3.58

505.17

.

51.59

6163.39

86.93

7.27

11429.63

2.03

20.41

208.99

4.16

8596.51

3.45

4.06

560.42

26.70

6285.01

88.36

0.01

17.50

0.47

2.50

2.94

. 0.00

301.00

0.52

1.30,

97.00

•

6.03

195.00

0.82

26.30

51100.00

7.00

104.00

1300.00

15.60

31600.00

22.00

24.20

2400.00

•

115.00

20300.00

416.00

146.55

106.27

88.07

125.07

187.19

159.17

110.55

84.65

113.34

110.94

•

51.75

101.97

101.65

3-37

Table 3.11 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

Sulfates

Cyanide

31

31

42

31

42

0

42

31

39

4

31

31

39

42

31

31

28

28

28

28

0

28

28

0

3711.77

1294.52

156.65

29610.97

66.99

594.52

25.83

1.72

1084.00

28.71

4267.15

7.98

73116.50

2.74

57.09

534.18

339.99

1514.86

11396.75

2960.50

3751.50

4076.18 219.00

2297.73 47.80

274.52 0.00

21026.95 5070.00

60.11 4.60

1188.35

15.22

1.81

1523.30

20.98

3979.27

11.92

85516.06

1.42

69.78

1095.16

687.00

2373.40

15168.04

2144.33

3288.49

5.00

9.70

0.30

190.00

2.43

94.60

0.30

451.00

0.50

1.50

5.00

5.00

17.50

10.00

147.00

250.00

13000.00

11100.00

1510.00

68700.00

233.00

7320.00

50.00

5.40

3360.00

66.20

16400.00

36.10

330000.00

5.40

362.00

3280.00

2840.00

11900.00

42000.00

7900.00

9400.00

Unweighted statistics over MVST Tank Farm(mass fraction = 0.573226)

109.82

177.50

175.24

71.01

89.73

199.88

58.92

105.07

140.53

73.06

93.25

149.38

116.96

51.64

122.23

205.01

202.07

156.67

133.09

72.43

87.66

Ag

Al

As

8

8

8

11.75

5153.75

43.13

8.36

5036.15

15.73

5.40

830.00

27.00

30.00

16000.00

69.00

71.11

97.72

36.48

3-38

Table 3.11 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

. U

V

Zn

Bromides

Chlorides

8

8

8

8

8

0

8

0

0

8

8

8

8

8

8

8

0

8

0

8

0

8

8

8

8

0

0

0

0

7.18

68.38

0.00

39950.00

14.79

72.13

235.00

50.00

6.81

49.83

0.00

18116.05

13.69

44.34

1.20

17.00

0.00

5600.00

1.50

27.00

22.00

180.00

0.00

62000.00

42.00

170.00

118.92

16.98

120.00

29.00

470.00

86.00

94.92

72.87

45.35

92.58

61.48

2061.25

27.63

8775.00

6521.25

0.00

63250.00

43.25

2408.82

18.29

2971.17

4474.90

0.00

8713.70

24.80

420.00

11.00

6100.00

870.00

0.00

48000.00

17.00

7700.00

64.00

15000.00

15000.00

0.00

71000.00

92.00

116.86

66.21

33.86

68.62

•

13.78

57.34

50.61

33.96

122.50

4448.75

16.13

8308.75

42.34

3929.44

5.62

8098.35

30.00

1370.00

9.00

1960.00

170.00

11800.00

27.00

24100.00

34.57

88.33

34.84

97.47

3-39

Table 3.11 (continued)

Std. Dev. Minimum Maximum %R.E

e .12 Summary statistic for radiological measurements (Bq/g) on sludge samples

Variable N MeaiA Std. Dev. Minimum Maximum %R.E.

Unweighted statistics over all tanks

H20 fraction

Gross alpha

Gross beta

2 4 1Am198Au

4C1

252C f

M4Ce

243Cm

244Cm

60Co

134Cs

37

87

87

40

8

15

17

10

10

71

74

36

0.71

92537.24

8360650.57

9787.75

5133.75

494.80

126.12

12880.00

12340.00

61336.63

35237.11

3337.,14

0.11

131079.69

12640862.86

9352.41

3622.21

563.00

174.52

8787.09

7840.24

102126.04

55253.91

7769.81

0.42

900.00

70000.00

0.00

1480.00

17.00

2.00

3900.00

3600.00

6.00

12.00

20.00

0.89

650000.00

59000000.00

52000.00

9990.00

2200.00

500.00

28000.00

26000.00

530000.00

260000.00

46000.00

15.37

141.65

151.19

95.55

70.56

113.78

138.38

68.22

63.54

166.50

156.81

232.83

Variable

137Cs

152Eu

154Eu

I55Eu

3H

9SNb

237Np

B 8 P u / M 1 A m .

339Pu/M0Pu

238Pu

a 9 P u

240Pu

2 4 1 Pu

2 4 2 Pu

244pu

1 0 6Ru

9 0 Sr

"Tc

2 3 2 T h

233u

234u

a su2 3 6 u

238JJ

2 3 3 U/ 2 3 4 U

9 5 Zr

H20 Section

Gross alpha

N

76

66

68

62

16

12

7

42

60

63

44

28

28

30

26

10

76

8

39

64

35

28

28

40

4

18

37

87

3-40

Table 3.12 (conti

Mean

704835.53

130293.18

68259.07

20478.87

39.35

3517.50

10.44

765331

5401.60

8092.32

3457.32

1735.88

13840.98

3.93

0.32

22860.00

3418910.53

202.63

62.59

3231.99

846.37

21.14

1.93

846.03

1061.75

36782.22

Weighted

0.71

61104.97

Std. Dev._

1459871.60

2?7221.69

137313.41

35811.K

47.54

3656.52

4.48

10705.22

4965.43

10244.45

2801.62

2302.64

17230.17

5.97

0.42

17927.33

6108028.55

273.81

120.81

4675.30

908.01

31.10

2.26

894.32

483.64

45837.85

statistics over

0.05

35157.89

'lued)

ft*. . —

l2[)nn nnVUU.OO

i 90.00

Xoo•V 52.00\

O.OQ

S. 560.00I6.10

'o.oo

•j 210.00

6.00

100.00

3.50

• 0.10

0.00

0.00

5700.00

16000.00

13.00

0.40

0.00

8.80

0.40

0.00

11.40

342.00

1700.00

all tanks

0.42

900.00

^oooooo.oo13ooooo.oo64oooo.oo

^^Qdao

, 12210.00

19.00

51300.00

24900.00

48000.00

11000.00

8800.00

66300.00

20.00

1.00

62000.00

32000000.00

810.00

500.00

24000.00

2719.90

106.90

9.50

3000.00

1365.00

130000.00

0.89

650000.00

- _

207.12

212.77

201.17

174 87

42.87

139.88

91.93

126.59

81.03

132.65

124.49

151.95

130.24

78.42

178.65

135.13

193.02

144.66

107.28

147.15

117.28

105.71

45.55

124.62

6.68

57.54

Variable

Gross beta

241Am

198Au

4C1

252C f

I44Ce

243Cm

244Cm

60Co

134Cs

I37Cs

152Eu

i54Eu

155Eu

3H

9sNb

237Np

a MPu/M IAm

239pu/240pu

2 3 8Pu2 3 9Pu240pu

2 4 1Pu

242pu

244Pu

l06Ru

?0Sr

"Tc

232Th

N

87

40

8

15

17

10

10

71

74

36

76

66

68

62

16

12

7

42

60

63

44

28

28

30

26

10

76

8

39

3-41

Table 3.12 (continued)

Mean

6181567.57

8446.27

3732.39

415.05

38.27

10647.08

10330.07

36370.20

33519.35

4893.24

577076.13

131531.25

69723.86

21166.34

34.73

2296.02

7.77

7402.61

4767.57

6198.78

3031.95

950.28

10716.94

2.05

0.19

18256.71

1850860.69

372.46

25.88

Std. Dev.

4818034.97

3084.74

1887.97

209.50

34.96

4842.21

4285.77

24780.28

21958.20

5555.53

667622.19

135123.47

67133.79

17751.62

20.03

1827.92

0.99

4870.59

2277.67

. 3491.46

1188.23

541.16

6639.40

1.53

0.13

9435.32

1424708.15

92.83

22.72

Minimum

70000.00

0.00

1480.00

17.00

2.00

3900.00

3600.00

6.00

12.00

20.00

13000.00

90.00

64.00

52.00

0.00

560.00

6.10

0.00

210.00

6.00

100.00

3.50

0.10

0.00

0.00

5700.00

16000.00

13.00

0.40

Maximum

59000000.00

52000.00

9990.00

2200.00

500.00

28000.00

26000.00

530000.00

260000.00

46000.00

11000000.00

1300000.00

640000.00

133000.00

140.00

12210.00

19.00

51300.00

24900.00

48000.00

11000.00

8800.00

66300.00

20.00

1.00

62000.00

32000000.00

810.00

500.00

%R.E.

77.94

36.52

50.58

50.48

91.36

45.48

41.49

68.13

65.51

113.53

115.69

102.73

96.29

83.87

57.68

79.61

12.77

65.80

47.77

56.32

39.19

56.95

61.95

74.82

68.84

51.68

76.98

24.92

87.81

Variable

2 3 5 u

2 3 8 u233U/234U

95Zr

N

64

35

28

28

40

4

18

Table

Mean

2136.82

950.46

24.86

2.07

943.56

1061.75

26302.35

3-42

3.12 (continued)

Std. Dev.

1596.40

390.14

13.48

0.99

383.49

218.43

27804.62

Minimum

0.00

8.80

0.40

0.00

11.40

342.00

1700.00

Maximum

24000.00

2719.90

106.90

9.50

3000.00

1365.00

130000.00

%R.E.

74.71

41.05

54.21

47.68

40.64

• 20.57

105.71

Unweighted statistics over OHF Tank Farm(mass fraction = 0.029317)

H 2 0 fraction

Gross alpha

Gross beta

241Am

198Au

4C1

252C f

144Ce

243Cm

244Cm

60Co

I34Cs

137Cs

152Eu

154Eu

155Eu

3H

9SNb

5

10

10

6

0

5

7 .

0

0

9

10

5

10

10

10

8

5

0

5

0

0.67

386000.00

35900000.00

20366.67

.

707.00

287.43

.

•

280777.78

104000.00

556.00

573000.00

67100.00

48690.00

7875.00

52.00

•

12.18

0.05

169784.18

14301903.53

16831.12

.

891.77

171.17

.

•

141060.07

69124.69

96.33

471594.22

35328.46

30710.20

6700.91

31.82

•

4.11

0.60

150000.00

16000000.00

8000.00

.

17.00

2.00

•

•

97000.00

43000.00

480.00

250000.00

35000.00

8900.00

2700.00

26.00

•

8 :90

0.72

650000.00

59000000.00

52000.00

.

2200.00

500.00

.

•

530000.00

260000.00

710.00

1600000.00

140000.00

120000.00

23000.00

95.00

•

19.00

7.79

43.99

39.84

82.64

.

126.14

59.55

•

50.24

66.47

17.33

82.30

52.65

63.07

85.09

61.19

•

33.71

.'" --*"-"-

95Zr

3-43

Table 3.12 (continued)

Minimum

Unweighted statistics over BVEST Tank Farm(mass fraction = 0.193480)

H2O fraction

Gross alpha

Gross beta

241Am

I98Au

4C1

252C f

144Ce

243Cm

3

11

11

6

3

2

0

2

2

0.55

146703.64

4220890.91

8566.67

9373.33

272.50

.

27500.00

25500.00

0.17

56160.32

2346336.02

6918.14

770.22

130.81

.

707.11

707.11

0.42

73260.00

1986900.00

1110.00

8510.00

180.00

.

27000.00

25000.00

0.74

257890.00

8769000.00

17000.00

9990.00

365.00

.

28000.00

26000.00

29.84

38.28

55.59

80.76

8.22

48.01

.

2.57

2.77

3-44

Table 3.12 Ccon«n i l e d )

Mean \Std.^ e v .

78162.50

87232.50

7378.00

297730.00

742775.00

377396.25

100046.25

95NbM 7 N p

240pu

• 2 4 I Pu

2 4 2Pu

244pu

106Ru

90Sr

" T c

232Th

233JJ

234JJ

2 3 5 U

236U

23 8 u

233JJ/234U

95Zr

8

8

5

8

8

8

8

0

4

2

3

8

6

3

3

3

3

3

2

8

3

3

8

3

3

3

3

0

5

7827.50

6.10

37133.33

12418.75

16128.33

3460.00

2836.67

48100.00

2.47

0.70

53000.00

1058012.50

453.33

34.67

7926.94

538.23

5.53

6.53

415.33

83252.00

159989.94

26505.62

3154.63

0.00

12438.78

7302.58

8194.94

1015.28

555.91

15888.05

0.64

0.52

12727.92

921790.65

326.24

7.23

5803.50

378.65

1.10

2.74

91.80

38975.31

130000.00

403300.00

197950.00

58000.00

4700.00

6.10

28000.00

4800.00

7200.00

2600.00

2300.00

37000.00

2.00

0.10

44000.00

377400.00

170.00

30.00

1850.00

144.70

4.30

4.10

313.60

39000.00

l67OOO.oo252000.00

1 ^00.00 '

'$000.00

56.34

95.79

44.30

43.01

46.33

12210.00

6.10

51300.00

24900.00

30710.00

4580.00

3410.00

66300.00

3.20

1.00

62000.00

2726900.00

810.00

43.00

19408.10

900.00

6.40

9.50

492.00

40.30

0.00

33.50

58.80

50.81

29.34

19.60

33.03

26.06

74.23

24.01

1 87.12

71.96

20.87

73.21

70.35

19.82

41.93

22.10

125800.00 46.82

3-45

Table 3.12 (continued)

Variable N Mean Std. Dev. Minimum Maximum %R.E.

Unweighted statistics over GAAT Tank Farm(mass fraction = 0.203977)

Ufi fraction

Gross alpha

Gross beta

24IAm

I98Au

4C1

252G f

I44Ce

243Cm

244Cm

60Co

I34Cs

137Cs

152Eu

I 5 4Eu

I 5 5Eu

3H95Nb

237Np

7nPu/ulAm

239pu/240pu

238pu

239pu

240Pu

24IPu

2«pu

244Pu

29

42

42

20

0

0

10

0

0

38

41

18

42

33

35

30

11

0

0

31

31

39

31

20

20

22

18

0.73.

25179.52

3294190.48

7306.50

13.20

•

14471.34

2232.10

1126.67

992119.05

4054.55

1833.91

2549.00

33.60

.

•

4970.94

3199.29

3748.10

2891.68

499.73

4712.37

1.56

0.07

0.10

28326.30

3110677.98

6439.53

•

14.44

•

18549.17

2943.14

1093.41

1903719.42

4489.32

2052.90

2869.55

53.57

.

•

6917.63

2836.97

6462.45

3090.54

439.33

3886:16

3.02

0.05

0.58

900.00

70000.00

0.00

•

4.00

•

6.00

12.00

20.00

13000.00

90.00

64.00

52.00

0.00

.

•

0.00

210.00

- 6.00

100.00

3.50

0.10

0.00

0.00

0.89

110000.00

12000000.00

22000.00

-

50.00

.

58300.00

13000.00

3500.00

11000000.00

17000.00

8000.00

11000.00

140.00

.

•

28200.00

11800.00

29000.00

11000.00

1220.00

12000.00

14.00

0.10

13.32

112.50

94.43

88.13

.

109.36

.

128.18

131.86

97.05

191.88

110.72

111.94

112.58

159.42

.

•

139.16

88.67

172.42

106.88

87.91

82.47

193.43

63.82

Variable

10SRu

90Sr

"Tc

BaTh

233U

*8u»u/B 4u

95Zr

N

0

42

0

31

31

27

20

20

32

4

0

3-46

Table 3.12 (continued)

Mean

•

1076904.76

.

17.33

785.45

1016.16

28.47

1.47

1010.57

1061.75

Std. Dev.

•

1615290.40

.

16.16

831.48

960.68

34.27

1.61

926.18

483.64

•

Minimum

•

16000.00

•

0.40

0.00

8.80

0.40

0.00

11.40

342.00

Maximum

•

8600000.00

.

66.60

3100.00

2719.90

106.90

6.10

3000.00

1365.00

%R.E.

•

149.99

.

93.26

105.86

94.54

120.40

109.74

91.65

45.55

Unweighted statistics over MVST Tank Farm(mass fraction = 0.573226)

H2O fraction

Gross alpha

Gross beta

24IAm

I98Au

4C1

252G f

144Ce

243Cm

244Cm

60Co

"<Cs

137Cs

I52Eu

I54Eu

155Eu

0.

24

24

8

5

8

0

8

8

16

15

8

16

15

15

16

•

63310.83

7649616.67

8972.50

2590.00

417.75

.

9225.00

9050.00

40793.13

51878.00

7523.38

236666.25

123490.00

71424.00

20615.63

•

46264.74

10604502.46

4761.99

1046.52

352.12

.

4781.74

4136.25

35331.19

30373.67

15590.23

210159.51

• 204770.58

104381.74

27318.46

10730.00

758500.00

2960.00

1480.00

76.00

•

3900.00

3600.00

3700.00

8100.00

620.00

17760.00

3700.00

3700.00

740.00

•

222000.00

51800000.00

17390.00

3700.00

1050.00

•

17000.00

14000.00

132090.00

112110.00

46000.00

684000.00

718000.00

320000.00

97000.00

•

73.08

138.63

53.07

40.41

84.29

•

51.83

45.70

86.61

58.55

207.22

88.80

165.82

146.14

132.51

3-47 ,

Table 3.12 (continued)

Variable

3H

95Nb

237Np

238Pu^4IAm

^ P u / ^ P u

238pu

239pu

240pu

2 4 I Pu

242Pu

244pu

I06Ru

90Sr

"Tc

232Th

233U

235U

236U

238U

233U/234U

95Zr

Table 3.13

Variable

N

0

8

0

8

16

8

0

0

0

0

0

8

16

0

0

16

(\0

0

0

0

0

13

Weighted

• N

Mean

•

1362.50

•

6992.50

4460.50

6983.75

•

•

15325.00

2221443.75

1867.69

•

18909.23

Std. Dev.

•

907.10

•

4137.87

2892.38

4735.99

.

8101.63

2176495.73

1606.63

34991.15

Minimum

560.00

•

2430.00

878.00

740.00

.

5700.00

210900.00

.

444.00

1700.00

Maximum

•

2900.00

•

14800.00

9250.00

14430.00

28000.00

7437000.00

6660.00

•

130000.00

%R.E .

66.58

.

59.18

64.84

67.81

.

52.87

97.98

.

86.02

185.05

summary statistics for physical measurements on sludge samples

Mean Std. Dev. Minimum Maximum % R . E .

Weighted statistics by each tank's mass fraction in the OHF tank farm

Density (g/mL) 7 1.30 0.04 1.16

H20 fraction

PH

5

5

0.65

10.42

0.02

0.43

0.60

9.30

1.39

0.72

11.50

2.72

3.79

4.13

3-48

Table 3.13 (continued)

' Variable N Mean Std. Dev. Minimum Maximum %R.E.

TSOL (mg/g)

DSOL (mg/g)

SSOL (mg/g)

TOC (mg/g)

ICAR(mg/g)

TCAR (mg/g)

5

0

0

10

5

5

405.07

•

•

10233.34

11275.07

18244.16

Weighted statistics by each

Density (g/mL)

H20 fraction

pH

TSOL (mg/g)

DSOL (mg/g)

SSOL (mg/g)

TOC (mg/kg)

ICAR (nig/kg)

TCAR (mg/kg)

5

3

0

3

, 1

1

5

5

5

Weighted

Density (g/mL)

H20 fraction

pH

TSOL (mg/g)

DSOL (mg/g)

SSOL (mg/g)

TOC (mg/kg)

ICAR (mg/kg)

TCAR (mg/kg)

23

29

8

11

0

0

38

27

27

1.39

0.50

•

, 486.93

25.50

242.00

4360.38

21901.42

26214.45

statistics by each

1.26

0.71

10.20

500.60

•

•

5061.59

4251.67

7677.06

. 104.32

•

•

3575.86

1973.65

2903.09

253.00

•

•

100.00

5200.00

13000.00

921.00

•

•

28000.00

16000.00

29000.00

tank's mass fraction in the BVEST tank farm

0.06

0.08

•

67.31

•

• •

3990.69

5363.75

3462.71

1.17

0.42

••

268.00

25.50

242.00

100.00

10400.00

18500.00

1.46

0.74

•

544.00

25.50

242.00

22100.00

32000.00

32500.00

tank's mass fraction in the GAAT tank farm

0.06

0.03 .

0.25

72.28

•

•

1484.73

548.16

1434.39

1.07

0.58

9.10

300.00

•

•

200.00

1110.00

1900.00

1.57

0.89

11.10

944.00

•

•

14600.00

7900.00

16600.00

25.75

•

•

34.94

17.50

15.91

4.00

15.17

•

13.82

•

•

91.52

24.49

13.21

4.38

4.55

2.48

14.44

•

•

29.33

12.89

18.68

Weighted statistics by each tank's mass fraction in the MVST tank farm

Density (g/mL) 7 1.36 0.04 1.26 1.54 3.26

H,0 fraction 0

3-49

Table 3.13 (continued)

Variable

pH

TSOL (mg/g)

DSOL (mg/g)

SSOL (mg/g)

TOC (mg/kg)

ICAR (mg/kg)

TCAR (mg/kg)

Table 3.14.

Variable

N

0

16

0

0

8

8

8

Weighted

N

Mean

•

467.53

•

•

3720.44

8507.72

12217.10

Std. Dev.

•

42.95

•

•

811.29

2082.74

2839.87

Minimum

•

342.00

•

•

410.00

1410.00

1820.00

Maximum

•

964.00

•

•

8530.00

21900.00

30400.00

%R.E.

•

9.19

•

21.81

24.48

23.25

summary statistics for chemical measurements on sludge samples

Mean Std. Dev. Minimum Maximum %R.E.

Ag

Al

As

B

Ba

Be

Ca

Cd

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Weighted statistics

10

5

10

5

10

10

5

10

5

10

5

5

5

10

5

5

10

5

(mg/kg) by

1.21

17136.05

1.91

40.72

60.10

6.30

32104.01

11.03

8.76

109.42

8.48

144.16

6593.58

122.45

3380.95

3181.73

157.58

10375.18

each tanks mass fraction in the

0.38

3463.19

0.47

3.50

10.20

5.19

3448.25

1.44

1.88

29.15

3.82

42.48

1866.36

81.96

1025.98

449.19

81.58

3145.80

0.15

9320.00

1.00

31.80

26.50

0.00

20600.00

6.60

4.24

10.00

1.43

64.30

3150.00

1.80

974.00

1730.00

0.00

4040.00

OHF tank farm

2.90

34500.00

4.00

49.70

115.00

45.40 '

37900.00

16.40

14.20

241.00

22.50

293.00

17900.00

585.00

6140.00

5140.00

472.00

18800.00

31.35

20.21

24.67

8.60

16.97

82.47

10.74

13.05

21.45

26.64

45.08

29.47

28.31

66.93

30.35

14.12

51.77

30.32

Variable

Ni

P

Pb

Sb .

Se

Si

Sr

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates •

Nitrites

Phosphates

Sulfates

Cyanide

N

10

5

10

5

10

5

5

5

10

10

5

5

5

5

5

5

5

5

5

0

Weighted statistics

Ag

Al

• A s

B

Ba

Be

Ca

Cd

5

5

5

4

5

5

5

5

3-50

Table 3.14 (continued)

Mean

146.94

8116.99

460.82

17.92

1.24

14099.12

586.63

91582.99

1.13

3534.13

7.00 ,

180.26

31.01

812.86

235.31

1891.13

2187.65

118.65

1555.57

Std. Dev.

53.45

673.98

86.59

0.55

0.16

6771.38

164.30

9877.01

0.17

1001.20

0.18

16.29

10.32

439.89

20.07

907.76

931.45

36.92

533.21

. •

Minimum

50.00

6940.00

229.00

17.00

0.74

3640.00

282.00

56800.00

0.60

1000.00

6.60

149.00

4.63

247.00

140.00

27.90

219.00

18.50

339.00

•

(mg/kg) by each tank's mass fraction in the

18.35

1917.03

23.89

7.41

61.63

1.27

56566.48

27.15

11.83

508.89

13.70

1.41

6.39

1.06

9334.11

5.31

2.03

852.00

4.40

5.03

48.40

0.00

33600.00

16.10

Maximum

452.00

12600.00

860.00

20.00

2.00

32500.00

992.00

124000.00

2.00

7870.00

7.80

236.00

70.00

3760.00

, 272.00

4250.00

4670.00

195.00

2960.00

•

%R.E.

36.38

8.30

18.79

3.08

13.20

48.03

28.01

10.78

15.34

28.33

2.57

9.04

33.30-

54.12

8.53

48.00

42.58

31.12

34.28

•

BVEST tank farm

50.00

2800.00

50.00

10.00

78.00

3.66

83900.00

39.00

64.46

26.55

57.33

19.09

10.37

83.71

16.50

19.54

Variable

Co

Cr

Cs

Cu

Fe

Hg

K

Mg

Mn

Na

Ni

P

Pb

Sb

Se

Si

Sr

Th

Tl

U

V

Zn

Bromides

Chlorides

Fluorides

Nitrates

Nitrites

Phosphates

Sulfates

N

3

5

2

3

5

5

5

5

5

5

5

2

5

3

5

3

4

5

5

5

3

3

2

2

2

2

0

2

2

Table

Mean

3.48

180.54

2.72

50.16

2386.09

29.21

15553.49

11988.83

112.73

58462.33

86.98

14606.89

365.60

50.65

17.80

2470.75

268.70

10459.46

26.99

28932.06

3.50

935.15

319.77

2361.69

173.96

141771.96

•

203.94

5310.40

3-51

3.14 (continued)

Std. Dev.

1.21

22.92

0.10

12.94

510.28

19.01

4807.06

2563.11

75.26

13065.42

11.28

982.99

40.10

7.50

9.75

734.05

24.90

1836.37

14.92

5735.31

1.52

88.41

162.83

876.14

11.97

17095.42

•

4.27

1918.96

Minimum

1.30

146.00

2.57

33.70

1900.00

8.44

3270.00

3620.00

0.00

15400.00

69.60

13700.00

290.00

26.00

4.40

159.00

200.00

7460.00

10.00

17000.00

0.38

756.00

89.00

1120.00

157.00

126000.00

•

200.00

3540.00

Maximum

5.20

248.00

2.81

77.40

4040.00

105.00

25200.00

16000.00

275.00

82000.00

110.00

16000.00

450.00

56.00

39.00

3360.00

295.00

14000.00

75.20'

39700.00

5.37

1100.00

470.00

3170.00

185.00

166000.00

•

210.00

8030.00

%R.E.

34.86

12.70

3.78

25.80

21.39

65.09

30.91

21.38

66.76

22.35

12.96

6.73

10.97

14.81

54.78

29.71

9.27

17.56

55.28

19.82

43.27

9.45

50.92

37.10

6.88

12.06

•

2.10

36.14

Variable

23SU

236U

95Zr

N

5

5

5

5

u

0Weighted statistics

H2O fraction

Gross alpha

Gross beta

2 4 tAm

198Au

4C1

252C f

I44Ce

243Cm

244Cm

60Co

I34Cs

137Cs

I52Eu

I54Eu

I55Eu

3H

95Nb

^ N p

»«Pu/""Am

a39Pu/M0Pu

238p^

3

11

3-56

Table 3.15 (continued)

Mean

125.06

1.33

1.14

58.91

Std. Dev.

17.61

0.32

0.27

14.11

t

Minimum

57.00

0.50

0.50

26.00

#

(Bq/g) by each tank's mass fraction in the

0.50

156401.96

11 4925721.73

6

3

2

0

2

2

8

8

5

8

8

8

8

0

4

2

3 • ,

8

6

8591.79

9181.76

292.05

27394.30

25605.70

84398.99

106422.69

7208.64

312783.07

774975.69

415056.76

106592.57

•

7187.63

6.10

37715.28

13030.79

16025.20

0.08

34252.46

1393002.58

4064.70

466.69

79.07

.

427.39

427.39

26825.16

52165.76

1730.28

74500.08

192758.69

91203.83

13352.37

•

1387.89

o.oo.

6511.04

4258.75

• 4693.07

0.42

73260.00

1986900.00

1110.00

8510.00

180.00

.

27000.00

25000.00

29970.00

27380.00

2600.00'

130000.00

403300.00

197950.00

58000.00

•

4700.00

6.10

28000.00

4800.00

7200.00

Maximum

180.00

2.10

1.90

97.00

t

BVEST tank farm

0.74

257890.00

8769000.00

17000.00

9990.00

365.00

28000.00

26000.00

167000.00

252000.00

11000.00

495000.00

1300000.00

640000.00

133000.00

•

12210.00

6.10

51300.00

24900.00

30710.00

%R.E.

14.08

23.74

24.02

23.95

;

15.17

21.90

28.28 i

47.31

5.08

27.07

1.56

1.67

31.78

49.02

24.00

23.82

24.87

21.97

12.53

•

19.31

0.00

17.26

32.68

29.29

Variable

239pu

2 4 0Pu

2 4 1Pu

242pu

244pu

106Ru

9 0Sr

9 9Tc

2 3 2Th

2"U

2 3 4U

235u

2 3 6 u2 3 8 u

233U/234JJ

9 5Zr

N

3

3

3

3

3

2

8

3

3

8

. 3

3

3

3

0

5

3-57

Table 3.15 (continued)

Mean

3128.67

2650.09

43221.83

2.27

0.85

54902.62

1274498.36

485.96

32.68

9149.90

665.14

5.63

7.45

424.80

81490.75

Std. Dev.

477.09

276.08

7120.45

0.29

0.23

7692.94

576176.29

161.61

3.15

3520.33

187.05

0.64

1.47

54.12

.

23799.88

Minimum

2600.00

2300.00

37000.00

2.00

0.10

44000.00

377400.00

170.00

30.00

1850.00

144.70

4.30

4.10

313.60

.

39000.00

Weighted statistics (Bq/g) by each tank's mass fraction in the

H 2 0 fraction

Gross alpha

Gross beta

24IAm

198Au

4C1

252C f

M4Ce

243Cm

244Cm

60Co

l34Cs

29

42

42

20

0

0

10

0

0

38

41

18

0.71

26765.83

4359201.43

8806.78

.

16.10

•

14847.74

2732.23

1527.05

0.03

9520.43

1148923.61

2658.60

.

6.20

•

•

6522.78

1113.34

426.05

0.58

900.00

70000.00

0.00

.

•

4.00

•

6.00

12.00

20.00

Maximum

4580.00

3410.00

66300.00

3.20

1.00

62000.00

2726900.00

810.00

43.00

19408.10

900.00

6.40

9.50

492.00

.

125800.00

GAAT tank farm

0.89

110000.00

12000000.00

22000.00

.

•

50.00

•

•

58300.00

13000.00

3500.00

%R.E.

15.25

10.42

16.47

12.80

26.83

14.01

45.21

33.25

9.64

38.47

28.12

11.37

19.71

12.74

.

29.21

4.56

35.57

26.36

30.19

.

•

38.50

•

•

43.93

40.75

27.90

Variable

137Cs

152Eu

I54Eu

I55Eu

3H

95Nb

ospu^opu

«spu

2 3 9 p u

24 0 p u

24IPu

242Pu

244Pu

. 0 6 R u

90Sr

"Tc

232-jfc

233U

234U

235U

236U

23SU

233U/234U

95Zr

N

42

33

35

30

11

0

0

31

31

39

31

20

20.

22

18

0

42

0

31

31

27

20

20

32

4

0

3-58

Table 3.15 (continued)

Mean

1481629.67

5318.24

2117.40

3435.81

52.26

•

5329.55

2962.45

4207.84

2884.69

501.39

4703.98

1.90

0.07

.

1399653.26 -

.

21.90

706.36

976.64

22.24

1.11

956.50

941.40

Std. Dev.

812424.49

1881.17

780.67

1179.67

21.81

•

2385.96

919.40

2363.51

1074.53

158.05

1346.74

1.35

0.02

.

679425.59

•

6.53

263.03

358.53

10.74

0.48

321.56

199.58

Minimum

13000.00

90.00

64.00

< 52.00

0.00

•

0.00

210.00

6.00

100.00

3.50

0.10

0.00

0.00

•

16000.00

•

0.40

0.00

8.80

0.40

0.00

11.40

342.00

Maximum

11000000.00

17000.00

8000.00

11000.00

140.00

•

28200.00

11800.00

29000.00

11000.00

1220.00

12000.00

14.00

0.10

•

8600000.00

•

66.60

3100.00

2719.90

106.90

6.10

3000.00

1365.00

%R.E.

54.83

35.37

36.87

34.33

41.72

•

44.77

" 31.04

56.17

37.25

31.52

28.63

70.75

24.65

.

48.54

•

29.81

37.24

36.71

48.28

42.81

33.62

21.20

Weighted statistics (Bq/g) by each tank's mass fraction in the MVST tank farm

H2O fraction 0 . - •

Gross,alpha 24 63525.30 14994.04 10730.00 222000.00 23.60

Variable

Gross beta

241Am

198Au

4C1

252C f

144Ce

2 4 3Cm

2 4 4Cm

6 0Co

134Cs

137Cs

I52Eu

154Eu

155Eu

3H

9 5Nb

2 3 7Np

2 3 8 Pu^ 4 1 Am

239pu/240pu

238pu

239pu

240pu

241pu

106Ru

90Sr

"Tc

2 3 2 T h

N

24

8

5

8

0

8

8

16

15

8

16

15

15

16

0

8

0

8

16

8

0

0

0

0

0

8

16

0

0

3-59

Table 3.15 (continued)

Mean

8623035.41

8961.73

2746.08

362.54

8405.96

8726.07

39864.28

54244.28

4785.35

265307.46

116775.87

69914.70

19800.08

•

1354.98

•

7638.53

4726.84

7179.42

.

•

14954.49

2188122.11

•

Std. Dev.

4268252.48

1483.18

408.00

108.66

.

1551.56

1461.37

11560.82

11653.02

4284.99

80458.20

68181.33

38749.52

9370.67

•

324.35

•

1573.13

1042.83

1587.48

•

•

2901.39

713319.23

.

Minimum

758500.00

2960.00

1480.00

76.00

.

3900.00

3600.00

3700.00

8100.00

620.00

17760:00

3700.00

3700.00

740.00

•

560.00

•

2430.00

878.00

740.00

_•

•

•

5700.00

210900.00

•

Maximum

51800000.00

17390.00

3700.00

1050.00

.

17000.00

14000.00

132090.00

112110.00

46000.00

684000.00

718000.00

320000.00

97000.00

•

2900.00

•

14800.00

9250.00

14430.00

•

•

•

28000.00

7437000.00

..

%R.E.

49.50

16.55

14.86

29.97

.

18.46

16.75 .

29.00

21.48

89.54

30.33

58.39

55.42

47.33

•

23.94

•

20.59

22.06

22.11

•

•

•

19.40

32.60

•

3-60

Table 3.15 (continued)

Variable

23 3 U

JMy

235JJ

236u

238JJ

233U/234U

95Zr

N

16

0

0

0

0

0

13

Mean

1999.76

.

21068.79

Std. Dev.

658.43

' • .

15413.00

Minimum

444.00

.

•

•

1700.00

Maximum

6660.00

.

•

130000.00

%R.E.

32.93

.

•

73.16

4-1

4. ESTIMATING PROPERTY BOUNDS

4.1 ASSUMPTIONS FOR STATISTICALLY CORRECT CHARACTERIZATION

A correct and valid analysis of data for the purpose of making statistical inference (e.g.,creating confidence intervals or bounds on some parameter) requires certain assumptions.Three major assumptions allow correct results to follow from an analysis:

1. the assumption of a specified population,2. the assumption of a random sample, and3. the assumption that the sampled population is the target population.

The first assumption assumes that the data come from a specific and well-definedpopulation. This population should be stated explicitly; if not, the results are generally aprecise statement about an unknown object group with vague conclusions. In our setting, thepopulation consists of the possible set of analytes that is contained in the sludge stored inMVST. The fact that we do not analyze for all possible analytes means that we do not have acomplete description of the population of interest. Thus, we may be missing important analytesthat may have important interaction effects with analytes that are measured. This interactioncould have serious implications when trying to determine bounds on a given analyte.

The second assumption is that the sample taken is random. The most elementary type ofrandom sample is called a simple random sample. This means that if we take a simple randomsample of n objects from the population that every possible sample of size n from thepopulation has the same probability of being selected. In our situation, this is violated inseveral respects. The most obvious and serious violation is that the samples selected camefrom one position in the tank because there is only one opening in the tank from which tosample. The requirement of a random sample is critical in that the statistical intervals reflectonly the variability introduced by the sampling process and do not take into account any biasesthat might be introduced by nonrandom samples. In addition, the samples that were taken werecore type samples. These cores showed definite layers of material. Rather than, sampling fromeach layer, the layers were composited (blended) and then analyzed. This results in no estimateof the variability of the analyte in a given tank and yields a mean concentration. Because thereis no way to adjust for this compositing and sampling from a single position in the tank, thereis no way to adjust the statistical intervals that are calculated. This nonrandomness can lead toheavily biased observations, and the results are not amenable to adjustment. A major concernhere is the lack of information on the variability of the analyte concentrations. This variabilityis necessary to determine the spread of the distribution, and by mixing the layers andanalyzing the homogenized sample this information is lost.

Third, the methods used assume that the population of interest is the same as that whichis sampled. Because the population of interest is MVST after transfer from the other tanks, wesimply are not sampling the population of interest. The intervals we calculate will contain onlythe variability from the aggregate of the various tank farms and not the additional variabilitythat will come from the transfer of the sludge from the tank farms to the yet undeterminedMVST tanks. Again, what one may find in the MVST tanks can be quite different from whathas been found in these tank farms. Even knowing which tanks will ultimately be transferredto which MVST will not reduce this uncertainty because we have only a point source sample,which was homogenized, to use to make any predictions.

4-2

4.2 AN OVERVIEW OF STATISTICAL INTERVALS

Consider the problem of estimating the concentration of some chemical compound insludge. Suppose further that 10 samples were taken from the sludge container. The arithmeticaverage of the concentrations obtained from the samples yield a value, say 10.3 mg/kg. Thisvalue is called a point estimate of the average concentration found in the sludge analyzed. Thefollowing question comes to mind: Can we expect future observations to lie in the interval10.3 ± 5? The size of the interval depends on the variability associated with the estimate, andthis depends on the variability of the concentration values to be found in samples from thesludge. An appreciation of this variability is important in making decisions concerning thelikely values of the concentration of the chemical compound and the possible effects this mayhave, say, in handling or treating the compound. If the uncertainty of our estimate is too great,as measured by the length of the interval, we may need to collect more data to improve ourunderstanding and knowledge of the concentration of the chemical compound in the sludge.

>There are three major types of statistical intervals:

1. confidence intervals,2. tolerance intervals, and3. prediction intervals. • ••

These are different but are often confused with each other. The following definitions willhopefully remove any confusion.

A confidence interval is an interval that is formed to contain an unknown characteristic ofthe sample population. This unknown characteristic could be the mean or variance of thepopulation of interest or a function of such parameters. Referring back to the concentration ofthe chemical compound, we might be interested in an interval, which we can claim with aspecified degree of confidence, contains the mean concentration or the standard deviation ofthe concentration values for the chemical compound or the probability that the concentration ofa randomly selected sample from the sludge population will exceed a stated threshold value,M.

A tolerance interval is an interval that contains aspecified proportion of the sampledpopulation with a given level of confidence. For example, we might wish to construct aninterval to contain, with a specified degree of confidence, the concentration values of at least90% of the population.

A prediction interval is an interval that will contain one or more future observations orsome function of such future observations from a previously sampled population. For example,based on a past sample of concentration values for a specified chemical compound, we want toconstruct an interval to contain, with a specified degree of confidence, the concentration of allten future samples or the average concentration of ten future samples.

Now that we have stated the definitions for the various types of intervals it is proper todiscuss the purpose of the interval. Is the main purpose to describe the population from whichthe sample has been selected? Or is the purpose to predict the results of a future sample takenfrom the same population? Intervals that describe the sampled population are confidenceintervals on the population mean, confidence intervals on the population standard deviation, ortolerance intervals for a population proportion. On the other hand, prediction intervals for a

4-3

future mean, for a future standard deviation, or prediction intervals to include all of n futureobservations are concerned with predicting the results of a future sample.

In any of these cases, the sample we have taken is our only reference concerning thepopulation of interest. How well the sampling is done will directly affect how well we candescribe the population or predict what future samples may be like. The assumptions necessaryto make valid conclusions were discussed earlier, but we emphasize again that poor data makepoor conclusions, which can lead to poor decision making.

4.3 DEFINITIONS AND EXAMPLES

The following intervals will be given with examples on how to use them:

1. confidence interval for the population mean,2. confidence interval for the probability of being greater than a specified value,3. tolerance intervals to contain a population proportion, and4. one-sided prediction bounds to contain all of m future observations.

We emphasize one last time that these intervals are appropriate under given assumptions.In addition to the assumptions already given, we also assume for the four intervals that thesample was drawn from a normally distributed population. These same intervals for 2, 3, and 4can be calculated if we assume the underlying distribution is lognormal, and finally, weexamine the situation where we look at prediction intervals for the exponential distribution.The user of any of these techniques must take responsibility for checking any of theassumptions needed to use these methods for their purposes.

Because the four tank forms may have different distributions of analytes and differentamounts of sludge mass (see Table 3.8), it may be prudent to use a weighted analysis tocombine the data and obtain a weighted average and weighted standard deviation, say

x , and s , based on the weights derived from the sludge mass. It is these two statistics,

xw, and sw, that are used in the calculated intervals. The question then is how does one usethe sludge mass and data from the tank forms to calculate the weighted mean and standarddeviation to be used in calculating the intervals.

To simplify things, suppose that we are interested in combining the data from the BVESTand MVST forms only. To calculate the weights that observations from each form should begiven, we simply use the proportion of sludge mass that each tank form contributes to thetotal. Using the data from Table 3.8, we come to the following conclusion:

BVEST Sludge Mass = 195,636 kg

MVST Sludge Mass = 579,613 kg

Total = 775,249 kg

Then the weight associated with each observation from BVEST is given by

w, = 195,636 / 775,249 = 0.2524

4-4

and for MVST is given by

w2 = 579,613 / 775,249 = 0.7476 .

The formulas needed to calculate the two statistics we need for the intervals are

2 "/ "l «2

£ £ w/*/y w i E xy+w2E— _ <=i J = i'\ M

y=i

2 »,

E E

For example, consider the silver measurement from BVEST and MVST. Using thesummary data, we find the following statistics for the silver analyte:

BVEST: ^ = 5 , x; = 17.33, Sj =21.27, .

MVST: ^ = 8 , iF2 = 11.75, J2 = 8.36.

By using the above information and the formula for the weighted average, it is easy tocalculate the weighted average. Recall that w, = .2523 for BVEST and w, = .7476 for MVSTso that

"2

E

w1n1x1+w2n2x2

0.2524(5)(17.33)+0.7476 (8) (11.75)5(0.2524)+(.7476)(8)

92.14497.2428

12.72

4-5

To calculate the weighted standard deviation, one must go to the original data values. It iseasy to show that

-x 12+w V (x -x ~\2

, 2 _ J'l M

_ 486.5548 + 372.860212

= 71.61792,so that sw = 8.44.

4.3.1 Confidence Interval for the Population Mean (Halm and Meeker, pp. 54-55)

A 100(1 - a)% two-sided confidence interval to contain the population mean \i of anormal population is

where x is the sample mean; x = J ^ AT/H, « the number of observations in the sample,

is the upper 100(1 - a/2) percentile of the student t distribution with (n - 1) fa^^ degrees

of freedom, s is the sample standard deviation;

1 SLi (*r*)2

To obtain an upper 100(l-a)% confidence use

P = * + hi-cn-

We note that this method is dependent on the assumptions of normality and independentsamples all taken from the same population. Intervals calculated above are for the mean of thepopulation and will result in intervals of shortest length.

Example: Suppose we want to obtain a 95% confidence interval for silver at BVEST. Thereare a total of 5 observations (namely, 2.03,3.30,3.30,28.00,50.00 mg/kg) withx = 17.33 and 5=21.27. Student's f table (see Table 4.1, all Chap. 4 tables are located at the end ofthe chapter) we find f(97J4) = 2.776 and /(954) = 2.132. A two-sided 95% confidence interval for fi

is given by

[ji.jl] = 17.33 ± 2.776 (21.27/^5)= 17.33 ± 26.4060= [-9.08, 43.74].

4-6

Note than because a concentration cannot be negative, we would replace -9.08 with 0. Anupper 95% confidence bound for p. is

jl = 17.33 + 2.132 (21.27/v/S)= 17.33 + 20.28= 37.61

4.3.2 Confidence Interval for the Probability of Being less than a Specified Value(Hahn and Meeker, pp. 57-58)

A 100(1 - a)% two-sided confidence interval to contain

the probability that a normally distributed random variable Y is less than a specified lower limit,Lis

wherek = (x-L)/s

and the factors h^.^ are given in Odeh and Owen27 (1980, Table 7) for all combinations of

k = -3.0 (0.20) 3.0,n = 2 (1) 18, 30, 40, (20) 120, 240, 600, 1000, ,1200

andI-all = 0.50, 0.75, 0.90, 0.95, 0.975, 0.99, 0.995.

Similarly, a 100(l-a)% two-sided confidence interval to contain pG = P(YzL) = l-pL, the

probability that a normally distributed random variable Y is greater than the upper limit L, isgiven by

4.3.3 Tolerance Intervals to Contain a Specified Population Proportion(Hahn and Meeker, pp. 58-60)

A 100(1 - <x)% two-sided tolerance interval to contain at least a proportion,/?, of a normalpopulation is computed as:

Where g^.^,,,) is given in Odeh and Owen (1980, Table 3) for all combinations of

4-7

p = 0.75,0.90,0.95,0.975,0.99, and 0.995K = 2 (1) 100 (2) 180 (5) 300 (10) 400 (25) 650 (50) 1000,1500

2000, 3000, 5000, 10000, and «.

and1-a = 0.50,0.75,0.90,0.95,0.975,0.99, and 0.995.

Tables 4.2 and 4.3 contain values of g( 1 -a;p, n)

for/? =0.90,0.95,0.99n =4,5,6,7,8,9,10,12,15,20

and 1-a =0.95,0.99.

A one-sided upper 100(l-a)% tolerance bound to exceed at least 100/?% of the population is

where g[i.BiPtlti is given in Odeh and Owen (1980, Table 1) for the same values of/?, n, and

1-a as for the two-sided factors. Table 4.4 contains values of g"^.a.p n).

for n = 2,3,4,5,6,7,8,9,10,11,12,15,20,35,60,120l-a=0.95,0.99,

and p=0.90,0.96, and 0.99.

Example: Using the silver data from BVEST, we have n = 5 observations withx = 17.33 and s = 21.27. It is desired to construct a 95% two-sided tolerance bound (i.e.,1-a = 0.95) to contain 90% of the population values (i.e., p = 0.90) and a one-sided 95% uppertolerance bound to exceed at least 90% of the population values.

We use g(0-95.090 5) = 4.291 [Odeh and Owen (1980, Table 3.4.1) or Table 4.2] and

£(0.9$; o.9o, s> = 3-4 0 7 [ ° d e h and O w e n (1980, Table 1.4.1) or Table 4.4]. A standard 95% two-sided

tolerance interval is

B ^ o . ^ U ] = 17.33 ±(4.291) (21.27)= [-73.94,108.60]

Again, because we cannot have a negative concentration, we replace -73.94 by 0. A 95%upper tolerance bound to exceed at least 90% of the population is

T090 = 17.33 + 3.407 (21.27)= 89.80

One might compare the above intervals to those based on the weighted values obtained bycombining the MVEST and BVST values for silver. Recall that xw = 12.72 and sw = 8.44, but

now the sample size is 5 + 8 = 13. Using Table 4.2, we do not have an entry for a sample of size13, so we will use the smallest sample size corresponding to n = 12. This will be more

. - ; ."•?-..•;• ;. ' ;

4-8

conservative than using n = 15 or some interpolating scheme. The corresponding entry forn = 12, p = 0.90 and 1-a = .95 is g(.95,90,12) = 2.67. Thus, a standard 95% two-sidedtolerance interval for the weighted data is

\T9Q,fS0[ = 12.72 ±2.67 8.44)

= [-9.81,35.25].

4.3.4 One-sided and Two-sided Prediction Bounds to Contain All of M Future Observations(Hahn and Meeker, pp. 62-63)

A 100(1 - a)% two-sided prediction interval to contain the values of all of m futurerandomly selected units from the previously sampled normal population is

iXm,yJ =x + r(1_a;n)n)s

where r(1.o.mn) is tabulated in Hahn (1969) for all combinations of

« = 6(1)21, 25, 31, 41, 61, 121, -m = 1 (1) 12, 15, 20

and1-a = 0.90,0.95,0.99.

In addition, Hahn and Meeker (1987, Table A.13) contains r(1_B.m n) for

n = 4(1) 12, 15, 20, 25, 30, 40, 60, 120m = 1 (1) 10, 12, 16, 20, 40, 60, 80, 100

and1-a = 0.90,0.95, and 0.99.

A conservative approximation for J"(1.B.min) is given by

The above approximation is based on a Bonferroni inequality and was suggested by Chew(1968). The approximation was investigated by Hahn (1969) and found to be satisfactory for mostcases, except for combinations of small n, large m, and small 1-a. The expression is exact form = 1 future observation. Tables 4.2 and 4.3 contain values ofmn)for l-a=.95and .99,»=4(l)10,12,15,20,andm = l,2,5,l One-sided upper 100(1 - a )%

prediction bounds to exceed all of m future observations from a previously sampled normalpopulation is

where /•(1.tt;m#n) are tabulated in Hahn and Meeker (1987, Table A. 14) for

4-9

n = 4(1) 10, 12, 15, 20, 25, 30, 40, 60, 120m = 1 (1) 10, 12, 16, 20, 40, 60, 80, 100

and\-a = 0.90, 0.95, and 0.99.

Again, a conservative approximation for r^.aimtn) is

The expression was evaluated by Hahn (1970) with results similar to those for theapproximation of the two-sided prediction interval. Table 4.5 contains values forr'(l_a.mn)for 1 -a = 95.99,m = 1,2,5,10,20,and »=4(l)10,15,20.

Example: Using the silver data from BVEST, we have h = 5 observations withx = 17.33 and s = 21.27. It is desired to form a 95% two-sided prediction interval to contain thefuture values of m = 10 future observations and an upper 95% one-sided prediction boundfor m = 10 future observations. From Table 4.2, r(0 9S; I0 S) = 5.229

and from.Table 4.5, ''('0.95; 10,5) = 4.418.

A 95% two-sided prediction interval to contain all 10 future observations is given by

\X10,yw] = 17.33 ± 5.229 (21.27)= [-93.91, 128.57].

A one-sided upper 95% prediction bound to exceed all 10 future observations is given by

y10 = 17.33 + (4.418) (21.27)= 111.34.

4.3.5 Log Transformations

In some situations, the data do not have a symmetrical distribution, and a transformation isnecessary to use normal theory statistics. In the case where taking logarithms (base e) of the datatend to make the distribution of the transformed data more symmetrical, we can still apply themethods given in Sects. 4.3.2 through 4.3.4 to obtain intervals or bounds on the transformed dataand then apply the inverse transform to get back to the original data units. [Interested readers cansee Hahn and Meeker29 (1991), page 73]. For example, in Sect. 4.3.3.we obtained a 95% two-sided tolerance bound to contain 90% of the population values. If we assume that the truedistribution of the data is lognormal, then we log transform the data. The resulting mean andstandard deviation for the silver data from BVEST (after taking logarithms) are

? = 2.068s' = 1.447

4-10

Using Table 4.2, we find g(0 9i.O]9oj5) = 4.291 and the two-sided tolerance interval on the

transformed data is given by

|To 90.^090] =2.068 ±4.291 (1.447)= [-4.141,8.277].

The 95% two-sided tolerance bound to contain 90% of the population values of theuntransformed data is given by

, eS277] = [0.016,3932.380]

4.4 PREDICTION INTERVALS WHEN THE DATA IS EXPONENTIALLYDISTRIBUTED

In Sect. 4.3.4 we discussed prediction intervals to contain all of m future observations whenthe underlying distribution is normal. In this section we shall derive the equations necessary to dothis for the exponential distribution. We assume that we are given a sample of size n firom thisexponential population and we use this information to guide us in determining a bound that willcontain all of m future observations.

To begin, let us define the exponential distribution. The exponential distribution ischaracterized by a single parameter, 0, and its density function is given by

f(x;B) = ±e-M, x>0, 6>0.

Suppose that we observe x,, x2,..., x,, from this exponential distribution. It is easy to showthat the minimum variance unbiased estimator of 0 is given by

It is also easy to show that 2w@/6 has a chi-squared distribution with 2n degrees offreedom (see Mann, Schafer, and Singpurwalla28, pages 164 and 165).

Now suppose we consider a future sample of size m from this same population, say y,, y^...,ym. The distribution of these future observations are also dependent on the unknown parameter 0,but we can use our prior sample to remove the dependence by the following transformation.Consider the variables

4-11

The variables r,, r2,..., rm are independent of 8 because it disappears in the ratio. Thus weneed to find the distribution of r,, r2,..., rra, and th'is will enable us to determine future y values byusing what are called pivotal statistics.

To begin with, we shall consider the conditional distribution of r,, r2,..., rm given

2±Xl/e.

To simply the notation we shall let i = 2 J^ x,/d1=1

then we want the distribution of r; conditional on u where

rt= J = 1,2,...,J».u

Recall that we are conditioning on u can be treated as a'constant.

Because r,=u

then ys = u 8 r;, and it is easy to show that the conditional density of r; given u is given by

f(rt\u) = ue ~"r' i= 1,2,...,m.

Because the y{ values are a random sample and therefore independent, it follows that the r;

values are independent also, and we can write the joint density of r,, r2,..., rm conditional on u asthe product of the marginals. Therefore

-«tr,f(rvr2,...,rju) = um e '"' .

Recall that u is distributed as a chi-square random variable with 2n degrees of freedom so wemay write the joint density of r,, r2,..., rm and u as

/0*i> r2,..., rm, u) =f(rv rv..., rm \ u) g (u)

=M 2T(n)

4-12

Finally, we integrate out u to find the distribution on rl5 r2,..., rm which is given by

r r \_v rv..., rm)

Recall that we want to find the value for which each V; will be less than with a givenprobability. This corresponds to a value, call it B, for which all r; values will be less than with aspecified probability. Because the density decreases as r; increases, it can be shown that theshortest interval that will contain a given probability is one whose left end point is zero. Thus, theshortest bounding interval is [0, B] and we desire

B B BT(m+n)

0 0 0

The value of B is a function of m, n, and y so we shall denote this by B[y; m, n].For the case when m = 1, we can solve the above integral equation analytically. The integralevaluates to

1 - = Y

and hence

- 1

(1-Y)"

Because we have that

ri =

2±x,/d 2±x,1=1 K

it follows that

and by substitution for r{ we have

Pr (r, < B[T,l,n]) = Y

Pr = Y

or

4-13

and finally

Pr £** - i

(1-Y)n

= Y

As an example of the use of the above equation, suppose that the ten samples of total organiccarbon (TOC) obtained from the OHF came from an exponential distribution. We found theaverage value of TOC to be 9898.0, so that the sum of TOC is 10 (9898.0) = 98980. Suppose wewant a prediction interval for a single (m = 1) future observation and we want to be 95%confident that any single future observation will be less than this bound. Because we want to be95% confident then y = -95, our previous sample size is n = 10, and our equation gives us

1(1-.95)1'10

<. 98980 [1.349 - l ]<. 34572.

-1

We note that the maximum for TOC from the ten samples was 28,000. Note the value0.349 = B[.95; 1,10], which can be found in Table 4.6. For values of m £ 2, the integral equationmust be used, and this equation is nontrivial and must be solved using computer programs.Table 4.6 contains the results of evaluating the integral equation for y = 0.95, n = 1 (1) 10, andm = 1(1)5.

4-14

Table 4.1. Selected percentiles of the student's /-distribution

Degreesof freedom

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

. 21

22

23

24

25

26

27

28

29

oo

0.90

3.078

1..886

1.638

1.533

1.476

1.440

1.415

1.397

1.383

1.372

1.363

1.356

1.350

1.345

1.341

1.337

1.333

1.330

1.328

1.325

1.323

1.321

1.319

1.318

1.316

1.315

1.314

1.313

1.311

1.282

0.95

6.314

2.920

2.353

2.132

2.015

1.943

1.895

1.860 '

1.833

1.812 •

1.796

1.782

1.771

1.761

1.753

1.746

1.740

1.734

1.729

1.725

1.721

1.717

1.714

1.711

1.708

1.706

1.703

1.701

1.699

1.645

P

0.975

12.706

4.303

3.182

2.776

2.571

. 2.447

2.365

2.306

2.262

2.228

2.201

2.179

2.160

2.145 •

2.131

2.120

2.110

2.101

2.093

2.086

2.080

2.074

2.069

2.064

2.060

2.056

2.052

2.048

2.045

1.960

0.99

31.821

6.965

4.541

3.747

3.365

3.143

2.998

2.896

2.821

2.764

2.718

2.681

2.650

2.624

2.602 -

2.583

2.567

2.552

2.539

2.528

2.518

2.508

2.500

2.492

2.485

2.479

2.473

2.467

2.462

2.326

0.995

63.657

9.925

5.841

4.604

4.032

3.707

3.499

3.355

3.250

3.169

3.106

3.055

3.012

2.977

2.947

2.921

2.898

2.878

2.861

2.845

2.831

2.819

2.807

2.797

2.787

2.779

2.771

2.763

2.756

2.576

4-15

Table 4.2. The factor g (0.95, p,n) for calculating two-sided 95% tolerance intervals and the factorr (o.9s,ra,n) for calculating two-sided 95% prediction intervals for m future observations

Numberof given

observations(n)

4

5

6

7

8

9

10

12

15

20

g(0.95)P)n) for toleranceintervals to contain at least

100p% of the distribution

0.90

5.368

4.291

3.733

3.390

3.156

2.986

2.856

2.670

2.492

2.319

• P

0.95

6.341

5.077

4.422

4.020

3.746

3.546

3.393

3.175

2.965

2.760

0.99

8.221

6.598

5.758

5.241

4.889

4.633

4.437

4.156

3.885

3.621

1

3.558

3.041

2.777

2.616

2.508

2.431

2.373

2.290

2.215

2.145

r (0.95, m,n) for simultaneous predictionintervals to contain

all m future observations

2

4.412

3.697

3.333

3.114

2.968

2.863

2.785

2.680

2.574

2.480

m

5

5.564

4.577

4.076

3.774

3.573

3.429

3.321

3.170

3.031

2.902

10

6.407

5.229

4.628

4.265

4.022

3.848

3.717

3.530

3.365

3.208

20

7.206

5.853

5.159

4.749

4.457

4.256

4.103

3.890

3.689

3.503

Table 4.3. The factor g (o.9s,p,n) for calculating two-sided 99% tolerance intervals and the factorr (ess, m,n) for calculating two-sided 99% prediction intervals for m future observations

Numberof given

observations(n)

4

5

6

7

8

9

10

12

15

20

g (0.95,p,n) for toleranceintervals to contain at least

100p% of the distribution

0.90

9.416

6.655

5.383

4.658

4.189

3.860

3.617

3.279

2.967

2.675

P

0.95

11.118

7.870

6.373

5.520

4.968

4.581

4.294

3.896

3.529

3.184

0.99

14.405

10.220

8.292

7.191

6.479

5.980

5.610

5.096

4.621

4.175

1

6.530

5.044

4.355

3.963

3.712

3.537

3.408

3.230

3.074

2.932

r (0.95, m,D) f ° r simultaneous predictionintervals to contain

all m future observations

2

7.942

5.972

5.071

4.562

4.238

4.014

3.850

3.630

3.426

3.247

m

5

9.884

7.253

6.055

5.382

4.953

4.659

4.442

4.150

3.888

3.655

10

11.325

8.219

6.803

6.006

5.499

5.148

4.892

4.540

4.234

3.957

20

12.698

9.154

7.535

6.621

6.038

5.634

5.339

4.940

4.578

4.256

4-16

Table 4.4. Factors g'^ _a. . for calculating normal distributionone-sided 10'(f(l-a)% tolerance bounds

n

2

3

4

5

6

7

8

9

10

11

12

15

20

35

60

120

0.90

20.581

6.155

4.162

3.407

3.006

2.755

2.582

2.454

2.355

2.275

2.210

2.068

1.926

1.732

1.609

1.503

1-a = 0.95

P

0.95

22.260

7.656

5.144

4.203

3.708

3.399

3.187

3.031

2.911

2.815

2.736

2.566

2.396

2.167

2.022

. 1.899

0.99

37.094

10.553

7.042

5.741

5.062

4.642

4.354

4.143

3.981

3.852

3.747

3.520

3.295

2.995

2.807

2.649

0.90

103.029

13.995

7.380'

5.362

4.411

3.859

3.497

3.240

3.048

2.898

2.777

2.521

2.276

1.957

1.764

1.604

1-a = 0.99

P

0.95

131.426

17.370

9.083

6.578

5.406

4.728

4.285

3.972

3.738

,3.556

3.410

3.102

2.808

2.430

2.202

2.015

0.99

185.617

23.896

12.387

8.939

7.335

6.412

5.812

, 5.389

5.074

4.829

4.633

4.222

3.832

3.334

3.038

2.797

4-17

Table 4.5. Factors4.5. Factors f'•« w for calculating normal distributionone-sided 100(1 - aj°/J prediction bounds for m future

observations using the results of a previous sampleof n observations.

n

4

5

6

7

8

9

10

15

20

4

5

6

7

8

9

10

15

20

1

2.631

2.335

2.177

2.077

2.010

1.960

1.923

1.819

1.772

5.077

4.105

3.635

3.360

3.180

3.053

2.959

2.711

2.602

2

3.401

2.952

2.715

2.570

2.471

2.400

2.346

2.198

2.132

6.305

4.943

4.298

3.926

3.685

3.517

3.393

3.067

2.927

m

5

l - a = 0.95

4.472

3.788

3.433

3.217

3.071

2.966

2.887

2.671

2.574

l - a = 0.99

8.070

6.126

5.221

4.705

4.372

4.141

3.972

3.531

3.342

10

5.285

4.418

3.971

3.699

3.516

3.384

3.284

3.013 -

2.891

9.434

7.043

5.935

5.305

4.900

4.619

4.412

3.877

3.649

20

6.063

5.029

4.495

4.168

3.948

3.790

3.670

3.342

3.194

10.764

7.946

6.643

5.902

5.425

5.094

4.851

4.219

3.950

Table 4.6. Factors B (.95; m, n) for calculating exponential distribution two-sided95% prediction intervals for m future observations using the results

of a previous sample of n observations

n

1

2

3

4

S

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

1

19.0

3.472

1.714

1.115

0.821

0.648

,0.534

0.454

0.395

0.349

0.313

0.284

0.259

0.239

0.221

0.206

0.193

0.181

0.171

0.162

2

28.830

4.833

2.299

1.465 •

1.064

0.833

0.682

0.578

0.500

0.441

0.394 .

0.356

0.325

0.299

0.277

0.257

0.241

0.226

0.213

0.211

3

35.372

5.725

2.677

1.688

1.219

. 0.949

0.775

0.654

0.565

0.498

0.444

0.401

0.365

0.336

0.310

0.288

0.269

0.253

0.238

0.225

4

40.276

6.395

2.960

1.855

1.333

1.035

0.843

0.710

0.613

0.539

0.480

0.433

0.395

0.362

0.335

0.311

0.290

0.272

0.257

0.242

5

44.196

6.931

3.186

1.987

1.424

1.103

0.897

0.755

0.651

0.571

0.509

0.459

0.418

0.383

0.354

0.329

0.307

0.288

0.271

0.256

m

6

47.462

7.379

3.374

2.098

1.500

"1.160

0.942

0.792

0.682

0.598

0.533

0.480

0.437

0.401

0.370

0.343

0.321

0.301

0.283

0.267

7

50.259

7.763

3.537

2.193

1.565

1.208

0.980

0.823

0.709

0.622

0.553

0.498

0.453

0.415

0.383

0.356

0.332

0.311

0.293

0.277

8

52.707

8.101

3.679

• 2.277

1.622

1.251

1.014

0.851

0.732

0.642

0.571

0.514

0.467

0.428

0.395

0.367

0.342

0.321

0.302

0.285

••

9

54.882

8.401

3.806

2.351

1.673

1.289

1.044

0.876

0.753

0.660

0.587

0.528

0.480

0.440

.0.406

0.377

0.351

0.329

0.310

0.292

10

56.839

8.671

3.920

2.418

1.719

1.323

1.071

0.898

0.772

0.676

0.601

6.541

0.491

0.450

0.415

0.385

0.359

0.337

0.317

0.299

15

64.454

9.728

4.367

2.681

1.899

1.457

1.177

0.985

0.845

0.739

0.657

0.590

0.536

0.490

0.452

0.419

0.391

0.366

0.344

0.325

20

69.920

10.491

4.691

2.871

2.029

1.555-

1.254

1.048

0.898

0.785

0.697

0.626

0.568

0.520

0.479

0.444

0.413

0.387

0.364

0.343

0 0

5-1

5. REFERENCES

1. F. T. Binford, S. D. Orfi, The Intermediate Level Waste System at the Oak RidgeNational Laboratory Description and Safety Analysis, ORNL TM-6859, August, 1979.

2. J. R. DeVore, T. E. Herrick, K. E. Lott, Technology Study ofGunite Tank SludgeMobilization at Oak Ridge National Laboratory, Oak Ridge Tennessee, ORNL/ER-286, December, 1994.

3. Advanced Integrated Management Services, Inc., .Site Characterization SummaryReport for the Old Hydrofracture Facility, November 30, 1995 draft.

4. Lockheed Martin Energy Systems, Inc., Preliminary Engineering Report, OldHydrofracture Facility Tanks Content Removal Project, April 3, 1996 draft.

5. Field Task Proposal, Cesium Removal Demonstration Project

6. Martin Marietta Energy Systems, Inc., Design Criteria for Melton Valley StorageTanks - Capacity Increase, September 10, 1993.

7. F. J. Peretz, B. R. Clark, C. B. Scott, and J. B. Berry, Characterization of Low-LevelLiquid Wastes, at the Oak Ridge National Laboratory, ORNL/TM-10218, December1986.

8. J. W. Autrey, D. A. Costanzo, W. H. Griest, L. L. Kaiser, J. M. Keller, C. E. Nix, B.A. Tomkins, Sampling and Analysis of the Inactive Waste Storage Tank Contents atORNL, ORNL/ER-13, September 1990.

9. J. W. Autrey, J. M. Keller, W. H. Griest, J. L. Botts, R. L. Schenley, and M. A. Sipe,Sampling and Analysis of the Inactive Waste Tanks TH-2, WC-1, and WC-I5,ORNL/ER-19 (February 1992).

10. M. B. Sears, J. L. Botts, R. N. Ceo, J. J. Ferrada, W. H. Griest, J. M.Keller, R. L.Schenley, Sampling and Analysis of Radioactive Liquid Wastes and Sludges in theMelton Valley and Evaporator Facility Storage Tanks at ORNL, ORNL/TM-11652,September, 1990.

11. Bechtel National, Inc., Results of Fall 1994 Sampling of Gunite and Associated Tanksat the Oak Ridge National Laboratory, Oak Ridge, Tennessee,ORNL/ER/Sub/87-99053/74, June 1995.

12. Bechtel National, Inc., Results of the 1995 Sampling ofGunite and Associated Tanksat Oak Ridge National Laboratory, ORNL/ER/Sub/87-99053/79, February, 1996.

13. C. W., Francis, S. W. Herbes, Chemical Characterization of Liquid and SludgeContained in the Old Hydrofracture Tanks, Letter report to C. A. Bednarz, August,1996.

14. J. M. Keller, J. M. Giaquinto, W. H. Griest, Characterization of Selected Waste Tanks

5-2

from the Active LLLW System, ORNL/TM-13248, August, 1996.

15 M. B. Sears, Results of Sampling the Contents, of the Liquid Low-Level WasteEvaporator Feed Tank W-22, ORNL/TM-13234 (in preparation).

16. USEPA, Test Methods for Evaluating Solid Waste, SW-846, 3rd ed., Office of SolidWaste and Emergency Response, Washington, D.C., November 1986.

17. Evaluation of Phase I and Phase II Sampling and Analysis Data for the Gunite andAssociated Tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee,OKNL/ER-365 (March 1996).

18. J. M. Giaquinto, A. A. Essling, and J. M. Keller, Comparison of SW-846 Method 3051and Sw-846 Method 7471A for the Preparation of Solid Waste Samples for MercuryDetermination, ORNL/TM-13236

19. A. M. Meeks and J. M. Keller, Separation Techniques for the Clean-up of RadioactiveMixed Waste for ICP-AES/ICP-MS Analysis, ORNL/TM-12329 (March 1993).

20. Radian Corporation, Remedial Investigation Report/Feasibility Study for the Guniteand Associated Tanks Operable Unit at Waste Area Grouping 1 at Oak Ridge NationalLaboratory, Oak Ridge Tennessee, November, 1993 Draft.

21. H. O. Weeren, Sluicing Operations at Gunite Waste Storage Tanks, ORNL/NFW-84/42, September, 1984.

22. J. F. Walker, Jr., J. J. Perona, S. M. Robinson, In-Tank Evaporator DemonstrationsDuring 1990/1991 at the ORNL Melton Valley Storage Tanks, ORNL/TM-1203 6,October, 1992.

23. V. L. Fowler, J. J. Perona, Evaporation Studies on Oak Ridge National LaboratoryLow Level Liquid Waste, ORNL/TM-12243, March, 1993.

24. T. E. Kent, Cost Effectiveness of the In-tank Evaporator for Removal of ExcessWater from the ORNL Melton Valley Storage Tanks.

25. A. J. Lucero, H. L. Jennings, D. C. VanEssen, V. C. Fowler, R. L. Cummins, B. S.Evans, J. D. Hewett, S. A. Richardson, D. R. McTaggart, W. R. Reed, R. J. Wood,T. E. Kent, Out-of-Tank Evaporator Demonstration Final Report, May 15, 1996 draft.

26. T. E. Kent, letter to C. B. Scott, "In Tank Evaporation Progress", March 7, 1995.

27. R.E. Odeh, and D.B. Owen, Tables for Normal Tolerance Limits, Sampling Plans,and Screening, Marcel Dekker, Inc., New York, 1980.

28 N.R. Mann, R.E. Schafer, and N.D. Singparwalla, Methods for Statistical Analysis ofReliability and Life Data, John Wiley and Sons, Inc., New York, 1976.

29. G. J. Hahn, and W. P. Meeker, Statistical Interviews. A Guide to Practicioners. JohnWiley and Sons, Inc. New York, 1991.

APPENDIX A

A fflSTORY OF TANK WASTE AT ORNL

A-3

From the beginning of Oak Ridge National Laboratory (ORNL)20, radioactive wastemanagement required classification of the waste into categories dependent upon boththe level and type (e.g., alpha or beta emitting) of radioactivity in the waste and thevolume of waste. The category names and divisions between the categories havechanged over time reflecting changes in the system of categorization. Despite this, thenature of the early categories are generally recognizable and can be related to currentcategories. Initially, liquid wastes were divided into three main categories: metalwastes, radiochemical wastes, and process wastes. A fourth category, referred to aswarm waste, was also used during early operations.

Metal wastes, while radioactive, contained primarily uranium with small quantities ofplutonium and/or thorium. These elements are all long-lived radionuclides and are afissionable source material as well. Metal waste were generated and collected from avariety of facilities throughout the laboratory.

Radiochemical waste contained primarily fission product radionuclides that havesignificantly shorter half-lives than the metal waste radionuclides. Radiochemical liquidwastes were also referred to as "hot" chemical wastes and intermediate level wastes,and are currently referred to as liquid low-level waste (LLLW). Radiochemical wastewas discharged from process vessels in laboratories and Building 3019 cells into hotdrains or via hot sinks or glove boxes. They contained 137Cs and 90Sr, which haverelatively long half-lives, in addition to other radionuclides with short half-lives,various metals and small amounts of organics. The wastes usually originated as nitratesolutions, although some wastes were acidic chlorides or other corrosives. The acidicsolutions were generally neutralized by the addition of sodium hydroxide before thewastes were sent to the Gunite tanks.

The process waste was considered to be nonradioactive or to have very low activity.Present guidance classifies process waste as containing total beta-gamma activity not toexceed 10,000 Bq/L (0.27 [iCi/L). Process waste is derived from cooling water,laboratory sinks other than hot sinks, and floor drains from facilities devoted to hotwork.

A fourth category referred to as "warm waste" was in use during early operations.Warm waste was moderately radioactive and was an intermediate between processwaste and radiochemical waste. Depending on the level of radioactivity present, "warmwaste" was handled as either radiochemical waste or process waste.

Gunite and Associated Tanks (GAAT) OPERATIONS

The Gunite tanks, which were originally projected to have a one-year duration, wereinitially constructed to store all the radioactive liquid (radiochemical and metal) wastesgenerated by the X-10 site operations. However, before the Graphite Reactor first wentcritical on November 4, 1943, expansion of the scope of work required that the periodof operation be extended to three years. Due to expanding requirements for managingthe radioactive waste liquids, the capacity of the tanks proved inadequate for

A-4

permanent storage, and it became necessary to consider disposal of some portion of the. waste. Various approaches were used to manage the increasing volumes of waste, withthe Gunite tanks remaining the central facility for most of ORNL's waste managementactivities into the 1970s.

The first waste management approach used in the 1940s was to separate the differentwaste streams as much as practical and to concentrate the radioactive components inthe liquids via precipitation. The large Gunite tanks in the South Tank Farm were usedfor the precipitation process, with the smaller Gunite tanks in the North Tank Farmused either for the storage of metal waste or the collection of waste forcharacterization before transfer to the appropriate system. At that time the tanks in theSouth Tank Farm were operated in three pairs. The three tanks on the north side of theSouth Tank Farm (W-5, W-7, and W-9) received the waste stream and overflowed tothe corresponding tanks on the south side (W-6, W-8, and W-10, respectively). TanksW-5 and W-6 were used for the collection and treatment of the radiochemical wastestream, while Tanks W-7, W-8, W-9, and W-10 were used for the collection andtreatment of the metal waste stream. The precipitation step concentrated most of theradionuclides in the precipitate (sludge) at the bottom of the tank and significantlyreduced the level of activity in the remaining liquid (supernatant). The sludge wasstored in the bottom of the tanks until a process was developed to recover the uranium,plutonium, and/or thorium. The supernatant was discharged to a settling basin (WasteHolding Basin 3513, completed in July 1944) and then diluted with large volumes ofprocess waste before discharge into White Oak Creek.

In 1945, precipitation was discontinued and Tanks W-5 and W-6 were used to collect andhold the radiochemical waste so that radionuclides with short half-lives could decay, whichsignificantly reduced the total radioactivity of the waste. Tanks W-5 and W-6 held theradiochemical waste for about one month on average, after which it was discharged to thesettling basin for dilution with process waste. Tanks W-7, W-8, W-9, and W-10 continuedto be used to collect metal waste.- However, the original piping for the transfer system wasmodified so that waste in any one tank in the South Tank Farm could be transferred toany other tank. Tank W-9 was used as the initial collection tank for metal waste; it wasthen transferred to either Tank W-7 or W-10 for precipitation. The supernatant from theprecipitation process was transferred to the radiochemical waste system. At this time, TankW-8 was only used for the temporary storage of metal waste.

Beginning in 1949, the radiochemical waste stream was treated by concentration using apot-type evaporator. The evaporator allowed for the processing of larger volumes ofwastes. In 1950, further ORNL expansion required additional modifications in the wastemanagement system in order to handle the increased waste volumes and levels ofradioactivity. Underground stainless steel tanks were installed near each building or areathat was a source of radiochemical or metal waste. These tanks (W-1A, W-13^ W-14, andW-15) installed in the North Tank Farm permitted better collection and segregation of thewaste types, as well as sampling and measurement of waste volumes and rates ofaccumulation from each source. From 1952 to 1957, a metal recovery plant (building3505) extracted approximately 130 tons of uranium from the accumulated metals waste in

A-5

storage in the Gunite tanks. Residual waste from this process was incorporated into theradiochemical waste stream. Disposal of radiochemical waste in seepage pits began in1952. The pot evaporator operation continued until 1954, when it's use was discontinuedin favor of direct disposal of the waste in seepage pits. At this time, tanks W-5, W-6 andW-7 were used to hold the waste for the decay of the short half life radionuclides, whiletanks W-8, W-9 and W-10 continued to be used for the precipitation and storage of metalwaste.

In 1965, a new evaporator was constructed and placed in operation. Radiochemical wastewas initially accumulated from the various collection tanks into tank W-5, which alsocontinued to receive the supernatant from the precipitation of metal waste in tanks W-7and W-10. The radiochemical waste was transferred to the evaporator for concentration,and the concentrate was returned to tanks W-6 or W-8 for holding prior to disposal in theseepage pits. Disposal of liquid wastes continued in this manner until 1966 when routineuse of the hydrofracture process was initiated.

Continuous improvements and modifications to the ORNL waste management systemeventually eliminated the need for most of the older tanks. Tanks W-l, W-2, W-3, W-4,W-13, W-14, and W-15 in the North Tank Farm were removed from service in the late1950s or early 1960s. After the tanks were removed from service, the liquid waste wastaken from the tanks while sludge and a small volume of residual liquid remained in thetanks. The large Gunite tanks in the South Tank Farm were removed from service in thelate 1970s in favor of the Bethel Valley Evaporator Service Tanks (BVEST), evaporator,Melton Valley Storage Tanks (MVST) and New Hydrofracture Facility. Accumulatedsludge precipitated from solution and residual solutions remained in the GAAT tanks untilthey were removed from the South Tank Farm tanks in 1982 and 1983. However someliquid and sludge still remain. An estimated 1100 tons of sludge was removed from theGAAT and transferred to the New Hydrofracture Facility for disposal.

DESCRIPTION OF 1982-83 GAAT SLUICING CAMPAIGN21

During 1982-83, over a period of about 18 months, the six tanks in the South Tank Farmwere sluiced, the sludge re-suspended, and the re-suspended slurry pumped to the MeltonValley Storage Tanks and the New Hydrofracture facility for disposal. Analyses of sludgesamples showed great variability between tanks and between samples in a given tank.About half the sludge consisted of very small particles (less than 10 \im). The other halfappeared to be agglomerates of the smaller particles. Laboratory tests demonstrated thefeasibility of breaking the agglomerates in a grinder and suspending the fragments in a2-1/2% bentonite suspension. Field tests demonstrated that a sluicer could be used forslurry re-suspension and that the re-suspended slurry could be pumped at concentrationsup to 20% by weight. Strontium-90 was the major radionuclide.

The slurry was re-suspended in a series of batch operations. A 150,000-L (40,000-gal)batch of 2-1/2% bentonite and water was mixed and collected in a near-empty waste tank.This suspension was then pumped through a sluicer nozzle to impinge on and re-suspendthe sludge in the tank being sluiced. The re-suspended sludge was pumped from the tank,

A-6

through a grinder, and returned to the feed tank. This operation was continued until theslurry concentration approached 15 to 20 wt %. At this point, the slurry was pumped tostorage at the MVSTs, pending disposal by hydrofracture injection. The cycle was then

• repeated until the sluiced tank was as empty as practicable.

The equipment required for the sluicing operation included the bentonite makeup system,the remotely controlled sluicer assembly, a grinder to break up oversized slurry particles,and two Moyno pumps for slurry transfer between tanks. An adjustable suction leg wasprovided for one of the pumps so that this leg could be extended as the sludge wasremoved from the tank. Because the structural strengths of the tank domes were unknown,all equipment that had to be mounted above a tank was supported on a platform thatstraddled the tank. The necessary penetrations into the tanks were made by a drilling rigmounted on the platform through a caisson cemented to the tank dome. The grinder andthe two slurry pumps were installed in pits adjacent to the tanks. All slurry piping wascontained within a larger pipe to limit the spread of contamination in the event of a leak.Most slurry lines were buried; those that were not were shielded to minimize radiationexposure. ; . ,

About 90% of the sludge was re-suspended and transferred in 36 batches. A four-monthfacility shutdown occurred during the winter of 1982-1983 because the disposal well at thehydrofracture site was plugged. Sluicing operations were resumed in April 1983 andcontinued without serious difficulty until completion in January 1984.

The material remaining in the GAAT after the conclusion of the sluicing campaign isincluded in the inventory of material to be processed for the request for proposal, and thedata from this material is what is included in this report. «

Old Hydrofracture Facility (OHF) OPERATIONS3

Beginning in 1964, the liquid wastes from the radiochemical and supernatant from themetal waste precipitation streams were injected into a shale formation 1000 ft. belowthe ground surface in the Old Hydrofracture Facility. Using the hydrofracture process(described previously) a total of eighteen liquid waste injections were made at theOHF during its operational lifetime. The first seven injections were tests of the methodand involved only waste blends with low levels of radioactivity. A total of about 2.3million gal of grouted waste containing about 650,000 curies of radionuclides wasdisposed of in the subsequent injections until 1979, when New Hydrofracture Facility(building 7960) operations were initiated.

Liquids processed during OHF operations were not supposed to have solids foraddition to the grout being injected, therefore, solids were never deliberatelyintroduced into the OHF storage tanks. But during OHF operations it was noted thatsludge was accumulating in the waste storage tanks at the hydrofracture site. This wasevidenced by the loss of pump suction while an appreciable volume of waste remainedin the tank. Stirring of the tank by. the air lift pumps and by recirculating the tankcontents temporarily alleviated the problem but generally the loss of pump suction

A-7

recurred. It is believed that small particles of insoluble materials were transferred tothe hydrofracture tanks with the waste solution, settled out in the tanks, and probablyagglomerated to form larger and less pumpable masses. Material currently in the tanks'consists of deposits accumulated within the tanks during their operational life ofserving as surge and feed tanks to the hydrofracture process (U.S. Department ofEnergy 1996). Since being shut down in 1980, the OHF system has been maintained ina safe storage mode.

OPERATIONS IN THE BVEST's AND MVSTs22'23

The BVESTs were placed in service in 1979? and have received dilute LLLW andhave stored evaporator concentrate. They were never a part of the sluicing operationsin the GAAT system. Solids present in these tanks result from precipitation ofmaterials in the waste when the evaporator concentrate is cooled, and from liquidtransfers from the gunite tanks which had some solids incidental to the transfer. Theselatter transfers were discontinued completely in 1986?. The solids present haveaccumulated over the 17 year period of operations. No previous attempts have beenmade to remove these solids.

Originally, the MVSTs received sludges from the GAAT and were used as feed tanksfor the New Hydrofracture Facility. During 1984, radioactivity was detected inmonitoring wells surrounding the New Hydrofracture Facility, indicating possiblemigration of the radionuclides that had been injected into the shale formation. Theinjection operations were immediately shut down. Subsequent to this, the regulationscontrolling underground injection (Chap. 120046 of the rules of the Water QualityBoard for the state of Tennessee, first issued May 22, 1985) would not allow the NewHydrofracture Facility to be permitted, leading to the abandonment of restart efforts.At the time of the migration detection, a batch of suspended GAAT sludge was in theMVSTs awaiting injection. This material was never injected underground and wasallowed to precipitate in the MVST tanks. Additionally, materials generated byunplugging the hydrofracture well in 1982 were transferred to the MVSTs and neverremoved. Since late 1984, all LLLW concentrate generated at ORNL has been storedin the MVSTs and BVESTs.

The operational safety requirement for these tanks dictates that they be filled to nomore than 95% of their capacity (and maintain at least 50,000 gal free volume), or520,000 gal. An operational flexibility limit (OFL) of 470,000 gal for the subject tankshas been established by Waste Management personnel. Data indicated that as ofJanuary 1992, this OFL was being approached. To avoid shutdown of the ORNLLLLW system before the new MVST-Capacity Increase Project storage tanks willcome on line, interim waste treatment options were implemented. Interim treatmentoptions included source reduction, supernatant evaporation (in- tank and out-of-tank),and supernatant solidification in concrete. Since late fiscal year 1988, foursolidification campaigns were conducted, processing some 200,000 gal of supernatants.Currently, there is no U.S. Department of Energy (DOE)-approved disposal method forthis class of waste, although shipment to Nevada Test Site for disposal is being

A-8

pursued. .

EVAPORATION AT THE ORNL MELTON VALLEY STORAGE TANKS

Bench-scale tests at ORNL showed that 50-70% of the liquid in the MVST could beevaporated prior to solids precipitation, therefore one near-term strategy formanagement of the LLLW stored in the MVST was to sparge the tanks with air toevaporate the excess water from the tanks and to concentrate the stored LLLW to thepoint of near saturation. Operation of the in-tank-evaporation (ITE) process and anout-of-tank evaporation (OTE) process were chosen as the waste treatment option.The in-tank evaporation campaigns were performed in tanks W-24 to W-28 and W-31and were conducted during 1990-94. An out-of-tank evaporation demonstration wascompleted in 1996. These programs are described in more detail below.

IN-TANK EVAPORATION (ITE)22'24

The transfer line from the concentrate storage tank at the evaporator to the MVST's isflushed with water after each transfer, and the flush water is collected in the MVST'salso. As a result, the supernatant undergoes dilution can be concentrated by about 30percent before solids precipitate from it. In-tank evaporation is a method forevaporating water from the supernatant without removing the supernatant from theMVST's. It was estimated that about 17,000 gal/year could be evaporated if 600 cfm(100 cfm through each of 6 tanks) of air was supplied at a -40°F dewpoint and thesystem was on-line 80 percent of the tune. To facilitate supernatant solidificationcampaigns, two tanks remained quiescent and were not treated in this manner.

In ITE, an air sparge system is piped into each tank. Compressed air is metered intothe tanks at a rate of 20 scfm at 30 psig per rotameter, which translates into 100 scfmper tank. Each tank is also equipped with an air line providing sweep air that operateswhen the tanks are not being sparged, when the flow of sweep air may be reduced oreliminated . The ah* from both the spargers and the sweep exhausts through aflowmeter, mist eliminator and high-efficiency particulate ah- (HEPA) filters prior toexiting through a blower and a stack.

OUT-OF-TANK EVAPORATION (OTE)22'23'25

ITE is a relatively slow process and cannot keep up with the current LLLW generationrate nor would it suffice to increase MVST storage capacity hi case of an emergencyneed. In order for ITE to process the.expected future waste generation plus work offthe present inventory in the MVSTs, measures were needed to increase the evaporationrate. This was done by installing a small external evaporator.

Evaporation studies were performed with MVST LLLW concentrate and withsurrogates (nonradioactive) to determine the feasibility of a proposedout-of-tank-evaporation project. The volume of water evaporated hi tests usingsurrogate and actual MVST supernatant ranged from 30 to 55% before precipitation of

A-9

solids occurred. Vendor-site tests were also conducted with surrogate waste formsusing a bench-scale single-stage, sub-atmospheric pressure, low- temperatureevaporator. These tests were successful, and a 30% volume reduction was attained withno crystallization of solids, no foaming, and no fouling of the heat exchanger surfaces.Based on a study by Bechtel National, Inc.(completed in 1991), a single-stage,motor-driven vapor compression evaporator was suggested for the OTE process.

The OTE demonstration project was conducted to demonstrate the feasibility of using askid mounted sub-atmospheric evaporator to process these wastes. Operation withradioactive waste began March, 1996 and was completed April, 1996. The systemsuccessfully processed approximately 22,000 gallons of MVST LLLW. Approximately5,500 gallons of distillate were produced and sent to the Process Waste TreatmentPlant while the remaining 16,500 gallons of concentrate were returned to the MVSTtanks. Decontamination factors (DFs, defined as the ratio of contaminantconcentrations in the distillate to that of the feed) achieved in the evaporator were onthe order of 5x106, exceeding design requirements. Following completion of theCesium Removal Demonstration project, the evaporator system is expected to beupgraded and routinely used at ORNL by WMRAD to process additional LLLW.

WASTE COMPOSITION CHANGES DUE TO EVAPORATION23-26

In December 1994, the MVST supernatants were sampled to assist in MVSTtreatability studies and waste management planning activities. The preliminary results10

from the analyses indicated that the supernatants were generally more concentrated,higher in cesium concentration, and have a lower pH than in previous samplingcampaigns. The ITE process was started in June 1992 and was calculated to havesuccessfully removed over 48,000 gal of free water. This has resulted in concentratingthe supernatants and decreasing the pH by neutralization of free hydroxide by carbondioxide in air. The increase in cesium concentration was caused both by concentratingthe waste and by adding newly-generated LLLW which has a higher cesium content.(Radiochemical Engineering Development Center processing of Mark 42 targets hasincreased cesium concentration by one to two orders of magnitude.)The introduction ofcarbon dioxide by air sparging tends to lower the solution pH, increasing thesolubilities of the dissolved salts. Because the MVSTs were sparged with dry air (theITE process), it could be expected that this occurred.

The increased nitrate and cesium concentrations of the MVST supernatant impacttreatment disposal options. There is evidence that concentrations greater than 5 Mcould lead to expansion, spalling, and cracking of the solidified forms caused bygrowth of large sodium nitrate crystals within the pore structure of the concrete. TheEmergency Avoidance Solidification Campaign (EASC), Liquid Waste SolidificationProject (LWSP) I, and LWSP II campaigns have been successfully performed withwaste containing a maximum of 4.8 M nitrate. Therefore, the supernatants from TanksW-29 and W-30 were blended to reduce the nitrate concentration to 4.8 M for LWSPIII, performed in the spring of 1995??. In addition, a test program was implemented to

A-10

determine, for the MVST supernatant, the highest nitrate concentration that can besolidified and still produce a physically stable product. This testing may indicate that ahigher nitrate supernatant can be solidified safely, however until the test results areavailable, further LWSP campaigns will be designed to use combinations of tanks thatresult in nitrate and cesium concentrations within previous solidification concentrationranges. < .

APPENDIX B

TANK SAMPLING DATA

TABLES B.1, B.2 AND B.3

Measurement Data on Sludge Samples: 1985-1996

B-5

. Table B.I. Physical variable measurements on sludge samples from 1985 to 1996.

bs

12345678910111213141516171819202122232425262728293031323334353637383940414243 .44454647484950 .515253545556575859606162636465666768

Tank

W03W03W03W03W03WO 4W04W04W04W04W05W05W05W05W06WO 6WO 6W06 'W07W07W07W07W07W07W07W07W07W08W08W08W08WO 9WO 9W09W09W10W10W10W10W10W21W21W21W21W22W22W22W23W23W23W23W24W24W24W24W25W25W25W25W26W26W26W26W27W27W27W27W27

Year

19891994199419951995198919891994199519951989199419951995198919941995199519891989199419941995199519951995199519891994199519951989199419951995198919891994199519951985198519901996198519851994198519851990199619851985198519891985198519851989198519851985198919851985198519891989

S_No

S19212216309310S24H26217H306307S75230314315S80221311312S84H85228229303A-H303B-H304301H302S88224320321S92227323324H120S9622632532600W21-SW21S-17800W22S-13900W23-SW23S-141000W24-S000W25-S000W26-S000W27-H1-SW27-H1-H

Density(g/ml)

1.071.35

1.20

1.261.07.

1.191.171.46

1.211.231.181.451.57

1.47.

1.241.081.19.

1.101.281.25

1.131.251.23#

1.401.46

1.17

1.341.46

#

1.26

1.32

1.54

1.261.33

H20Fraction

.

o!5760.6350.8790.886

#0.7110.8340.766

0.7200.6830.780

0.6560.7280.625

0.7040.6790.5870.6210.5770.6590.747t

0.7860.8340.835,

0.8280.8660.867

m

0.7280.6110.771

0.498

0.739

0.423

PH

10.510.6

.

t

11.1

10.310.2

9.1

9.9

10.6

TSOL DSOL(mg/g) (mg/g)

300

307349

348

406

367360

558

944

845449

511

268 25.5

544

454487

580531

413449

408386471

SSOL TOC(mg/g) (mg/kg)

34105302004240448091909020

45311304020700847627

911024003310117009030401013001300866

1520796

17401130084006420529013900290029302120146008180490026404870

6480100

242 22100

4120100

2940

2330

6220

24403830

ICAR(mg/kg)

2400170018601110

19901380

180019001990

330034805000

47004700408044505040

4290

790060504240

190015902180

510035503430

1200028000

10400

1810032000

6630

3920

12000

525012700

TCAR(mg/kg)

5100190061005590

r

24502510

250027402620

56006790

16600

61006000495059605830

6030

16400125009530

.480045204300

1000061808300

1850028000

32500

2220032000

9570

6250

18200

769016500

B-6

Table B.I (continued)

Obs Tank Year S No

69707172737475767778798081828384858687888990

W28W28W28W28W29W29W30W30W31W31W31W31T01T01T02T02T03T03T04T04T09T09

1985198519851989198519851985198519851985198919891989199619891996198919961989199619891996

000W28-S000000W31-SVJ31-HS370 •

S400S430S460S480

Density H2O(g/ml) Fraction

1.49

1.26

PH TSOL DSOL SSOL TOC ICflR TCflR(mg/g) (mg/g) (mg/g) (mg/kg) (rag/kg) (mg/kg)

1.33

1.331.391.311.231.21

1.16

0.683

0.619

0.604

0.722

0.702

9.6

10.4

450533

428

342

344369964921

324

364

253

343

2500 3620 6120

.4108530

186004100

2800013000914040004 62098007620100

141021900

8900

16000

12000

5200

16000

182030400

13000

29000

16000

15000

16000

B-7

OBS

123456789

101112131415161718192021222324252627282930313233343536373839404142434445464748495051525354555657585960616263646566676869

Table B.2.

Tank Year

W03W03W03W03WO 4W04W04W04W04W04W05W05W05W05WO 6W06W06W06W07W07W07W07W07W07W07W07W07W07W07W08W08W08W08W09W09W09W09W10W1OW10W10W10W21W21W21W21W22W23W23W23W23W24W25W26W27W27W28W31W31T01T01T02T02T03T03T04T04TO 9T09

19891994199519951989198919941994199519951989199419951995

,19891994199519951989198919941994199519951995-19951995199519951989199419951995198919941995199519891989199419951995199019961996199619941990199619961996198919891989198919891989198919891989199619891996198919961989199619891996

S_No

S19212309310S24H26216217H306307S75230314315S80221311312S84H85228229301H302303A-H303B-H304303C-H303D-HS88224320321S92227323324H120S96226325326W21-SW21S-178W21S-012W21S-012W22S-139W23-SW23S-141W23S-011W23S-011W24-SW25-SW26-SW27-H1-SW27-H1-HW28-SW31-SW31-HS370S400S430S460S480

Chemical variable measurements (mg/kg) on sludge samples from 198:1996.

Ag

0.051.10

25.1022.700.080.061.101.10

23.1026.300.260.923.903.800.018.603.809.210.360.120.921.401.241.241.201.204.06

18.0010.101.301.303.703.900.770.983.703.700.890.792.095.828.40

50.00m

3.30#

2.0328.00

3.30

7.707.60

30.007.20

13.0017.006.105.402.101.002.901.000.151.101.701.000.211.20

Al

51100.00733.00'913.00

2550.00815.00

8150.007480.00

.21200.0015700.0010400.00

10900.0012100.009630.00

5130.005970.006580.004130.001190.004660.003160.00

17.501170.00

.9800.009880.00

10300.00.

8850.008540.009150.00

.30200.0034000.0029000.00

1000.00852.00

#

1900.002800.002330.00

1600.002800.007500.004300.006800.00830.00

1400.0016000.00

26200.00

15900.00#

15600.00

9320.00

34500.00

As

2.001.100.500.504.002.001.201.100.500.501.003.700.700.712.000.480.702.226.006.000.921.40

4.975.005.005.00

4.001.300.682.325.000.980.650.687.005.701.300.470.50

42.005.10

,

4.4050.004.70

.

42.0041.0065.0039.0069.0027.0033.0029.002.001.201.001.203.001.304.001.202.001.40

B

.

2.503.302.94

.2.802.604.865.44

.104.0016.3011.80

.6.369.87

14.30.

30.1021.5024.2019.9015.3061.9024.3013.6013.40

.34.5013.1010.60

.6.167.076.76

9.413.473.506.607.89

10.005.03

3.101.507.306.40

11.004.901.20

22.00

43.70

43.90

31.80

49.70

41.60

Ba

6.409.015.402.94

11.005.805.665.496.54

18.00140.00

6.9039.7095.30

350.00210.00210.00107.00

1300.0016.00

231.0079.9054.7023.9061.10

318.0016.7076.9024.8038.0052.0045.9025.40

200.0089.6099.30

114.0024.0094.0075.30

310.0083.7078.0048.40

#

70.1063.0055.40

.

44.0059.0087.0049.0072.0039.0017.00

180.0088.0051.9033.0052.3076.0069.6050.0026.50

115.0081.30

Be

0.000.190.020.020.000.000.210.19

15.606.550.000.671.501.500.000.091.501.400.000.002.192.320.990.500.050.050.050.050.050.008.67

14.609.710.004.917.267.530.000.00

10.407.223.900.000.15

2.590.003.66

.

0.000.000.000.000.000.000.000.000.00

24.300.00

19.600.002.900.002.700.00

45.40

Ca

.716o!oO

13400.008120.00

683.00620.00

1660.002040.00

.11300.00

9000.0019900.00

31600.0025800.0029800.00

1300.001440.002600.00

791.00384.00

1020.00477.00301.00326.00

. .9140.007850.007230.00

.6010.006090.006350.00

5960.0013900.00

8810.0045000.0083900.00

33600.0055000.0055500.00

.

29000.0038000.0036000.0038000.0054000.0057000.00

5600.0062000.00

27900.00

36600.00

37900.00

20600.00

32800.00

Cd

0.521.301.501.40

22.002.101.401.975.554.84

10.005.372.382.201.004.956.758.132.002.201.101.603.643.653.603.603.703.603.704.104.695.223.784.903.493.102.706.104.704.685.442.70

27.0039.00

22.9032.0016,10

.

6.1011.0042.0013.0017.0026.00

1.701.50

12.9014.40

6.6014.408.50

10.2010.0016.40

7.8010.90

Co

.

1^503.203.82

1.601.504.765.64

1.302.502.40

4.897.35

24.20.

1.301.902.702.702.702.702.702.672.80

.2.452.952.50

1.723.102.90

1.702.304.50

.1.30

2.55

5.20

4.24

14.20

5.53

11.00

9.54

Cr

1300.00468.00288.00252.00720.00200.00316.00158.00212.00227.00580.00

1220.001580.001020.002400.001390.00

930.001770.00

660.00130.00264.00337.00115.00143.00168.00

1550.00132.00124.00114.00410.00314.00256.00206.00160.00131.00113.00115.00

97.00140.00171.00122.00'214.00160.00248.00

146.00190.00152.00

36.0059.00

170.0065.0090.0055.0027.0075.00

130.0079.40

180.00241.00

69.0051.80

102.00118.00

10.0085.10

Cs

m

m

.

#

2 .

2 .

1 .

2 2 .

5 ..

5 .

1 .

57

81

48

50

68

53

43

Cu

17^5032.3027.20

.

7i086.03

38.3039.60

30.7040.5026.50

#

31.2041.5058.80

.

98.00100.00115.0080.0059.8043.8078.4030.8049.30

62.6062.2044.00

50.4048.6046.10

86.8071.4075.00

.77.40

33.70

37.90

156.00

126.00

64.30.

293.00

117.00

B-8

Table B.2 (continued)

OBS

123456789101112131415161718192021222324252627282930313233343536373839404142434445464748495051525354555657585960616263646566676869

Tank

W03W03W03W03W04W04W04W04W04W04W05W05W05W05W06WO 6W06W06W07W07W07WO7W07W07W07W07W07W07W07W08W08W08W08W09W09W09WO 9VJ10W10wioW1OW1OW21W21W21W21W22W23W23W23W23W24W25W26W27W27W28W31W31T01TO1T02T02T03T03TO4TO4TO 9T09

Year

1989199419951995198919891994199419951995198919941995199519891994199519951989198919941994199519951995199519951995199519891994199519951989199419951995198919891994199519951990199619961996199419901996199619961989198919891989198919891-98919891989199619891996198919961989199619891996

S_No

S19212309310S24H26216217H306307S75230314315S8O221311312S84H85228229301H302303A-H303B-H304303C-H303D-HS88224320321S92227323324H12OS96226325"326W21-SW21S-178W21S-012W21S-012W22S-139W23-SV123S-141W23S-011W23S-011W24-SW25-SW26-SW27-H1-SW27-H1-HW28-SW31-SW31-HS370S4O0S430S460S480

Fe

.2890.00245.00195.00

.1020.00294.00839.001700.00

.19200.0019400.0014400.00

14700.009950.00

14200.00

.4670.006570.005250.00887.00787.00

20300.00715.00240.00423.00

9240.005920.004100.00

t3410.003040.003170.00

#

8400.004010.0010900.002300.004040.00

2150.001900.001930.00

#600.00940.00

2300.001400.002500.00630.00420.00

7700.00

3440.00

6240.00

- 1790,00

3150.00

17900.00

Hg

0.836.42

22.3016.702.400.825.753.41

25.9062.6018.00107.00132.0071.8036.0040.2082.80

112.00141.0052.00

137.00111.00264.00138.00121.00140.00104.0058.6060.5050.00416.0081.3055.4040.0062.7075.3062.1011.0048.00

294.0093.10

288.0056.0011.30

#

105.0019.008.44

26.0037.0064.0011.0018.0012.0014.0039.0074.00187.0070.00

196.0040.007.89

585.0015.1039.001.80

K.

38l!oO334.00298.00

.299.00251.00219.00459.00

310.00509.00436.00

.595.00764.001120.00

.

8310.008330.0013000.009170.00

10200.006150.00

10900.0011100.008930.00

1420.001500.001370.00

4010.002520.002430.00

3860.003240.002650.008500.0010300.00

g

3270.0018000.0025200.00

7600.009200.00

15000.006100.006700.00

11000.007900.006700.00

1680.00

2130.00

6140.00

2080.00

974.00

•Mg

303.00874.00577.00

47.8066.20

291.00538.00

284.00482.00476.00

746.001910.003540.00

m273.00299.00.409.00267.0095.00

203.00145.00247.00176.00

5520.005460.0011100.00

613.00845.00843.00

592.00728.00

2180.009600.008630.00

3620.0016000.0014500.00

m5600.005900.00

11000.004800.005900.0015000.00

870.003100.00

3460.00

3170.00

3570.00

1730.00

5140.00

Mn

0.00127.0026.4044.100.000.00

24.9047.2018.0028.600.00

276.00433.00530.00

0.001510.00801.00341.00

0.000.00

110.00116.0083.4034.8036.60479.0020.5027.9019.500.00

163.00142.0098.500.00

143.00144.00152.00

0.000.00

152.00270.00180.00

0.00114.00

#

182.000.00

275.00

0.000.000.00

• 0.000.000.000.000.000.00

318.000.00

336.000.00

199.000.00

472.000.00

337.00

Na

16900.009540.008380.00

30200.0025000.0011700.0010900.00

21100.0052700.0030900.00

43900.0035800.0042400.00

42900.0043200.0041100.0054400.0066100.0068700.0063500.0059500.0056100.00

5070.0010100.009730.00

7050.006310.005660.00

#

14700.0012300.0012100.0048000.0042400.00

#

15400.0082000.0066500.00

.

6900o!oO66000.0051000.0071000.0066000.0066000.0069000.0048000.00

4040.00

5060.00

18800.00

7400.00

6640.00

Ni

7.005.715.505.7815.0014.005.926.50

15.2014.2052.00129.00' 96.3086.9085.00

102.00138.00212.0084.0022.0043.5054.7037.1019.6012.60

178.007.354.604.80

160.00133.00130.0095.60

110.0073.3073.0071.8031.0083.0071.2084.30

233.0075.0098.50

.70.90

110.0069.60

22.0034.0092.0027.0040.0062.0017.0052.00190.00373.0072.00173.0057.0050.00160.00134.00380.00452.00

P

.

t

t

i .

: ,

1 .

160P0.00

#

13700.00

: ,i >

6940.00,

8340.00

7510.00

8O8o!oO

12600.00

Pb

52.0071.005.009.90

150.0062.0079.0073.0015.6017.10

388.00333.00213.00303.00

1100.001010.002110.007320.00300.0077.0063.0092.0062.6040.0015.00

106.0018.7041.0056.10

1800.001440.001520.001150.00620.00513.00487.00488.00190.00480.00473.00706.00920.00290.00302.00

#

341.00450.00380.00

150.00220.00470.00120.00200.00190.00170.00360.00860.00568.00350.00654.00300.00229.00510.00598.00540.00521.00

B-9

Table B.2 (continued)

Obs

123456789101112131415161718192021222324252627282930313233343536373839404142434445464748495051525354555657585960616263646566676869

Tank

W03W03W03W03W04W04W04W04WO 4W04W05W05W05W05W06W06W06W06W07W07W07W07W07W07W07W07W07W07W07W08W08W08W08W09W09W09W09W10W10W10W10W10W21W21W21W21W22W23W23W23W23W24W25W26W27W27W28W31W31T01T01T02T02T03T03T04T04T09T09

Year

198919941995199519891989199419941995199519891994199519951989199419951995198919891994199419951995199519951995199519951989199419951995198919941995199519891989199419951995199019961996199619941990199619961996198919891989198919891989198919891989199619891996198919961989199619891996

S_No

S19212309310S24H26216217H306307S75230314315S80221311312S84H85228229301H302303A-H303B-H304303C-H303D-HS88224320321S92227323324H120S96226325326W21-SW21S-178W21S-012W21S-012W22S-139W23-SW23S-141W23S-011W23S-011W24-SW25-SW26-SW27-H1-SW27-H1-HW28-SW31-SW31-HS370S400S430S460S480

Sb

.27.0020.0020.00

3o!oO28.0020.0020.00.

24'.0010.7010.40.

13.0010.0010.00

24.0035.0049.0049.0050.0050.0050.0050.0050.00

33.0010.0011.00.

25.0010.0010.00

32.009.7010.00

55.00

26.00

56.00

m

m

17.00

17.00

19.00

17.00

20.00

Se

0.301.100.500.500.700.491.201.100.500.500.813.700.520.502.000.480.500.491.001.003.705.40,

4.975.005.005.00

0.705.100.490.510.703.900.480.481.000.905.000.470.5025.005.00#

4.4039.004.70#

52.0051.0055.0049.0086.0029.0041.0037.002.001.201.001.200.741.301.501.202.001.40

Si

.509.00

277.00190.00

3360.00

3360.00

159.00

2660.00

r

#

4010.00

3950.00

32500.00

4570.00

3640.00

Sr

niso31.8021.20

.3.393.2216.5022.20.

33.9024.5033.10.

54.5065.1064.60

11.4012.6016.107.714.20

13.003.802.433.79.

55.4050.2035.40.

37.4039.3041.60

34.0066.2063.90

200.00295.00

290.00275.00

.110.00150.00120.00120.00150.00130.0030.00170.00

946.00.

992.00

282.00

334.00

908.00

Th

.340.002160.001320.00

.370.00350.004430.003050.00

94.60399.00319.00

679.001810.001320.00

3920.004490.004180.003180.004240.001510.004710.005160.005060.00

16400.0014300.009750.00

6260.005780.005870.00

6250.0010400.004180.0014000.007460.00

10600.0013000.007520.00

.1480.003860.009360.001890.003040.001370.002790.0011800.00

90500.00

94300.00

77500.00

124000.00

56800.00

Tl

0.3025.000.500.500.700.4028.0026.000.500.500.5022.000.520.502.0036.100.500.491.001.0022.0032.00

4.975.005.005.00

0.7031.000.490.510.7023.000.480.481.000.9030.000.470.5010.0075.20

#

29.0016.0017.00

16.0016.0017.0020.0027.009.0013.0011.001.701\181.001.400.601.300.731.202.001.40

0

61300.00128000.0047900.0042300.00

330000.00296000.00211000.00186000.0043100.0049900.001420.00927.00451.00895.006340.008860.0017900.0091100.0045000.0086000.0073400.0086800.0084600.0063500.00179000.0063100.00195000.00222000.00212000.008560.005070.005690.005930.0025800.0031600.0014000.0011900.0082300.0010800.0020500.0010600,004350.0031000.0025300.00

35500.0017000.0039700.00

r

f3700.004800.0024100.002710.001960.0017000.003000.009200.002800.002420.001000.002090.003060.005920.001850.007870.002930.002510.00

V

.4^200.500.50.

4.604.300.500.50

3.702.702.60

1.902.602.50

3.705.402.471.741.481.471.302.912.28

5.104.632.60

3.902.502.50

5.002.402.60

0.38

4.00.

5.37

6.60

6.70

7.30

6.80.

7.80

Zn

18.203.101.50

9.8812.607.9310.30

35.2027.1026.00

89.90157.00362.00

#31.1033.4049.7031.8018.5028.8022.108.258.09.

100.0095.6078.50

67.0051.0050.10

110.00123.00102.00

756.00

1100.00.

997.00

178.00«

236.00

151.00

183.00

149.00

B-10'

Table B.2 (continued)

Obs

123456789101112131415161718192021222324252627282930313233343536373839404142434445•464748495051525354555657585960616263646566676869

Tank

W03W03W03W03W04W04WO 4W04W04HO 4W05W05W05W05WO 6W06HO 6W06W07H07W07W07W07H07W07W07H07W07W07VIOBW08W08H08W09H09W09WO 9W10W10W10W10W10W21W21W21W21W22W23W23W23W23W24W25W26W27W27W28W31W31T01T01T02T02T03T03T04T04T09TO 9

rear

198919941995199519891989199419941995199519891994199519951989199419951995198919891994199419951995199519951995199519951989199419951995198919941995199519891989199419951995199019961996199619941990199619961996198919891989198919891989198919891989199619891996198919961989199619891996

S_No

S19212309310S24H26216217H306307S75230314315S80221311312S84H85228229301H302303A-H303B-H304303C-H303D-HS88224320321S92227323324H120S96226325326W21-SW21S-178W21S-012W21S-012W22S-139W23-SW23S-141W23S-011W23S-011W24-SW25-SW26-SW27-H1-SW27-H1-HW28-SW31-SW31-HS370S400S430S460S480

Bromide

.5.006.005.00

53.00

5.005.00

48.0034.0038.00

64.00•42.0040.00

88.00111.002360.003280.002820.002930.002730.00

.mt

110.009.639.04

61.007.277.43t

t46.0013.0029.80.

89.00

470.00

4.63

5.20

43.00

41.00

70.00

Chloride

.5.006.005.00

53.00

5.005.00

48.0034.0072.70.

64.00167.00144.00

2840.002530.00101.00106.00118.00102.00109.00

.

.110.00422.00423.00

61.00134.00141.00

m

546.00571.00

' 597.00

1120.00

3170.00

247.00

366.00

947.00

401.00.

3760.00

Fluoride

.23^020.9017.50

53.00

22.6020.00

#1960.001880.002080.00

.11900.004170.001760.00

2320.001870.002770.002480.001100.003850.001720.00

518.00151.00130.00

.305.0076.6083.80

#

437.00364.00333.00

157.00

185.00

•176.00

233.00

257.00.

272.00.

140.00

Nitrate Nitride

87.0012.0010.00

1370.00 , .

1730.001420.00

m m422.00602.00639.00

12300.0011600.008570.00

38500.00 '32600.0030000.0042000.0037300.0037700.0036700.00

2500.002690.002580.00

122! oo '.572.00613.00

6270.004440.005760.00

166000.00

126000.00

52.60 629.00

27.90 576.00

4250.00 4670.00

1470.00 1460.00

869.00 219.00

Nitride Phosphate Sulfate HCN

3240.00 318.001510.00 513.001370.00 539.00

3070.00 1910.00

434.00 2220.00147.00 1530.00

267830903650

.00 •

.00

.00

250308315

.00

.00

.00

7900.00 9400.006660.00 8510.004430.00 5690.00

5320.004750.003470.004490.004770.005200.005190.00

8130.007700.006540.008720.007700.007990.007510.00

1100.00 4300.00191.00 3470.00361.00 3280.00

3660.00 622.002990.00 476.002230.00 511.00

460.00 2870.00291.00 1770.00242.00 1950.00

210.00 8030.00

200.00 3540.00

5% 40

18.50 339.00

20.80 7 2 6 J 0 0

174.00 2960.00

165.00 1210.00

195.00 616.00

B-ll

0bs

123456789101112131415161718192021222324252627262930313233343536373839404142434445464748495051525354555657585960616263646566676869

Tank

W03W03W03W03W04W04W04W04WO 4WO 4W05W05W05W05no 6W06W06W06W07W07W07W07W07W07W07W07W07W07W07W08W08W08W08W09W09WO 9W09W10W10W10W10W10W21W21W21W21W22W22W22W23W23W23W23W24W24W24W25W25W25W26W26W26W27W27W27W27W28W28W28

Table B.3.

Year

198919941995199519891989199419941995199519891994199519951989199419951995198919891994199419951995199519951995199519951989199419951995198919941995199519891989199419951995198519851990199619851985199419851985199019961985198519891985198519891985198519891985198519891989198519851989

Radiological variable measurements (bq/g)to

H,0S_No Fraction

S19S212S309S310S24H26S216H217S306S307S75S230S314S315S80S221S311S312S84H85S228S229H303AH303BS304H301S302H303CH303DS88S224S320S321S92S227S323S324H120S96S226S325S32600W21-SW21S-17800W22S-13900W23-SW23S-14100W24-S00W25-S00W26-S00W27-H1-SW27-H1-H00W28-S

0.5760.8790.886

0.6350.7110.8340.766

0.7200.6830.780

0.6560.7280.625

0.7040.6790.5870.6210.5770.6590.747

0.7860.8340.835.

0.8280.8660.867

#0.7280.6110.771.m

0.498t

0.739

t

0.423

#

.t

#

1996GrossAlpha

840012000650084005900660057004700720016000130019009009408000

1100033000220001400080002000022000650024007100170001200058006300

2900047000330002400011000010000061000650004100084000810004400057000189070732601290001500001298708362014000025789011803022300012000062900407002340096200814004650096200592009130051800444002250031000329302294053900

GrossBeta

1500000100000014000015000031000087000120000700009000009200001800002000009800081000

1000000110000030000001200000310000017000003100000380000039000002500000280000033000002500000640000031000006700000750000064000004800000500000047000004900000520000012000000530000076000008000000120000003141300252710033600003000000209050019869003100000876900075850006670000420000069190006290000262000015318000135050004000000662300066970005700000518000004662000144000020200008732007585002400000

2"Am

260

.00

570

170001400015000110009700

2200015000200

#570040007200

52005200

.4500

440052002590

#

170003700

120001110

150008510

11470

7030

8140

3700

198Au

9990

9620

8510

1480

3700

1850

3700

2220

' "c

#

#

#

180

365

843

171

213

189486

76

252Cf

10

67

4

8

144

4

2550

14lCe

#

t

28000

27000

3900

4200

12000

56007700

17000

2OCrn

#

25000

26000

3600

3900

13000

650010000

14000

on sludge samples from

i 2"Cm

10180

76

234197

35066119311842006886

22440743642002500121601621450767

5049486685258252

1500021620176559288

54000583004123644785140004700050544314604930529970

446009900040700

9500081030

1670006800010360

1630064750

3320012950

6140058090

160002150011100

38300

t0Co

245012015012

23271401402602301401109105601400450

500020002700310047072076029001400720620400480033001900780

73007000710014001300072006600560039220

807005500027380

3100032560

25200018000058460

3390050320

4030054390

103000112110

.161002500080660

.79100

"<Cs

220210

r

t.

260480

100

.2800230022001600150035002300

42036020

3103001400

69902600

11000

65009800

620

707

2970

12001800

46000

137Cs

47000460004700043000310001300038000

. 2000085000340000300002400015000190008200090000

150000180000

12000001000000110000014000003100Q00210000022000001100000890000

540000025000004700076000069000051000022000

390000330000330000

11000000860000

1700000950000790000250120

249000130000186850

420000240870

a49500041000062160

196000288970

22100032560

#684000111000

37500057100031080

194000

B-12

Table B.3 (continued)

obs Tank

70 W2971 W2972 W3073 W3074 W3175 W3176 W3177 W3178 T0179 T0180 T0281 T0282 T0383 T0384 T0485 T0486 T0987 TO9

Year S No

198519851985198519851985198919891989199619891996198919961989199619891996

000000W31-SW31-HS370S400S430S460S480

H2O GrossFraction Alpha

2220008140014060107301147001110002310085200650000460000250000530000200000300000370000600000150000350000

0.683

0.604

0.702

GrossBeta

1591000130980019684001690900

149110001561400031800001170000059000000450000002000000044000000250000002300000036000000410000001600000050000000

2"Am >"Au

17390

2960

12580

>2Cf '"Ce l3Cm "Cm i0Co "Cs

. 132090 42920

3700

86950 45510

. 314 . 9400 8400 17100 8100 3640

. 1050 . 14000 13000 "68900 28300 325048 . . . . 260000

52000 . . 460 . . 350000 67000 49017 200 . . 180000 64000

26000 . 500 . . 460000 77000 510. 760 200 . . 180000 160000

15000 . 300 . . 250000 100000 7108200 . 510 . . 210000 600008000 . . . . . 530000 160000 590

. 2200 2 . . 97000 4300013000 . 350 . . 270000 49000 480

• 1 3 7 C s

61050

17760

142080

23500056400039000039000025000035000013000001600000450000340000400000260000

B-13

Table B.3 (continued)

0bs Tank

1 W032 W033 W034 W035 W046 W047 W048 W049 W04

10 W0411 W0512 W0513 W0514 W0515 W0616 WO 617 W0618 W0619 W0720 W0721 W0722 W0723 W0724 W0725 W0726 W0727 W0728 W0729 W0730 W0831 W0832 W0833 W0834 W0935 W0936 W0937 W0938 W1039 W1040 W1041 W1042 W1043 W2144 W2145 W2146 W2147 W2248 W2249 W2250 W2351 W2352 W2353 W2354 W2455 W2456 W2457 W2558 W2559 W2560 W2661 W2662 W2663 W2764 W2765 W2766 W2767 W2868 W2869 W28

Year S No 12Eu 15<Eu 155Eu 3H "Nb 2J7Np"Pu ZJ3PuAM 240Pu 238Pu 2"Pu 2<°Pu J"Pu 2 nPu 2"Pu m R u

198919941995199519891989199419941995199519891994199519951989199419951995198919891994199419951995199519951995199519951989199419951995198919941995199519891989199419951995198519851990199619851985199419851985199019961985198519891985198519891985198519891985198519891989198519851989

S19S212S309S310S24H26S216H217S306S307S75S230S314S315S80S221S311S312S84H85S228S229H303AH303BS304H301S302H303CH303DS88S224S320S321S92S227S323S324H120S96S226S325S32600W21-SW21S-17800W22S-13900W23-SW23S-14100W24-S00W25-S00W26-S00W27-H1-SW27-H1-H00W28-S

220880780

14015012002300

340

370130012001600

83001600

130001100012000790074001700012000

90250020001300230

340040004000

76130340490

6467

480340

290

4601100

4801300

4501200740

15001400120019001300700

1400140

240023006300440

560047004700

450640590

220150960

1500

36011

4600 80003400 46004300 44003300 3200

429200 216080

958

1200840. 120. 83

1200190081006700690052004800 .

110007300

014001500130052 0950

47001200 .

1. 140

180017001800

88800 7400

40810602159

00

4461536

,540228253

70457753344

57404400670194682

25672256481536

136778481847-2

282001372512545

2300481403876

483119002800

300210

513011800

.498340470.

246849007900

853109671057013002516830557699

530054004600

800042003700

r50004400590014060

170240180

141067411107057954160403021016426002001100640

18002300721666500

2100

2900480045002100

2200018000960076006700

290001100090003400

30710

39004400

1100440210290100

10200620370

t

1800940

2400480630810342110

32003500300037009200620018001700

110008200420014003400

280

492

164

1220

52

9120

120150374

760610770

1200610700

1100550

1200

1500

6900

.00.

8820

710

820m

1800330017819

810059005900

1200066007700

1100060007000

0

0

00#0

0#

6

00002

14

111.522

312

0

0

00

0

0

0

.0000

m

0

000

000

1300000 477000 133000 . 4700980000 420000 99000403300 197950 76220 . 12210

560000 250000 58000447700 304140 94350

722000 514000 1210001100000 640000 130000

3700 53280 22570

62000 36000 1030043290 39220 11840

81400 5060029600 3700

492000 31900037370 3700

19900 1260024200 15100112110 65120

163008880

751006660

34003260

25530

. 7000

560

590

.' 2600

730. 1400

. 51300 24900 . . . . . 440006 . 7400 14000 3200 2800 41000 2 1

. 7030 10360 . . . . .

! 28000 7900 16000 4580 3410 66300 3 6. 21460 18500 . . . .

.* 32100 11800 .' . . . . ! 620006 . 4800 7200 2600 2300 37000 2 1

. 7030 7770 . . . . .

718000 320000 97000 . 2900

3740 1540. 6290 11840

7350 2930 • '.. 9250 7030

14800 5110. 7400 3330

4410 10406730 1860

. 1850 2220

5280 1510 '.

. . . 5700

. . . 5900

.' '. '. 25000

. . . 11000

. . . 16000

. . . 28000

C0C0C0C0C0C0C0CD-J»J*J-J-J^J-J-J-J-O(rt D* O•J(nUi>UU|OHOlOCOslO\(JiAUtOMO

O O O O O O O O O O W l O U U U W t O W D

^D \D 10 10 ^D 10 10 10 ID 10 IP ID ID 10 ID 10 ID ^D fDtDCO^DCO^DCOlOCOlDCOCOOOCOCOOOOOCOOOQJ

OCOOOOCOOUOOSISOOOOOOU)

C 0 C \ U ) O ^ J H * M S

uuowmptJcowoMjO O O O O O O O O O C\ OO O O O O O O O O O O Ooooooooooooo*

V^ CO ^ it^ kbfe 03 ^ J 0^ OJ C^ Cn ^ ^ C ^ ^ yowjooooooootoco ID o J:OOOOOOOOOOOC O COS

o o oo o o o o o o o o • o. • • o c

y* to to M

C\ M -4(J l tO CJ fO CO CO Cn H-» t-1 MtO OOID SICDNJO-J IC CO -J COnO OOO OOOOOO Ui J M rO« OOO« O O O O O O * O» ©• O

COro 00ro -JO CO*

o oo oo o •

SSSSSSSS5!SSSMN)MI010tONtONNtOM

SSSSSSSSSSS33SS)IOIO|OIOh9IOIONNMIOIOHH)-'JUU(JUMMMHPHHOOO

VD I D CO CO

u

tD ID IDIOVD\D101OIDVDVDIOIDID*D1D*O'D'>DIOVD\O ID VO ID VD VO ID ID ID VD \D ID \O *D IDID \D CO\D*D\DCO\D\OVDVDIOVOIO'D'DCQCOID\OVOCQIO\O^OCO'£>ID\D\OCOCDIOVOIOCO

toCO1

210900

606000

to to

I i

H-X

:s-

x

1961000

421000

615000

26-S

2971100

1840000

25-S

1730000

1§o-

to

1

2812000

1150000

to to

cn i

141

2726900

2330000

580000

22S-139

377400

620000

21-S

21S-178

606800

783000

440000

(/)[nwwawtotnwwwMCftKawscniffiwwaMwww(/)WMMMt/)M3:wffitnwWUMlOPUWWWWWWCOUUWUUWWMMCDXDWUMCDULJtO'JWUlOMMNUWtOHNNtOO\N)N)MNNIOtOMCDOOOOOOOtOtOUIAHHMOHHU]UiOOHHAAHOMU)CT» W C\ O *» CO -J H O A W U (OH AUUIOCO tOMM CJI^O -J C\ -J O\ OlDtO

a o ro>

*JOJ*CTitOCO-J-JrOCOtO\DCOM OilOH H C O - J U O ^ l f l P U MtO U1POOOOOOOOOOOOOOMCOOl^MM^J^DMMOOl^OC^MM^ltO-JCnMWtOCOMUJCOOlo o o o o o o o o o o o o o co o o o co o o o o o o o o o a» .t* ID \D O O «> «s M \O ID \O O OO O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO

M tO O • MCOMtO"

O J M

cn -J CTI mo . (ooco-

toco -J cntOOJ OMO^J» pcn>

MVD>UCOMOOuicoo-

t U , M t O

ow« encoo

ino*

M M r O CO Ma> to LO -O i-j-J-JcrthJCn-JiOcr»UlVDtO(jJOlO*J"X>CnO(JiC*)C^OoMupoo^uuococnioo

MtO MMtOen M OJ CiJa>coMincn

C J a > c o J c nmiocrt* crtcrtto

Mis) to —i t n*JOlO*»

o o u> -J O O •

t O t O M M t O t O M

cnvx>VDmocntoiDCOtoMtoto-JcnvD^oo* • •

tO tO M M-J o M crtMOOC0 -JO

o o o o to • MO

IU

G

a*CD,

I

MMto co M M Cd

Cn co cn o Ji. -J co• U P U ) > O -J Cd V£> •

' t O M M M Mc o * J V D J M O ^

t O t O L J t O Mas>t*touioiocncncn.uM<x><x>tDOOtoco icoA sJ OCD O O P U OlO

CO tOai tocn o

G

>£>.

oo

tocnoo

M-ooo •

CO O-J Oo oo o •

CO-ooocnoo •

co to

sCOoo

B-16

Table B.3 (continued)

Obs

707172737475767778798081828384858687

Tank

W29W29W30W30W31W31W31W31T01T01T02T02T03T03T04TO 4T09T09

Year

198519851985198519851985198919891989199619891996198919961989199619891996

S_No

000000W31-SW31-HS370S400S430S460S480 '

MSr

455100

740000

743700014300005170000

3200000020000000120000001800000081000008500000

22000000160000001400000020000000

ssTc

.

13

47

33

28

140

!32Th l5Zr

370

380

320

500

230

2738

444

2257

5082050

79008300780083001500071002400044006400

47006600

110

95

130

180

57

1

1

2

2

1

1

1

1

2

1

• 30

26

73

97

31

TABLES B.4, B.5 AND B.6

Measurement Data on Liquid Samples: 1985-1996

B-19

Table B.4. Physical variable measurements on liquid samples from 1985 to 1996.

Obs Tank year S NoAlkalinity Density

(mg/kg) (g/ml)pH Si TSOL DSOL SSOL TOC ICAR TCAR

(rag/1) (mg/ml)(mg/ml)(mg/ral)(mg/1)(mg/1) (mg/1)

12345678910111213141516171819202122232425262728293031323334353637383940414243444546474849505152535455565758596061626364656667686970717273

W03W03W03W03W03W04W04W0 4W04W05W05W06W06W0 6W06W06W07W08W08W08W09W09W10W10W10W1OW21W22W22W23W23W23W23W23W24W24W24W24W24W24W24W24W24W24W25W25W25W25W25W25W25W25W25W26W26W26W26W26W26W26W26W26W26W27W27W27W27W27W27W27W27W27W27

1989198919891994199419891989198919941989199419891989198919941994198919891989199419891994198919891989199419901985199419851985198519901995198519851985198519851985198519851989199419851985198519851985198519851985198919851985198519851985198519851985198919941985198519851985198519851985198519891994

L16L17L18203204L22L119L23205 'L73218L77L78L79219220L82L86L87223L90222L93L94L9522500W22-L1-1000W23-L1W23-11500000000W24-L2W24-08400000000W25-L200000000W26-L2W26-08600000000W27-L2W27-087

61000

62000

72500

37000

38500

6400

2700

3200

5000

33000

32000

44000

1.001.011.01'1.001.011.011.011.031.011.041.011.001.011.061.011.021.131.021.031.021.021.011.001.011.031.01

1.01

1.24

1.28

1.27

1.30

1.281.231.19.

0.97

0.99

1.08.

1.231.20.

1.30

1.30

1.30

1.251.221.26.

1.14

1.15

1.16.

1.221.211.28.

9.010.111.19.4

10.69.1

10.010.99.8

10.69.88.7

10.411.88.4

10.810.79.69.79.3

10.29.99.2

10.510.99.96.9

12.A

12.813.0

13.113.0

12.5

11.29.3

11.87.2

6.505.307.20

2.552.071.75

3.992.981.65

7.351.391.14

1.711.902.34

2.74.48.4

6.310.327.9

12.90 48.2

2.514.774.1

170.029.437.6

2.53 21.2

5.513.636.7

114.924.6

575.8383.0

469.0

697.0

2.94.68.62.76.56.1

10.127.47.9

47.511.4'2.5

14.874.01.3

16.7158.729.437.815.221.210.75.7

13.737.111.0

23.4

381.0

487.0383.0

517.0

499.0

430 ..0

334.0

618 !o

377269

348

!o.0

.

•

.0

*

653.0

429.0366.0 369.0

385.0

287.0

310.0

326.0

405-.0355.0 358.0

. -407.0

0001200121100001

11001010000

32

38

772113015001971675060

55915

7007722

1804

5950

7201460107290899

86552

98

344 541543 876

461 461

1006 1083

21 25424 483

493 600

598 687

297 299

15 98

1160 8340 • 9500

489625

19101131

24001756

462 16 478

1280938

258015

3860938

48359407

590

364500

VDOOIOCOCOCO^DOOVOOOOOOOVDCOCOVDOOCOCOCOCOCOOOOOOOCOCOOOCOOOCOCOCOCOCOCOCOCOCOCOCOCOOOCOCOCOCOCOCOCOOOOOOO^OCOCOCDOOOOOOOOOOCOCOCOv o u 3 v o v o m v o t D u > & ^ u i a y 3 i o u C o c o c o o o o o o o a j a ) O o u u i ^

(t»

O O O I

I P

IDiOOHHHHIOWIOlOIO'OllXOHH totorococococoeoLJCocococo co

CO U) CdCOOsIM V£> -O

co co

o o

o o

o© o

CO CO CO

-O *J -J

en en eno o o

to A. en ** *» enk O O tO CO V£> - J

w'a*oa

g

muiuJaioiuoioporoJU)Wto o o co o o o o o o o o oo c> a\

to

> co •

co en en- j en o-J C0 -J •

S CO

IP

^ m v

tOlOlOVOlOlOlOlDlO \D lDlD\OVOVO(OlD^DU}<£tOVOU} VD IDU)U) *D <0<AtOlOlOlOVDU)lOlOVOlf i lOlOU}<DIO<OtO \O VO \D \O VO ID (D VO U) ID ID ID VD \O ID \D VO VO VD \D (DCOCOCOCOCOCOCOCOCOGOCOOOCOCOCOCOCOOOCOCOOOCOCOCOCOCOIOOOIDCO^DGOCOCOCOGOOOID CO ID ID KO CO CO CD ID CD \D COCOCOIO^DCOCOCO \O CO VD CO CO CO \D VD CO CO CO tUVDVOVDCOaJCOCOCOCOCOCOCOCOU3^D^COCOCOCOCOCOCOCOCOCO*iVOrfiVDt^\DViSC^C^C^Cn>t»^ M

UlOU)o o oi l l

tr* t* tr*IDVDVDi l l

tr* tr* tr1

aXOH^J^HJO tOHNOOHHI1

I I I

M CO t-0 t

HHtorOMNtOUXOVIOWMmcOaXOHJHJOtOHNOOHHI Z^^<b^uis)^ui<t)>u)toou<Jcnroou)iooi)<JtouuiUHM<^uco^(n o

i i i i voo t* f t*COMHH

>OOOOOOOMOMMOOOOOOOOOOOOOOO OOOOOOOMOOOOOOOO >

OOOOOOOMOOON3MOOO

. OJ ^. O -1 <O vl CO CO ^ W W O U 1 O J > - O J > . ^ MOlHOH PP ^P P ^ ^POOO * O COW OOO CO rf* O\ W N> LO tO W CO ts3 Ol O CO ID O O O OO O U> ^ IO

CJUUUUUUUU UUUUU)UUUUUUUUU)UOJOUOU)OUUOOIOOOUUOO&A^O^OAibiiiOO^iUlbOAOlbiE>lbOOit>&ib JP

*J-O-JOOOOOO ooo^i-i-Joooooooooow-oco-Jw^J-vjoouMW^Joooooooooooooooooooooooooooo

O O O O O O O O O O O O O O O O O W O - M M O O OO OO OO O O

^ !& u i ' * at ' * C T t O J i u i a i * * c ^ * t\n m c\^^i«JU)u>O) t j i o o ' i o W - J t o o MM tow

M H* MO O O O M M O O M O M M M M M M M H M M M M M M h J M * J U l t 0 J ^ W O U ) L J U ) 0 i t - ' O O O O O O O O O O O O O O O O O O O O O O O O O O O O O O tDC00)O)lDOOU}l0OOOOOOHOA^^4^Uslm(»(fll0(n^H^NNOOslOMUM(nOMMN}HNHh)N)NOOI0NMOl0NI0l0l0OOt0NIO

ooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooo woooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOit^OOOOOOOOOOOOOOOOOOOOOOOOOOOOO

MMO -J O tO MLO CO tf* O\ Ul tO

MM OOOOtoNCD M t O M t O t O M .U M MHlOO U) Wrfk (A) Ul it* .U J* OOOOOOO Ol -J CO O> CT1 N> U> U) ID CTV -J H ID O

O J » O * U ) U lU cnUIH O O t O O O O O O O O OllOOCf^CO M O D COCO C O M M C OOOO M OJ en O O O M * » • t O O O O O O O O >t>>OOOO OO -JO >bO OO

OOOOOOOOO O O O O O O O O O O O O O O O O O O O O O ^ O t O M t O O O O M O O O O O O O O O O O O O O O O O O O O O O O O O O O O

Ht|^|-)MMMMMM* M M M M M M M M M M M M M M M M C J U 1 W M U U I M O O U ) M C 0 M ^ O O N ) W W O W O W W M O O M M M O

OOOOOOO OOOO OO OO OO O O O

MOlMOlMtnOl * M U I O O t O M O O O * M * * O O * * *CO -J CO -J Ul -J -J .U -0 M M tOrfk M M COVD rf^N)

MM M M M * * CO ^ j_» M

tOtOCOWOJOJCJCJCJ WWUWWMMMWNWMMNNMHOHMHPHH(ni0^MUOOU«)6O''»J'JCDW0iUiOI0NOOI0ff\WWNO^O^U O

(DU70U)(t UlUitCbOt (Ji^CnUibAMl0Ml0OM0\m<n^OUO03UlC0U)OOO0}>UH^OC0OiU(JlCDU)a\OOOOOOinU)Cn^<£U1OC0Ul>JOC0UOOOOOOOOO OOOOOOOOOOOOOOOOLJCOLJOIOOOOOOOCnOtOMmOOUi^OOOOOCTt-JOOOtOOUlOOOOmoOO

o o o o n. * # • • • . • * * * . * * * • * > • • * . > • > * * * * . * • . . * • « * « * . • * • * • * * * * • * • * * * . • • • • • * * • * • (/)

ui to J* <uO CO \£> *£>

O O O O O O O O O O O O O O

*-j**-j*to lo* ' O H ' ' ' in' W' ' ' b b ' ' ' M ' o' ' ' bo* SO O CO CO O* O ID VO COO O O OO

B-22

Table B.5 (continued)

Obs

6869707172737475767778798081828384

Tank

W31W31T01T01T01T02T02T02T02T03T03T04T04T04T04T09T09

Year

19891994198919891996198919891989199619891996198919891989199619891996

S_No

W31-L2W31-089L35L360L38L112L390L420LlllL44L450L470

Ag

0.70.10.00.00.00.00.00.00.00.00.00.00.00.00.0o.o -0.0

Al

4.22.6

0.4

0.7

0.5

5.2

0.2

As

3.70.30.80.80.00.80.80.80.00.40.30.40.80.80.00.80.0

B

0.20.8

m

1.8t

5.0

m

1.5

0.7

Ba

3.51.00.00.10.00.00.10.00.00.00.00.00.00.00.00.10.0

Be

0.000.000.000.000.000.000.000.000.000.000.000.000.000.00

o.oo0.000.00

Ca

79.00153.00

5.78

8.98

2.81

1.53

14.20

Cd

0.10.80.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0

Co

0.570.15

.0.02

0.02

0.02

0.02

0.02

Cr

6.0011.800.290.181.520.440.10

• 0.101.4614.0016.6013.009.40

14.008.410.400.02

Cs Cu

0.37 0.24

0.27 0.2O

19.60 0.48

0.57 0.05

4.41 0.04

0.72 0.09

B-23

Table B.5 (continued)

Obs Tank Year S No Fe Hg Mg Mn Na Ni Pb

123456789

10111213141516171819202122232425262728293031323334353637383940414243444546474849505152535455565758596061626364656667

W03W03W03W03W03W04W04W04W04W05W05WO 6W06W06W06WO 6W07W08W08W08WO 9W09W10W10W10W10W22W23W24W24W25W25W25W25W25W26W26W27W27W28W28W29W29W29W29W29W29W29W29W29W29W29W29W29W30W30W30W30W30W30W30W30W30W30W30W30W30

1989198919891994199419891989198919941989199419891989198919941994198919891989199419891994198919891989199419941990198919941986198619861986198919891994198919941989199419881988198819881988198819881988198819881989198919891988198819881988198819881988198819881988198919891989

L16L17L18203204L22L119L23205L73218L77L78L79219220L82L86L87223L90222L93L941,95225W22-L1-1W23-L1W24-L2W24-0842IT1IT2TMA1TMAW25-L2 'W26-L2W26-086W27-L2W27-087W28-L2W28-08812312 '2D3123W29-L1W29-L2W29-L4122D3123123W30-L1W30-L2W30-L4

0.130.33

0.45

0.04

0.050.00

0.14

0.31

. *0.030.080.702.600.04

2^602.600.042.600.042.600.04

2.602.602.60.

2i602.602.60

0.010.010.020.010.030.010.010.010.000.410.030.010.010.070.000.0211.000.090.170.330.060.160.010.050.370.120.030.070.050.050.210.500.261.600.050.080.090.050.640.140.140.600.600.600.600.600.600.600.600.600.600.090.080.090.600.600.600.000.600.600.600.600.600.600.100.100.10

18.720.8

21.3

76.3

22.3151.0

627.0

896.0

819.040.9

78000.011O00.O20600.0

17000.051000.040900.08500.011500.026000.030100.0

11100.0

9720.0

10500.0

10000.010000.010000.0

7890.08440.0

.

8820.0

9200.09300.09400.0

3.600.79

0.02 '

1.98

2.060.61

5.39

3.97

2.810.033.401.300.34

1.303.50

145.001.30

1090.001600.001870.00

.0.02

0.01

0.02

1.301.301.30,

0.010.01

0.01

1.301.301.30

0.000.000.000.020.030.000.000.000.170.000.01'0.000.000.000.000.000.000.000.000.080.000.160.000.000.000.010.000.000.000.010.000.000.00 '0.000.000.000.010.000.290.000.030.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.000.00'0.000.000.00

10502360

2200

4250

3616440

4370

2640

280051908200010000074800

780006800079900900009510096000

110000

103000

103000

104000

110000110000110000

111000104000

111000

100000100000110000

1.001.001.000.060.101.001.001.000.231.000.111.001.001.500.010.151.001.001.000.271.000.291.001.001.000.060.143.000.380.83

0.458.206.990.383.181.402.84

t

0.380.380.38.

0.380.380.38

2.002.002.000.010.012.002.002.000.062.000.432.002.002.000.430.432.002.002.000.472.001.032.202.002.000.430.432.706.702.005.5011.08.0011.02.103.202.202.102.202.102.20

2.102.102.30

3.002.902.30

B-24

Table B.5 (continued)

Obs Tank Year S No Fe Hg Mg Mn Na Ni Pb

6869707172737475767778798081828384

W31W31T01T01T01T02T02T02T02T03T03T04T04T04T04T09T09

19891994198919891996198919891989199619891996198919891989199619891996

W31-L2W31-089L35L360L38L112L390L420LlllL44L450L470

2.600.09

0.01

0.08

0.02

0.01

0.01

0.150.710.060.070.540.100.100.150.275.7012.807.901.102.701.983.400.90

9500.016500.0

847.0

1380.0

3420.0

1320.0

695^0

1.300.37.

1.11

4.86

0.03

0.07

2.97

0.000.010.000.000.000.000.000.000.000.000.000.00 '0.000.000.000.000.00

9400099200

2210

3590'

14800

4550

4830

0.380.950.200.200.040.200.200.200.040.100.070.100.200.200.040.200.04

m

48.6

#

. 33^4

129.0

30.1

25.6

2.102.201.001.000.011.001.001.000.020.500.010.501.001.000.011.000.01

oJ^V^UNPOIOCOJmUl^WMHOlOCl^mOlAWNHOlDCD^OlUl^WMHOUJro^Ol^AUMHOtOCO^mUiAUNHOWCOJmUl^UNH W

VOVDlClOlOlOlOfOlOU)t010\OU}W^OlOUtOtO\OVO ID l D t O l O l D l 0 l 0 l D l D t O I© \D \D \O *O ID ID ID ID ID ID ID ID ID <O *D ID to *D tCOCOCOGOGOGOCOQOGOCOGOO3COCOCOCOCOCOO3COGOCOCOCOCOCOVDCOt0GOt0COCOGOCOO3COlOGOlOV0VOCOCOCOVQCO ^o CO CO'CO I\OW1000COOOGOOOOOCOOOCOCO\OVO^OCOCOCSOOOOOOOOCOCOCOCWCVO^^OU}C^C^OalVOO^^lOU3VOIVO^WOD

' 1 1 1 1 U>otr« f tr<CDNHH

toCO

o

o o

tCD

wO H» M tO M o

o'ob" o

OIOUIOO

gCOH'OOOOOOMO)-'OOtOOOOOOO<

O O iivikib sHUH

MUIm>llOMHIOHDtO<ba)C0PQ3M00Cn

OOUOUOOOOOOUMISUUtDOOOlvooou>ooooooooooo^ooooooo<

o o ob ' b ' b '

ob '

ob '

ob '

•f* O O oo

ooOl

B-26

Table B.5 (continued)

bs

6869707172737475767778798081828384

Tank

W31W31T01TOXT01T02T02T02T02T03T03T04T04TO 4T04TO 9T09

Year

19891994198919891996198919891989199619891996198919891989199619891996

S_No

W31-L2W31-089135L360L38L112L390L420LlllL44L450L470

Sb

2^80

0.37

0.39

0.37

m

0.37

0.37

Se

4.700.500.200.200.010.090.090.090.010.500.030.230.090.090.010.090.01

Si

941

103

118

317

167

47

Sr

12.001.44

.0.20

0.14

0.04

0.04

1.02

Th

2.200.68

0.24

1.95

0.08

0.14

0.24

Tl

1.4019.000.200.200.010.090.090.090.010.500.010.230.090.090.010.090.01

U

0.252.28

172.00175.00281.00166.00161.00158.00219.00

0.200.39

' 23.3025.7027.80195.00852.00303.00

0.07

0.01

0.01

0.42

0.01

0.01

Zn

0.96

0.05

0.11

0.06

0.05

OtDCD^0Ui*UMHOWC0^010l^WMHOl J-JC-Ui^WtOH

JOOOOOOOOO

VD IDCOCO

VDVOVDVDVDVDVOVDVOVDVDVDVDVOVO VD VD VD VO VO VD VD VO VDCDCOCOCOVDCOVOVO VD COCOCOVOCO^DCOCOCQVDVOCOCOCOVO

VO VD VO VD \D \DCOVOCQCOCOVO

KD %O KD \OVDCOCOCO

oo oo o o • o o o o o o o • f 7

a\ vo o m o\oo o o oo o o o oo o o oo•ggo oo o •

_t o\o oo oo o • 1to to toCO VO COo o oo o o

to to toVD CO VOo o oo o o

m -t_. a) to *_. OJ toVD co co en co en 01Ul O O O O O O

01 en uio o oo o oui in 01o o oo o o

oo o oooo

O Ul ID Ul O Ul Ul-J O -J O ._• O OO O Ul O O O O

o o o o o

OUlO MCO O O CO Ao o o a. o

boobbbb obobo

P-9 a-a n - <—>n o CD

oa

)COCOCOCOVOCO'K]loVOVDCOCOCOVOVOVOVDVDVDCOVOCOVOt0^1*^COVDOO.OOOOOOOOOOOOOOOOOOOOOOOOOOCnOt0OV0tt_.OooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooooOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO'

•J VO Ol Ul **Jo o o o oo o o o o • •

M tO tOIDO.OPO O O -d MO O O O Ao o o o o • •

700

898

o oo o •

to -J<n oO CO •

a aro no g

rtrtni

ty *oQ>

rt(D

§•01

Ol Ul Oio o oo o ooo o*

Ul Ul Ulooooooooo*

Ol Ul Ul Olo o o o

I-*O M O M O Oo o o o o o o •OOo o

t-» O O M J*H* O O O O •

Ul Ul Oio o oo o oooo*

Ul Ul Uloooooooo o •

H* Ui M Ol tO Ul Ul-J O Ul O VO O OUl O J O J* O Oo o o o o o o •

Ul COto toVO Ul •

B-28

Table B.5(continued)

Obs

6869707172737475767778798081828384

Tank

W31W31T01T01T01T02T02T02T02T03T03T04T04T04T04T09T09

Yeai

19891994198919891996198919891989199619891996198919891989199619891996

: S No bonate

W31-L2 600W31-089 6100L35L360L38L112L390L420LlllL44L450L470

Bicar- Brora- Carbon- Chlor-ate ride

Fluo- Hydro- Nitr- Nitr- Phosp-ride xide ate ite hate

425.0

10.4

25.5

11.8

50.9

6006000

2600.0 500.0 2004370.0 1050.0 1700

280000311000

500010

Sulf- HCNate

5000 .1670 .22

464.0

737 !o

1630.0

650.0

5490.0

37.5

5 3 ^

283 !o

59.2

141 948 20 557 .

95

7140

3010

2100

975

6300

1680

8

20

20

20

20

1380 .

4890 .

1580 .

821 .

B-29

0bs

123456789

10111213141516171819202122232425262728293031323334353637383940414243444546474849505152535455565758596061626364656667

Table B.6. Radiological variable measurements (bq/g) on liquid samples from 1!

Tank

W03W03W03W03W03W04W04W04W04W05W05W06WO 6W06W06WO 6W07W08W08W08W09W09W10W10W10W10W21W22W23W23W24W24W25W25W25W26W26W27W27W28W28W29W29W29W29W29W29W29W29W29W29W29W29W29W30W30W30W30W3OW30W30W30W30W30W30W30W30

Year

19891989198919941994198919891989199419891994198919891989199419941989198919891994198919941989198919891994199019941990199519891994198919931994198919941989199419891994

- 19881988198819881988198819881988198819881989198919891988198819881988198819881988198819881988198919891989

to

S_No

L16L17L18L203L204L22L119L23L205L73L218L77L78L79L219L220L82L86L87L223L90L222L93L94L95L2250W22-L1-1W23-L1W23-115W24-L2W24-084W25-L2W25-O19W25-085W26-L2W26-086W27-L2W27-087W28-L2W28-O88123122D3123W29-L1W29-L2W29-L4122D3123123W30-L1W30-L2W30-L4

1996.GrossAlpha

612177

15333376313311

20015020026060565102877

207082

3305452#

201030

821

3004418022223333331010102222220221

101010

GrossBeta

490670

1200560960

16002600220017004200140028006000

1900089007630

5600002400002800001900007100031000310007800019000089000

226000150000462000

20000002300001300000392000

140000022000001700000330000530000980000

1000000m

.

m

211000198000209000

#

197000193000192000

2<1Am

0.0

9

2800

3000

3100

1500

2100

#

"c

64

787

329

123

181

167.1212222221

14373565565465656

6886110

"'Ce

1600

740

1300

2300

750

1800

140013001300

120012001300

"2Cf

555.

0.000..022.3.222

2"Cm

555.

0.000

.022

3939333

.

467

"Co

1000001010130

1609

13289068

29030059091011017283414012

427013621

1800329320

1880

310122002700309

200087204900125811101036925

1184777122111841258925644599626925814666777851851629962814888493483491

"'Cs

85

369097004630

520001340

710003770

82000131003600016101400

10600420080667141706770676697673472526993684574742510257025303885

" 410741444107410739224033425541073663205020301960

'"Cs

5808401300470820890

1400210011005500110016005600

2000010006200

64000034000040000016000063000260003100083000

24000074000

228000100000436000

15000002210001100000327000

120000020700001400000216000330000566000620000240870240130230140234025226070219040238095234950237910239020221000222000216000130055132090130980126910130980130055123025132090128020123025186000187000190000

O C O

rr

VD 00 VD CO 00 CO \D CO \£> CO CO CO t D CO CO *O CD {U

cniootu?ioiocnioo)tou>u>cnioiOJ»u} Hwo t< o tr1 tr11* o t* o tr« (r* H o t* t~* s: s: |

*1 U l i t fcH M IOHC0 G\Ul t-> h* O

CO N>

fOiUMMCDHWCOUlAJiJiWJCDOUl QOOOOOOOOOOOOCf OOMOCO COHOOOOOOOOOOOOOOOOO ( O Oooooooooooooooooo rt uOOOOOOOOOOOOOOOOO WW

aO) tn CD t-» E Oo o o - . • • to n o

CD

s

o oO HO O

U 5 l O C D O O O U J l f O ^ . U Q J J C D t Oto o o o o o o o o o o o >r* m a*, o \£> -OOOOOOOOOOOOOOOOO 3ooooooooooooooooo OOOOOOOOOOOOOOOOOO W

HHHHHHH W O* O

3pr

COCOOOCOCDCOOOCOOOCOCOCOCCOCOCOCOCOCOCOCOCO

LOLJU)O O O1 1 1F f F

C D jI I Io F oCONJOOCO j

I IF oMCO

I I I Io o F oCOHMCOUIID ^

VD VDIDVDVOVOVOVDVDVDV0VO VD VD ID VD VD VD VO ID VO VD VD VO VD VD VD VD ID VD VOOOIDIAIDIDVDCOCOCOVDCOVOOOCOCDIDVDCOCOOO \O COVDCOCOCOVOVOCOCOCOVOC^

1 ] |O N] to (O H N IO tO H H HCDsJH U O W H WO OCO-Jm

CO Ul VD J CO

D U) «O tOU) tU U M N (Ji Ji(J(O OM •

I I I I Ui IO WF H» t* FNHHH

W W H»V-J tO -Jooo

MN3H*JOO\ooo

M M K-> tO tO-J en tO )-• CO W *».O^JOt-»Ot->Oooooooo*

tO MH U W H M HcrtOtOOMMoooooo«

m u J o\ U) A uio-o o en o o o

poo c\ i-»to vo a\ to o\ <o o o o o vo •

H» -J en to 01ovo*>-ooooOU)OOOOO

WMMtOtOMMWMMMMMtOtOtOWWUlOUWUUWM PPtOMfflPOOOtOtOtOtorotOtOtOtOtOOOOMI-»hJOOOOOOVDCnH-»U)OOMVOPP^NmUlWUUPOlMWPPPNOWOCDOlJ^tOWCOloOlOOCDO

encnencncn-JOOO

*-* roen * * «&> u> co MID o o o en coo o o o o o *CO M CO CO MA v o o m H

to Mc n c o oco» o« o«

U)PP> tO • tO W H •

oO

o oco

^ . . O - ' - O ' O * . . .

o otototoocootototoo oooooooooo

o o to to to o co o to to J*M OOOOOOOOOO

tototo tooOOO OO

cncncnOOO

cninuiooo

g

g

td

Oo

Oo

Oo

ob *

ob'

ob

OO

OO

OO

OO

OO

o o o

tOtOtOoooD ^^ ^^

B-32

Table B.6 (continued)

0bs Tank

68 W3169 W3170 T0171 T0172 T0173 T0274 T0275 T0276 T0277 T0378 T0379 T0480 T0481 T0482 T0483 T0984 T09

Year

19891994198919891996198919891989199619891996198919891989199619891996

S_No

W31-L2W31-089L35L360L38L112L390L420LlllL44L450L470

1MEu

931500

35

39

35

35.

11

I5<Eu

67580

31

31

50

m44

35

1MEu

420900

m

140

190

240

240

170

3H

1561007171.

210210210.

-170,

110110110.

160

33 1100. 0.0 0.1 0.0 0.0 0.0 0.0

1.9

2 3.3

2 3.7

6 0.9

B-33

Table B.6 (continued)

Obs Tank Year S No »Sr "Tc l2Th

12345678910111213141516171819202122232425262728293031323334353637383940414243444546474849505152535455565758596061626364656667

W03W03W03W03W03W04W04W04W04W05W05W06WO 6W06W06WO 6W07W08W08W08WO 9W09W10W10

, W10W1OW21W22W23W23W24W24W25W25W25W26W26W27W27W28W28W29W29W29W29W29W29W29W29W29W29W29W29W29W30W30W30W30W3OW30W30W30W3OW30W30W30W30

19891989

• 1989199419941989198919891994-1989199419891989198919941994198919891989199419891994198919891989199419901994199019951989199419891993199419891994198919941989199419881988198819881988198819881988198819881989198919891988198819881988198819881988198819881988198919891989

LI 6L17L18L2O3L204L22L119L23L205L73L218L77L78L79L219L220L82L86L87L223L90L222L93L94L95L2250W22-L1-1W23-L1W23-115W24-L2W24-084W25-L2W25-019W25-085W26-L2W26-O86W27-L2W27-087W28-L2W28-088123122D3123W29-L1W29-L2W29-L4122D3123123W30-L1W30-L2W30-L4

40649033.m

29020094

31078190

3800150600660460490370200

1200760210780

510003900436

5100886650

19400* t

1100251

170005240066000

122000120000

48474625521747365217481047734514421842556980708070803626392235523441336742553959403339594033673062406550

3

13000

660.

20720

1900

260

400

0.00.0.

0.2

0.0

0.00.0

0.0

0.0

0.0.

0.00.1

0.00.00.00.00.00.00.00.00.00.00.0.

0.2

0.2

0.2

0.00.00.0

0.20.2

0.2

.0.00.00.0

!J2U

36

00

22

104302276

060

1920

1

211

98

1.710 • 3.6

1 18!8

0 0.0

0.00.0

0.0

olo

0.0

0.0

0.0

0.0

o!o

o!o

o!o

o!o

0.10.1

0.00.0

0.4

0.7

olo

0.0

0.0

0.0

0.0

0.0

0.1

0.0

0.00.0

0.0 0.0

0.00.0

0.0

o!o

0.0

0.0

0.0

0.0

o!o

o!o

o!o

o!o

l5Zr

19

1

192231

0

0

0

610

0

6

3

100

500

120

270

52

220

93110100

9511093

B-34

Table B.6 (continued)

Obs

6869707172737475767778798081828384

Tsnk

W31W31T01T01T01T02T02T02T02T03T03T04T04T04T04TO 9T09

Year

19891994198919891996198919891989199619891996198919891989199619891996

S_No

W31-L2W31-089L35L360L38L112L390L420LlllL44L450L470

>"Sr

6570870033003400350025002800270028003002401400120014001700

3600010000

9 9Tc 232Th 232U 233U 234U 235U 23*U 239U S 5Zr

0.0 . . . . . . 5 7570 0.0

13 0.0

20 0.0

29 0.0

24 0.0

118020034019018018027020232229240660470

0.0

6.4

5 0

0.0m

#

4.4

6.9

0.0

0.1

0.1

0.0

m

0.1.

0.1

0.0

0.1

0.1

0.0

0.0.

0.1

0#

4

3

0

2

4

TABLES B.7, B.8, B.9, B.10, B.ll, AND B.12

Organic Analysis

B-37

Table B.7. Sludge organic concentrations (ng/kg) reported in Sears' report [10].

Semi-VolatileCompounds

Di-n-butylphthalate

Bis-(2-ethylhexyl)phthalate

Di-n-octylphthalate

Naphthalene

Phenanthrene

Unknown

Unknown hydrocarbon

Unknown Phthalate

Diethylbenzene

Dimethylbenzene

Tributyl Phosphate

W24

9800

17000

18000

187830

22260

69300

Tanks

W25

4000

2400

15000

460

480

145900

110100

55400

9900

W31-1

19000

1300

143200

48200

1900

W31-2

2000

1800

440

520

149700

175700

5500

120000

B-38

Table B.8. Sludge organic concentrations (|ig/kg) reported in Autrey's report [9].

Semi-VolatileCompounds

Di-n-butylphthalate

Diethylphthlate

Bis(2-ethylhexyl)phthalate

Napthalene

Di-n-octylphthalate

Fluoroanthene

Phenanthrene

Pyrene

Chiysene

2-MethyInaphaIene

Benzo(a)pyrene

Benzo(b)fluoroanthene

Benzo(g,h,i)peiylene

Benzo(a)anthrecene

T02 T04

4600 3400

2800 2400

24000

2300

W03

47

23

12

4

W04-1

1400

49

5700

160

110

130

W04-2

2100

33

11000

51

220

170

170

69

Tanks

W06 W07-1

210 2200

150 510

31000

340

680

350

W07-2

300

200

57000

260

W08

630

430

2600

740

1300

850

1300

W09

760

450

160000

370

1100

1300

850

W10-1

770

270

8000

5100

8100

1900

2200

870

W10-2

2600

130000

1800

1700

1400

760

660

B-39

Table B.9 Sludge Arochlor concentrations (|ig/kg) reported for GAAT tanks. Thesymbol "<" indicates'the measurement is less than the value [17].

Arochlors

1016

1221

1232

1242

1248

1254

1260

W03

<120

<120

<120

<120

9

3

<240

•

W04

<120

<120

<120

<120

12

33

43

W05

<1200

<1200

<1200

<1200

<1200

145

60

W06

<248

<248

<248

<248

<248

290

110

Tanks

W07-1

<120

<120

<120

<120

<120

82

<240

W07-2

<112

<112

<112

<112

<112

111

14

W08

<2400

<2400

<2400

<2400

<2400

120

<4800

W09

<5860

<5860

<5860

<5860

<5860

88

11360

W010

<8560

<8560

<8560

<8560

<8560

28257

6336

B-40

Table B. 10. Sludge ogranic concentrations (mg/kg) reported in GAAT Phase 2 reportand Keller's report [17,14\. The same concentration values were reportedfor all tanks with a few noted exceptions.

Tanks

W06-1W06-2W07-1W07-2W08-1W08-2W09-1

W09-2YT7"I f\ 1WlO-1W10-2

W21W23

i

Concentration forAll Tanks

NHVOA

10

VOA

1

Organic Compounds

Acetone, Butanol, Ethyl Ether, Isobutanol,Methanol,

Methyl Ethyl Ketone, Pryridine

1,1,1 -Trichloroethane, 1,1,2,2-Tetrachloroethane,1,1,2-Trichloroethane, 1,1,2-

Trichlorotrifluoroethane,1,1 -Dichloroethylene, 1,2-Dichloroethane,

1,4-Dichlorobenzene, 2-Nitropropane, Benzene,Bromoform, Carbon Disulfide, Carbon

Tetrachloride,Chlorobenzene, Chloroform, Cyclohexane,

Ethylbenzene, Methylene Chloride,Ortho-Dichlorobenzene, Tetrachloroethylene,

Toluene, Trichloroethylene,Trichlorofluoromethane, Vinyl Chloride, Xylene

Exceptions

W06-l = 16 for Butanol

W06-l = L4forTCEW06-2 = 4.0forTCE

TCE = Trichloroethylene

W09-2 = 1.4forl,l-DCEW10-l=2.1forl,l-DCEW10-2 = 1.7forl,l-DCEDCE = Dichloroethylene

W10-2=l. lforTetrachloroethylene

B-41

Table B. 11. Sludge semi-volatile organic concentrations (mg/kg) reported inGAAT Phase 2 report and Keller's report [17,14].

Semi-VolitileCompound

2-4-Dinitrotoluene

2,4-Dinitrophenol

2-Methylphenol

4-MethyIphenol

Hexachlorobenzene

Hexachloroethane

Nitrobenzene

Pentachlorophenol

Di-n-butylphthalate

Unknown-1

Unknovra-2

Unknown-3

Unknown-4

W06-1

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W06-2

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W07-1

0.6

10.0

10.0

0.6

10.0

10.0

10.0

6.2

3.4

1.1

1.0

W07-2

0.6

10.0

10.0

16.0

0.6

10.0

10.0

10.0

2.0

3.3

3.5

W07-3

0.6

10.0

10.0

0.6

10.0

10.0

10.0

8.4

1.1

3.4

1.6

1.1

W08-1

0.9

15.0

15.0

0.9

15.0

15..0

15.0

Tanks

W08-2

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W09-1

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W09-2

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W10-1

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W10-2

0.9

15.0

15.0

0.9

15.0

15.0

15.0

W21

0.6

10.0

10.0

10.0

0.6

10.0

10.0

10.0

W23

0.6

10.0

10.0

10.0

0.6

10.0

10.0

10.0

B-42

Table B. 12. Tenatively identified volatile and semi-volatile concentrations (mg/kg)reported in Keller's report [14]. Arochlor concentrations (mg/kg) areincluded.

Tenatively IdentifiedOrganic Compounds

Volatile Organics

Bromomethane

Heptanone

Dodecane

Tridecane

Tetradecane

Unknown

Semi-Volatile Organics

Dodecane

Tridecane

Tetradecane

Dibutylphthalate

Tributylphosphate

Tris(ethylhexyl)phosphate

Unknown

Ethylphenylethanone

Bis-(2-ethylhexyl)phthalate

Arochlors

1016

1221

1232

1242

1248

1260

1254

W21

1.00

0.13

0.10

0.18

0.11

1.00

14.0

43.0

29.0

3.1

25.0

18.0

180.0

18.0

10.0

0.025

0.050

0.025

0.025

0.025

0.025

0.025

Tanks.

W23

0.17

1.00

1.00

1.00

1.00

0.28

3.3

5.7

4.9-

5.9

1.0

3.8

27.0

10.0

10.0

0.025

0.050

0.025

0.025

0.025

0.025

0.025

B-43

Table B. 13. Liquid organic concentrations (|ig/l) reported in Sears' report

urgaiiicCompounds

Volatile Oreanics

Methylene CWoride

Acetone

Toluene

Semi-Volatile Oreanics

Benzoic Acid

Diethylphthalate

Di-n-octylphthalate

2-Nitrophenol

Tenative EDCompounds

Volatile Oreanics

Trichlorotrifluoromethane

Unknown

Semi-Volatile Oreanics

Unknown

Unknown Phenol

Dibromonitrophenol

2,4-Dibromo-4-nitrophenol

W24

30

12

40

36

6066

W25

37

12

" 2500

63

6

34280

W29-1

7

27

9

3500

250

29

13

17030

1800

W29-2

10

15

6

3000

430

19810

2000

Tanks

W29-3

7

11

6

2300

69

11940

1600

W30-1

17

11

7

1300

31

7

6188

W30-2

6

16

18

f

2300

290

7603

420

600

[701.

W30-3

10

18

19

1400

1400

20

5

5449

W31

30

18

2400

6

38480

2400

Table B.I4. Liquid organic concentrations (ng/1) measured by direct aqueous injection gaschromatograph reported m Autrey s report \8,9\.

OrganicCompounds

Acetone

Ethyl Alcohol

I-Propyl Alcohol

Methyl Alcohol

n-Butyl Alcohol

2-Butanone

4-Methyl-2-Pentanone

T4/L-044

7000

37000

3000

46000

3000

T4/L-045

8000

37000

3000

27000

6000

T4/M11

7000

37000

3000

42000

3000

Tanks/Samples

W3/L-O16 W3/L-017

38000 40000

W3/L-018 W4/L-023

7000

20000

7000

5000

7000

B-44

Table B.I4 (continued)

OrganicCompounds

Acetone

Ethyl Alcohol

I-Propyl Alcohol

Methyl Alcohol

n-Butyl Alcohol

2-Butanone

4-MethyI-2-Pentanone

W6/L-079

3000

W7/L-082 W8/L-086

1000

14000

Tanks/Samples

W8/L-O87 W10/L-093

3000

1000 27000

2000

1000

W10/L-094 W10/L-095

3000

: 1000

37000 41000

1000

1000

B-45

Table B.15.

OrganicCompounds

Acetone

Benzene

Bromodichloromethane

Chloroform

Ethylbenzene

Methylene Chloride

Toluene

4-MethyI-2-Pentanone

Trichloroethene

Xylene

2-Hexanone

Tetrachloroethene

Carbon Tetrachloride

Chlorobenzene

1,2-DichIoroethene

2-Butanone

Liquid organic concentrations (ug/1) measured by gaschromatograpmmass spectrometry reported in Autrey s report \8,9\.

T2L-O38A

20

3

340

1000

12

T2L-039A

22

370

820

7

T2W12A

17

310

860

8

T4L-044A

400

7

7

170

20

12

78

11

T4L-045A

220

10

160

20

14

98

10

3

170

20

4

Tanks/Samples

T4M11A

72

7

120

5

12

60

36

W3L-

16A

2

4

5

11

6

W3L-17A

26

1

4

14

14

8

W3L-18A

5

4

3

37

18

11

8

W4 W4L-022A L-23A

55

3

10 10

13 14

1102

49

W4L-I19A

2

10

46

3

14

B-46

Table B.I5 (continued)

OrganicCompounds

Acetone

Benzene

Bromodtchloromethane

Chloroform

Ethylbenzene

Methylene Chloride

Toluene

4-Methyl-2-Pentanone

Trichloroethene

Xylene

2-Hexanone

Tetrachloroethene

Carbon Tetrachloride

, Chlorobenzene

1,2-DicMoroethene

2-Butanone

W6L-077

67

5

9

6

13

47

4

W6L-078

44

2

9

8

10

9

24

158

W6L-079A

111

10

3

7

10

91 .

82

9

507

75

W7L-082A

26

3

7

14

7

24

1088

Tanks/Samples

W7 •L-082B

31

3

4

9

7

39

1021

W8L-086A

64

3

12

3

15

41

W8L-087A

45

6

7

4

W9L-090A

70

2

44

13

9

11

5

4

5

W10 W10L-094A L-094B

6 38

13 19

12

27

21

11

W10L-

095A

97

22

16

12

26

23

81

48

5

31

B-47

Table B.16.

Semi-VolatileCompounds

Di-n-Butylphthalate

Bis(2-ethylhexyl)phthalate

2-Nitrophenol

2,4-Dichlorophenol

2,4,5-TrichIorophenol

Napthalene

Di-n-octylphthalate

Fiuoroanthene

Phenanthrene

Pyrene

Benzoic Acid

Liquid semi-volatile organic concentrations (ug/1) reported in Autrey'sreport \8,9\.

T2L-038

200

170

100

99

T2L-039

300

200

140

110 •

T2L-112

24

280

180

120

Tanks/Samples

T3 W3 W3 W4 W4 W4L-016 L-017 L-018 L-022 L-023 L-119

60 48 230 11

53

160 35

49 80

56

33

60

Table B.16 (continued)

Semi-VolatileCompounds

Di-n-Butylphthalate

Bis(2-ethylhexyl)phthalate

2-Nitrophenol

2,4-Dichlorophenol

2,4,5-TrichIorophenol

Napthalene

Di-n-octylphthalate

Fiuoroanthene

Phenanthrene

Pyrene

Benzoic Acid

W6L-079

290

W7L-082A

1900

Tanks/Samples

W8 W9L-087 U)90

17 20

28

W10L-094

400

W10L-095

20

2900

B-48

Table B. 17. Liquid ogranic conceand Keller s rerjort \1for all tanks. F

itions(mg/l) reported in GAAT Phase 2 report ,4\. The same concentration values were reported

Tanks

W6W8-1W8-2W9

WIO

Concentration forAll Tanks

VOA

5.00E-03

Organic Compounds

1,1,1 -Trichloro ethane, 1,1,2,2-Tetrachloroethane,1,1,2-Trichloroethane, 1,1,2-Trichlorotrifluoroethane,

lJ-Dichloroethylene, 1,2-Dichloroethane,1,4-Dichlorobenzene, 2-Nitropropane. Benzene,

Bromoform, Carbon Disulfide, Carbon Tetrachloride,Chlorobenzene, Chloroform, Cyclohexane,

Ethylbenzene, Methylene Chloride,Ortho-Dichlorobenzene, Tetrachloroethylene,

Toluene, Trichloroethylene,Trichlorofluoromethane, Vinyl Chlonde, Xylene

QUALITATIVE DESCRIPTIONS OF SAMPLES TAKENIN THE VARIOUS SAMPLING CAMPAIGNS

B-51

MVST TANKS

Description and volume estimates of sludges in the Melton Valley Storage Tanks from thePeretz Report7.

EstimatedTank

Volume

W-24

W-25

W-26

W-27

W-28

W-29

W-30

W-31

Radiation Level

200 mR/hr at 6"

About 1 R/hr

200 mR/hr at 6"

not reported

not reported

200 mR/hr at 6"

(gal)3,600

14,600

7,500

7,500

Sludge Description

Approximately 1.5 ft of a soft, fluid sludge.

About 4 ft of sludge similar to that in W-24,but containing at 1 ft. noticeable amounts ofsand (possibly from hydrofracture slotting.)Higher radiation levels than W-24.

About 2.5 ft of soft sludge containing moresand than found in W-25. Radiation levelssimilar to W-24.

A hard, crusty layer about 3 in. thick wasfound 2.5 ft from the bottom of the tank.Sludge under the crust was similar to thatin W-24; a somewhat thicker consistencymay have been due to the crust breakingoff into the sample.

About 8 in. of sludge similar to that foundin W-24.

About 1.5 ft of soft sludge a little thickerthan in W-24 but with similar radiationlevels

(same as W-29)

About 3 ft. of extremely thick sludge. Thesampler rod had to be hammered throughthe sludge to reach the tank bottom. Thesludge was not at all fluid, and was much"hotter" than the other tanks.

Notes: It is generally believed that there is more sludge on the discharge side of the tanks than on the suctionside, relative to the depth at the center. The tank contents were not circulated during sampling, but theaerators were left on. A liquid sample was not taken from W-31 because the contents consisted mainlyof sludge. (

1,100

3,600

200 mR/hr at 6" ' 3,600

4 R/hr at 4 in. 9,800

B-52

MVST TANKS

Description and volume estimates of sludges in the Melton Valley Storage Tanks from theSears Report10.

Tanks W-29 and W-30 were modified to serve as feed tanks to the EASC system. The tankpenetrations were used for the pump module suction legs. Samples of the aqueous supernatantwere collected from these tanks using the pump module (Isolock) sampler. It is not possible togain access through the penetrations to sample the tanks by the methods described in above.No sludge samples were taken from tanks W-29 and W-30 and no checks were made for anorganic layer..

In the first sampling effort of tank W-27, a soft-sludge sample was collected at thesupernatant-sludge interface (sample W27-S1). When the effort was made to sample the nextlayer of sludge, a very hard layer that felt like concrete was encountered about 38 in. abovethe tank bottom. This layer was hard enough to bend the stainless steel closure plate on thesampler and, thus, no sample was collected. A sample.of the upper soft sludge layer(W27-S2) was collected later in the second sampling effort. This core overlaps the solidsphase of sample W27-S1. The auger bit sampler was used to cut through the hard layer. Itwas estimated that the hard layer was about 1-ft thick. The sampler was then pushed throughan underlying soft sludge layer (no cutting force needed) to the bottom of the tank. Uponexamination of the sampler (W27-H1) at the analytical laboratory, it was found that the hardsludge had plugged the lower part of the sampler (i.e. the cutting bit end between the bladesand immediately above the gate valve). The barrel section of the sampler contained softsludge from the upper layer. At the analytical laboratory, the soft sludge was poured into onejar (W27-H1-S) and the hard sludge was scraped with a spatula into a second jar(W27-H1-H). A sample of the soft sludge that lies under the hard sludge was not obtained.

Liquid: Sludge samplesradiation RadiationLevels3 Organic levels

Tank (R/K) layer Number/type (R/h*) Comments

W-21 0.3 No 2/soft sludge 1.0-1.5 Sonicated sludge: consistency ofprepared mustard;medium yellow withdark flecks

W-23 0.12 No 3/soft sludge 1.0-2.5 Top sample (W23-S1): smoothbrownish-yellow paste; 2.5 R/h.Sonicated sludge: consistency ofprepared mustard; medium brown withdark fleck •

a: Field survey.b: R. N. Ceo and J. T. Shor Physical Characterization of Radioactive Sludges in Selected Melton

B-53

c:Valley and Evaporator Facility Storage Tanks ORNL/TM-11653.NA = not applicable because of no access to tanks W-29 and W-30 for sampling.

Liquid:radiationLevels"

Tank (R/h)

W-24 0.18

Sludge samplesRadiation

Organic levelslayer Number/type fR/hi

No 2/soft sludge 1.2

W-25 0.26 No 3/soft sludge 1.3

Comments

Could probably pump with a peristalticpump except for the thin layer of mudon bottom Sonicated sludge: lightyellow tan; very fine particles with afew coarser particles

Thicker sludge than in tank W-24.Could probably pump with a peristalticpump except for the thin layer of mudon bottom. Sonicated sludge: light tan;very fine particles with a few coarserparticles.

W-26 1.2 No 3/soft sludge 0.8-2.0

W-27 0.16pieces of

pieces of

-0.2No 2/soft sludge 0.2

1/auger bit 0.3(soft and

hard sludge)

Top sample (W26-S1): highestradiation level Bottom sampler(W26-S3): highest viscosity of the tanksamples studied by Ceo and Shorb

Sonicated sludge: dense and plasticwith the consistency Of peanut butter;gritty particles

Sample W27-S2: appearance of small. concrete in a softer sludge

Soft sludge in auger-bit sampler:(a) Un-sonicated: appearance of small

concrete in a softer sludge(b) Sonicated sludge (W27-H1-S): grayand gritty; consistency of cookedoatmealHard sludge:(a) Felt like hitting concrete duringsampling; on first attempt to collectsample W27-S2 bent closure plate ofsoft sludge sampler when hit hard layer(b) Consistency like a hard mud; nofree liquid; appearance of concretepieces mixed with mud or clay; toostiff to sonicateGeneral: soft sludge over hard layer;

B-54

had to cut hard layer with auger-bitsampler; estimated I ft thick; belowhard layer about 2-fl thick layer of softsludge; hard sludge plugged sampler;no sample of underlying soft layer

a:b:

c:

Field survey.R. N. Ceo and J. T. Shor Physical Characterization of Radioactive Sludges in Selected MeltonValley and Evaporator Facility Storage Tanks ORNL/TM-11653.NA = not applicable because of no access to tanks W-29 and W-30 for sampling.

Tank

Liquid:radiationLevels*(R/h)

W-28 0.480to the

sample

W-29 0.1

W-30 0.11

W-31 0.18wateryparticles

Organiclayer Number/type (R/h)

Sludge samplesRadiationlevels

Comments

No

NAC

NA

No

I/soft sludge 1.2to the bottom;took second

for morematerial

with a

NA NA

NA NA

2/soft sludge 1.5-2.2

I/hard sludge 2.8

Fluid (weight of handle carried samplerbottom of the tank)Sludge (W28-S1): deep yellow; seems

homogeneousSonicated sludge: very finely divided

few dark flakes

NA

NA

Sonicated soft sludge: medium tansludge; fine and very fine

separated during centrifugationHard sludge:appearance of clay or mudwith a little grit

B-55

a: Field survey.b: R. N. Ceo and J. T. Shor Physical Characterization of Radioactive Sludges in Selected Melton

Valley and Evaporator Facility Storage Tanks ORNL/TM-11653.c: NA = not applicable because of no access to tanks W-29 and W-30 for sampling.

B-56

OHF Tanks

The OHF Chemical Characterization Report Description of sludges in the Melton ValleyStorage Tanks4.

The sludge in tank T-9 appeared neutral grayish in color with a greenish tint in thesupernatant. The sludge appeared to be soft, thick mud. A sludge column of 10.5 in. wasobtained. This measurement correlates fairly well with field log notes generated by LGWODpersonnel during 1988 sampling (9 in. was documented). The sludge read 50 R/h (through theplastic bag) after it was removed, but this was mostly from a deposit on the outside of thesample tube. The sample read 6 R/h through the metal can in the sample carrier.

The sludge in tank T-4 appeared brownish-grey in color with a greenish tint in thesupernatant. The sludge appeared to be soft, thin mud. A sludge column of 14 in. wasobtained. This measurement correlates fairly well with field log notes generated by LGWODpersonnel during 1988 sampling (12 in. was documented). The sludge read 30 R/h (throughthe plastic bag) after it was removed. The sample read 5 R/h through the metal can in thesample carrier. The background at the top of the hole was 110 mR/h at the hole.

The sludge in tank T-3 appeared brownish in color with a greenish tint in the supernatant. Thesludge appeared to be soft, thin mud. A sludge column of 10 in. was obtained. Thismeasurement does not correlate very well with field log notes generated by LGWODpersonnel during 1988 sampling (16 in. was documented). The sludge read 15 R/h (throughthe plastic bag) after it was removed. The sample read 1.5 R/h through the metal can in thesample carrier.

The sludge in tank T-2 appeared tan to brownish in color with a greenish tint in thesupernatant. The sludge appeared to be soft, thin mud. A sludge column of 6 in. was obtained.This measurement does not correlate very well with field log notes generated by LGWODpersonnel during 1988 sampling (12 in. was documented). The sludge read 35 R/h (throughthe plastic bag) after is was removed. The sample read 100 mR/h through the metal can in thesample carrier.

The sludge in tank T-l from both samples appeared tan to brownish in color with a greenishtint in the supernatant. Both samples looked like soft, thin mud. A sludge column of 8 in. wasobtained. This measurement correlates fairly well with field log notes generated by LGWODpersonnel during 1988 sampling (9 in. was documented). Radiation readings showed 18 R/hand 20 R/h at contact for the first and second samples, respectively. Through the can, thereadings were 0.7 R/h and 2.5 R/h for the first and second samples, respectively.

B-57

GAAT Tanks

The following observations were obtained when the field sampling was completed and thePhase I sampling team debriefed11:

• What is known as "hard sludge" is more accurately described as "dense sludge."The sampler had good tactile feedback from the sampling tool and could feel agradual thickening of the sludge, but no distinct hardpan was evident. The feelof the sample tool on the concrete tank bottom was very distinct. Thelaboratory technicians who emptied the tubes reinforced this observation.

• The sludge generally rinsed clean from the outside of the sampling tool with agentle stream of water, although some small clayey pieces adhered to thesample tube.

• Except for tanks W-5 and W-10, all of the sludges appeared to have similartextures. The only variations are colors.

• Tank W-10 contains "trash" including cotton string, pieces of plastic, andconcrete chips up to the size of a dime that prevented the sampler from closingon the first two tries.

• Tank W-5 contains almost no sludge, and the sample team was able to see whatthey thought was the concrete bottom of the tank at the west port. The teamscraped the sample tube along the bottom at the west port and retrieved a smallamount of "sludge" that consisted mostly of small white flakes (thought to beconcrete chips).

A discrepancy exists between the sludge probe reading and the depth of sludge retrieved fromtank W-6. In four instances, the probe read approximately 2 in. but 7- to 8-in. cores wererecovered. In all other tanks, the probe depth correlated with the recovered core height.Liquids from the tanks tend to be pale yellow, but those from W-3 and W-4 are brightyellow.

During Phase II the tank characterization system was used to characterize tanks W-3, W-4,W-5, W-6, W-8, W-9, and W-10. The samples retrieved were a variety of colors andconsistencies. The grab sample from tank W-3 was a yellow soupy liquid with small flakes.The W-7 tube sample had three distinct layers: an orange, pasty layer; a brown, gravelly,sandy layer; and a yellow, silty layer. The grab sample from W-10 was a mixture of brown,gravelly, silty liquid sludge. The W-5 grab sample contained hard orange chunks that werelarge enough to be separated out.

ORNL/TM-13351

INTERNAL DISTRIBUTION

1. D. Anderson2. R. D. Bailey3. J. S. Baldwin

4-5-. C. K. Bayne6. E. C. Beahm7. J. Beauchamp8. C. A. Bednarz9. J. M. Begovich

10. D. E. Benker11. J. E. Bigelow12. D. A. Bostick13. R. W. Brandenburg14. D. E. Brashears15. J. Chapman16. D. E. Coffey17. T. B. Conley18. A. G. Croff19. N. Dailey20. D. Daugherty

21-22. S. M.DePaoli23-24. J.R. DeVore

25. D. K. Downing26. B. Z. Egan27. M.Evans28. J. E. Francis29. J. R. Forgy30. T. M. Gilliam31. W. Griest32. O. W.'Hale33. R. Hagenauer34. L. Holder35. T. D. Hylton36. M. A. Johnson37. R. T. Jubin

38-39. J. M. Keller40. C. M. Kendrick41. T. E. Kent42. F. Kornegay43. G. R. Larson44. D. D. Lee45. M. R. Leuze46. A. J. Lucero47. J. J. Maddox48. C. A. Manrod49. R.Martin50. R. C. Mason51. A. J. Mattus52. B. C. McClelland

53. C. P. McGinnis54. L. E. McNeese55. A. Meeks56. G. T. Mei

57-59. T. H. Monk60. J.W.Moore61. T. W. Morris62. T. E. Myrick63. Li Nguyen64. C. E. Oliver65. C. D. Parks66. S. M. Robinson67. T. O. Rogers68. S. T. Rudell69. J. Saffell70. T. F. Scanlan71. R. E. Schreiber72. F. J. Schultz73. C. B. Scott74. D. H. Smith75. J. L. Snyder76. R. D. Spence77. J. L. Stellern78. R. C. Stewart79. J. R. Stokely80. P. A. Taylor81. J.R. Trabalka82. D. Van Hoesen83. J. F. Walker, Jr.84. J. S. Watson85. T. D. Welch86. R. M. Wham87. J.Williams88. J. H. Wilson89. B. V. Wojtowicz90. C. Wynn91. L.Yong

92-93. Central Research Library94. Document Reference Section

95-96. Laboratory Records Department97-98. WMRAC Document Management

Center99. Laboratory Records, ORNL

100. ORNL Patent Section101. ER Document Management

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