a)~j h’0 /y7’j

A)~J h’0 /Y7’J~

qiq EERING DATA TRANSMITTALPage1 of ~

I. ED, 6259(30

2. TO (Re.xMng Organization). 3. From:(0riginatingOrganuation) 4.RelatedEDTNo:

Distribution I BWEIC/300 Area ~izabilization ~mj .I

5.PrOj./PrOgJDept./Oii: DesignAutl?.arity/DetignAgenffCog,Engr.:

300 Area Stabilization Project JG Riddelle

8.OriginatorRemarks

Release of HNF-3636, Rev. O, “Technical Basis for Characterization ofB-Cell Waste for Shipment in the 3-82B Shipping Cask”

=

NA7. PurchaseOrderNo.:

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324 Facilityajorsm. wg. 0.:

11. Receiver Remarks 11A. Design Ba.setineDocument? ❑ Yes ❑ No NA

This supporting documents the historical technical basis for13. PermiVPermit Application No.:

shipping 324 Facility B-Cell low-level waste. NA14.Requwed Response Date:

11/18/98

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,[$/$Origi- Receiv-

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1 HNF-3636 All o Technical Basis for Char. . NA 2 1 1

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Approval Designator (F) Reason for Transmittal (G) Disposition (H) 8. (i)

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BD-7400-172-2 (10/97)8D-7400-1 72-1

HNF-3636, Rev, ONovember 1998

TECHNICAL BASIS FOR EXEMPTION FROMALPHA SURVEYS FOR PERSONNEL, MATERIAL,AND EQUIPMENT IN THE 324 FACILITY

JS DurhamJSD& Associates,FortCollins,CO 80526

PreparedforB&W HanfordCompany,Richland,WA 99352U.S.Departmentof EnergyContractDE-AC06-96RL13200

EDT/ECN 625900 Uc: 2000OrgCede 19300 ChargeCede: 101031 /GAOO HN990151B&R Cal.: )/A TotalPages: 39’ 41

PKeyWords B-CellWa8te,Alph%Transuranic,Ceshq Strondw,ShippingCask.

Abstract Thisreportdocumentsthetechnicalbasisfor themeasurementsandanalysesusedto characterizethe324FacilitygroutedB-Cell wastefor disposalattie HanfordBurialGroundsusingthe3-82B shippingcask.

TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by tradename, tradema,k, .an.fact.wr, or otherwise, does not necessarily constitute or imply its endorsement,

reconme”dati on, or favori “g by the United States Government or .a”y agency thereof or its contractors or

subcontractors.

Printed i n the United States of Aneri c.a. To obtain copies of this document, contact: Document control

Services, P.O. Box 950, IWl$top H6-08, Richl.and WA 99352, Phone (509) 372-2420; Fax (509) 376-4989.

))- 30-78Date

Approved for

.-.. -Rel ease Stamv

Public Release

A-6400-073. 1 (10/97)

RELEASE AUTHORIZATION

Document Numbw HNF-3636, Rev. O

Technical Basis for Exemption from Alpha Surveys for

Document Title: Personnel, Material, and Equipment in the 324Facility

This document reviewed in accordance with DOE Order 241.1,“Scientific and Technical Information Management,’’and 241.1-1,

“Guide to the Management of Scientific and TechnicalInformation,” does not contain classified or sensitive unclassified

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APPROVED FOR PUBLIC RELEASE

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A-dQOl-400.2(09/94)

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v.VLVII.

Vm.Ix.

13NF-3636, Rev. O

CONTENTS

Purpose, . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1Applicable Limits for Disposal of B Cell Waste Packages . . . . . . . . . . . . . . ...3Methodology for Determining tbe Radionuclide Content in aBCell Waste Container . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...4A. Dose Rate Measurements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...4B. Estimating the Cs Activity of the Grout Container . . . . . . . . . . . . ...4c. Determining WSrand Alpha Activities. . . . . . . . . . . . . . . . . . . . . . . . . . . ...6D. Establishing the Waste Designation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...9E. Establishing the Heat Generation Rate . . . . . . . . . . . . . . . . . . . . . . . . . ...10F. Loading Lirnhsfor Grout Containers., . . . . . . . . . . . . . . . . . . . . . . . . ...10Determination of the Maximum Activity of a LLW Package 10Dose Rate Limits During Shipping Using the 3-82B Shipping Cask 11Additiorsal Source Term Characterization . . . . . . . . . . . . . . . . 11Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12References . . . . . . . . . . . . . . . . . . . . . . 12

Appendix A. . . . . . . . . . . . . . . . . . . . . . . . . ...14Appendix B. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...16Appendix C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...19Appendix D. . . . . . . . . . . . . . . . . . . . . . . . . ...34

Figure 1.Figure 2.

Figure 3.

Table 1.Table 2.Table 3.

FIGURES AND TABLES

Linear Regression Fit of the Alpha and ‘37CsActivity Data . . . . . . . . . . . . . . . ..7

Linear Regression Fit of the %r and *3’CSActivhy Data for Boththe1993and 1998 Smear Data.... . . . . . . . . . . . . . . . . . . ...8Linear Regression Fit of the %r and ‘3’CSActivity Data forthe1993 Smear Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...8

Results of Source Geometry Comparison . . . . . . . . . . . . . . . . . . . . 5Resuksof Smears (pCJsample) Analyszed in1993and 1998 . . . . . . . . . . . . ...6Results of Npha Ener~Aalysis for1998 Smear Samples . . . . . . . . . . . . . . . . . 9

i

HNF-3636, Rev. O

~ R 1~RIZATION OF B-CELL WASTEMENT IN TH E 3-82B SHIPPING CASK

I Purpose

The purpose of this document is to establish the technical basis for characterizing grouted B-Cellwaste for disposal at the Hanford Burial Grounds using the 3-82B shipping cask. The scope ofthis document includes establishing the technical basis for loading the shipping package, an HN-200 Grout Container, to ensure that: 1) the amount of material in the grout container does notexceed the 100 nCl alpha/g limit that would cause the waste to be designated as “greater thatCategory 3” (GC3) or transuranic (TRU) waste 2) the amount of heat generated by the waste inthe grout container does not exceed the 60 Watt heat generation limit established in the 3-82Bshipping cask Safety Analysis Report (SAR] and 3) the dose rate on the surface of the shippingcask atler loading does not exceed the 200 rnrernh limit established in the cask SAR. Thisdocument establishes the technical basis for performing measurements and analyses that willensure that none of these three limits are exceedecl.

II Background

Historical operations between 1965 and 1992 in the 324 Facility B Cell have generated anenormous amount of legacy radioactive waste. These operations included manufacturingradioisotopic heat sources for the Federal Republic of Germany, demonstration of liquid-fedmelters and spray calciners for preparation of waste packages, and dksolution of spent nuclearfiel. During these operations, millions of Curies c,f radioactive material, primarily 137CSand %r(and their related radioactive progeny, 137Ba~d ~]y), were processed in B Ce]l and some material

was spilled or volatilized into the cell. No attempt was made to clean up or completelycharacterize the material remaining in B Cell after each operation was concluded. Consequently,many tons of highly contaminated material in B Cell require disposal. MNions of Ci ofradioactive contamination, both in dispersible and fixed form, currently reside in B Cell.

In 1992, the US Department of Energy, the U. S. Environmental Protection Agency, and the StateOf Washington Department of Ecology established a Hanford Federal Facility Agreement andConsent Order, also known as the Tri-Party Agreement (TPA). TPA milestones M-89-02,“Complete Removal of 324 Building REC B-Cell MW Equipment: scheduled for completion on5/3 1/1999, states that “actions under this milestone include containment and removal of all B Celldispersible materials, equipment and debris” to rechrce “risks to human health and theenvironment.” In order to gain access to the dispersible material on the floor of the cell, theprocess racks and support equipment in B Cell must be size-reduced and placed into shippingcontainers, removed from the hot cell, and sent to disposal. The dispersible material on theexposed areas of the floor, which is known to contain hazardous components and has beendesignated as mixed waste, will be collected and placed into engineered containers. Theengineered containers will be shipped to an interim storage location until a remote-handled mixedwaste disposal facility is established. Cleanup activities to date have removed several racks andvessels t?om B-Cell and has allowed removal of dispersible mixed waste from approximately TSO/O

1 of 38

HNF-3636, Rev. O

of the floor area. The material in B Cell that must be removed to allow access to the remainingfloor area consists of three equipment racks l-~ l-B, and 2-A. These racks contain structuralmaterial, process piping, and tanks.

Until 1997, the waste packages containing structural material from B Cell was designated asremote-handled low-level rtiloactive waste (LLW), A B-Cell waste package consists of a groutcontainer containing the waste and grout (to till void spaces and lower the external dose rate) anda liner that reduces the amount of contamination introduced into the shipping cask from the groutcontainer. Waste is removed fkom B Cell by size-reducing the racks, placing the rack materialinto grout containers, adding grout to the containers, loading the grout container (which becomeshighly contaminated when it is introduced into B-Cell) into a liner in a relatively low-contamination area (the REC Airlock), Ioadmg the liner into an 3-82B shipping cask, and shippingthe sealed cask to the Hanford burial grounds. Designation of B Cell waste to date has relied onprocess knowledge and limited data on the removable contamination on the structural material.

Before shipping the waste to the Hanford burial grounds, the amount of 137CSand ‘Sr isdetermined by measuring the dose rate on the surface of the grout container (atler grouting) at 24locations (6 equally-spaced measurements from top to bottom at each of the four compasslocations on the grout container) and determining the WCS activity from the average of these 24

measurements using a gamma dose computer code. In the past the assumption was made that thefixed alpha contamination level of the waste was O. When the quantity of fixed contaminationlevel was added to the low quantity of removable contamination that had been measured, thematerial would not be designated as “greater than Category 3” (GC3) or TRU waste.

The dose rates at the surtace of waste packages originating from B Cell are sufficiently high thatthey must be handled remotely. Thus, all waste from B Cell is “remote handled.” The termremote handled is not a waste designation, rather it is a descriptor that indicates how it is to behandled and stored. Throughout this document, the waste designation is independent of whetherthe waste packed is remote handled or contact handled.

It is important to note that designating waste as TRU or GC3 is based on the amount of alpha-emitting radionuclides and the weight of the waste. There is no generic allowable quantity ofalpha-emitting radionuclides for a given quantity of 13’CS. According to WHC-EP-0063-4, wastepackages that exceed 100 nCi of TRU radionuclides per g of waste are designated as TRU wasteand those that exceed 100 nCl of alpha radionuclides per g of waste are designated as GC3. In B

244cm w~lch i5 not a TRU radionuclideCell, approximately 15% of the alpha activity is from ,because the half-life of 2MCm is less than 20 years. However, designation of the waste as GC3 isbased on the total alpha activity, because there is no established disposal pathway for GC3 waste,B Cell waste must be less than the GC3 limit in order for the Hanford burial grounds to accept it.

In 1997, the basis for shipping B Cell waste to the Hanford burial grounds was reviewed. Duringthe review, it was discovered that the waste designation was based on 3 smear samples%btainedfrom rinsed surfaces of B Cell waste in 1993. These samples were used to establish the ratio of‘Sr to 137CSso that the quantity of ‘Sr could be determined from a gamma dose computer code

2 of 38

HIW-3636, Rev. O

calculation. The alpha content of waste shipped from B Cell to the Hanford burial grounds priorto 1997 was not explicitly determined. After reviewing the existing procedure for shipping wasteto the burird grounds, it was decided that obtaining additional smear data was warranted.

Three additional smears were obtained for rinsed surfaces of non-waste material in B Cell in 1998.After analyzing the data, a ratio of the alpha activity to the ‘37CSactivity was developed and

shipments of waste to the Hanford burial grounds were resumed. However, a formal technicalbaais was never completed; a technical basis for maximizing the amount of waste in a B Cell wastepackage is needed to ensure that the minimum amount of resources are used withoutcompromising stiety.

This document is intended to establish the technical basis for shipping B Cell waste in HN-200grout containers to the Hanford burial site for permanent disposal. To meet this objective, thisdocument will include:

1)

2)

3)

4)

5)

III

A review of the applicable requirements for shipping and waste acceptance,

A justification for a methodology to determine the activity of *37CS,‘Sr, and alpha-emhting radionuclides in a grout container, the heat generation rate, and the wastedesignation based on measurable dat~

A determination of the maximum activity in a B Cell waste package that can be designatedas LLW,

A discussion of the dose rates to be encountered during shipping of LLW packages fromB Cell, and

Recommendations for additional characterizations of the contamination in B Cell.

Applicable Limits for Disposal of B Cell Waste Packages

Limits for B Cell waste packages (grout containers) are established by the Certificate ofCompliance (COC)’ and the Safety Analysis Report (SAR)2 for the 3-82B shipping cask,Department of Transportation (DOT) shipping regulations, and Hanford solid waste acceptancecriteria, WHC-EP-0063-44. The following limits are applicable to grout container wastepackages:

1) The maximum alpha activity is 100 nci per g of waste as described in the Hanford solidwaste acceptance criteria

2) The maximum heat generation rate is a grout container is 60 Watts as defined in the SARfor the 3-82B Cask

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HNF-3636, Rev. O

3) The maximum dose rate of a loaded 3-82B shipping cask is 200 mrenih at contact withthe cask surface and 10 mrernllr at a distance of 2m from the cask surface as required byDOT shipping regulations

The only practical method for ensuring that these limits are met for each shipment is to measurethe dose rate profile at the surface of the grouted grout container, determine the Cs activity in thegrout container using a computer calculatio~ and estimate the Sr and alpha activity in the groutcontainer tlom the 137CSactivity based on established ratios of alpha and ‘Sr activity to 137CSactivity. The heat generation rate can then be determined from the estimated quantities of ‘Srand 137CSactivities. The likelihood of exceeding the shipping dose rate limit can be minimized byevaluating the results of a pre-grout dose rate profile.

Iv Methodology for Determining the Radionuclide Content in a B Cell GroutContainer

The methodology for determining the radionuclide content in a B Cell Grout Container consists ofthree steps:

1) Measure the surface (contact) dose rate at 24 locations around the grout container andobtain the dose rate profile

2) Estimate the ‘37CScontent of the grout container based on the average dose rate usingconversion factors computed using the computer code WISE

3) Apply measured ratios of ‘Sr/’37Cs and alpha/’37Cs to determine the heat generation rateand to establish a waste designation.

A. Dose Rate Measu rements

The dose rate in contact with the exterior of the grout container should be measured in auniform pattern. Measurements should be made at six heights at each of fourcircumferential positions that correspond to the four major compass directions. Fromstatistical purposes, 24 measurements is adequate to characterize the dose rate fieldaround the grout container. The twenty four dose rate measurements should be added anddivided by 24 to obtain the average dose rate at the surface of the grout container. AnExcel spreadsheet is provided in Appendix A that, in addition to a number of othercapabilities to be discussed later, calculates the average dose rate for 24 dose ratemeasurements for a single grout container.

B. Estimatirw the Cs Activitv of the Grout Co ntainer

The activity of Cs in the grout container should be estimated using the spreadsheetprovided in Appendix A, The conversion factor from IVlr to Ci in the Excel Spreadsheetwas derived from calculations completed using the computer code WISES. The calculated

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HNF-3636, Rev. O

conversion factor from average dose to Cl of‘37CSis0.219 R/b/CI

WISE, which was written by Pacific Northwest National Laboratory (PNNL) for theElectric Power Research Institute (EPRI), is a shielding code that calculates the dose ratefrom a known source. By calculating a dose rate for a 1 Cl source uniformly distributedthroughout the interior of the grout container, a conversion factor in Ctidose rate can beobtained that applies to the B Cell waste.

The HN-200 Grout Container was modeled as a right circular cylinder with an inner radiusof 58 cm, a wall thickness of 0.34 cm and a height of 132 cm. The density of the groutused in B Cell is 1.6 g/cm3. Dose rates were calculated in contact with the surface of thegrout container, The conversion factor for a uniformly distributed source in an HN-200grout container is 0.219 IMr/CI. Results of the calculations performed to establish theconversion factors for HN-200 grout containers are given in Appendix B.

In order to verify the methodology for estimating the Cs activity in a grout container, thecomputer code WISE was used to perform a more detailed estimate of the sourcestrength. Using WISE, the grout container was “sliced” into 6 stacked disks, whichcorresponds to the number of measurements taken at each compass location during a doserate profile measurement, A dfferent source strength was assigned to each slice of thegrout container, and the dose rate profile obtained from actual measurements wasmodeled, Equations for the source strength in each slice were derived as a function of sixdose rates that were obtained by averaging the 4 dose rates measured in contact with thesurface of each slice at each major compass direction. Determining the six sourcestrengths in terms of six dose rate measurements required solving six dependent equationscontaining six unknowns. The algebraic equations used to determine the six sourcestrengths are provided in Appendix C. In addition, the same grout container was modeledas a single homogeneous source and all 24 of the dose rate profile measurements wereaveraged.

The purpose of slicing the grout container into six discrete sources was to determine thesensitivity of the activity calculation to the level of complexity of the model. Table 1shows the results of the two calculations, For the dose rate profile modeled, thedifference in total ‘37CSactivity determined using the single source method and using thesix slice method was only 4.50%. This exercise verifies that the method of modeling theHN-200 grout container as a single, homogeneous source to determine the ‘37CSactivity isvalid. The results of the two calculations are provided in Appendix C.

Source Geometry Cs Curie Content

Single Homogeneous Source 1133 Ci

6 Independent Sources 1186C1

Table 1. Results of Source Geometry Comparison

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HNF-3636, Rev, O

WISE uses buildup factors when calculating gamma dose. Buildup factors, if used whenmodeling detailed, heterogeneous sources, can lead to overestimates of calculatedradiation doses because buildup is the greatest in homogeneous sources and is reduced inheterogeneous sources. When shieldmg codes are used to determine source strengthsfrom dose rates, buildup factors can underestimate calculated source strengths. However,in this application the source is modeled as homogeneous and the effect of the buildupfactor is appropriately modeled.

c. Determirrirw ‘Sr and Abha A-

‘Sr and alpha activities are determined from measured ratios of ‘Sr activity to ‘37CS

activity and alpha activity to ‘37CSactivity. The ‘37CSactivity determined based on theWISE calculations is multiplied by the two ratios to obtain the ‘Sr and aJpha activities,respectively. The 137cs and ~Sr activities are used to compute the heat generation rate

and the alpha activity, divided by the weight of the grouted container, is used to designatethe waste as either GC3, TRU, or LLW. It is the goal of the B Cell Cleanout SafetyProject to load the grout containers so that they meet the LLW designation.

Waste material that is loaded into grout containers is rinsed prior to loading the container.Limited data exist on the ‘Sr and alpha activity to ‘37CSactivity ratios for rinsed wastematerial. The only existing data of this type was obtained in 1993 and is shown in Table 2.The analytical counting laboratory report for these smears is included in Appendix D.

As stated in the introduction, additional smears were obtained in 1998. However, the1998 smears were obtained from rinsed surtaces of non-waste material and not fromsurfaces of waste material. Although these smears are not representative of smearsobtained fkom rinsed waste material surfaces, the data are indicative of the B Cellenvironment and may be usetld in developing the activity ratios, The smear data tlom the1998 smears are also shown in Table 2, The analytical data laboratory reports associatedwith the data in Table 2 are provided in Appendix D,

S4rrQ!s Q Ah?h & Al~hriJCs w1993-1 0.135 5.92E-05 0.365 0.000439 2.701993-2 0.0505 2.29E-05 0.113 0.000453 2.241993-3 0.0437 2.22E-05 0.074 0.00050s 1.69

1993Average 0.000467 2.21

199s-1 0.00973 5.45E-5 0.0012s 0.00560 0.1321998-2 0.229 1.30E-4 0.0769 0.000437 0.3361998-3 8.93 3.65E-3 0.622 0.000409 0.0697

1998 AVeR3ge 0.00215 0.179

Table 2. Results of Smears (pCi/sample) Analyzed in 1993 and 1998,Note: Ziie averages shown in the table are not weighted.

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HNF-3636, Rev. O

Because of the similarity of the ratio of alpha activity to 137CS aCtivitY in Table 2 from both

1993 and 1998, a ratio of alpha activity to ‘37CSactivity based on these data can beestablished, To establish the ratio, a plot of the alpha activity as a function of 137CSactivitycan be made and linear regression used to determine the slope of the line. The slope of theline, by definitio~ is the ratio of alpha activity to ls@ acti~ty, The data in Table 2 are

plotted in Figure 1, which rdso shows the results of the linear regression and thecorrelation coefficient. The nearness of the correlation coefficient (R2 = 0.9998) to 1indicates a very high level of confidence associated with the regression. Note that theregression was forced through the point (0,0). The linear regression was performed usingtinrctions included with Microsoft Excelc. Based on a linear regression of the data foralpha and ‘37CSin Table 2, the ratio of alpha activhy to ‘37CSactivity is 0.000408.

The data in Table 2 for the ratio of ‘Sr activity to ljTcs acti~ty are rrot consistent because

in the 1993 data the ratio of ?Sr activity to ‘37CSactivity is greater than 1, while in the1998 data the ratio is less than 1. A linear regression of both the 1993 and 1998 data isplotted in Figure 2. The correlation coefficient (RZ) of 0.4800 indicates an unacceptablylow confidence in the fitted curve. Because the 1998 data results in a higher predicted%Sr activity, which leads to a conservative estimate of the heat generation rate in thewaste package, the data from 1993 was used in a regression analysis to determine the ratioof ‘Sr activity to 137cs activity, This regression is shown in Figure 3 and the COmelatiOn

coefficient, although not indicating a very high degree of confidence, is adequate for theavailable data. Based on the analysis, the ratio of %r activity to ‘37CS activity to be usedfor B Cell waste should be 2.57. Additional studies are warranted to veri@ and refine thisratio, however,

4.00 E-03

3.50E-03

3.00E-03

2.50 E-03

2.00 E-03

1.50E-03

1.00E-03

5.00E-04

0.00 E+OO

I o 2 4 6 6 10

CS-137 Activity (uCi)

Figure 1, Linear Regression Fit of the alpha and ‘37CSactivity data.

7 of 38

HNF-3636, Rev. O

0.7

0.6

~ 0.5~

,2 0.4>.-

5 0.30?$ 0.2

0.1

0

0 2 4 6 6 10

CS-137 Activity (uCi)

F@me2. Linear Regression Fitofthe WSrand’3’Cs activity datafor both the 1993 and 1998 smear data.

0.4

0,.35

=u

0.3

= 0.25.2>.- 0.220 0.15Ua

& 0.1

0.05

0

0 0.05 0.1 0.15

Cs-137 Activity (uCi)

Figure3. Linear Regression Fitofthe WSrand’37Cs activitydata for the 1993 smear data.

8 of 38

HNF-3636, Rev. O

D. Estab Iishirw the Waste Desi~ in

The waste designation is established by determining the activity per gram of alpha-emittingradlonuclides. This is accomplished by multiplying the calculated ‘37CSactivity by theratio of alpha activity to IVCS acti~~ and di~ding@ theweight of the grouted container.

If this value is greater than 100 nCti& then the waste is designated as GC3. In B Cell, theonly non-TRU radioisotope is ‘“Cm, which has a half life of less than 20 years. Alpha

energy analysis of the smears obtain in 1998, the results of which are tabulated in Table 3,indicate that 26°/0 of the alpha activity in B Cell is fkom *“Cm. The contributions fromother alpha-emitting radlonuclides areas shown in the analytical counting laboratoryreport in Appendix D. Therefore, if the activity per gram of alpha-emitting radionuclidesis greater than 135 nCtig, then the waste is designated as TRU waste. The calculation of

alpha activity per gram, and thus the designation of the waste type, is performed in theExcel spreadsheet in Appendix A.

Total Alpha 244= ~ Fraction Non-TRU f37~a

Sample1998-1 5.45E-5 1.21E-5 2.22 E-I 9.73 E-31998-2 1.00E-4 4.12E-5 4.12 E-I 2.29 E-I1998-3 3.65E-3 5.72E-4 1.57E-I 8.93E+0Average 2.63E-I

Table 3. Results of Alpha Energy Analysis for 1998 Smear Samples

It should be noted that the value determined in the Excel spreadsheet can be directlycompared to the 100 nCdg limit. Whenever measurements are made and compared to alimit, there are four possible outcomes of the comparison, two of which are “good” andtwo of which are “bad.” The two good outcomes is that the measurement is correct, thatis, when the dose rate profile indicates that the waste is non-TRU and it is actually non-TRU (true negative) and when the measurement indicates that the waste is TRU and it isactually TRU (true positive). Problems arise when the dose rate measurement indicatesthat the waste is non-TRU when it is actually TRU (false negative) and when themeasurement indicates that the waste is TRU when it is actually non-TRU. Whencomparing any measurement to an established limit, all four of these outcomes are alwayspossible, and the possibility increases when the measurements are within 20’%.of the limits.It is common to establish confidence intervals that change the probability of either a falsepositive or a false negativ~ however, decreasing one form of error necessarily increasesthe other form of error proportionally. In other words, decreasing the probability of afalse negative by 50% necessarily increases the probability of a false positive by 50%.

At first thought, it may seem that a false negative result is worse than a false positiveresult. However, one must balance the cost and risk associated with each outcome for thesituation to which it is applied. A false negative outcome results in the disposal of wastecontaining a slightly elevated quantity of TRU radionuclides. A false positive outcomeresults in the generation of a waste package for which no final dkposal pathway exists.

9 of 38

HNF-3636, Rev. O

Given the size of the waste package (roughly 1.4 m3) and the low activity of thetransuranic radionuclides (0.272 Cl [see calculation below]), the risk of a slightly elevated

activity of TRU radionuclides appears to be no more than equivalent to the incrementalcost of storing, retrieving, and potentially repackaging the waste once a disposal pathwayhas been identified. Therefore, it is recommended that the measurements of alpha activitybe directly compared to the limit for TRU waste without adding the value associated witha corriidence interval to the measurement.

E. Estab Iishirw the Heat Generat ion Rate

The heat generation rate for a grouted container is based on the ‘Sr and ‘37CSactivities.%r has a heat generation rate of 0.0067 W/CI ‘Sr and 137r.s h= a heat generation rate of

0.0048 W/Cl ‘37CS7.The heat generation rate is calculated in the Excel spreadsheet inAppendix A.

F. Loadirw Limits for Grout Container$

The heat generation rates and the ratio of ‘Sr activity to 137CSactivity can be used toestablish a maximum activity loading for a B Cell grout container. The maximum heatgeneration rate for a grout container is 60 W (205 BTU)2. Based on this limit, themaximum activities of the waste are 2725 Cl ‘37CSand 7003 Ci ‘Sr. The activity of alpha-

“ IS7CSis 1,11 cl, and the weight of a tyPicrdemitting radionuclides associated with 2725 Clgrout container is 2,600 kg (5,700 lb). In this case the specific alpha activity is 427 nCtigand the waste would be designated as remote-handled TRU. Thus, at the maximum heatgeneration rate of the grout container, the associated quantity of alpha-emittingradionuclides would require that the waste package be designated as TRU. Therefore, theheat generation rate of any waste package that is designated as LLW will be significantlylower than the limit of 60 W.

Note that in the previous discussion the weight of the grout container was assumed to be2,600 kg (5,700 lb). If the actual weight is greater, more activity maybe placed into thegrout container. If the weight of the grouted container is less, however, the limit is morerestrictive. In either case, it is not conceivable that the heat generation limit would beexceeded for a waste package that is designated as LLW using the data included in thisreport.

v Determination of the Maximum Activity of a LLW Package

The maximum activity of alpha-emitting radionuclides in a waste package that isdesignated as LLW can be determined fkom the 100 nCtig alpha activity limit, the weightof a typical waste package (6,OOOlb [2720 kg]), the ratio of alpha activity to ‘37CSactivity(0.000408), and the ratio of%r activity to ‘37CSactivity (2.57). The maximum alphaactivity of a 2720 kg LLW package is 100 nCJg * 2720 kg= 0.272 Ci. The ‘37CSactivityassociated with this alpha activity is 0.272 CJ.000408 = 667 Cl ‘37CS. The ‘Sr activity for

10 of 38

I-INF-3636. Rev. O

this package is 667 * 2.57= 1713 Cl ‘Sr.

The heat generation rate for this waste package, based on a ‘Sr heat generation rate of0.0067 W/CI ‘Sr and a ‘37CSheat generation rate of O.0048 W/CI 137CS4,is 667 * 0.0048+ 1713 * 0,0067= 14.7 W. Thus, the heat generation rate is less than the limit of 60 W.

VI Dose Rate Limits During Shipping Using the 3-82B Shipping Cask

Calculations of the quantity of ‘37CSthat could be loaded into a grout container, based onthe external dose rate of a loaded 3-82B shipping cask have been previously deterrninedsfor a RSr activity to 137CS aCtiviV ofz. 1, ‘fhe report concluded “The 3-82B cask ~i]

meet the transportation dose rate limits of 0.002 Sv/h (200 mredr) on the cask surface,and 0.0001 Svih (10 mremih) at 2 m tlom cask surface for a mixture containing 3600 Clof ‘37CSand 7560 Cl of %3r. The limits will be met for a radioactive source that isuniformly distributed throughout the grout container as well as a concentrated radioactivesource located near the periphery of the grout container.” Based on the ratio establishedin this document, a mixture containing 3600 Cl of 137CSand 9252 Cl ‘Sr would notexceed the shipping dose rate limits. A 137cs activity of 667 Ci, which is the m~imum

‘37CSactivity allowed for the B Cell waste to be designated as LLW, is well below theactivity of ‘37CSthat will cause the dose rate to exceed 200 mWh at contact”or 10 mIUb ata distance of 2 m. Because the dose rate for shipping camot be exceeded for a B CellLLW package, it can be concluded that the limiting parameter for loading LLW packagesis the activity of alpha-emitting radionuclides.

Should firrtber analysis of the B Cell environment indicate that the alpha to ‘37CSratio issignificantly lower than the data in this document indicates, it is possible that a differentconstraint would exist on the activity of a waste package. The heat generation rate for agrout container loaded with the maximum activity that can still be below the shipping doserate limit, 3600 CI of ‘37CSand 9252 Ci ‘Sr, would have a heat generation rate of3600*0.0048 + 9252*0.0067=79 W, which is greater than the heat generation rateestablished by the 3-82B COC, The maximum activity of a loaded grout container thatwill not exceed the heat generation rate limit is 2725 Cl of ‘37CSand 7003 Cl ‘Sr. Iftlrrther analysis of the B Cell environment reduces the ratio of ‘Sr activity to 137CSactivity, then the allowed activity of WCS and ~Sr would increase. In fact, if the ratio

were to drop to below 1.77, then the heat generation rate would no longer limit theactivity and the shipping dose rate would be the limiting factor, providing the alphacontamination level is negligible.

V13 Additional Source Term Characterization

Characterization of the source term in B Cell is necessa~ to resolve the discrepancy in theratio of ‘Sr activity to ‘37CSactivity between the 1993 smear data and the 1998 smeardata. Should this ratio change significantly, the maximum cask loading could be increasedif the alpha contamination issue is resolved. One method of resolving this issue is to

llof38

Vm

Ix

HIW-3636, Rev. O

pursue additional characterization of the ratio of alpha activity to ‘37CSactivity in B Cell.Another method is to investigate methods of removing the contamination from the wastematerial using a nonhazardous decontamination foam or soap before introducing it into thegrout container. This would reduce the 13TC5and alpha activity in the waste package

while increasing the amount of waste material in the container. The removed activitycould then be collected with the dispersible contamination on the B Cell floor.

Conclusions

This document has established the technical basis for performing dose rate profilemeasurements and, based on the results of these measurements, has established themti’mum activity Ioadlng of a grout container that will allow the waste package to beaccepted at the Hanford burial grounds as remote-handled low level waste. In addition,this document provides the teclrrical basis for determining the isotopic activity, the heatgeneration rate, and the waste designation of the waste package. The limit that currentlyrestricts the activity that can be shipped to the Hanford burial grounds is the 100 nCl alphaactivity per gram of waste. Because of this limit, the maximum activity that can begrouted in an HN-200 Grout Container is 667 Cl ’37Cs based on a waste package weightof 2,720 kg (6,000 lb). For grouted HN-200 Grout Containers that weigh more than2,720 kg, the activity is greate~ for grout containers that weigh less, the activity will beless. Regardless of the weight of the container, the heat generation rate of the contentswill not exceed the SAR for the cask nor DOT shipping regulations provided that thewaste package can be designated as LLW. The ratio of alpha activity to ‘37CSactivity

137C5 activity should be 2.57. Theshould be 0.000408, and the ratio of %3r activity toconversion from average dose rate to ‘37CSactivity should be 0.219 R/tr/CI. Additionalcharacterization of the waste is needed to refine the ratio of alpha and ‘Sr activity to ‘37CSactivity in order to allow more material to be buried.

References

1. Nuclear Regulatory Commission Certificate of Compliance. MMT-TN 3-82BCertificate of Compliance #6574.

2. Safety Analysis Report for the 3-82B Radwaste Shipping Cask, STD-R-02-014,Scientific Ecology Group, Inc., Oak Ridge, TN. 1991.

3. DOT Shipping Regulations.

4. WHC-EP-0063-4. Hanford Site Solid Waste Acceptance Criteria.

5. WZSE. Electric Power Research Institute, 3412 I-Mview Avenue, Palo Alto,California. 1987.

6. Excel 97 SR-1. Microsotl Corporation, 1997.

120f 38

HNF-3636, Rev. O

7, 85600-Battelle-b f222673. Characteristics of Radioisotopic Heat Sources. 1973.

8. EBU-RCAL-002. 3-82B Shipping Cask Shielding Analysis. Waste ManagementNorthwest, 1998.

13 of 38

HNF-3636, Rev. O

Appendix A. Excel Spreadsheet for Useh Calculating the Average Dose Rate, '37Cs Activity,‘Sr Activity, and Alpha Activity in a Grouted HN-200 Liner

To use the spreadsheet, enter the Grout Container Identification Number in field B-2, enter thedose rate profile measurements infields B-3 through E-8, and enter the weight of the groutedliner in field B-12. Theresults of thesprdsheet wetheaverage doserate (field F-IO), the'37Csactivity (field G-6), the ‘Sr activity (field G-8), and the nCJg of alpha activity (field B-1 6).

14 of 38

HNF-3636, Rev. O

50

405040

5060

48

5700

2585

ID numberAverage

Odegrees 90degrees 180degrees 270degrees (Rsd/h)

Dose (rad/h)Dose (rad/h)

Dose (rad/h)Dose (rad/h)Dose (rad/h)Dose (rad/h)

Average DoseRate (radih)

Weight of Waste(lb)

LWeight of Waate(walpha/CsFraction 0.000408

Ci of alpha ingrout container 0.1250nClg alpha in

rout container 46.3

40 4040 40

120 2070 40

400 30100 60

40 42.5 1 Ci Cs = 0.219 rad

30 37.530 55 Cs Activity(Ci)30 45 306

40 130 Sr Activity(Ci)

150 92.5 787

128 38 53 67,1

15 of 38

HNF-3636, Rev. O

Appendix B. Results of the Calculations Performed to Establish the Conversion Factors forHN-200 Grout Containers

160f 38

HNF-3636, Rev. O

** ~Lco~ To ~CJE/s~LE **

DEVELOPED FOR EPRIBY BATTELLE PACIFIC NORTHWEST LABORATORIES

WRITTEN AND TESTED BY WD REECE LAST ON 15 JULY 1987

FOR THIS RUN:NUMBER OF SHAPES IS 1

ISOTOPE LIBRARY

1 CS-137

MAX BETA ENERGY = .512 AVE BETA ENERGY= .157BETA YIELD = .946

5.000E-03 1.040E-023.200E-02 2.070E-023.200E-02 3.820E-023.600E-02 1.390E-026.620E-01 8.998E-01

SHIELDING MATERIALS LIBRARY

FOR MATERIAL 1 --groutATOMIC NUMBER (Z) IS 1.000E+OIFOR ENERGY (IN MEV).200 .300 .400 .500 .600 .8001 .0001.5002,0003.000 4.0006.000MU (IN CM(-1)) IS.203 .173 .154 .141 .130 .114 .102 .083 .072 .058 .051 .043FOR MATERL4L 2 --steelATOMIC NUIW3ER (Z) IS 2.600E+OIFOR ENERGY (IN MEV).200 ,300 .400 .500 .600 .8001 .0001.5002.0003.000 4.0006.000MU (IN CM(-1)) IS1.148 .865 .739 .660 .605 .527 .472 .385 .338 ,283 .259 .244

SOURCE LIBRARY

SOURCE KEY 1

170f 38

HNF-3636, Rev. O

FOR CS-137 THE CONCENTRATION = 7. 190E-01 (MICROCURIEWGEOMETRICUNIT)

ESTIMATED BREMSSTRAHLUNG CONTRIBUTIONS

BREMSTRAHLUNG SHOULD Contribute LESS THAN 20% TO ANY DOSE

FOR SHAPE 1 (CYLINDER)(X1, Y1,Z1)= .000E+OO .000E+OO .OOOE+OO(X2, Y2,Z2)= ,000E+OO .000E+OO 1.320E+02

RADIUS= 5.794E+01WALL THICKNESS IS 3.250E-01

FILL MATERIAL IS groutWALL MATERIAL IS steelSOURCE KEY IS 1.

ENTER THE COORDINATES FOR THE DOSE POINTMEASUREMENTS ARE IN CENTIMETERS

EXAMPLE -0.0,10.0,0.0.0000000 58.3000000 66.0000000

RESULTS FROM THIS INPUT FOLLOW

FOR SHAPE # 1 RESULT IS 218.9430000

***** ***** ***** *********************************************FOR THE POINTWHOSE COORDINATES ARE... .000E+OO 5.830E+01 6.600E+01TOTAL DOSE (MREMIHR) IS .....2. 189E+02

WOULD YOU LIKE ANOTHER DOSE POINT? (Y/N)n

180f 38

HNF-3636, Rev. O

Appendix C. Results of Hand Calculations and Computer Models Used to Model the HN-200Grout Container as Six Source Slices (14 pages)

190f 38

HNF-3636, Rev. O

1’

I

I

1“1

HNF-3636, Rev. O

r I

,

D,=J (/5(c, -c15Q +,7~J2 +1115-~3 j

HNF-3636, Rev. O

1B=

I

9,=; /(5 55 +,77),59 $“ ,//5s5

I

y= (((557 4,77s9 +t(/s-5G

5. ‘

HNF-3636, Rev. O

o@L]

HNF-3636, Rev. O

- WELCOME TO WISE/SIMPLE*DEVELOPED FOR EPRI

BY BATTELLE PACIFIC NORTHWEST LABORATORIESWRITTEN AND TESTED BY WD REECE LAST ON 15 JULY 1987

FOR THIS RUN:NUMBER OF SHAPES IS

ISOTOPE LIBRARY

1 Cs-137

MAX BETA ENERGY = .512BETA YIELD = .946

5.000E-03 1.040E-023.200E-02 2.070E-023:200E-02 3.820E-023.600E-02 1,390E-026.620E-01 8.998E-01

6

AVE BETA ENERGY= .157

SHIELDING MATERIALS LIBRARY

FOR MATERIAL 1 --SteelATOMIC NUMBER (Z) IS 2.600E+OIFOR ENERGY (IN MEV).200 .300 .400 .500 .600 .8001 .0001.5002.0003.000 4.0006.000MU (IN CM(-1)) IS1.148 .865 .739 .660 .605 .527 .472 .385 .338 .283 .259 .244FOR MATERIAL 2 --groutATOMIC NUMBER (Z) IS I.000E+OIFOR ENERGY (IN MEV).200 .300 .400 .500 .600 .8001 .0001.5002.0003.000 4.0006.000MU (IN CM(-1)) IS.203 .173 .154 .141 .130 .114 .102 .083 .072 .058 .051 .043FOR MATERIAL 3 --leadATOMIC NUMBER (Z) IS 8.200E+OIFOR ENERGY (IN MEV).2OO .3oO .400 .500 .600 .8001 .0001.5002.0003.000 4.0006.000MU (IN CM(-1)) IS

11.2484.5852.6221.827 1.4191.010 .806 .590 .511 .477 .477 .488FOR MATERIAL 4 --air

24 of 38

HNF-3636, Rev. O

ATOMIC NUMBER (Z) IS 7.000E+OOFOR ENERGY (IN MEV).200 .300 .400 .500 .600 .8001 .0001.5002.0003.000 4.0006.000MU (IN CM(-1)) IS.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

SOURCE LIBRARY

SOURCE KEY 1

FOR Cs-137 THE CONCENTRATION = 7.180E-01(MICROCURIES/GEOMETRIC UNIT)

SOURCE KEY 2

FOR Cs-137 THE CONCENTRATION = 7.180E-01(MICROCURIEWGEOMETRIC UNIT)

SOURCE KEY 3

FOR (2+1 37 THE CONCENTRATION = 7.180E-01(MICROCURIEWGEOMETRIC UNIT)

SOURCE KEY 4

FOR G.-l 37 THE CONCENTRATION = 7.180E-01(MICROCURIES/GEOMETRIC UNIT)

SOURCE KEY 5

FOR CS-137 THE CONCENTRATION = 7.180E-01(MICROCURIES/GEOMETRIC UNIT)

SOURCE KEY 6

FOR CS-137 THE CONCENTRATION = 7.180E-01(MICROCURIES/GEOMETRIC UNIT)

ESTIMATED BREMSSTRAHLUNG CONTRIBUTIONS

BREMSTRAHLUNG SHOULD CONTRIBUTE LESS THAN 20% TO ANY DOSE

..25 of 38

FOR SHAPE 1 (CYLINDER)(X1, YI,ZI)= .000E+OO .000E+OO .000E+OO(~,Y2,Z2)= .OOOE+OO .000E+OO 2.200E+OI

RADIUS= 5.794E+OIWALL THICKNESSES 3.250E-01

FILL MATERIAL IS groutWALL MATERIAL IS SteelSOURCE KEY IS 1.

FOR SHAPE 2 (CYLINDER)(Xl ,Yl ,Zl )= .000E+OO .000E+OO 2.200E+OI(~,Y2,Z2)= .000E+OO .000E+OO 4.400E+OI

RADIUS= 5.794E+OIWALL THICKNESS IS 3.250E-01


FOR SHAPE 3 (CYLINDER)(Xl ;Yl ,Zl )= .000E+OO .000E+OO 4.400E+OI(X2, Y2,Z2)= .000E+OO .000E+OO 6.600E+OI



FOR SHAPE 4 (CYLINDER)(XI, YI,ZI)= .000E+OO .000E+OO 6.600E+OI(X21Y2,Z2)= .000E+OO .000E+OO 8.800E+OI



FOR SHAPE 5 (CYLINDER)(Xl ,Yl ,21)= .000E+OO .000E+OO 8.800E+OI(X2,Y2,Z2)= .000E+OO .000E+OO 1. 100E+02

RADIUS= 5.794E+OIWALL THICKNESS 1S 3.250E-01

FILL MATERIAL IS grout

26 of 38

HNF-3636, Rev. O

WALL MATERIAL IS Steel

HNF-3636, Rev. O

SOURCE KEY IS 5.

FOR SHAPE 6 (CYLINDER)(Xl ,Y~ ,Zl)= .000E+OO .000E+OO 1.1 OOE+02(X2, Y2,Z2)= .000E+OO .000E+OO 1.320E+02




EXAMPLE -0.0,10.0,0.058.5000000 .0000000 11.0000000




FOR SHAPE # 2 RESULT IS 25,.0342000




FOR SHAPE # 4 RESULT IS I,316853E-001


27 of 38

FOR SHAPE # 5 RESULT IS 9.286723 E-O03

HNF-3636, Rev. O


FOR SHAPE # 6 RESULT IS 6.294497 E-O04

*—*——*—FOR THE POINTWHOSE COORDINATES ARE... 5.850E+OI .000E+OO 1,IOOE+OITOTAL DOSE (MREM/HR) lS .....1.948E+02

WOULD YOU LIKE ANOTHER DOSE POINT? (Y/N)

Y’


EXAMPLE -0.0,10.0,0.058.5000000 .0000000 33.0000000








28 of38

HNF-3636, Rev. O

FOR SHAPE # 4 RESULTIS 1.8639540


FOR SHAPE # 5 RESULT IS 1.316853 E-001


FOR SHApE # 6 RESULT IS 9.286723 E-O03

..*W*M********—*MW*—-

FOR THE POINTWHOSE COORDINATES ARE... 5.850E+OI .000E+OO 3,300E+OITOTAL DOSE (MREM/HR) IS .....2.198E+02


Y


EXAMPLE -0.0,10 .0,0,058.5000000 .0000000 55.0000000






29 of 38

HNF-3636, Rev. O





FoR SHAPE # 5 RESULT IS 1.8639540

,RESULTS FROM THIS INPUT FOLLOW


*********-* **********************************FOR THE POINTWHOSE COORDINATES ARE... 5.650E+OI .000E+OO 5,500E+OITOTAL DOSE (MREM/HR) IS .....2.217E+02


Y


EXAMPLE -0.0,10 .0,0,058,5000000 .0000000 77.0000000




30 of 38

HNF-3636, Rev. O

FO”R SHAPE # 2 RESULT IS 1.8639540



RESULTS FRoM THIS lNpUT FOLLOW





FOR SHAPE # 6 RESULT IS 1,8639540

**-** ********************************H*****.*********

FOR THE POINTWHOSE COORDINATES ARE... 5.850E+OI .000E+OO 7.700E+OITOTAL DOSE (MREM/HR) IS .....2.217E+02


Y


EXAMPLE -0.0,10 .0,0.058.5000000 .0000000 99.0000000


31 of38

HNF-3636, Rev. O

FOR SHAPE # 1 RESULT [S 9.286723 E-O03


FOR SHAPE # 2 RESULT IS 1,316853E-001




FOR SHAPE # 4 RESULT [S 25.0342000





********* ******************************,..********FOR THE POINTWHOSE COORDINATES ARE... 5.850E+OI .000E+OO 9.900E+OITOTAL DOSE (MREM/HR) IS .....2.198E+02


Y


32 of 38

HNF-3636, Rev. O

EXAMPLE -0.0,10 .0,0.058.5000000 .0000000 121.0000000

,!


FOR SHAPE # 1 RESULT IS 6,294497 E-004



RESULTS FROM THIS INPUT FOLLOW,,

FOR SHAPE # 3 RESULT IS 1.316853E-001






FOR SHAPE # 6 RESULT IS 167,7474000

*.*.**..**.**-—***—*— *—****

FOR THE POINTWHOSE COORDINATES ARE.., 5.850E+OI .000E+OO 1.210E+02TOTAL DOSE (MREM/HR) IS .....1.948E+02

33 of 38

HNF-3636, Rev. O

Appendix D. Analytical Counting Laboratory Data Sheets (4pages)

340f 38

Eu3vhwer I

mLo#

!%’Q 93-9080‘8Ta

%3 93-9o111

.. ,

-=iCustanrIll stY90 Ci-n? ‘. Totii Beta

ae llex-90

-

71393 #l, WHXYSFIL= a $2 3.6S x-1 1.35 S-1 7.47 E-1. .

71393 ifz WHXXErxrmm cm #2 .1.13 E-1 s. 05 E-2 2.49 x-l

71393 #3 14HXTSrmm ~ rz 7.40 E-2 4.37 ~-z 1.69 e-l

6993 fl BLACK ~XLTER CM #l “ 6-74 i-l 1.35 EO 2.s6 co

6993 #z ma ?XLm CM #1 3.f19 E-2 ‘,2;34 Z-2’ 9*M E-z

6933 #3 BiJKK FXLTES CM #l 2.44 E-l 2.S5 E-1 - S.92 3?-1

S..92 X-5

2.29 X-5

“2. 2i s-s

6+SS X-4

.4:g4 ?-6

3..26 x-s

x?erPOO!! inet.rmtionm, each filter w- lz~ch=l ●nd the leaclmte aWYMM3. .ma valuen Almted MS? uCi-/n~of the leach uolntion hot no effect was made toqwntkate the reeu$t-, therefore the ~ikr6 are nqk dicmctly caepeza.ble.xota that the xwults for s~mti~ re~lte =e Sr o~bi~ * Sr+y at e-fi=”

0

Battelle Pacific Northwest LaboratoryAnalytical Chemishy Laboratory’Radioanalytical Group -325 Bldg.

HNF-3636, Rev. O

98-28123124198

Client: S. Landsman !JVPfi K82285

Cognizant Scientist“a’”-

Concur: Date: s~xq ~

Measured Activities (pCi/sample)

Gamma Energy Analysis

ALOID Mn-54 CO-60 Sb-125 Cs-134 Cs-137 Eu-154 Eu-155 Am-241

Client ID Error YO Error YO Error % Error Y. Error % Error% Error% Error %

98-2812 <4. E-5 ~7. E-5 <2. E-4 <3. E-5 9.73 E-3 <1. E-4 <1. E-4 <2,”E-4

B-Cell 1 5%

98-2813 <8. E-5 <2. E-4 <2.E-3 <6. E-5 2.29 E-I -=3.E-4 <7. E-4 <2. E-3

B-Cell 2 5%

98-2814 <2. E-3 7.66 E-2 <2. E-2 <3. E-3 8.93E+0 <4. E-3 <7, E-3 <2. E-2

B-Cell 3 5% 5%

36 of 38

HNF-3636, Rev. O

Battelle Pacific Northwest Laborato~ 98-2812

Analytical Chemistry Laboratory 3/27/98

Radioanaly6cal Group -325 Bldg.

Client: S. Landsman Wp#; K82285

CognizantScientist @Ae F/z ?/7Y

Concur 7Tti ,7C, -1. ..,+S 3JW jw

Measured Activities (pCi/sample)

ALO ID Sr-90

CiientlD Error %

98-2812 1,28E-3B-Cell 1 5%

98-2813 7.69E-2

B-Cel[ 2 6%

98-2814 8,22 E-1

B-Cell 3 8%

Standard. 96%

Sample Spike 93%

Blank <9. E-5

37 of 38

Battelle Pacific Northwest Laboratov

Analytical ,Chemistry Laboratow

Radioanalylical Group -325 Bldg.

HNF-3636,Rev. O

98-28123/25/98

Client: S. Landsman Wp$ K82285

%ni=.tsci.ntist .-R&QK-

Measured Activities (pCi/.$ample)

ALO ID Total Alpha Pu-239/240 Pu-238/Am-241 Cm-243/244 Cm-242

ClientlD Error % Error Yo \ Error % Error % Error %

98-2812 5.45E-5 <1. E-5 4,24 E-5 1.21 E-5 <5. E-8

B-Cell 1 17% 33% 62”h

98-2813 1;OOE-4 <2. E-5 5.88 E-5 4.12 E-5 <5. E-8

B-Cell 2 14% 24% 27%

98-2814 3.85E-3 8.00E-4 2.28 E-3 5.72 E-4 <3. E-5

B-Cell 3 4% 7“/0 6% 8%

Standard 101%

Sample Spike 101%

Blank .2, E-5

38 of 38

a)~j h’0 /y7’j

Documents