Draft

ADVISORY BOARD ON 

RADIATION AND WORKER HEALTH

National Institute for Occupational Safety and Health 

SC&A’S EVALUATION OF CS-137/SR-90, FISSION AND 

ACTIVATION PRODUCT, AND ACTINIDE VALUES USING 

ANL-W MONTHLY AND ANNUAL WASTE REPORTS 

IN RELATIONSHIP TO ASSIGNING INTAKES

Contract No. 211-2014-58081 

SCA-TR-2017-SEC002, Revision 0 

Prepared by 

Ron Buchanan, PhD, CHP

SC&A, Inc.

1608 Spring Hill Road, Suite 400 

Vienna, Virginia 22182 

Saliant, Inc.

5579 Catholic Church Road 

Jefferson, Maryland 21755 

January 2017 

DISCLAIMER

This is a working document provided by the Centers for Disease Control and Prevention (CDC) technical 

support contractor, SC&A for use in discussions with the National Institute for Occupational Safety and 

Health (NIOSH) and the Advisory Board on Radiation and Worker Health (ABRWH), including its 

Working Groups or Subcommittees. Documents produced by SC&A, such as memorandum, white paper, 

draft or working documents are not final NIOSH or ABRWH products or positions, unless specifically 

marked as such. This document prepared by SC&A represents its preliminary evaluation on technical 

issues.

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.
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SC&A, INC.: Technical Support for the Advisory Board on Radiation & 

Worker Health Review of NIOSH Dose Reconstruction Program

DOCUMENT TITLE: 

SC&A’s Evaluation of Cs-137/Sr-90, Fission and Activation Product,

and Actinide Values Using ANL-W Monthly and Annual Waste 

Reports in Relationship to Assigning Intakes

DOCUMENT NUMBER/

DESCRIPTION:

SCA-TR-2017-SEC002 

REVISION NO.: 0

SUPERSEDES: N/A

EFFECTIVE DATE: January 20, 2017

TASK MANAGER: John Stiver, MS, CHP [signature on file]

PROJECT MANAGER: John Stiver, MS, CHP [signature on file]

DOCUMENT 

REVIEWER(S): Joe Fitzgerald, John Stiver [signature on file] 

Record of Revisions

Revision 

Number

Effective 

Date Description of Revision

0 (Draft) 01/20/2017 Initial issue
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TABLE OF CONTENTS

Abbreviations and Acronyms ..........................................................................................................4

Executive Summary .........................................................................................................................6

1.0 Introduction and Background ..............................................................................................9

2.0 Cs-137/Sr-90 Values ............................................................................................................9

3.0 FAP/Sr-90 Values ..............................................................................................................14

4.0 Actinide/Cs-137 Values .....................................................................................................18

5.0 Summary and Conclusions ................................................................................................20

6.0 References ..........................................................................................................................23

Attachment A. Documents and Data Used to Evaluate Cs-137/Sr-90 Values ..............................24

Attachment B. Documents and Data Used to Evaluate FAP/Sr-90 and FAP/Cs-137 Values .......25

Attachment C. Documents and Data Used to Evaluate Actinide/Cs-137 and Actinide/Sr-90 

Values ................................................................................................................................26
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ABBREVIATIONS AND ACRONYMS

ABRWH Advisory Board on Radiation and Worker Health 

Al aluminum 

Am americium

ANL Argonne National Laboratory (West)

ANL-W Argonne National Laboratory – West

BORAX Boiling-Water Reactor Experiment

Ce cerium

Ci curie

Co cobalt

Cs cesium

DR dose reconstruction

EBR Experimental Breeder Reactor

ER evaluation report

FAP fission and activation product 

Max maximum

μCi microcurie

uCi/gm uCi/gram 

uCi/m3 microcurie per cubic meter

uCi/ml microcurie per milliliter

NIOSH National Institute for Occupational Safety and Health

ORAUT Oak Ridge Associated Universities Team

OTIB ORAUT technical information bulletin

pCi/g picocurie per gram

Pu plutonium 
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Ru ruthenium 

SEC Special Exposure Cohort 

Sr strontium 

SS stainless steel

SRDB Site Research Database

TKBS site technical basis document

U uranium 

Zr zirconium 
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EXECUTIVE SUMMARY

In the National Institute for Occupational Safety and Health’s (NIOSH’s) evaluation report for 

the Argonne National Laboratory West (ANL-W) Special Exposure Cohort (SEC) petition SEC00224 of February 18, 2016 (NIOSH 2016), one of the major assumptions was that a bioassayed 

indictor radionuclide (strontium-90 [Sr-90] and/or cesium-137 [Cs-137]) can be used to assign 

dosimetric-significant fission and activation product (FAP) and actinide (alpha emitter) intakes 

using the ratio method. This method requires that radionuclide ratios remain fairly constant for 

the many processes and locations, and over most of the operating history of ANL-W. However, 

SC&A found that apparently most of the radionuclide ratios recommended by NIOSH were 

generated by computer modeling, and that there was no indication that the computer-generated 

ratio values had been compared to ratio values derived from physical measurement.

SC&A searched the Site Research Database for documents that could provide quantitative 

radionuclide data. During this search, SC&A located ANL-W waste reports that contained 

quantitative Cs-137 and Sr-90 measurements performed on the same samples (some also

contained FAP and actinide analyses). These reports spanned a relatively long time period 

(1958–1993) for a number of areas at ANL-W. Quantitative radionuclide data for waste materials 

(air, liquid, and solid) at the ANL-W facilities provide a good representation of the potential 

intake exposures to workers. Therefore, these data were analyzed in detail to evaluate if there is a 

reasonably consistent relationship between the Cs-137/Sr-90 concentrations, and if these 

indicating radionuclides could be used to assign other radionuclide intakes such as FAP for dose 

reconstruction (DR) purposes. In addition, quantitative actinide data in relationship to Sr-90 and 

Cs-137 were analyzed when available. Data for this report included both monthly and annual 

radionuclide concentrations. A former SC&A ANL-W progress report analyzed mostly annual 

radionuclide concentrations (SC&A 2016). 

Cs-137/Sr-90 

A total of 34 monthly and 16 annual matched pairs of measured Cs-137 and Sr-90 activities were 

located and analyzed, spanning the period 1958–1993 at the ANL-W site. Of these matched 

monthly data pairs, approximately 32% contained Cs-137/Sr-90 values centered on unity, within 

a factor of 2 (i.e., Cs-137/Sr-90 = 0.5 to 2.0), and 56% for annual data pairs. The remaining 

Cs-137/Sr-90 values were outside this interval, with values ranging from 0.38 to 120. Similar 

results were obtained for Sr-90/Cs-137 values, with the ratio values being the inverse of the 

Cs-137/Sr-90 ratio values. Cs-137 activities were generally slightly greater than Sr-90 activities. 

Fission and Activation Product Ratios 

A total of 35 monthly and 12 annual matched pairs of measured Sr-90 and FAP (cerium-144 

[Ce-144], cobalt-60 [Co-60], and ruthenium-106 [Ru-106]) activity were located and analyzed, 

spanning the period 1958–1993 for the ANL-W site. The measured FAP/Sr values were

compared to the FAP/Sr values recommended in Table 7-3a (with a 1-year decay time) of 

ORAUT-OTIB-0054, Fission and Activation Product Assignment for Internal Dose-Related 

Gross Beta and Gross Gamma Analyses, Revision 03, dated February 6, 2015. A comparison 

ratio value centered on 1.0 would indicate agreement between the measured and recommended 

values; however, ratio values not centered on unity would indicate insufficient or excessive FAP 

intake assignments during DR. Of these matched pairs, measured Ce-144/Sr-90 values generally 

fell below the recommended ratio of 12.5, measured Co-60/Sr-90 values were greater than the 
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recommended value of 1.8E-4, and the relatively few measured Ru-106/Sr-90 values tended to 

scatter both above and below the recommended ratio of approximately 1. Using annual data to 

calculate Ce-144/Sr-90 values appeared to provide some smoothing effect compared to using the 

monthly data. There was no significant difference in using annual versus monthly data for 

determining the Co-60/Sr-90 values. There were too few Ru-106/Sr-90 data pairs to evaluate 

annual versus monthly data. Similar results were obtained using FAP/Cs-137 data. 

Actinide Ratios 

As outlined in SC&A’s progress report of July 2016 (SC&A 2016), a total of only 15 matched 

pairs (monthly plus annual) of ANL-W measured actinide and Cs-137 activity were located for 

analysis. (SC&A did not locate any additional actinide data pairs during the recent search for 

monthly and annual data.) The measured actinide/Sr values were compared to the actinide/Sr 

values recommended in Table 5-23 of ORAUT-TKBS-0007-5, Idaho National Laboratory and 

Argonne National Laboratory – West – Occupational Internal Dose, Revision 03, dated March 2, 

2010. In general, the measured actinide/Cs-137 ratio values were greater than those 

recommended by NIOSH, but some were less. There was considerable scatter in the ratio values, 

and there were too few data pairs to allow for meaningful statistical analysis. Similar results were 

obtained using actinide/Sr-90 data. 

Conclusions

These results indicate that at ANL-W, the Cs-137/Sr-90 values may not be centered on unity as 

indicated in ORAUT-OTIB-0054, Revision 03, and some FAP/Sr and FAP/Cs measured values 

may be greater or less than recommended for assigning FAP intakes. Also, actinide/Sr or 

actinide/Cs values may not be sufficiently constant (or known) as required by ORAUT-TKBS0007-5, Revision 03, Tables 5-22 and 5-23, for assigning actinide intakes, even in situations 

where it can be assumed that the actinides are tied to an indicating radionuclide, such as Sr-90 or 

Cs-137. Therefore, SC&A finds:

1. Cs-137/Sr-90 values are not sufficiently constant to assume a ratio of unity. Using the 

results of Cs-137 bioassays versus Sr-90 bioassays may lead to differences in FAP intake 

assignments for the radionuclides listed in Table 7-3 of ORAUT-OTIB-0054, 

Revision 03, for DR. 

2. Measured Ce-144/Sr-90 or Ce-144/Cs-137 values indicate that the recommended values 

in Table 7-3 of ORAUT-OTIB-0054, Revision 03, are reasonable for DR purposes.

3. Measured Co-60/Sr-90 or Co-60/Cs-137 values are not in agreement with the 

recommended values in Table 7-3 of ORAUT-OTIB-0054, Revision 03. Using the 

recommended ratio values would usually lead to significant underestimation of Co-60 

intake for the waste materials analyzed in this report.

4. Measured Ru-106/Sr-90 or Ru-106/Cs-137 values were too few in number to indicate if

the recommended values in Table 7-3 of ORAUT-OTIB-0054, Revision 03, are 

reasonable for DR purposes for ANL-W claimants. For the few data pairs located, there 

was noticeable scatter in the measured ratio values. 
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5. Measured FAP ratio values could only be obtained for relatively long-lived radionuclides 

(Cs-137, Sr-90, Ce-144, Co-60, and Ru-106). Therefore, the actual ratio values for the 

short-lived FAPs in Table 7-3 of ORAUT-OTIB-0054, Revision 03, are not known at this 

time for the material analyzed. 

6. Measured actinide/Sr-90 or actinide/Cs-137 values are difficult to obtain because FAPs 

are generally not analyzed when actinide samples are taken. During the search for 

monthly and annual FAP data pairs, SC&A did not locate any additional actinide/Sr-90 or 

actinide/Cs-137 data pairs that were not already analyzed in a previous SC&A progress

report for ANL-W (SC&A 2016). In that progress report, the few matched pairs indicated 

considerable scatter in the ratio values and did not provide statistically significant results.
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1.0 INTRODUCTION AND BACKGROUND 

The National Institute for Occupational Safety and Health (NIOSH) responded to the Argonne 

National Laboratory West (ANL-W) Special Exposure Cohort (SEC)-00224 in an evaluation 

report (ER) of February 18, 2016 (NIOSH 2016). In that ER, and also in the technical basis 

document for ANL-W, ORAUT-TKBS-0007-5, Revision 03, Idaho National Laboratory and 

Argonne National Laboratory – West – Occupational Internal Dose, issued March 2010, 

NIOSH’s basis for assigning internal intakes and doses for most years and locations at ANL-W 

(except the period covered by NIOSH’s proposed SEC class) relies on the important assumption 

that the cesium-137/strontium-90 (Cs-137/Sr-90) values are approximately unity, that fission 

activation products (FAPs) are directly tied by a known ratio to Sr-90 or Cs-137 (as per ORAUTOTIB-0054, Fission and Activation Product Assignment for Internal Dose-Related Gross Beta 

and Gross Gamma Analyses1), and that actinides are directly tied by a known ratio to Sr-90 or 

Cs-137 (as per Tables 5-22 and 5-23 of ORAUT-TKBS-0007-5, Revision 03). However, SC&A 

found that apparently most of the radionuclide ratios recommended by NIOSH were generated 

by computer modeling, and that there was no indication that the computer-generated ratio values 

had been compared to ratio values derived from physical measurement. 

1 NIOSH used ORAUT-OTIB-0054, Revision 02 of March 6, 2014, for the ER, and Revision 00 PC-1 of 

November 19, 2007, for ORAUT-TKBS-0007-5. For this analysis, SC&A used ORAUT-OTIB-0054, Revision 03 

of February 6, 2015.

SC&A searched the Site Research Database and located ANL-W waste management reports that 

contained quantitative Sr-90 and Cs-137 measurements performed on the same samples (some 

also contained FAP and actinide data). These reports span a relatively long time period (1958–

1993) and cover a number of operational areas within ANL-W. These data provide a good 

representation of the materials workers could have been exposed to and the potential intake 

mixtures. SC&A analyzed annual and one-of-a-kind (i.e., point sample) radionuclide pairs in a 

progress report issued in July 2016 (SC&A 2016). In response to Work Group tasking at the joint 

Idaho National Laboratory/ANL-W meeting held in August 2016, SC&A prepared this report in 

which SC&A analyzed both monthly and corresponding annual data pairs to determine if the 

measured-to-recommended ratio values were useful for dose reconstruction (DR) purposes, and 

to determine if there is any difference in resulting ratios using monthly versus annual activity 

data. A list of the documents that contained useful radionuclide measures and some of the 

recorded data that were used in this evaluation are provided in this report as Attachment A (for 

Cs-137 and Sr-90), Attachment B (for FAP), and Attachment C (for actinide). Analyses of these

data are provided in the following sections. 

2.0 Cs-137/Sr-90 VALUES

NIOSH’s ER and ORAUT-TKBS-0007-5, Revision 03, rely heavily on the use of ORAUTOTIB-0054 to assign FAP intakes using Sr-90 or Cs-137 as the indicating radionuclide for many

other FAP radionuclides at ANL-W for most locations and time periods. An example of 

Table 7-3a from ORAUT-OTIB-0054, Revision 03, is provided here as Figure 1. As can be seen 

 
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from this table, assignment of FAP intakes is dependent on the Cs-137/Sr-90 value being 

approximately 1. 

Figure 1. Table 7-3a, FAP-to-Sr-90 or -Cs-137 Ratios for ATR-1 (ORAUT-OTIB-0054) 

SC&A located a total of 34 monthly and 16 annual matched pairs of measured Cs-137 and Sr-90 

activity in the ANL-W waste reports, spanning the period 1958–1993 for the ANL-W site. 

SC&A analyzed these data to determine the Cs-137/Sr-90 values for each matched pair for the 

ANL-W site. Only recorded and paired data points specifically listing Cs-137 and Sr-90 in units 

of activity (microcurie [μCi], curie [Ci], etc.) on the same material were used in these analyses; 

this included air, liquid, and solid waste. Figures 2 and 3 contain the results for the 34 monthly 

(represented by orange squares) and 16 annual (represented by blue diamonds) ANL-W data 

pairs analyzed.
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Figure 2. Cs-137/Sr-90 Values for Monthly and Annual Data Pairs from ANL-W Waste 

Reports

Cs-137/Sr-90 from ANLW Waste records

0.1

1.0

10.0

100.0

1,000.0

0 10 20 30 40 50

Recorded Data Point (1958 to 1993)

Cs-137/Sr-90

Monthly Cs-137/Sr-90 Annual Cs-137/Sr-90 Cs/Sr = 0.5 Cs/Sr = 2.0

Figure 3. Sr-90/Cs-137 Values for Monthly and Annual Data Pairs from ANL-W Waste 

Reports

Sr-90/Cs-137 from ANLW Waste records

0.01

0.10

1.00

10.00

100.00

1,000.00

0 10 20 30 40 50

Recorded Data Point (1958 to 1993)

Sr-90/Cs-137

Monthly Sr-90/Cs-137 Annual Sr-90/Cs-137 Sr/Cs = 0.5 Sr/Cs = 2.0

Of the 34 monthly pairs, 32.4% contained Cs-137/Sr-90 or Sr-90/Cs-137 values centered on

unity, within a factor of 2 (i.e., ratio = 0.5 to 2.0) of the recommended values; these are 

represented by the data points between the solid and dashed thick green horizontal lines in 

Figures 2 and 3. Of the 34 monthly pairs, 44.1% fell within a factor of 3 (i.e., 0.33 to 3.0). The 
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remaining Cs-137/Sr-90 values were outside these intervals, with values ranging from 0.38 to 

120. Table 1 summarizes the distribution of the ratios that fell below, within, and above the 

recommended ratio by a factor of 2 (i.e., 0.5 to 2.0), and the corresponding data for a factor of 3 

(i.e., 0.33 to 3.0) for both the monthly and annual data. 

Table 1. Summary of Measured Cs-137/Sr-90 and Sr-90/Cs-137 Values Compared to Ratio 

Values Recommended in Table 7-3a of ORAUT-OTIB-0054 

Radionuclides*

Number 

of Pairs

Type of 

Data

Percent 

of Pairs 

with 

Ratios 

<0.5

Percent 

of Pairs 

with

Ratios 

0.5–2.0

Percent 

of Pairs 

with 

Ratios 

>2.0

Percent 

of Pairs 

with 

Ratios 

<0.33

Percent 

of Pairs 

with 

Ratios 

0.33–3.0

Percent 

of Pairs 

with 

Ratios 

>3.0

Cs-137/Sr-90 34 Monthly 5.9% 32.4% 61.8% 0.0% 44.1% 55.9%

Cs-137/Sr-90 16 Annual 0.0% 56.3% 43.8% 0.0% 62.5% 37.5%

Sr-90/Cs-137 34 Monthly 61.8% 32.4% 5.9% 55.9% 44.1% 0.0%

Sr-90/Cs-137 16 Annual 43.8% 56.3% 0.0% 37.5% 62.5% 0.0%

*NIOSH recommended a ratio value of approximately 1 (ORAUT-OTIB-0054, Revision 03, Table 7-3a, at 1 year).

As can be seen from Table 1, the annual data provided a greater number of the Cs-137/Sr-90 

values that fell within a factor of +2 (or +3) as compared to the monthly data (the annual data 

tended to average out the individual monthly readings if there was considerable variance in their 

ratio values). The ratio values derived using annual activity data pairs in these analyses were 

similar to those obtained using only annual data in the July 2016 progress report (SC&A 2016). 

Figures 4 and 5 show the ratio values derived from the measured monthly and annual data 

compared to NIOSH’s recommended ratios. The black bar inside the smaller shaded rectangle 

(gray) represents a central estimate of the value of the ratio from measured pairs (with the 

smaller shaded rectangle representing the 95% confidence interval2

 of the central estimate of the 

value of the ratio from measured pairs). The center horizontal red line inside the larger shaded 

rectangle (pink) represents the NIOSH-recommended ratio value of approximately 1. The larger 

shaded rectangle represents the recommended ratio value, + a factor of 3.

 

2 The small rectangle (gray) represents the 95% confidence interval of the center estimate of the ratio value derived 

from statistical analysis, which is different from the 95% confidence level of the original data in the data pairs.
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Figure 4. Comparison of Cs-137/Sr-90 Ratio of 1.0 Recommended by NIOSH with the 

Central Estimated Ratio and Its Confidence Interval from Measured Pairs

Figure 5. Comparison of Sr-90/Cs-137 Ratio of 1.0 Recommended by NIOSH with the 

Central Estimated Ratio and Its Confidence Interval from Measured Pairs

Figures 4 and 5 indicate that the central estimate of the ratio from measured pairs for 

Cs-137/Sr-90 was 2.7 and for Sr-90/Cs-137 was 0.3, and that the associated 95% confidence 
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intervals generally fall near the boundaries of a factor of 3 of the recommended ratio. There was

considerable scatter of the ratio values over a wide range, as shown in Figures 2 and 3. 

3.0 FAP/Sr-90 VALUES

Although a large number of radionuclides are listed in Table 7-3 of ORAUT-OTIB-0054, 

Revision 03, many have relatively short half-lives (compared to the time from when the 

radionuclide was created until the time the waste sample was analyzed); therefore, when 

analyzing the ANL-W waste reports, only those with relatively long half-lives (equal to or 

greater than approximately 1 year) were selected for analysis. A total of 35 monthly and 12 

annual matched pairs of measured Sr-90 and FAP (cerium-144 [Ce-144], cobalt-60 [Co-60], and 

ruthenium-106 [Ru-106]) activities were located and analyzed, spanning the period 1958–1993 

for various facilities at the ANL-W site. The measured FAP/Sr values were compared to the 

FAP/Sr values recommended in Table 7-3a (with a 1-year decay time) of ORAUT-OTIB-0054, 

Revision 03. A comparison ratio value centered on 1 would indicate agreement between the 

measured and recommended values; however, ratio values not centered on unity would indicate 

insufficient or excessive FAP intake assignments during DR. Figures 6 through 8 contain the 

results for the monthly (represented by orange squares) and annual (represented by blue 

diamonds) FAP ANL-W data pairs analyzed.

Figure 6. Ce-144/Sr-90 Values for Monthly and Annual Data Pairs from ANL-W Waste 

Reports

Ce-144/Sr-90 from ANLW Waste records

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

0 10 20 30 40 50

Recorded Data Point (1958 to 1993)

Ce-144/Sr-90

Monthly Ce-144/Sr-90 Annual Ce-144/Sr-90 Ce/Sr = 0.5 Ce/Sr = 2.0
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Figure 7. Co-60/Sr-90 Values for Monthly and Annual Data Pairs from ANL-W Waste 

Reports

Co-60/Sr-90 from ANLW Waste records

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E+04

1.E+05

1.E+06

1.E+07

1.E+08

1.E+09

1.E+10

0 10 20 30 40 50

Recorded Data Point (1958 to 1993)

Co-60/Sr-90

Monthly Co-60/Sr-90 Annual Co-60/Sr-90 Co/Sr = 0.5 Co/Sr = 2.0

Figure 8. Ru-106/Sr-90 Values for Monthly and Annual Data Pairs from ANL-W Waste 

Reports

Ru-106/Sr-90 from ANLW Waste records

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

0 10 20 30 40 50

Recorded Data Point (1958 to 1993)

Ru-106/Sr-90

Monthly Ru-106/Sr-90 Annual Ru-106/Sr-90 Ru/Sr = 0.5 Ru/Sr = 2.0

Of the 35 monthly and 12 annual data pairs, some fell within a factor of 2 (i.e., ratio = 0.5 to 2.0) 

of the recommended value; these are represented by the data points between the solid and dashed 

thick green horizontal lines in Figures 6 through 8. The remaining ratio values were outside this 
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interval. Table 2 summarizes the distribution of the ratios that fell below, within, and above the 

recommended ratio by a factor of 2 (i.e., 0.5 to 2.0), and the corresponding data for a factor of 3 

(i.e., 0.33 to 3.0). 

As can be seen from Table 2, in general, the annual data provided a slightly greater number of 

the Cs-137/Sr-90 values that fell within a factor of +2 (or +3) as compared to the monthly data 

(the annual data tended to average out the individual monthly readings if there was considerable 

variance in their ratio values). Measured Ce-144/Sr-90 values generally fell below the 

recommended ratio of 12.3, and measured Co-60/Sr-90 values were always greater than the 

recommended value of 1.8E-4. There were very few measured Ru-106/Sr-90 pairs, but those that 

were obtained had ratio values that were scattered both below and above the recommended ratio 

value of 1. Similar results were obtained for FAP/Cs-137 values. 

Table 2. Summary of Measured FAP/Sr-90 and FAP/Cs-137 Values Compared to Ratio 

Values Recommended in Table 7-3a of ORAUT-OTIB-0054 

Radionuclides

*Recommended 

Ratio

# of 

Pairs

Type of 

Data

% of 

Pairs 

with 

Ratios 

<0.5

% of 

Pairs 

with 

Ratios 

0.5–2.0

% of 

Pairs 

with 

Ratios 

>2.0

% of 

Pairs 

with 

Ratios 

<0.33

% of 

Pairs 

with 

Ratios 

0.33–3.0

% of 

Pairs 

with 

Ratios 

>3.0

Ce-144/Sr-90 12.5 17 Monthly 82.4% 17.7% 0.0% 82.4% 17.7% 0.0%

Ce-144/Sr-90 12.5 4 Annual 100.0% 0.0% 0.0% 100.0% 0.0% 0.0%

Ce-144/Cs-137 12.3 17 Monthly 47.1% 5.9% 47.1% 47.1% 29.4% 23.5%

Ce-144/Cs-137 12.3 4 Annual 100.0% 0.0% 0.0% 100.0% 0.0% 0.0%

Co-60/Sr-90 1.85E-04 13 Monthly 0.0% 0.0% 100.0% 0.0% 0.0% 100.0%

Co-60/Sr-90 1.85E-04 7 Annual 0.0% 0.0% 100.0% 0.0% 0.0% 100.0%

Co-60/Cs-137 1.83E-04 13 Monthly 0.0% 0.0% 100.0% 0.0% 0.0% 100.0%

Co-60/Cs-137 1.83E-04 7 Annual 0.0% 0.0% 100.0% 0.0% 14.3% 85.7%

Ru-106/Sr-90 1 5 Monthly 40.0% 20.0% 40.0% 40.0% 20.0% 40.0%

Ru-106/Sr-90 1 1 Annual 100.0% 0.0% 0.0% 100.0% 0.0% 0.0%

Ru-106/Cs-137 1 5 Monthly 40.0% 20.0% 40.0% 40.0% 40.0% 20.0%

Ru-106/Cs-137 1 1 Annual 100.0% 0.0% 0.0% 100.0% 0.0% 0.0%

*NIOSH-recommended ratio values (ORAUT-OTIB-0054, Revision 03, Table 7-3a, at 1 year).

Figures 9 and 10 show the ratio values derived from the measured monthly and annual data 

compared to NIOSH’s recommended ratios. The black bar inside the vertical shaded rectangle 

(gray) represents a central estimate of the value of the ratio from measured pairs (with the

vertical shaded rectangle representing the 95% confidence interval of the central estimate of the 

value of the ratio from measured pairs). The center horizontal red line inside the horizontal 

shaded rectangle (pink) represents the NIOSH-recommended ratio value. The horizontal shaded 

rectangle represents the recommended ratio value, + a factor of 3.
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Figure 9. Comparison of Ce-144/Sr-90 Ratio of 12.5 Recommended by NIOSH with the 

Central Estimated Ratio and Its Confidence Interval from Measured Pairs

Figure 10. Comparison of Co-60/Sr-90 Ratio of 1.8E-4 Recommended by NIOSH with the 

Central Estimated Ratio and Its Confidence Interval from Measured Pairs

Figure 9 illustrates that the measured center estimated Ce-144/Sr-90 value, as well as the 95% 

confidence interval area, fell below the recommended Ce-144/Sr-90 value (with a central 
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estimate of the ratio from measured pairs of 0.63 compared to a recommended ratio of 12.5), 

with some scatter as shown in Figure 6. 

Figure 10 illustrates that the measured center estimated Co-60/Sr-90 value, as well as the entire 

95% confidence internal area, were well above the recommended Co-60/Sr-90 value of 1.8E-4, 

with considerable scatter as shown in Figure 7. 

There were too few Ru-106/Sr-90 (or Ru-106/Cs-137) data pairs to allow for meaningful 

statistical analysis, but those that were obtained had ratio values that were scattered both below 

and above the recommended ratio value of 1. 

Similar results were obtained for FAP/Cs-137 values. 

4.0 ACTINIDE/Cs-137 VALUES

According to NIOSH’s ER, the basis for assigning actinide intakes, except for special situations, 

is directly tied (in a constant ratio) to an indicating radionuclide (Sr-90 or Cs-137) using 

Table 5-22 (Sr-90 ratios) and/or Table 5-23 (Cs-137 ratios) of ORAUT-TKBS-0007-5, 

Revision 03. These tables are reproduced here as Figures 11 and 12. 

Figure 11. Table 5-22, Actinide-to-Sr-90 Ratios (ORAUT-TKBS-0007-5, Revision 03) 
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Figure 12. Table 5-23, Actinide-to-Cs-137 Ratios (ORAUT-TKBS-0007-5, Revision 03) 

Because this method involves assigning actinide intakes and doses over a long time span and 

many areas and operations, it results in the majority of the internal alpha dose assignments for 

ANL-W workers who did not have specific actinide radionuclide bioassays. Therefore, SC&A 

searched for measured actinide/Sr-90 and actinide/Cs-137 values to determine if the ratio values 

recommended in Tables 5-22 and 5-23, respectively, are applicable to DR for ANL-W workers. 

The major dose-contributing radionuclides in these tables are americium-241 (Am-241), 

plutonium-238 (Pu-238), Pu-239, uranium-234 (U-234), and U-236; therefore, these were the 

radionuclides searched for in this analysis (with emphases on Pu-238, Am-241, and U-234, the 

largest of the dose contributors). SC&A found that there were not significant entries for actinides 

in the waste reports until the late 1970s, and actinides were many times not included in the waste 

reports even in the 1970s and afterward. During the recent search of FAP monthly and annual 

data pairs, SC&A did not locate any additional actinide data pairs compared to those presented in 

the earlier progress report of July 2016 (SC&A 2016), which consisted of a total (monthly plus 

annual) of 15 matched pairs of measured Cs-137 and an actinide (four pairs for Am-241, three

pairs for Pu-238, and eight pairs for Pu-239). These data are illustrated in Figure 13 and 

summarized in Table 3. 
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Figure 13. Measured Actinide/Cs-137 Values Compared to Ratio Values in 

Table 5-23 from ORAUT-TKBS-0007-5, Revision 03 

ANL-W Soil and Waste Samples

Measured Actinide/Cs-137 Compared to Table 5-23 Ratio

0.01

0.10

1.00

10.00

100.00

1970 1975 1980 1985 1990 1995

Year Data Point Recorded

(Meas Actinide/Cs)/(Table 5-23 Ratio)

Am241/Cs [>2.0] Pu238/Cs [<0.5] Pu239/Cs [<0.5] Pu239/Cs [0.5 to 2.0] Pu239/Cs [>2.0]

Table 3. Summary of Measured FAP/Cs-137 Values Compared to Ratio Values 

Recommended in Table 7-3a of ORAUT-OTIB-0054, Revision 03 

Radionuclides

Recommended 

NIOSH Ratio 

(TKBS-0007-5, 

Tables 5-22 & 

5-23 at Max.)

# of 

Pairs*

Type of 

Data 

(monthly 

or 

annual)

% of 

Pairs 

with 

Ratios 

<0.5

% of 

Pairs 

with 

Ratios 

0.5–2.0

% of 

Pairs 

with 

Ratios 

>2.0

% of 

Pairs 

with 

Ratios 

<0.33

% of 

Pairs 

with 

Ratios 

0.33–

3.0

% of 

Pairs 

with 

Ratios 

>3.0

Am-241/Cs-137 1.30E-04 4 Mixed 0.0% 0.0% 100.0% 0.0% 25.0% 75.0%

Pu-238/ Cs-37 1.40E-02 3 Mixed 100.0% 0.0% 0.0% 100.0% 0.0% 0.0%

Pu-239/ Cs-37 3.40E-03 8 Mixed 25.0% 25.0% 50.0% 25.0% 25.0% 50.0%

*In this analysis, two data pair were removed from the earlier data used in the progress report of July 2016 (SC&A 2016) because 

recent analyses of detailed monthly data sheets indicated that the recorded Cs-137 and Sr-90 activities were exactly equal (to four 

significant figures) for each month, which would indicate invalid data. 

SC&A did not find sufficient ANL-W quantitative actinide data to provide for meaningful 

statistical analysis. The data that were obtained indicate that actinide/Sr-90 and actinide/Cs-137 

values vary considerably from those recommended in ORAUT-TBKS-007-5, Revision 03, 

Tables 5-22 and 5-23, respectively. 

5.0 SUMMARY AND CONCLUSIONS 

The following list summarizes the results based on the measured data points analyzed to date and 

SC&A’s conclusions about those results: 
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• Cs-137/Sr-90 – Many of the Cs-137/Sr-90 values were not centered on unity; 32.4% of 

34 monthly data points analyzed for Cs-137/Sr-90 from the 1958–1993 ANL-W waste 

reports fell within a range of 0.5 to 2.0, and 44.1% fell within a range of 0.33 to 3.0, of 

the recommended ratio of 1. Some ratio values were a magnitude above or below unity. 

Somewhat better results were obtained using annual data pairs because they averaged

recorded monthly activity values over the year. SC&A finds that the measured 

Cs-137/Sr-90 values are not sufficiently constant to assume a ratio of unity. Differences 

in FAP intake assignments during DR for the radionuclides listed in Table 7-3 of 

ORAUT-OTIB-0054 could occur depending on whether Cs-137 bioassays or Sr-90 

bioassays were performed. 

• FAP/Sr-90 – Analysis of a total of 35 monthly and 12 annual measured FAP/Sr-90 and 

FAP/Cs-137 data pairs provided the following results: 

– Ce-144: All of the measured Ce-144/Sr-90 values were below a factor of 2 of the 

recommended ratio value of 12.5; Ce-144/Cs-137 results were similar. Therefore, 

SC&A finds that the use of the recommended Ce-144 ratios is reasonable for DR 

purposes. 

– Co-60: All of the measured Co-60/Sr-90 and Co-60/Cs-137 values were greater 

than the recommended value of 1.8E-4, with many values orders of magnitude 

greater. Therefore, SC&A finds that the use of the recommended ratio of 1.8E-4 

would result in significant underestimation of Co-60 intakes for much of the 

materials analyzed in this report.

– Ru-106: There were too few Ru-106/Sr-90 (or Ru-106/Cs-137) data pairs to allow 

for meaningful statistical analysis, but those that were obtained had ratio values 

that were scattered both well below and above the recommended ratio value of 1. 

– Measured FAP ratio values could only be obtained for relatively long-lived 

radionuclides (Cs-137, Sr-90, Ce-144, Co-60, and Ru-106). Therefore, the actual 

ratio values for the shorter-lived FAPs in Table 7-3 are not known at this time for 

the materials analyzed.

• Actinide ratios – SC&A did not locate additional actinide data from those used in 

SC&A’s progress report of July 2016 (SC&A 2016), in which SC&A did not locate 

sufficient ANL-W quantitative actinide data to provide for meaningful statistical analysis. 

The data that were obtained indicate that actinide/Sr-90 and actinide/Cs-137 values vary 

considerably from those recommended in ORAUT-TBKS-007-5, Revision 03, Tables 5-

22 and 5-23, respectively.

• Use of only Sr-90 or Cs-137 – Evaluation of the data pairs and radionuclide 

combinations indicates that the sole use of Sr-90 or Cs-137 does not offer an advantage in 

consistency when assigning FAP or actinide intakes. In addition, many bioassays only 

analyzed for Cs-137 or Sr-90, not both. 
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• Monthly versus annual data – Comparing the results obtained from using monthly and 

annual data in the ANL-W waste reports indicates that the use of annual data compared to 

using monthly data tends to average out the variations in the monthly recorded activity 

values. SC&A’s analysis in this report provides similar results as those obtained in the 

July 2016 progress report (SC&A 2016), which used mostly annual results. 
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6.0 REFERENCES

NIOSH 2016. SEC Petition Evaluation Report – ANL-W Petition SEC-00224 of February 18, 

2016, National Institute for Occupational Safety and Health, Division of Compensation Analysis 

and Support, Cincinnati, Ohio. February 18, 2016. 

ORAUT 2009. INEL-Actinide Ratios [Microsoft Excel® workbook], Revision 0, Oak Ridge 

Associated Universities Team, Oak Ridge, Tennessee. December 18, 2009. [SRDB Ref. 

ID 77440] 

ORAUT-TKBS-0007-5. 2010. Idaho National Laboratory and Argonne National Laboratory – 

West – Occupational Internal Dose, Revision 03, Oak Ridge Associated Universities Team, 

Cincinnati, Ohio. March 2, 2010. 

ORAUT-OTIB-0054. 2007. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Revision 00 PC-1, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. November 19, 2007. 

ORAUT-OTIB-0054. 2014. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Revision 02, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. March 6, 2014. 

ORAUT-OTIB-0054. 2015. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Revision 03, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. February 6, 2015. 

SC&A 2016. Progress Report: SC&A’s Evaluation of Sr-90/Cs-137, FAP/Cs-137, and 

Actinides/Cs-137 Ratios Using ANL-W Measured Values in Relationship to Assigning Intakes, 

SC&A, Inc., Vienna, Virginia, and Saliant, Inc., Jefferson, Maryland. July 14, 2016. 
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ATTACHMENT A. DOCUMENTS AND DATA USED TO EVALUATE

Cs-137/Sr-90 VALUES

SRDB Ref 

#

PDF Page 

#

Time 

Period Area

Type of 

Waste

Units of 

Activity

Monthly 

Measured 

Cs-137 

Activity

Monthly 

Measured 

Sr-90 Activity

Monthly 

Measured 

[Cs-137/Sr-90]

Annual 

Measured 

Cs-137 

Activity

Annual 

Measured 

Sr-90 Activity

Annual 

Measured 

[Cs-137/ 

Sr-90]

27049 16 1958 BORAX IV Rx water dpm/ml No data No data No data 1.100E+04 4.200E+02 26.19

27049 16 1958 BORAX IV Rx water dpm/ml No data No data No data 1.200E+04 4.840E+02 24.79

118781 2-23 1970 EBR-I AIR filter-E uCi/m3 3.000E-04 2.130E-04 1.41 No data No data No data

118781 2-23 1970 EBR-I AIR filter-F uCi/m3 1.000E-04 8.200E-05 1.22 No data No data No data

118781 2-23 1970 EBR-I AIR filter-G uCi/m3 1.000E-04 3.140E-05 3.18 No data No data No data

118781 2-23 1970 EBR-I AIR filter-H uCi/m3 1.000E-05 5.010E-06 2.00 No data No data No data

85427 7 1972 ANL_EBR-I air uCi/ml No data No data No data 3.500E-15 2.000E-15 1.75

118781 211 1972 ANL Air filter uCi/cc 4.600E-15 6.000E-15 0.77 No data No data No data

85523 25 1972 ANL Liquid Ci 4.346E-04 1.413E-05 30.76 5.892E-03 4.929E-05 119.54

85523 25 1972 ANL Liquid Ci 7.575E-04 1.672E-05 45.31 No data No data No data

85523 25 1972 ANL Liquid Ci 3.951E-04 1.844E-05 21.43 No data No data No data

140037 89 1973 ANL Liquid Ci 5.311E-04 7.611E-06 69.78 4.360E-03 1.605E-04 27.17

140037 89 1973 ANL Liquid Ci 2.060E-04 6.782E-06 30.37 No data No data No data

140037 89 1973 ANL Liquid Ci 3.073E-04 2.151E-05 14.29 No data No data No data

140037 89 1973 ANL Liquid Ci 4.477E-05 1.506E-05 2.97 No data No data No data

140037 89 1973 ANL Liquid Ci 1.211E-04 1.289E-05 9.39 No data No data No data

85524 30 1973 ANL Liquid Ci 6.916E-04 2.165E-05 31.94 3.681E-03 1.028E-04 35.81

85524 30 1973 ANL Liquid Ci 7.685E-04 1.934E-05 39.74 No data No data No data

85524 30 1973 ANL Liquid Ci 4.884E-04 1.280E-05 38.16 No data No data No data

85524 30 1973 ANL Liquid Ci 5.342E-04 4.140E-05 12.90 No data No data No data

85524 30 1973 ANL Liquid Ci 5.310E-04 7.611E-06 69.77 No data No data No data

85524 771 1973 ANL Liquid Ci 2.060E-04 6.782E-06 30.37 4.600E-03 1.605E-04 28.66

85524 771 1973 ANL Liquid Ci 3.073E-04 2.151E-05 14.29 No data No data No data

85524 771 1973 ANL Liquid Ci 4.477E-05 1.506E-05 2.97 No data No data No data

85524 771 1973 ANL Liquid Ci 1.211E-04 1.289E-05 9.39 No data No data No data

83153 8 1978 ANL_EBR-I soil uCi/gm No data No data None 1.100E+00 5.700E-01 1.93

83153 8 1978 ANL_EBR-I soil uCi/gm No data No data None 1.300E+00 8.600E-01 1.51

83153 8 1978 ANL_EBR-I soil uCi/gm No data No data None 1.070E+00 5.700E-01 1.88

118841 163 1978 ANL Solid waste Ci 7.037E+00 2.000E+00 3.52 1.160E+02 8.842E+01 1.31

118841 163 1978 ANL Solid waste Ci 5.000E+00 1.000E+00 5.00 No data No data No data

118841 163 1978 ANL Solid waste Ci 6.500E+00 1.500E+00 4.333 No data No data No data

118841 163 1978 ANL Solid waste Ci 4.400E+00 2.500E+00 1.76 No data No data No data

118841 165 1978 ANL Solid waste Ci 8.700E+01 6.200E+01 1.40 1.949E+02 1.000E+02 1.95

118841 165 1978 ANL Solid waste Ci 7.000E+01 3.500E+01 2.00 No data No data No data

118841 165 1978 ANL Solid waste Ci 2.000E+00 1.000E+00 2.00 No data No data No data

83007 33&34 1980 BORAX I soil pCi/gm No data No data None 7.000E+00 2.500E+00 2.80

87191 190 1985 ANL solid waste Ci No data No data None 1.876E+01 1.840E+01 1.02

87191 192 1985 ANL Solid waste Ci 1.000E+00 2.000E+00 0.50 3.400E+00 4.400E+00 0.77

87191 192 1985 ANL Solid waste Ci 2.400E+00 2.400E+00 1.00 No data No data No data

136493 152 1993 ANL Solid waste Ci 9.918E-02 2.629E-01 0.38 6.303E-01 1.188E+00 0.53

136493 152 1993 ANL Solid waste Ci 4.202E-01 6.361E-01 0.66 No data No data No data

136493 152 1993 ANL Solid waste Ci 1.108E-01 2.886E-01 0.38 No data No data No data
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ATTACHMENT B. DOCUMENTS AND DATA USED TO EVALUATE

FAP/Sr-90 AND FAP/Cs-137 VALUES

Table B.1. Documents and Data Used to Evaluate Ce-144/Sr-90 and Ce-144/Cs-137 Values 

SRDB 

Ref #

PDF 

Page #

Time 

Period Area

Type of 

Waste

Units of 

Activity

Monthly 

Measured 

Cs-137 

Activity

Monthly 

Measured 

Sr-90 

Activity

Annual 

Measured 

Cs-137 

Activity

Annual 

Measured 

Sr-90 

Activity

Monthly 

Measured 

Ce-144 

Activity

Monthly 

Measured 

[Ce-144/ 

Sr-90]/ 

12.5

Annual 

Measured 

Ce-144 

Activity

Annual 

Measured 

[Ce-144/ 

Sr-90]/12.5

118781 2-23 1970 EBR-I AIR filter-E uCi/m3 3.000E-04 2.130E-04 No data No data 5.000E-04 0.19 No data No data

118781 2-23 1970 EBR-I AIR filter-F uCi/m3 1.000E-04 8.200E-05 No data No data 6.000E-04 0.59 No data No data

118781 2-23 1970 EBR-I AIR filter-G uCi/m3 1.000E-04 3.140E-05 No data No data 6.000E-04 1.53 No data No data

118781 2-23 1970 EBR-I AIR filter-H uCi/m3 1.000E-05 5.010E-06 No data No data 1.000E-04 1.60 No data No data

118781 211 1972 ANL Air filter uCi/cc 4.600E-15 6.000E-15 No data No data 2.300E-14 0.31 No data No data

118841 163 1978 ANL Solid waste Ci 7.037E+00 2.000E+00 1.160E+02 8.842E+01 3.000E+00 0.12 8.641E+01 0.0782

118841 163 1978 ANL Solid waste Ci 5.000E+00 1.000E+00 No data No data 3.000E+00 0.24 No data No data

118841 163 1978 ANL Solid waste Ci 6.500E+00 1.500E+00 No data No data 4.500E+00 0.24 No data No data

118841 163 1978 ANL Solid waste Ci 4.400E+00 2.500E+00 No data No data 3.000E+00 0.10 No data No data

118841 165 1978 ANL Solid waste Ci 8.700E+01 6.200E+01 1.949E+02 1.000E+02 8.700E+01 0.11 1.625E+02 0.1300

118841 165 1978 ANL Solid waste Ci 7.000E+01 3.500E+01 No data No data 7.000E+01 0.16 No data No data

118841 165 1978 ANL Solid waste Ci 2.000E+00 1.000E+00 No data No data 2.000E+00 0.16 No data No data

87191 192 1985 ANL Solid waste Ci 1.000E+00 2.000E+00 3.400E+00 4.400E+00 3.000E+00 0.12 9.000E+00 0.1636

87191 192 1985 ANL Solid waste Ci 2.400E+00 2.400E+00 No data No data 6.000E+00 0.20 No data No data

136493 152 1993 ANL Solid waste Ci 9.918E-02 2.629E-01 6.303E-01 1.188E+00 4.328E-03 0.0013 3.087E-02 0.0021

136493 152 1993 ANL Solid waste Ci 4.202E-01 6.361E-01 No data No data 2.047E-02 0.0026 No data No data

136493 152 1993 ANL Solid waste Ci 1.108E-01 2.886E-01 No data No data 6.077E-03 0.0017 No data No data

Table B.2. Documents & Data Used to Evaluate Co-60/Sr-90 & Co-60/Cs-137 Values 

SRDB 

Ref #

PDF 

Page #

Time 

Period Area

Type of 

Waste

Units of 

Activity

Monthly 

Measured 

Cs-137 

Activity

Monthly 

Measured 

Sr-90 

Activity

Annual 

Measured 

Cs-137 

Activity

Annual 

Measured 

Sr-90 

Activity

Monthly 

Measured 

Co-60 

Activity

Monthly 

Measured 

[Co-60/ 

Sr-90]/ 

1.85E-4

Annual 

Measured 

Co-60 

Activity

Annual 

Measured 

[Co-60/ 

Sr-90]/ 

1.85E-4

118781 2-23 1970 EBR-I AIR filter-G uCi/m3 1.000E-04 3.140E-05 None None 5.000E-05 8.61E+03 No data No data

85523 25 1972 ANL Liquid Ci 4.346E-04 1.413E-05 5.892E-03 4.929E-05 2.354E-04 9.01E+04 2.354E-04 2.58E+04

140037 89 1973 ANL Liquid Ci 5.311E-04 7.611E-06 4.360E-03 1.605E-04 No data No data 2.412E-06 8.12E+01

85524 30 1973 ANL Liquid Ci 6.916E-04 2.165E-05 3.681E-03 1.028E-04 No data No data 6.678E-04 3.51E+04

85524 30 1973 ANL Liquid Ci 5.342E-04 4.140E-05 No data No data 6.678E-04 8.72E+04 No data No data

118841 163 1978 ANL Solid waste Ci 7.037E+00 2.000E+00 1.160E+02 8.842E+01 No data No data 1.474E+03 9.01E+04

118841 163 1978 ANL Solid waste Ci 5.000E+00 1.000E+00 No data No data 1.930E+02 1.04E+06 No data No data

118841 163 1978 ANL Solid waste Ci 6.500E+00 1.500E+00 No data No data 7.000E+01 2.52E+05 No data No data

118841 163 1978 ANL Solid waste Ci 4.400E+00 2.500E+00 No data No data 2.170E+02 4.69E+05 No data No data

118841 165 1978 ANL Solid waste Ci 8.700E+01 6.200E+01 1.949E+02 1.000E+02 2.000E+00 1.74E+02 2.950E+02 1.59E+04

118841 165 1978 ANL Solid waste Ci 7.000E+01 3.500E+01 No data No data 7.000E+01 1.08E+04 No data No data

118841 165 1978 ANL Solid waste Ci 2.000E+00 1.000E+00 No data No data 7.600E+01 4.11E+05 No data No data

87191 192 1985 ANL Solid waste Ci 1.000E+00 2.000E+00 3.400E+00 4.400E+00 No data No data 9.250E+02 1.14E+06

87191 192 1985 ANL Solid waste Ci 2.400E+00 2.400E+00 No data No data 8.300E+01 1.87E+05 No data No data

136493 152 1993 ANL Solid waste Ci 9.918E-02 2.629E-01 6.303E-01 1.188E+00 6.505E+03 1.34E+08 6.557E+04 2.98E+08

136493 152 1993 ANL Solid waste Ci 4.202E-01 6.361E-01 No data No data 1.389E-01 1.18E+03 No data No data

136493 152 1993 ANL Solid waste Ci 1.108E-01 2.886E-01 No data No data 2.921E-02 5.47E+02 No data No data

Table B.3. Documents and Data Used to Evaluate Ru-106/Sr-90 and Ru-106/Cs-137 Values 

SRDB 

Ref #

PDF 

Page #

Time 

Period Area

Type of 

Waste

Units of 

Activity

Monthly 

Measured 

Cs-137 

Activity

Monthly 

Measured 

Sr-90 

Activity

Annual 

Measured 

Cs-137 

Activity

Annual 

Measured 

Sr-90 

Activity

Monthly 

Measured 

Ru-106 

Activity

Monthly 

Measured 

[Ru-106/ 

Sr-90]

Annual 

Measured 

Ru-106 

Activity

Annual 

Measured 

[Ru-106/ 

Sr-90]

118781 2-23 1970 EBR-I AIR filter-E uCi/m3 3.000E-04 2.130E-04 None None 3.000E-04 1.408 No data No data

118781 2-23 1970 EBR-I AIR filter-F uCi/m3 1.000E-04 8.200E-05 None None 2.000E-05 0.244 No data No data

118781 2-23 1970 EBR-I AIR filter-G uCi/m3 1.000E-04 3.140E-05 None None 3.000E-04 9.554 No data No data

118781 2-23 1970 EBR-I AIR filter-H uCi/m3 1.000E-05 5.010E-06 None None 4.000E-05 7.984 No data No data

136493 152 1993 ANL Solid waste Ci 9.918E-02 2.629E-01 6.303E-01 1.188E+00 1.793E-04 6.81E-4 1.793E-04 1.51E-4
Effective Date:

01/20/2017

Revision No.

0 (Draft)

Document No./Description:

SCA-TR-2017-SEC002

Page No.

26 of 26

NOTICE: This report has been reviewed to identify and redact any information that is protected by the 

Privacy Act 5 U.S.C. § 552a and has been cleared for distribution.

ATTACHMENT C. DOCUMENTS AND DATA USED TO EVALUATE 

ACTINIDE/Cs-137 AND ACTINIDE/Sr-90 VALUES

Table C.2. Documents and Data Used to Evaluate Am-241/Cs-137 and Am-241/Sr-90 

Values

SRDB Ref # PDF # Time Period Area

Type of 

Sample Type of Data

Measured

Cs-137 

Activity Units

Measured

Am-241 

T1/2=433y 

Activity

(Am-241/ 

Cs-137)

OTIB-54

(Am-241/ 

Cs-137) 

Ratio

[Meas. 

Am241/Cs-137]/ 

[1.3E-4])

83153 8 1978 ANL_EBR-I soil One sample 1.10E+00 pCi/g 9.00E-03 8.18E-03 1.30E-04 62.94

83153 8 1978 ANL_EBR-I soil One sample 1.30E+00 pCi/g 1.50E-02 1.15E-02 1.30E-04 88.76

136493 152 1993 ANL solid waste Monthly 4.20E-01 Ci 1.63E-04 3.88E-04 1.30E-04 2.99

83153 8 1978 ANL_EBR-I soil One sample 1.07E+00 pCi/g 9.00E-03 8.41E-03 1.30E-04 64.70

Table C.1. Documents and Data Used to Evaluate Pu-238/Cs-137 and Pu-238/Sr-90 Values

SRDB Ref # PDF # Time Period Area

Type of 

Sample

Measured 

Cs-137 

Activity Units

Measured 

Pu-238 

T1/2=88y 

Activity

(Pu-238/ 

Cs-137)

OTIB-54 

(Pu-238/ 

Cs-137) ratio

[Meas. Pu238/

Cs-137]/[1.4E-2])

83153 8 1978 ANL_EBR-I soil One sample 1.10E+00 pCi/g 1.70E-03 1.55E-03 1.40E-02 0.11

83153 8 1978 ANL_EBR-I soil One sample 1.30E+00 pCi/g 2.50E-03 1.92E-03 1.40E-02 0.14

83153 8 1978 ANL_EBR-I soil One sample 1.07E+00 pCi/g 4.10E-03 3.83E-03 1.40E-02 0.27

Table C.3. Documents and Data Used to Evaluate Pu-239/Cs-137 and Pu-239/Sr-90 Values

SRDB Ref # PDF # Time Period Area

Type of 

Sample

Measured

Cs-137 

Activity Units

Measured

Pu-239 

T1/2=2.4E4y 

Activity

(Pu-239/ 

Cs-137)

OTIB-54

(Pu-239/ 

Cs-137) 

Ratio

[Meas. Pu239/

Cs-137]/[3.4E-3])

87191 190 1985 ANL solid waste Annual 1.88E+01 Ci 1.09E-02 5.79E-04 3.40E-03 0.17

87191 192 1985 ANL solid waste Annual 3.40E+00 Ci 1.61E-01 4.73E-02 3.40E-03 13.92

83153 8 1978 ANL_EBR-I soil One sample 1.10E+00 pCi/g 2.20E-02 2.00E-02 3.40E-03 5.88

83153 8 1978 ANL_EBR-I soil One sample 1.30E+00 pCi/g 1.90E-02 1.46E-02 3.40E-03 4.30

83153 8 1978 ANL_EBR-I soil One sample 1.07E+00 pCi/g 1.50E-02 1.40E-02 3.40E-03 4.12

118841 163 1978 ANL solid waste Annual 1.16E+02 Ci 1.19E-02 1.02E-04 3.40E-03 0.03

118841 165 1978 ANL solid waste Annual 1.95E+02 Ci 1.07E+00 5.49E-03 3.40E-03 1.61

83007 34&35 1980 BORAX I soil One sample 7.00E+00 pCi/g 2.10E-02 3.00E-03 3.40E-03 0.88