ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 41

DOE Review Release 04/19/2012

Document Title:

Internal Dosimetry Coworker Data for 

the Mound Site

Document Number: ORAUT-OTIB-0061

Revision: 02

Effective Date: 04/13/2012

Type of Document: OTIB

Supersedes: Revision 01

Subject Expert(s): Matthew G. Arno and James M. Mahathy

Approval: Signature on File Approval Date: 04/09/2012

Donald N. Stewart, Document Owner

Concurrence: Signature on File Concurrence Date: 04/05/2012

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 04/05/2012

Edward F. Maher, Objective 3 Manager

Concurrence: Viickie S. Short Signature on File for Concurrence Date: 04/10/2012

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 04/13/2012

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 2 of 41

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

06/22/2007 00 Approved new technical information bulletin for assigning Mound 

internal doses based on coworker bioassay data. Incorporates 

formal internal and NIOSH review comments. There is no change to 

the assigned dose and no PER is required. Training required: As 

determined by the Task Manager. Initiated by Clark B. Barton.

02/17/2011 01 Revision to change modeling of intakes of Type S plutonium to 

provide best-estimate intakes. Deleted previous underestimating 

intakes and instructions for dose reconstructors to perform casespecific intake modeling. Added 95th-percentile intake rates for all 

radionuclides. Constitutes a total rewrite or the document. 

Incorporates formal internal and NIOSH review comments. Training 

required: As determined by the Objective Manager. Initiated by 

Matthew G. Arno.

04/13/2012 02 Revision to extend intake assignments for plutonium from 1990 to 

2002 and add evaluation of tritium for 1981 through 2005. 

Incorporates formal internal and NIOSH review comments. 

Constitutes a total rewrite of the document. Training required: As 

determined by the Objective Manager. Initiated by Matthew G. Arno.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 3 of 41

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 6

1.0 Introduction .............................................................................................................................. 7

2.0 Purpose ................................................................................................................................... 7

3.0 Data Overview ......................................................................................................................... 8

3.1 Bioassay Data Selection............................................................................................... 8

Polonium Urinalysis Data.............................................................................................. 8

Plutonium Urinalysis Data............................................................................................. 8

Tritium Urinalysis Data.................................................................................................. 9

3.2 Analysis........................................................................................................................ 9

Polonium Bioassay Analysis......................................................................................... 9

Plutonium Bioassay Analysis...................................................................................... 10

Tritium Bioassay Analysis........................................................................................... 10

4.0 Intake Modeling...................................................................................................................... 11

4.1 Assumptions............................................................................................................... 11

Polonium Assumptions ............................................................................................... 11

Plutonium Assumptions .............................................................................................. 11

4.2 Bioassay Fitting .......................................................................................................... 11

Polonium Fitting.......................................................................................................... 11

Plutonium Fitting......................................................................................................... 11

4.3 Material Types............................................................................................................ 12

Polonium .................................................................................................................... 12

Plutonium ................................................................................................................... 12

5.0 Assigning Intakes and Doses ................................................................................................. 12

5.1 Intake Rate Summary................................................................................................. 13

Polonium .................................................................................................................... 13

Plutonium ................................................................................................................... 13

Tritium...................................................................................................................... 14

5.2 Dose Assignment ....................................................................................................... 14

6.0 Attributions and Annotations .................................................................................................. 15

References ........................................................................................................................................ 18

ATTACHMENT A, COWORKER DATA TABLES............................................................................... 19

ATTACHMENT B, COWORKER DATA FIGURES ............................................................................ 25

LIST OF TABLES

TABLE TITLE PAGE

5-1 Derived polonium intakes, 1944 to 1973 ................................................................................ 13

5-2 Derived plutonium intake rates, 1956 to 2002 ........................................................................ 13

5-3 Tritium annual doses and GSDs............................................................................................. 14
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 4 of 41

5-4 Dose calculations for WGPU intakes...................................................................................... 15

A-1 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1973................................ 19

A-2 Type M 210Po intake rates and dates ...................................................................................... 21

A-3 Type F 210Po intake rates and dates....................................................................................... 21

A-4 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 2002 ................. 21

A-5 Type M plutonium intake rates and dates............................................................................... 24

A-6 Type S plutonium intake rates and dates ............................................................................... 24

LIST OF FIGURES

FIGURE TITLE PAGE

B-1 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M 210Po.......................................................................................................................25

B-2 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M 210Po.......................................................................................................................25

B-3 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type F 210Po........................................................................................................................26

B-4 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type F 210Po........................................................................................................................26

B-5 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1956 to 1957 ......................................................................................... 27

B-6 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1958 to 1960 ......................................................................................... 27

B-7 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1961 to 1969 ......................................................................................... 28

B-8 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1970 to 1984 ......................................................................................... 28

B-9 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1985 to 1997 ......................................................................................... 29

B-10 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1998 to 2002 ......................................................................................... 29

B-11 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1956 to 2002 ......................................................................................... 30

B-12 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1956 to 1960 ......................................................................................... 30

B-13 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1961 to 1967 ......................................................................................... 31

B-14 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1968 to 1969 ......................................................................................... 31

B-15 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1970 to 1977 ......................................................................................... 32

B-16 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1978 to 1984 ......................................................................................... 32

B-17 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1985 to 1997 ......................................................................................... 33

B-18 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1998 to 2002 ......................................................................................... 33

B-19 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes 

of type M plutonium, 1956 to 2002 ......................................................................................... 34

B-20 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 34
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 5 of 41

B-21 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 35

B-22 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 35

B-23 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 36

B-24 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 36

B-25 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 37

B-26 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 37

B-27 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 38

B-28 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 38

B-29 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 39

B-30 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 39

B-31 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 40

B-32 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 40

B-33 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 41
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 6 of 41

ACRONYMS AND ABBREVIATIONS

AMAD activity median aerodynamic diameter

Bq becquerel

d day

DOE U.S. Department of Energy

DTPA diethylene triamine pentaacetic acid

EEOICPA Energy Employees Occupational Illness Compensation Program Act

GSD geometric standard deviation

hr hour

HSPU heat-source plutonium

ICRP International Commission on Radiological Protection

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

m meter

mL milliliter

mrem millirem

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

pCi picocurie

PER Program Evaluation Report

POC probability of causation

SRDB Ref ID Site Research Database Reference Identification (number)

TIB technical information bulletin

U.S.C. United States Code

WGPU weapons-grade plutonium

μm micrometer

§ section or sections
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 7 of 41

1.0 INTRODUCTION

Technical information bulletins (TIBs) are not official determinations made by the National Institute for 

Occupational Safety and Health (NIOSH) but are rather general working documents that provide 

historic background information and guidance concerning the preparation of dose reconstructions at 

particular sites or categories of sites. They will be revised in the event additional relevant information 

is obtained about the affected site(s). TIBs may be used to assist NIOSH staff in the completion of 

individual dose reconstructions.

In this document, the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy (DOE) facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act of 2000 [42 U.S.C. § 7384l(5) and (12)].

ORAUT-OTIB-0019, Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAUT 

2005), describes the general process that is used to analyze bioassay data for assigning doses to 

individuals based on coworker results. ORAUT-PLAN-0014, Coworker Data Exposure Profile 

Development (ORAUT 2004a), describes the approach and processes to be used to develop 

reasonable exposure profiles based on available dosimetric information for workers at DOE sites.

Bioassay results were obtained through the PORECON (Polonium Reconstruction) and PURECON 

(Plutonium Reconstruction) databases that were created at the Mound Laboratory from logbooks and 

other original hard-copy records. Based on a spot check, this data set coincides well with original 

Mound paper records. It is appropriate for use only at Mound. The databases are representative of 

worker bioassay results at Mound during a substantial part of the operating history at this site. 

PURECON data was used through 1990. Plutonium data after 1990 and tritium bioassay data was 

retrieved from the MESH database.

The database results were labeled with units that varied among the radionuclides, analysis 

techniques, and measurement periods. These units were assembled into a common format to 

expedite the statistical analysis. The specific units for each radionuclide are provided in the 

appropriate sections of this document.

A statistical analysis of the data was performed as specified in ORAUT-OTIB-0019 (ORAUT 2005) 

and its implementing procedure, ORAUT-PROC-0095, Generating Summary Statistics for Coworker 

Bioassay Data (ORAUT 2006). The results were entered in the Integrated Modules for Bioassay 

Analysis (IMBA) computer software version 4.0.9 to obtain intake rates for assigning dose 

distributions.

2.0 PURPOSE

Some employees at DOE sites might not have been monitored for potential intakes of radioactive 

material. For other employees the records of such monitoring might be incomplete or unavailable. In 

such cases, data from monitored coworkers can be used to estimate an individual’s potential intake of 

radioactive material and the resulting internal dose. The purpose of this TIB is to provide monitored 

coworker information for calculating and assigning occupational internal doses to employees at 

Mound whose job titles, facility assignments, and other case-specific information indicate that they 

have the potential for unmonitored intakes of 210Po, plutonium, or tritium.

Attributions and annotations, indicated by bracketed callouts, are used to identify the source, 

justification, or clarification of the associated information, are presented in Section 6.0.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 8 of 41

3.0 DATA OVERVIEW

This section provides information on the general selection characteristics of the data and the methods 

of analysis. Plutonium, 210Po, and tritium are the radionuclides of interest, and significant numbers of 

monitoring records exist for them. More detailed radionuclide-specific information for these two 

nuclides is provided in Section 4.0.

3.1 BIOASSAY DATA SELECTION

Polonium Urinalysis Data

The urine bioassay data were extracted from the verified PORECON_FINAL_COPY database (Mound 

undated a), “dbo_SAMPLES” table, “BQ_DAY” field. By verified, it is meant that the original 

PORECON database was created by Mound from information that was recorded on cards as well as 

from a review of the original chemistry logbooks from which the cards were created. Data entry clerks 

entered the data using double-entry methods. Following this task, data entry was reviewed by health 

physicists. Samples with PROBLEM_FLG = “R” or BQ_DAY = blank were not included in the 

statistical analysis [1]. Samples were excluded for the following reasons:

• 147 nonurine samples (blood and feces),

• 116 lost in processing.

• 182 no sample submitted (vacation, illness, etc.).

• 1,595 insufficient volume.

• 1,685 duplicates or recounts.

• 162 rejected because they were submitted too late.

• 36 contaminated samples.

• 79 marked as “beta counts.” and

• 56 with no result and blank or cryptic comment.

Plutonium Urinalysis Data

Urine bioassay data (SAMPLE_TYPE = U) and the analysis date (Date = SAMPLE_DATE) were 

extracted from the PURECON table of the verified PURECON_MERGED database (Mound 

undated b). By verified, it is meant that the original PURECON database used for this analysis was 

created by Mound from logbooks and other original hard-copy records. Results with any of the 

following identifiers were excluded: PROBLEM_FLG = nonblank, DTPA = nonblank, LNAME = QC, or 

Result field (PICOC_PU238 or PICOC_PU239) = blank. There was a comment field for each result 

and, in most cases with a PROBLEM_FLG = nonblank, the comment indicated the reason for the flag. 

These included samples with low recovery, no tracer added, samples lost in process, insufficient 

volume for analysis, samples with no result, samples taken after diethylene triamine pentaacetic acid 

(DTPA) administration (chelation therapy), and samples that were analyzed for nuclides other than 

plutonium. There were 1,413 of 58,893 results marked with a problem flag. For the first quarter of 

1983, 26 sample results were excluded because the comment field indicated that 239Pu was added to 

the sample [2]. Samples were excluded for the following reasons:

• 57 were analyzed for radium, curium, or thorium rather than plutonium;

• 70 quality-control samples;

• 2307 DTPA (265 of which had a problem flag);

• 140 contaminated;

• 453 lost in processing (sample spilled, tracer not added, low recovery);

• 10 insufficient volume;

• 46 no result, no clear reason;
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 9 of 41

• 137 with blank or cryptic comment.

Plutonium urinalysis data beginning in 1991 were extracted from the MESH database. Samples were 

excluded because the s_reason field had a value of “S” or “N,” or because the Comment field 

contained:

• “No cert” or equivalent,

• “Baseline” or equivalent,

• “pre-job” or equivalent,

• “New hire” or equivalent,

• “Background” or equivalent,

• “Do not verify” or equivalent, and

• “Re-work” or equivalent.

In addition, the comment field was evaluated using professional judgment for comments indicating 

records should not be used.

Tritium Urinalysis Data

Tritium urinalysis data beginning in 1981 were also extracted from the MESH database. Samples with 

an SSN field value of “background,” “Spike 1,” “Spike 2,” “999999999,” or similar were excluded. No 

records were excluded on any other basis. The sampling date was based on the “sample date” if 

available and on the “read date” otherwise. Some samples had sample dates from before the 

creation of the MESH database but read dates that were consistent with the initiation of use of the 

MESH database and other bioassay data for that individual. For those samples, the read date was 

used instead of the sample date. A total of 212,522 samples from 2669 individuals were contained in 

the database.

3.2 ANALYSIS

Polonium Bioassay Analysis

Data were analyzed by calendar quarter from July 1944 through the end of 1970 and by year from 

1971 through part of 1973. The results of samples that were reported in 1940 and 1941 were not 

used because the site was not yet operational. Spot samples were collected for analysis; 50- or 100-

mL aliquots were analyzed, and the results were typically reported in units of counts per minute or 

disintegrations per minute. Values in the “BQ_DAY” field originally had been calculated and entered 

into the database assuming a counting efficiency of 50% and a chemical recovery of 85%. They were 

normalized to a 24-hour sample assuming an excretion rate of 1,400 mL/d. Before the statistical 

analysis was run, the results from 1944 through 1963 were multiplied by a factor of 8.5 in accordance 

with the guidance in ORAUT-TKBS-0016-6, Technical Basis Document for the Mound Site –

Occupational Internal Dosimetry (ORAUT 2010), which specifies a recovery efficiency of 10% (instead 

of 85%) for this timeframe. A factor of 1.35 was applied to results from 1964 through 1973, again 

according to ORAUT-TKBS-0016-6, which specifies a recovery efficiency of 63% (instead of 85%) for 

this timeframe.

A lognormal distribution was assumed for the urinary excretion data, and the 50th- and 84th-percentile 

excretion rates were calculated using the method ORAUT-PROC-0095 prescribes (ORAUT 2006). 

These excretion rates are given in Tables A-1 and A-2. Bioassay data that was collected over a 

specified period were analyzed to determine the 50th- and 84th-percentile excretion rates for that 

period. The effective bioassay dates are the midpoints of the periods, and they were used with IMBA 

to calculate the intake rates.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 10 of 41

Plutonium Bioassay Analysis

Data were analyzed by year from 1956 through the end of 1961, by calendar quarter from 1962 

through 1990, and by year from 1991 through 2002. The results from 1954 through 1960 were 

multiplied by a factor of 8.5, as specified in ORAUT-TKBS-0016-5 (ORAUT 2010). Analyses before 

June 1, 1981, which measured total plutonium alpha, were reported in the “PICOC_PU238” field, 

whereas later results, which were isotopic plutonium, were reported in the fields “PICOC_PU238” and 

“PICOC_PU239.” The 238Pu and 239/240Pu results for each sample that was analyzed after June 1, 

1981, were summed to create a total plutonium result for these samples. Most plutonium samples 

were 24-hour samples. Samples with no volume listed or more than 1,000 mL were assumed to be 

24-hour samples. Samples with volumes less than 1,000 mL were normalized to a 24-hour sample 

assuming an excretion rate of 1,400 mL/d.

The MESH data contained results for both plutonium-238 and plutonium-239. These results were 

summed to give a plutonium gross alpha concentration. Some samples were counted multiple times. 

The multiple results from samples with the same LIN number were averaged. All samples were 

assumed to represent a 24-hour sample and the sampling date was based on the “submit_date” field.

A lognormal distribution was assumed for the urinary excretion data, and the 50th- and 84th-percentile

excretion rates were calculated using the method in ORAUT-PROC-0095 (ORAUT 2006). These 

excretion rates are given in Tables A-5 and A-6. Bioassay data that was collected over a specified 

period were analyzed to determine the 50th- and 84th-percentile excretion rates for that period. The 

effective bioassay dates are the midpoints of the periods and they are to be used in IMBA to calculate 

the intake rates.

Tritium Bioassay Analysis

Tritium was evaluated differently than the other radionuclides in this coworker study. For tritium, the 

protocol in Technical Information Bulletin: Tritium Calculated and Missed Dose Estimates (ORAUT 

2004b) was used to calculate the dose for each individual with the following rules concerning the 

elapsed time between consecutive samples: 

• If there was a single urine sample in a calendar year and it was a nondetect, that result was 

excluded from the analysis because this was assumed to not be part of routine monitoring.

• Samples on the same date were ordered from lowest to highest

• All dose was assigned as if it occurred on the bioassay date. 

• Type 1 calculations were performed for samples separated by 40 or fewer days.

• Type 3 calculations were performed if there were no other samples within 90 days of a 

sample.

• Type 2 calculations were performed in all other situations.

The doses for a period were then plotted on a lognormal probability plot and the typical parameters 

[geometric mean, geometric standard deviation (GSD), and R2

] determined from a linear regression. 

Individuals that received less than 0.001 rem at three significant digits (i.e., less than 0.0005 rem)

were excluded from the statistical analysis. The plotting positions were calculated with i/n – 1/(2n) 

convention specified in ORAUT-PROC-0095 (ORAUT 2006). 
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 11 of 41

4.0 INTAKE MODELING

This section discusses intake modeling assumptions, fitting, and materials (polonium and plutonium). 

Intake modeling and bioassay fitting was not performed for tritium because the methodology 

discussed above for tritium directly calculates individual doses.

4.1 ASSUMPTIONS

Polonium Assumptions

Each urinary excretion rate used in the intake calculations was assumed to be normally distributed. A 

uniform absolute error of 1 was applied to all results, which thus assigned the same weight to each 

result [4]. IMBA requires results in units of activity per day; therefore, all urinalysis results were 

normalized, as needed, to 24-hour samples using 1,400 mL, which is the volume of urine that is 

excreted by Reference Man in a 24-hour period [3].

The excretion data were modeled with IMBA for multiple chronic intakes of type F or type M 210Po. 

Examination of excretion results for polonium indicated that relatively chronic exposures appear to 

have been likely at the start of the polonium program. Therefore, a chronic exposure pattern was 

assumed throughout the program because it also approximates a series of acute intakes with 

unknown intake dates. Intakes were assumed to be via inhalation with a default breathing rate of 

1.2 m3

/hr and a 5-μm activity median aerodynamic diameter (AMAD) particle size distribution [4].

Plutonium Assumptions

All urinary excretion rates were modeled as normally distributed 24-hr urine samples having a uniform 

absolute error of 1, which thus assigned the same weight to each urinary excretion rate. The 

excretion data were modeled with IMBA for multiple chronic intakes of type M and type S plutonium. 

Although it is unlikely that workers at Mound were chronically exposed to plutonium, this approach 

approximates a series of acute intakes with unknown intake dates. Intakes were assumed to be via 

inhalation with a default breathing rate of 1.2 m3

/hr and a 5-μm AMAD particle size distribution [5].

4.2 BIOASSAY FITTING

Polonium Fitting

The excretion data were modeled with IMBA for multiple chronic intakes of type F or type M 210Po. 

Polonium data from 1944 through 1973 were fit as a series of chronic intakes. 

The intake assumptions were based on patterns that were observed in the bioassay data. Periods 

with constant chronic intake rates were chosen by selecting periods during which the bioassay results 

were similar. A new chronic intake period was started if the data indicated a significant sustained 

change in the bioassay results. By this method, the period from 1944 through 1973 was divided into 

several chronic intake periods [6].

Plutonium Fitting 

The excretion data were modeled with IMBA for multiple chronic intakes of type M and type S 

plutonium. Plutonium data from 1956 through 2002 were fit as a series of chronic intakes.

The intake assumptions were based on patterns that were observed in the bioassay data. Periods 

with constant chronic intake rates were chosen by selecting periods during which the bioassay results 

were similar. A new chronic intake period was started if the data indicated a significant sustained 
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 12 of 41

change in the bioassay results. By this method, the period from 1956 through 2002 was divided into 

several chronic intake periods [7].

4.3 MATERIAL TYPES

ORAUT-TKBS-0016-6 discusses Mound internal dosimetry data and includes guidance for the 

appropriate use of that information (ORAUT 2010). According to that document, workers at Mound 

had the potential to receive intakes of polonium and plutonium.

Polonium

Excretion data for the 50th- and 84th-percentile values of 210Po for 1944 through 1973 are shown in 

Table A-1. Note that the third quarter of 1970 was omitted because of poor statistics [8]. The solid 

lines in Figures B-1 and B-2 show the individual fits to the 50th- and 84th-percentile excretion rates, 

respectively, for type M 210Po material. The solid lines in Figures B-3 and B-4 show the individual fits 

to the 50th- and 84th-percentile excretion rates, respectively, for type F 210Po material [9].

Plutonium

Because plutonium of either type S or type M has a very long half-life and the material is retained in 

the body for long periods, excretion results are not independent. For example, an intake in the early 

1950s could contribute to urinary excretion in the 1980s and later. To avoid potential underestimation 

of intakes for people who worked for relatively short periods, each intake period was fit independently 

using only the bioassay results from that intake period. For a particular dose reconstruction, this 

fitting method will result in a best estimate of dose if the person worked in only one period and a 

potential overestimate if an individual worked in multiple periods [10].

Plutonium urinalysis results were analyzed with IMBA using types M and S materials to derive intake 

rates for 1956 to 2002 [11].

Plutonium type M: The solid lines in Figures B-5 to B-10 show the individual fits to the 50thpercentile excretion rates for type M materials. Figure B-11 shows the 50th-percentile predicted 

excretion rates from all type M intakes. The solid lines in Figures B-12 to B-18 show the individual fits 

to the 84th-percentile excretion rates for type M materials. Figure B-19 shows the 84th-percentile 

predicted excretion rates from all type M intakes. The same intake periods were not applied for both 

percentiles because the values followed different patterns [12]. 

Plutonium type S: The solid lines in Figures B-20 to B-25 show the individual fits to the 50thpercentile excretion rates for type S materials. Figure B-26 shows the 50th-percentile predicted 

excretion rates from all type S intakes. The solid lines in Figures B-27 to B-32 show the individual fits 

to the 84th-percentile excretion rates for type S materials [13]. Figure B-33 shows the 84th-percentile 

predicted excretion rates from all type S intakes.

Table A-4 provides the bioassay data that were used for the intake modeling [14]. 

5.0 ASSIGNING INTAKES AND DOSES

This section describes the derived intake rates and provides guidance for assigning doses. For 

tritium, the doses to assign are provided rather than intake rates.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 13 of 41

5.1 INTAKE RATE SUMMARY

Polonium

Five intake periods were fit to the derived 50th- and 84th-percentile polonium excretion data. 

Because many of the geometric standard deviations (GSDs) were relatively similar, they were 

combined and the largest value in a given timeframe was assigned for simplicity [15]. 

The intake rates, GSDs, and periods in which they are applicable are given in Table A-2 for type M 

210Po and Table A-3 for type F 210Po. In most cases, doses for individuals who were potentially 

exposed routinely should be calculated from the 50th-percentile intake rates by assuming the 

solubility type that results in the largest probability of causation (POC)1

. Table 5-1 summarizes the 

derived polonium intake rates that produced the data-fitting results in Attachment B. Note that the 

results in Table 5-1 are in becquerels per day, because the original data were recorded as such [16]. 

If picocuries per day are preferred, divide the Table 5-1 values by 0.037.

Table 5-1. Derived polonium intakes, 1944 to 1973.

Period

Type F material Type M material

50th percentile

(Bq/d) GSD

95th percentile 

(Bq/d)

50th percentile

(Bq/d) GSD

95th percentile 

(Bq/d)

07/1944–03/1946 1,189.5 3.89 11,113 4,097.6 3.9 38,444

04/1946–03/1949 254.96 5.56 4,287 800.19 5.8 14,422

04/1949–03/1960 12.192 7.99 372 39.851 8.0 1,219

04/1960–03/1965 2.0696 6.70 47.3 5.7883 6.2 116

04/1965–12/1973 0.10303 8.88 3.74 0.34853 8.8 12.5

Plutonium

Seven intake periods were fit to the derived 50th- and 84th-percentile plutonium excretion data for 

type M material. Five intake periods were fit to the derived 50th- and 84th-percentile plutonium 

excretion data for type S material. If the GSD was less than 3, the value was set to 3 to account for 

biological variation when determining dose [17].

The intake rates, GSDs, and applicable periods are given in Table A-5 for type M plutonium and 

Table A-6 for type S plutonium. In most cases, doses for individuals who were potentially exposed 

routinely should be calculated from the 50th-percentile intake rates by assuming the solubility type 

that results in the largest POC. Table 5-2 summarizes the derived plutonium intake rates that 

produced the data-fitting results in Attachment B. Note that the results in Table 5-2 are in picocuries

per day, because the original data were recorded as such [18]. If becquerels per day are preferred, 

multiply the Table 5-2 values by 0.037.

Table 5-2. Derived plutonium intake rates, 1956 to 2002.

Period

50th percentile

(pCi/d) GSD

95th percentile 

(pCi/d)

Type M material

1956–1957 750.98 3.00a 4,576

1958–1960 436.49 3.00a 2,659

1961–1967 12.141 5.42 196

1968–1969 12.141 11.69 693

1970–1977 2.2361 9.14 85.2

1978–1984 2.2361 5.82 40.5

1985–1997 0.4106 7.38 11.0

 1 The U.S. Department of Labor is responsible under EEOICPA for determining the POC.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 14 of 41

1998-2002 0.04092 12.31 2.54

Type S material

1956–1957 27,150 3.00a 165,437

1958–1960 12,880 4.11 131,730

1961–1969 209.9 5.12 3,081

1970–1984 31.31 5.12 460

1985–1997 6.141 7.13 155

1998-2002 0.8638 12.32 53.7

a. Actual GSD <3. Adjusted to 3 for dose calculations.

Tritium

Tritium doses rather than intake rates were calculated. Table 5-3 lists the tritium doses and GSDs to 

be used for each year of potential tritium exposure.

Table 5-3. Tritium annual doses 

(rem) and GSDs.

Year Dose GSD

1981 0.001 5.88

1982 0.003 7.71

1983 0.002 8.22

1984 0.001 8.76

1985 0.001 8.69

1986 0.001 8.04

1987 0.001 7.26

1988 0.001 7.34

1989 0.0004 9.49

1990 0.0005 5.95

1991 0.0003 5.24

1992 0.0003 4.89

1993 0.0001 5.35

1994 0.0001 4.79

1995 0.0001 4.34

1996 0.0002 4.74

1997 0.0004 5.85

1998 0.0003 4.30

1999 0.0004 5.12

2000 0.0002 4.40

2001 0.0002 4.28

2002 0.0003 5.99

2003 0.0003 6.88

2004 0.0004 7.68

2005 0.0001 3.03

5.2 DOSE ASSIGNMENT

For most cases, individual doses are calculated from the 50th-percentile intake rates. Dose 

reconstructors should select the material type that is the most favorable to claimants.

The lognormal distribution is selected in the Interactive RadioEpidemiology Program (IREP), with the 

calculated dose entered as Parameter 1 and the associated GSD as Parameter 2. The GSD is 

associated with the intake, so it is applied to all annual doses that are determined from the intake 

period. 
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 15 of 41

There are situations when the 95th percentile of the coworker distribution and a constant distribution 

are more appropriate than the 50th percentile and lognormal GSDs. For cases where the 50thpercentile intake rates are not appropriate, dose reconstructors should use the 95th-percentile intake 

rates. The 95th-percentile intakes should be assigned as a constant rather than lognormal 

distribution.

To calculate doses from plutonium, the intakes of “total Pu” should be classified as either weaponsgrade plutonium (WGPU) or heat-source plutonium (HSPU) using the established protocol for Mound. 

HSPU is assumed to be 100% 238Pu by activity, but determining the isotopic mix of WGPU is more 

complex. Table 5-4 lists three WGPU mixes aged 1, 3.2, and 10 years. These values are taken from 

the technical basis document (ORAUT 2010). If the age of the isotopic mix is not known, the 10-yearaged material should be selected to be favorable to claimants in relation to the ingrowth of 241Am from 

241Pu [19].

Table 5-4. Dose calculations for WGPU intakes.

Material age

(yr)

Percentage of alpha activity

Beta activity

(times APu-239/240)

Pu-239/240 Pu-238 Am-241 Pu-241

1 92.9 6.6 0.55 4.8

3.2 91.6 6.4 2.0 4.3

10 88.4 6.0 5.6 3.1

6.0 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in this document, bracketed callouts have been inserted to indicate information, 

conclusions, and recommendations provided to assist in the process of worker dose reconstruction. 

These callouts are listed here in the Attributions and Annotations section, with information to identify 

the source and justification for each associated item. Conventional References, which are provided in 

the next section of this document, link data, quotations, and other information to documents available 

for review on the Project’s Site Research Database.

Thomas LaBone previously served as a Site Expert for this document. As such, he was responsible 

for advising on site-specific issues and incidents as necessary and ensures the completeness and 

accuracy of the document. Because of his prior work experience for the site, he possesses, or is 

aware of information that is relevant for reconstructing radiation doses experienced by claimants who 

worked at the site. In all cases where such information or prior studies or writings are included or 

relied upon by the document owner, those materials are fully attributed. Mr. LaBone’s Disclosure 

Statement is available at www.oraucoc.org.

[1] Lochamy, Joseph C. ORAU Team. Senior Health Physicist. February 2007.

PORECON records with “R” (Rejected) entries in the PROBLEM_FLG field were not used 

because they had been flagged as unreliable for some reason. Null entries in the results 

(BQ_DAY) field obviously cannot be used, because there are no data to use.

[2] Lochamy, Joseph C. ORAU Team. Senior Health Physicist. February 2007.

PURECON records with nonblank fields for PROBLEM_FLG or DTPA, LNAME=QC, or a blank 

result field were not used because they were unreliable (e.g., nonblank PROBLEM_FLG), not 

representative of normal exposures (e.g., nonblank DTPA entry), a quality control sample 

(e.g., LNAME=QC), or contained no results.

[3] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

The uniform absolute error of 1 weights all results equally; other fitting schemes weight high 

values or low values disproportionally. Because the median and 84th-percentile values were 
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 16 of 41

determined from statistical analysis of many samples in each interval, there was no a priori

reason to weight results from one interval over another. In addition, the polonium results were 

recorded as activity per milliliter and the statistical analyses were performed in those units. 

However, the IMBA software requires that all excreta data be entered as total excretion per 

day; therefore, the statistical parameters were converted to excretion per day before intake 

calculations were made using IMBA. 

[4] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist. The breathing rate and 

particle size distribution are Project default values to be used unless site-specific information 

indicates otherwise. No information has been found about intakes at Mound that shows that 

the default values should not be used. See, for instance, OCAS-IG-002, Internal Dose 

Reconstruction Implementation Guide (NIOSH 2002), and International Commission on 

Radiological Protection (ICRP) Publication 66, Human Respiratory Tract Model for 

Radiological Protection (ICRP 1994).

[5] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist. The breathing rate and 

particle size distribution are Project default values to be used unless site-specific information 

indicates otherwise. No information has been found about intakes at Mound that shows that 

the default values should not be used. See, for instance, OCAS-IG-002, Internal Dose 

Reconstruction Implementation Guide (NIOSH 2002), and ICRP Publication 66, Human 

Respiratory Tract Model for Radiological Protection (ICRP 1994).

[6] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist.

[7] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist.

[8] Mahathy, Michael, and Lochamy, Joseph C. ORAU Team. Coworker Statistics Analyst and 

Senior Health Physicist. February 2007. 

The table was compiled by Lochamy from data that was generated by Mahathy. 

[9] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Figures were generated by LaBone from IMBA results.

[10] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist. 

[11] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of types and 

applications were peer reviewed by the Principal Internal Dosimetrist. 

[12] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Figures were generated by LaBone from IMBA results.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 17 of 41

[13] Arno, Matthew G. ORAU Team. Senior Health Physicist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist. Figures were generated 

by Arno from IMBA results.

[14] LaBone, Thomas R., and Lochamy, Joseph C. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. 

Determinations were made by LaBone in accordance with ORAUT (2005). The tables were 

compiled by Lochamy from data generated by Lochamy. 

[15] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist.

[16] LaBone, Thomas R., Mahathy, Michael, and Lochamy, Joseph C. ORAU Team. Deputy 

Principal Internal Dosimetrist, Coworker Statistics Analyst, and Senior Health Physicist. 

February 2007. 

Determinations were made by LaBone in accordance with ORAUT (2005). The table was 

compiled by Lochamy from data generated by Mahathy.

[17] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made in accordance with ORAUT (2005). The choice of intervals and 

resulting fits were peer reviewed by the Principal Internal Dosimetrist. The minimum GSD of 3 

is established in ORAUT-OTIB-0060, Internal Dose Reconstruction (ORAUT 2007). It reflects 

the overall uncertainty that is associated with biokinetic modeling as well as usual 

radiochemical analysis, and it indicates that even though the spread in coworker excreta 

results for a given population (e.g., a year of excreta samples) can have a GSD of <3, the 

uncertainty of intakes that were determined using the biokinetic models is no less than 3.

[18] LaBone, Thomas R., and Lochamy, Joseph C. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. 

Determinations were made by LaBone in accordance with ORAUT (2005). The tables were 

compiled by Lochamy from data that were generated by Lochamy. 

[19] LaBone, Thomas R., and Lochamy, Joseph C. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. 

Determinations were made by LaBone in accordance with ORAUT (2005) and ORAUT 

(2004b). The table was compiled by Lochamy from ORAUT (2004a).
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 18 of 41

REFERENCES

ICRP (International Commission on Radiological Protection), 1994, Human Respiratory Tract Model 

for Radiological Protection, Publication 66, Pergamon Press, Oxford, England.

Mound (Mound Laboratory), undated a, Polonium Database – PORECON, Miamisburg, Ohio. [SRDB 

Ref ID: 12457]

Mound (Mound Laboratory), undated b, Plutonium Analysis Database – PURECON_MERGED, 

Miamisburg, Ohio. [SRDB Ref ID: 12457]

NIOSH (National Institute for Occupational Safety and Health), 2002, Internal Dose Reconstruction 

Implementation Guideline, OCAS-IG-002, Rev. 0, Office of Compensation Analysis and 

Support, Cincinnati, Ohio, August.

ORAUT (Oak Ridge Associated Universities Team), 2004a, Coworker Data Exposure Profile 

Development, ORAUT-PLAN-0014, Rev. 00, Oak Ridge, Tennessee, November 24.

ORAUT (Oak Ridge Associated Universities Team), 2004b, Tritium Calculated and Missed Dose 

Estimates, ORAUT-OTIB-0011, Rev. 00, Oak Ridge, Tennessee, June 29.

ORAUT (Oak Ridge Associated Universities Team), 2005, Analysis of Coworker Bioassay Data for 

Internal Dose Assignment, ORAUT-OTIB-0019, Rev. 01, Oak Ridge, Tennessee, October 7.

ORAUT (Oak Ridge Associated Universities Team), 2006, Generating Summary Statistics for 

Coworker Bioassay Data, ORAUT-PROC-0095, Rev. 00, Oak Ridge, Tennessee, June 5.

ORAUT (Oak Ridge Associated Universities Team), 2007, Internal Dose Reconstruction, ORAUTOTIB-0060, Rev. 00, Oak Ridge, Tennessee, February 6.

ORAUT (Oak Ridge Associated Universities Team), 2010, Mound Site – Occupational Internal 

Dosimetry, ORAUT-TKBS-0016-5, Rev. 01, Oak Ridge, Tennessee, December 13.
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 19 of 41

Table A-1. 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1973 

(Bq/d).

Effective 50th percentile 84th percentile # of samples # of employees

08/15/1944 8.33E+01 5.07E+02 531 48

11/15/1944 8.89E+01 3.56E+02 618 59

02/15/1945 1.01E+02 2.97E+02 716 72

05/15/1945 1.39E+02 5.13E+02 887 162

08/15/1945 5.17E+01 2.03E+02 1,582 241

11/15/1945 5.45E+01 2.27E+02 1,917 272

02/15/1946 4.56E+01 1.99E+02 2,052 289

05/15/1946 8.63E+01 2.92E+02 937 205

08/15/1946 2.10E+01 1.04E+02 2,277 333

11/15/1946 1.88E+01 9.53E+01 2,162 324

02/15/1947 9.26E+00 6.78E+01 2,541 362

05/15/1947 1.01E+01 6.84E+01 2,520 396

08/15/1947 1.32E+01 8.68E+01 3,027 486

11/15/1947 2.16E+01 1.10E+02 3,578 500

02/15/1948 3.18E+01 1.71E+02 4,247 553

05/15/1948 2.62E+01 1.36E+02 3,540 560

08/15/1948 1.52E+01 8.99E+01 3,395 556

11/15/1948 1.90E+01 1.23E+02 3,482 476

02/15/1949 7.12E+00 7.36E+01 3,220 517

05/15/1949 2.88E+00 2.27E+01 4,342 803

08/15/1949 2.77E+00 2.02E+01 3,919 773

11/15/1949 2.29E+00 2.00E+01 4,818 796

02/15/1950 1.43E+00 1.39E+01 4,907 786

05/15/1950 7.55E-01 8.97E+00 4,490 750

08/15/1950 7.96E-01 7.03E+00 4,138 739

11/15/1950 6.05E-01 8.06E+00 4,281 728

02/15/1951 1.02E+00 7.32E+00 4,269 708

05/15/1951 1.30E+00 9.08E+00 4,258 729

08/15/1951 1.41E+00 8.73E+00 4,085 735

11/15/1951 1.10E+00 7.89E+00 4,578 745

02/15/1952 1.25E+00 6.68E+00 4,822 733

05/15/1952 9.10E-01 5.33E+00 4,450 761

08/15/1952 7.03E-01 4.84E+00 4,380 784

11/15/1952 1.18E+00 7.19E+00 4,616 759

02/15/1953 1.05E+00 7.53E+00 4,814 767

05/15/1953 9.60E-01 5.68E+00 2,541 582

08/15/1953 1.03E+00 4.51E+00 1,975 479

11/15/1953 4.56E-01 4.09E+00 1,555 420

02/15/1954 7.22E-01 6.44E+00 844 210

05/15/1954 1.47E+00 6.37E+00 690 184

08/15/1954 3.24E+00 9.88E+00 482 154

11/15/1954 1.41E+00 8.96E+00 576 131

02/15/1955 1.62E+00 5.72E+00 470 126

05/15/1955 5.26E-01 2.62E+00 418 96

08/15/1955 5.54E-01 3.90E+00 421 91

11/15/1955 9.41E-01 1.26E+01 432 88

02/15/1956 4.31E-01 7.80E+00 498 95

ATTACHMENT A

COWORKER DATA TABLES

Page 1 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 20 of 41

Effective 50th percentile 84th percentile # of samples # of employees

05/15/1956 8.55E-01 5.51E+00 424 75

08/15/1956 1.78E-01 2.44E+00 452 90

11/15/1956 6.41E-02 3.01E+00 551 106

02/15/1957 2.98E-01 6.07E+00 562 111

05/15/1957 4.53E-02 2.09E+00 541 113

08/15/1957 4.34E-01 3.23E+00 569 97

11/15/1957 6.68E-01 6.92E+00 616 125

02/15/1958 9.75E-01 6.67E+00 716 145

05/15/1958 1.00E+00 1.20E+01 704 129

08/15/1958 6.22E-01 9.34E+00 577 123

11/15/1958 6.82E-01 8.50E+00 739 137

02/15/1959 1.37E+00 1.28E+01 751 138

05/15/1959 1.32E+00 7.19E+00 778 173

08/15/1959 9.35E-01 7.44E+00 703 169

11/15/1959 1.32E+00 1.08E+01 969 186

02/15/1960 6.88E-01 6.49E+00 1,142 215

05/15/1960 4.01E-01 4.16E+00 1,256 224

08/15/1960 5.34E-01 4.58E+00 1,266 231

11/15/1960 5.92E-01 4.91E+00 1,450 247

02/15/1961 6.98E-01 6.04E+00 1,498 244

05/15/1961 5.02E-01 3.75E+00 1,529 263

08/15/1961 4.12E-01 2.57E+00 1,553 259

11/15/1961 2.89E-01 2.33E+00 1,882 287

02/15/1962 2.51E-01 1.42E+00 2,016 293

05/15/1962 3.46E-01 1.98E+00 1,938 282

08/15/1962 4.88E-01 2.63E+00 1,760 293

11/15/1962 1.85E-01 1.80E+00 2,023 301

02/15/1963 2.09E-01 1.57E+00 1,721 287

05/15/1963 9.66E-02 7.90E-01 1,813 297

08/15/1963 9.01E-02 5.51E-01 2,158 336

11/15/1963 3.38E-01 1.66E+00 2,183 343

02/15/1964 4.71E-02 2.68E-01 2,114 317

05/15/1964 1.86E-02 1.56E-01 2,156 318

08/15/1964 4.43E-02 2.03E-01 2,030 319

11/15/1964 4.35E-02 2.00E-01 2,059 307

02/15/1965 3.60E-02 1.33E-01 2,185 319

05/15/1965 1.90E-02 6.91E-02 1,762 284

08/15/1965 3.27E-02 1.07E-01 1,506 288

11/15/1965 1.34E-02 7.85E-02 1,634 295

02/15/1966 8.63E-03 4.57E-02 1,798 287

05/15/1966 1.12E-02 5.53E-02 1,599 287

08/15/1966 1.53E-02 9.59E-02 1,605 305

11/15/1966 1.77E-02 8.22E-02 1,657 296

02/15/1967 2.11E-02 7.49E-02 1,901 315

05/15/1967 9.13E-03 4.15E-02 1,942 307

08/15/1967 2.00E-03 2.33E-02 1,757 317

11/15/1967 7.77E-04 2.24E-02 1,927 311

02/15/1968 4.09E-03 5.91E-02 1,702 288

05/15/1968 1.30E-02 9.17E-02 1,866 312

ATTACHMENT A

Page 1 of 6

ATTACHMENT A

COWORKER DATA TABLES

Page 2 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 21 of 41

Effective 50th percentile 84th percentile # of samples # of employees

08/15/1968 2.19E-03 1.24E-01 1,555 267

11/15/1968 7.16E-03 9.72E-02 1,313 264

02/15/1969 1.87E-03 2.55E-02 1,286 248

05/15/1969 5.10E-03 2.35E-02 747 153

08/15/1969 1.14E-03 1.15E-02 582 135

11/15/1969 3.99E-05 1.58E-03 572 116

02/15/1970 1.45E-03 9.66E-03 500 116

05/15/1970 1.37E-02 4.73E-02 272 88

11/15/1970 2.20E-02 6.67E-02 98 25

07/01/1971 5.96E-04 1.52E-02 353 56

07/01/1972 1.06E-02 2.40E-01 73 13

07/01/1973 4.38E-03 4.61E-01 30 3

Table A-2. Type M 210Po intake rates (Bq/d) and dates.

Start End 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 4097.6 15796 3.9

04/01/1946 03/31/1949 800.19 4602.3 5.8

04/01/1949 03/31/1960 39.851 320.28 8.0

04/01/1960 03/31/1965 5.7883 36.121 6.2

04/01/1965 12/31/1973 0.34853 3.0638 8.8

Table A-3. Type F 210Po intake rates (Bq/d) and dates.

Start End 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 1189.5 4628 3.89

04/01/1946 03/31/1949 254.96 1416.8 5.56

04/01/1949 03/31/1960 12.192 97.456 7.99

04/01/1960 03/31/1965 2.0696 13.856 6.70

04/01/1965 12/31/1973 0.10303 0.91451 8.88

Table A-4. 50th- and 84th-percentile urinary excretion rates of total plutonium,

1956 to 2002 (pCi/d).

Effective 50th percentile 84th percentile # of samples # of employees

07/01/1956 1.88E+00 4.49E+00 38 7

07/01/1957 2.26E+00 4.03E+00 86 19

07/01/1958 1.14E+00 2.00E+00 77 32

07/01/1959 1.53E+00 2.73E+00 99 32

07/01/1960 1.72E+00 9.81E+00 336 89

07/01/1961 8.01E-02 6.50E-01 792 178

02/15/1962 3.49E-02 2.25E-01 351 174

05/15/1962 7.15E-02 4.42E-01 338 169

08/15/1962 1.01E-01 3.63E-01 296 186

11/15/1962 1.06E-01 4.27E-01 390 205

02/15/1963 5.31E-02 2.88E-01 356 183

05/15/1963 7.53E-02 5.73E-01 553 317

08/15/1963 5.19E-02 3.41E-01 558 319

11/15/1963 7.01E-02 3.65E-01 535 327

02/15/1964 8.98E-02 3.53E-01 606 316

05/15/1964 1.19E-01 3.64E-01 674 408

08/15/1964 1.18E-01 3.62E-01 585 381

ATTACHMENT A

COWORKER DATA TABLES

Page 3 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 22 of 41

Effective 50th percentile 84th percentile # of samples # of employees

11/15/1964 1.59E-01 6.00E-01 755 443

02/15/1965 1.03E-01 5.95E-01 857 460

05/15/1965 1.07E-01 5.11E-01 835 492

08/15/1965 1.07E-01 5.58E-01 783 477

11/15/1965 5.56E-02 2.62E-01 723 474

02/15/1966 9.62E-02 3.70E-01 726 435

05/15/1966 7.11E-02 2.94E-01 897 578

08/15/1966 7.09E-02 2.29E-01 957 603

11/15/1966 8.56E-02 2.87E-01 954 567

02/15/1967 7.68E-02 2.87E-01 1,086 640

05/15/1967 8.63E-02 3.37E-01 791 515

08/15/1967 7.38E-02 2.91E-01 826 544

11/15/1967 4.86E-02 2.27E-01 911 550

02/15/1968 5.01E-02 2.17E-01 834 498

05/15/1968 7.91E-02 2.70E-01 769 476

08/15/1968 6.23E-02 2.26E-01 541 297

11/15/1968 4.47E-02 2.67E-01 670 363

02/15/1969 5.42E-02 4.69E-01 680 310

05/15/1969 5.14E-02 3.87E-01 674 351

08/15/1969 8.76E-02 8.74E-01 579 278

11/15/1969 4.45E-02 2.63E-01 489 246

02/15/1970 2.42E-02 1.47E-01 659 398

05/15/1970 3.27E-02 1.75E-01 632 370

08/15/1970 2.93E-02 1.31E-01 626 373

11/15/1970 1.98E-02 9.93E-02 796 484

02/15/1971 2.90E-02 1.64E-01 608 399

05/15/1971 2.03E-02 1.16E-01 629 416

08/15/1971 2.21E-02 1.15E-01 484 339

11/15/1971 2.77E-02 1.46E-01 540 375

02/15/1972 2.83E-02 1.62E-01 708 392

05/15/1972 2.01E-02 1.15E-01 653 387

08/15/1972 2.05E-02 1.21E-01 685 389

11/15/1972 2.21E-02 1.27E-01 533 360

02/15/1973 3.80E-02 1.80E-01 517 376

05/15/1973 3.32E-02 1.40E-01 502 354

08/15/1973 2.29E-02 1.08E-01 535 387

11/15/1973 1.21E-02 8.04E-02 525 369

02/15/1974 3.65E-02 1.41E-01 545 364

05/15/1974 4.34E-02 1.91E-01 453 328

08/15/1974 3.70E-02 1.83E-01 532 366

11/15/1974 4.74E-02 2.06E-01 407 296

02/15/1975 1.10E-02 7.75E-02 510 339

05/15/1975 1.13E-02 9.84E-02 499 326

08/15/1975 3.49E-02 1.69E-01 199 153

11/15/1975 1.71E-02 8.51E-02 320 273

02/15/1976 3.49E-02 1.66E-01 283 195

05/15/1976 1.19E-02 7.15E-02 327 246

08/15/1976 1.46E-02 6.91E-02 261 204

ATTACHMENT A

COWORKER DATA TABLES

Page 4 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 23 of 41

Effective 50th percentile 84th percentile # of samples # of employees

11/15/1976 1.80E-02 8.28E-02 278 213

02/15/1977 2.13E-02 9.59E-02 347 250

05/15/1977 2.13E-02 9.50E-02 294 233

08/15/1977 1.15E-02 7.02E-02 350 268

11/15/1977 1.56E-02 8.01E-02 278 227

02/15/1978 7.79E-03 4.92E-02 370 294

05/15/1978 4.68E-03 4.20E-02 298 236

08/15/1978 4.44E-03 2.99E-02 371 297

11/15/1978 8.12E-03 6.62E-02 272 231

02/15/1979 2.78E-03 2.96E-02 385 326

05/15/1979 6.74E-03 5.00E-02 304 246

08/15/1979 1.80E-02 7.82E-02 293 260

11/15/1979 7.70E-03 6.01E-02 210 196

02/15/1980 6.84E-03 4.16E-02 334 287

05/15/1980 1.77E-02 9.15E-02 268 237

08/15/1980 1.80E-02 7.22E-02 294 255

11/15/1980 2.41E-02 1.33E-01 284 235

02/15/1981 2.22E-02 1.06E-01 346 284

05/15/1981 2.63E-02 8.57E-02 323 282

08/15/1981 2.02E-02 9.85E-02 274 243

11/15/1981 2.17E-02 1.17E-01 283 247

02/15/1982 1.89E-02 9.22E-02 301 249

05/15/1982 9.69E-03 5.85E-02 340 301

08/15/1982 1.23E-02 7.39E-02 279 244

11/15/1982 2.97E-02 9.91E-02 269 243

02/15/1983 1.24E-02 6.12E-02 243 205

05/15/1983 1.24E-02 7.51E-02 365 308

08/15/1983 1.08E-02 6.97E-02 290 252

11/15/1983 7.71E-03 5.37E-02 310 287

02/15/1984 9.94E-03 5.88E-02 289 250

05/15/1984 1.22E-02 6.80E-02 339 304

08/15/1984 7.50E-03 4.01E-02 316 263

11/15/1984 8.39E-03 4.20E-02 315 283

02/15/1985 2.49E-03 2.29E-02 325 284

05/15/1985 3.05E-03 2.84E-02 363 319

08/15/1985 1.12E-03 1.44E-02 368 300

11/15/1985 1.28E-03 1.51E-02 266 249

02/15/1986 2.25E-03 2.05E-02 359 292

05/15/1986 3.86E-03 3.76E-02 316 275

08/15/1986 3.09E-03 2.71E-02 318 280

11/15/1986 4.11E-03 3.44E-02 147 136

02/15/1987 6.20E-03 3.27E-02 239 232

05/15/1987 6.85E-03 4.20E-02 173 168

08/15/1987 4.05E-03 2.85E-02 205 201

11/15/1987 4.61E-03 3.01E-02 200 197

02/15/1988 5.23E-03 3.55E-02 189 185

05/15/1988 5.50E-03 3.60E-02 211 202

08/15/1988 3.47E-03 2.52E-02 183 179

ATTACHMENT A

COWORKER DATA TABLES

Page 5 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 24 of 41

Effective 50th percentile 84th percentile # of samples # of employees

11/15/1988 2.65E-03 3.32E-02 199 185

02/15/1989 3.17E-03 3.06E-02 178 164

05/15/1989 3.90E-03 3.11E-02 204 201

08/15/1989 1.88E-03 1.83E-02 235 183

11/15/1989 1.23E-03 1.66E-02 300 247

02/15/1990 1.16E-03 1.52E-02 340 283

05/15/1990 1.27E-03 1.40E-02 288 242

08/15/1990 6.78E-04 1.07E-02 411 360

11/15/1990 1.83E-03 1.18E-02 350 286

7/1/1991 2.83E-03 1.44E-02 1612 712

7/1/1992 1.94E-03 1.08E-02 2211 1131

7/1/1993 1.07E-03 5.51E-03 2108 915

7/1/1994 9.79E-04 4.55E-03 2404 1149

7/1/1995 1.64E-03 7.26E-03 1799 797

7/1/1996 2.18E-03 8.09E-03 678 255

7/1/1997 1.30E-03 6.60E-03 834 233

7/1/1998 3.18E-04 3.67E-03 847 205

7/1/1999 1.92E-04 2.77E-03 756 256

7/1/2000 2.02E-04 2.31E-03 1033 329

7/1/2001 1.95E-04 2.26E-03 787 258

7/1/2002 1.32E-04 1.73E-03 577 321

Table A-5. Type M plutonium intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

01/01/1956 12/31/1957 750.98 1,073.4 1.43a

01/01/1958 12/31/1960 436.49 1,073.4 2.46a

01/01/1961 12/31/1967 12.141 65.823 5.42

01/01/1968 12/31/1969 12.141 141.98 11.69

01/01/1970 12/31/1977 2.2361 20.445 9.14

01/01/1978 12/31/1984 2.2361 13.013 5.82

01/01/1985 12/31/1997 0.4106 3.03 7.38

1/1/1998 12/31/2002 0.04092 0.5039 12.31

a. Actual. Adjust all GSD <3 to 3 for dose calculations.

Table A-6. Type S plutonium intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

01/01/1956 12/31/1957 27,150 52,240 1.92a

1/1/1958 12/31/1960 12,880 53,000 4.11

1/1/1961 12/31/1969 209.9 1,301 4.91

1/1/1970 12/31/1984 31.31 160.2 5.12

1/1/1985 12/31/1997 6.141 43.77 7.13

1/1/1998 12/31/2002 0.8638 10.64 12.32

a. Actual. Adjust all GSD <3 to 3 for dose calculations.

ATTACHMENT A

COWORKER DATA TABLES

Page 6 of 6
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 25 of 41

Figure B-1. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M 210Po.

Figure B-2. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming inhalation 

intakes of type M 210Po.

ATTACHMENT B

COWORKER DATA FIGURES

Page 1 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 26 of 41

Figure B-3. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type F 210Po.

Figure B-4. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming inhalation 

intakes of type F 210Po.

ATTACHMENT B

COWORKER DATA FIGURES

Page 2 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 27 of 41

Figure B-5. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M plutonium, 1956 to 1957.

Figure B-6. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M plutonium, 1958 to 1960.

ATTACHMENT B

COWORKER DATA FIGURES

Page 3 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 28 of 41

Figure B-7. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M plutonium, 1961 to 1969.

Figure B-8. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M plutonium, 1970 to 1984.

ATTACHMENT B

COWORKER DATA FIGURES

Page 4 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 29 of 41

Figure B-9. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming inhalation 

intakes of type M plutonium, 1985 to 1997.

Figure B-10. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1998 to 2002.

ATTACHMENT B

COWORKER DATA FIGURES

Page 5 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 30 of 41

Figure B-11. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1956 to 2002.

Figure B-12. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1956 to 1960.

ATTACHMENT B

COWORKER DATA FIGURES

Page 6 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 31 of 41

Figure B-13. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1961 to 1967.

Figure B-14. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1968 to 1969.

ATTACHMENT B

COWORKER DATA FIGURES

Page 7 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 32 of 41

Figure B-15. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1970 to 1977.

Figure B-16. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1978 to 1984.

ATTACHMENT B

COWORKER DATA FIGURES

Page 8 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 33 of 41

Figure B-17. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1985 to 1997.

Figure B-18. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1998 to 2002.

ATTACHMENT B

COWORKER DATA FIGURES

Page 9 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 34 of 41

Figure B-19. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming 

inhalation intakes of type M plutonium, 1956 to 2002.

Figure B-20. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1956 to 1957.

ATTACHMENT B

COWORKER DATA FIGURES

Page 10 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 35 of 41

Figure B-21. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1958 to 1960.

Figure B-22. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1961 to 1969.

ATTACHMENT B

COWORKER DATA FIGURES

Page 11 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 36 of 41

Figure B-23. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1970 to 1984.

Figure B-24. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1985 to 1997.

ATTACHMENT B

COWORKER DATA FIGURES

Page 12 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 37 of 41

Figure B-25. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1998 to 2002.

Figure B-26. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1956 to 2002.

ATTACHMENT B

COWORKER DATA FIGURES

Page 13 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 38 of 41

Figure B-27. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1956 to 1957.

Figure B-28. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1958 to 1960.

ATTACHMENT B

COWORKER DATA FIGURES

Page 14 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 39 of 41

Figure B-29. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1961 to 1969.

Figure B-30. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1970 to 1984.

ATTACHMENT B

COWORKER DATA FIGURES

Page 15 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 40 of 41

Figure B-31. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1985 to 1997.

Figure B-32. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1998 to 2002.

ATTACHMENT B

COWORKER DATA FIGURES

Page 16 of 17
Document No. ORAUT-OTIB-0061 Revision No. 02 Effective Date: 04/13/2012 Page 41 of 41

Figure B-33. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type S plutonium, 1956 to 2002.

ATTACHMENT B

COWORKER DATA FIGURES

Page 17 of 17