Page 1 of 60

DOE Review Release 08/28/2020

Internal Dosimetry Co-Exposure Data for the 

Mound Plant

ORAUT-OTIB-0061 Rev. 04

Effective Date: 09/01/2020

Supersedes: Revision 03

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

Document Owner 

Approval: Signature on File

Robert Leib, Document Owner

Approval Date: 04/03/2020

Concurrence: Signature on File

John M. Byrne, Objective 1 Manager

Concurrence Date: 04/03/2020

Concurrence: Signature on File

Joel Arana, Objective 3 Representative

Concurrence Date: 04/03/2020

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 04/03/2020

Approval: Signature on File

Grady J. Calhoun, Director, DCAS

Approval Date: 08/04/2020

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.

New Total Rewrite Revision Page Change
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 2 of 60

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 Program Evaluation Report 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.

08/14/2018 03 Revision initiated to incorporate an evaluation of MHI absorption type 

for 238Pu. Sections 4.1.2, 4.2.2, 4.3.2, 5.1.2, and Attachment A 

revised. 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.

09/01/2020 04 Revision initiated to include adding the potential and intake rates for 

type SS plutonium. No changes needed as a result of formal internal 

review. Incorporates formal 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. 04 Effective Date: 09/01/2020 Page 3 of 60

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 7

1.0 Introduction .............................................................................................................................. 8

1.1 Purpose........................................................................................................................ 8

1.2 Scope........................................................................................................................... 8

2.0 Data Overview ......................................................................................................................... 9

2.1 Data Selection .............................................................................................................. 9

2.1.1 Polonium........................................................................................................ 9

2.1.2 Plutonium..................................................................................................... 10

2.1.3 Tritium.......................................................................................................... 11

2.2 Analysis...................................................................................................................... 11

2.2.1 Polonium...................................................................................................... 11

2.2.2 Plutonium..................................................................................................... 12

2.2.3 Tritium.......................................................................................................... 12

3.0 Intake Modeling...................................................................................................................... 13

3.1 Assumptions............................................................................................................... 13

3.1.1 Polonium...................................................................................................... 13

3.1.2 Plutonium..................................................................................................... 13

3.2 Bioassay Fitting .......................................................................................................... 13

3.2.1 Polonium...................................................................................................... 13

3.2.2 Plutonium..................................................................................................... 14

3.3 Material Types............................................................................................................ 14

3.3.1 Polonium...................................................................................................... 14

3.3.2 Plutonium..................................................................................................... 14

4.0 Assigning Intakes and Doses ................................................................................................. 15

4.1 Polonium .................................................................................................................... 15

4.2 Plutonium ................................................................................................................... 16

4.3 Tritium ........................................................................................................................ 18

5.0 Attributions and Annotations .................................................................................................. 18

References ........................................................................................................................................ 21

ATTACHMENT A CO-EXPOSURE DATA TABLES .................................................................... 22

ATTACHMENT B CO-EXPOSURE DATA FIGURES .................................................................. 29

LIST OF TABLES

TABLE TITLE PAGE

4-1 Derived polonium intake rates for types F and M 210Po, 1944 to 1973.................................... 16

4-2 Derived plutonium intake rates for types M, S, MHI, and SS plutonium, 1956 to 2002 ........... 17

4-3 Dose calculations for WGPu intakes ...................................................................................... 17

4-4 Tritium annual doses and GSDs............................................................................................. 18
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A-1 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1973................................ 23

A-2 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 2002 ................. 25

A-3 Type M 210Po intake rates and dates ...................................................................................... 27

A-4 Type F 210Po intake rates and dates....................................................................................... 28

A-5 Type M plutonium intake rates and dates............................................................................... 28

A-6 Type S plutonium intake rates and dates ............................................................................... 28

A-7 Type MHI 238Pu intake rates and dates................................................................................... 28

A-8 Type SS 238Pu intake rates and dates .................................................................................... 28

LIST OF FIGURES

FIGURE TITLE PAGE

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

type M 210Po...........................................................................................................................32

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

type M 210Po...........................................................................................................................32

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

type F 210Po............................................................................................................................33

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

type F 210Po............................................................................................................................33

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

type M plutonium, 1956 to 1957 ............................................................................................. 34

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

type M plutonium, 1958 to 1960 ............................................................................................. 34

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

type M plutonium, 1961 to 1969 ............................................................................................. 35

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

type M plutonium, 1970 to 1984 ............................................................................................. 35

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

type M plutonium, 1985 to 1997 ............................................................................................. 36

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

type M plutonium, 1998 to 2002 ............................................................................................. 36

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

type M plutonium, 1956 to 2002 ............................................................................................. 37

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

type M plutonium, 1956 to 1960 ............................................................................................. 37

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

type M plutonium, 1961 to 1967 ............................................................................................. 38

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

type M plutonium, 1968 to 1969 ............................................................................................. 38

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

type M plutonium, 1970 to 1977 ............................................................................................. 39

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

type M plutonium, 1978 to 1984 ............................................................................................. 39

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

type M plutonium, 1985 to 1997 ............................................................................................. 40

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

type M plutonium, 1998 to 2002 ............................................................................................. 40

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

type M plutonium, 1956 to 2002 ............................................................................................. 41
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B-20 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 41

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

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 42

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

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 42

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

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 43

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

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 43

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

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 44

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

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 44

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

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 45

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

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 45

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

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 46

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

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 46

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

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 47

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

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 47

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

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 48

B-34 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 1957 .................................................................. 48

B-35 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1958 to 1960 .................................................................. 49

B-36 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1961 to 1969 .................................................................. 49

B-37 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1970 to 1984 .................................................................. 50

B-38 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1985 to 1997 .................................................................. 50

B-39 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1998 to 2002 .................................................................. 51

B-40 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 2002 .................................................................. 51

B-41 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 1957 .................................................................. 52

B-42 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1958 to 1960 .................................................................. 52

B-43 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1961 to 1969 .................................................................. 53

B-44 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1970 to 1984 .................................................................. 53

B-45 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1985 to 1997 .................................................................. 54
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B-46 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1998 to 2002 .................................................................. 54

B-47 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 2002 .................................................................. 55

B-48 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 1957............................................................. 55

B-49 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1958 to 1960............................................................. 56

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

inhalation intake of type SS plutonium, 1961 to 1969............................................................. 56

B-51 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1970 to 1984............................................................. 56

B-52 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1985 to 1997............................................................. 57

B-53 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1998 to 2002............................................................. 57

B-54 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 2002............................................................. 57

B-55 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 1957............................................................. 58

B-56 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1958 to 1960............................................................. 58

B-57 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1961 to 1969............................................................. 58

B-58 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1970 to 1984............................................................. 59

B-59 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1985 to 1997............................................................. 59

B-60 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1998 to 2002............................................................. 59

B-61 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 2002............................................................. 60
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ACRONYMS AND ABBREVIATIONS 

AMAD activity median aerodynamic diameter

AWE atomic weapons employer

Bq becquerel

d day

DOE U.S. Department of Energy

DTPA diethylene triamine pentaacetic acid

F fast (absorption type)

GM geometric mean

GSD geometric standard deviation

hr hour

HSPu heat-source plutonium

HTO tritiated water vapor

ICRP International Commission on Radiological Protection

IDOT Internal Dosimetry Tool

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

m meter

M moderate (absorption type)

MESH Mound Environmental Safety and Health (database)

MHI Mound highly insoluble

mL milliliter

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

pCi picocurie

S slow (absorption type)

SS super slow (absorption type)

SRDB Ref ID Site Research Database Reference Identification (number)

TIB technical information bulletin

USC United States Code

WGPu weapons-grade plutonium

yr year
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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 

historical background information and guidance to assist in 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), such as changing scientific understanding of operations, 

processes, or procedures involving radioactive materials. TIBs may be used to assist NIOSH staff in 

the completion of individual dose reconstructions.

In this document the word “facility” is used to refer to an area, building, or group of buildings that 

served a specific purpose at a U.S. Department of Energy (DOE) or Atomic Weapons Employer 

(AWE) facility. It does not mean, nor should it be equated to, an “AWE facility” or a “DOE facility.” The 

terms AWE and DOE facility are defined in 42 United States Code (USC) 7384l(5) and (12) of the 

Energy Employees Occupational Illness Compensation Program Act of 2000, respectively. 

1.1 PURPOSE

Some employees at the Mound Plant 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 co-exposure 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 had the potential for unmonitored intakes of 210Po, plutonium, or tritium.

1.2 SCOPE

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 co-exposure 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 for the Mound Plant were obtained through the PORECON (Polonium 

Reconstruction) and PURECON (Plutonium Reconstruction) databases, which were created from 

logbooks and other original hard-copy records. Based on a spot check, this dataset 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 were retrieved from the Mound Environmental Safety and Health (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 

facilitate 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) or Internal Dosimetry Tool (IDOT) to obtain intake rates for assigning dose 

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

justification, or clarification of the associated information, are presented in Section 5.0.

2.0 DATA OVERVIEW

This section provides information on the general selection characteristics of the urinalysis 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 210Po 

and 3

H nuclides is provided in Section 3.0.

2.1 DATA SELECTION

For all assessed nuclides, data were extracted from Mound-developed databases. Discussion of the 

creation and/or quality assurance testing of these databases can be found in MJW [2002]. Details of 

the specific datasets are discussed in the following sections.

Typically, the bioassay databases did not include incident information, so results associated with 

incidents were not explicitly excluded from the analyses. In general, the philosophy for the coexposure studies is that if results are in line with other samples from the time, then they are 

representative of worker intakes regardless of whether they were associated with an identified 

incident. The exception is when a result is much larger than the next highest result (e.g., an order of 

magnitude or more; this was applied subjectively); such a result would be excluded as not 

representative of the exposure potential for the general workforce.

2.1.1 Polonium

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

no date a), dbo_SAMPLES table, BQ_DAY field. In this case, verified means 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. Mound data entry clerks 

entered the data using double-entry methods. After that, data entry was reviewed by Mound 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 (e.g., vacation, illness),

• 1,595 insufficient volume,

• 1,685 duplicates or recounts,

• 162 submitted too late,

• 36 contaminated samples,

• 79 marked as beta counts, and

• 56 with no result and blank or cryptic comment.

Note that in many of the above cases, there is no associated result and the bulleted item is the site’s 

explanation of why the result is missing. This includes lost in processing, no sample submitted, 

insufficient volume, and submitted too late. The exclusion of recounts and duplicates was based on 

the site’s entry of “R” in the problem flag field of a given result, indicating that the result should be 

rejected. These were primarily due to the collection of several individual spot samples in a 24-hour 

period when an intake was suspected. Each was analyzed and reported individually. This was a 
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relatively frequent occurrence in some periods, and it was felt that too much weight would be put on a 

few samples if each result was included in the analysis.

2.1.2 Plutonium

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 no 

date b). 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,

• 2,307 DTPA (265 of which had a problem flag),

• 140 contaminated,

• 453 lost in processing (e.g., sample spilled, tracer not added, low recovery),

• 10 insufficient volume,

• 46 no result, no clear reason, and

• 137 with blank or cryptic comment.

Note that in some of the above cases, there is no associated result and the bulleted item is the site’s 

explanation of why the result is missing. This includes lost in processing and submitted too late. There 

were far fewer duplicates and recounts than in PORECON, and they were not marked as such in the 

plutonium database. Because there were so few, it was assumed that their inclusion would have little 

effect on the outcome and they were not excluded from the analysis.

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 the following (or equivalents):

• “No cert,”

• “Baseline,”

• “Pre-job,”

• “New hire,”

• “Background,”

• “Do not verify,” and

• “Re-work.”

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

records should not be used. Examples include “Wrong calcs. Don’t use,” “Void. Sample counted with 

wrong tracer,” “Void - do not certify,” “TH Contam - NO Cert,” “test/learning sample,” “Spectrum is 
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‘dirty’ - Recount,” “Nose wipe,” “sample ID switched, count results questionable,” and “low recovery--

do not verify.”

2.1.3 Tritium

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. The database contained 212,522 samples from 2,669 individuals.

It was not necessary to remove recounts and duplicates because ORAUT-OTIB-0011, Technical 

Information Bulletin: Tritium Calculated and Missed Dose Estimates [ORAUT 2004b), was used for 

the dose assessments. Sample times were taken into account. If multiple results had the same count 

date and time, the lower value was used to calculate the dose in the previous interval and the higher 

value was used in the subsequent interval.

2.2 ANALYSIS

This section describes the statistical analyses that were performed on the urine bioassay datasets 

described in Section 2.1 in preparation for intake assessments, which are described in Section 3.0. As 

noted in the previous section, ORAUT [2004b] was used for the tritium analysis because, due to the 

biokinetic and short retention time, dose assessments can easily be performed for each individual.

This is not the case for other nuclides, so the bioassay data were first analyzed and then doses 

assessed as though the data came from a single individual. ORAUT-PROC-0095, Generating 

Summary Statistics for Coworker Bioassay Data [ORAUT 2006], was used in the generation of the 

geometric mean (GM) and geometric standard deviation (GSD) of the polonium and plutonium 

datasets. The 84th percentile of the data was also calculated but used only for the determination of 

the GSD; it was not used to assign intakes.

2.2.1 Polonium

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

1971 through part of 1973. The analysis period was changed due to a decrease in the amount of 

available data. 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 

by Mound 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-0016-5, Mound Site – Occupational Internal Dosimetry [ORAUT 

2017], which specifies a recovery efficiency of 10% (instead of 85%) for this period. A factor of 1.35 

was applied to results from 1964 through 1973, again according to ORAUT-TKBS-0016-5, which 

specifies a recovery efficiency of 63% (instead of 85%) for this period.

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

excretion rates were calculated using the ORAUT-PROC-0095 method [ORAUT 2006]. These 

excretion rates are given in Table A-1. Bioassay data that were collected over a specified period were 

analyzed to determine the 50th- and 84th-percentile excretion rates for that period. The effective 
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bioassay dates are the midpoints of the periods, and they were used with IMBA to calculate the intake 

rates.

2.2.2 Plutonium

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 2017]. 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 listed volume 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 238Pu and 239Pu. 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 Laboratory Identification Number (denoted LIN) 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 ORAUT-PROC-0095 method [ORAUT 2006]. These 

excretion rates are given in Table A-2. Bioassay data from 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.

2.2.3 Tritium

Tritium was evaluated differently than the other radionuclides in this co-exposure study. For tritium, 

the protocol in ORAUT-OTIB-0011 [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 

(GM, GSD, and R2

) were determined from a linear regression. Individuals who 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 the i/n − 1/(2n) convention in ORAUT-PROC0095 [ORAUT 2006]. 
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 13 of 60

3.0 INTAKE MODELING

This section discusses intake modeling assumptions, fitting, and materials for 210Po and plutonium.

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

discussed above for tritium directly calculates individual doses.

The modeled material types were those that the International Commission on Radiological Protection

(ICRP) has assigned to each element and that workers at Mound might have encountered as 

discussed in ORAUT [2017]. With the exception of a special-case type (MHI) for very insoluble 

plutonium, discussed in the plutonium sections, other material types are not addressed.

3.1 ASSUMPTIONS

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 [3].

3.1.1 Polonium

Each urinary excretion rate 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, 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.

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 occurred 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.

3.1.2 Plutonium

All urinary excretion rates were modeled as normally distributed 24-hour 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 or IDOT for multiple chronic intakes of type M and type S 

plutonium, type MHI for 238Pu only [NIOSH 2016], and type SS for 239Pu only. This approach 

approximates a series of acute intakes with unknown intake dates.

3.2 BIOASSAY FITTING

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 an observable sustained 

change in the bioassay results. This fitting is subjective, but a general rule of thumb is to group results 

that are within about a factor of 2 of the average excretion rate of the group. This can vary if the data 

exhibit a general increasing or decreasing trend; in such cases, the fit that appears to most closely 

match the data is selected. By this method, the polonium and plutonium excretion data were divided 

into several chronic intake periods [5].

3.2.1 Polonium

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

Polonium data from 1944 through 1973 were fit as a series of chronic intakes.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 14 of 60

3.2.2 Plutonium

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

and type MHI for 238Pu only [NIOSH 2016]. Plutonium data from 1956 through 2002 were fit as a 

series of chronic intakes.

3.3 MATERIAL TYPES

ORAUT-TKBS-0016-5 discusses Mound internal dosimetry data and includes guidance for the 

appropriate use of that information. It concludes that workers at Mound had the potential to receive 

intakes of polonium and plutonium [ORAUT 2017]. 

3.3.1 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 [6]. The GM for 

this quarter was several orders of magnitude smaller than the other means, and the GSD exceeded 

250. 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 [7].

3.3.2 Plutonium

Excretion data for the 50th- and 84th-percentile values of total plutonium for 1944 through 1973 are 

shown in Table A-2 [8]. Because plutonium of types S, M, MHI (applicable to 238Pu only [NIOSH 

2016]), or SS (applicable to 239Pu only [ORAUT 2020]) 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.

Plutonium urinalysis results were analyzed with IMBA or IDOT using types M, S, MHI, and SS

materials to derive intake rates for 1956 to 2002.

Plutonium Type M 

The solid lines in Figures B-5 to B-10 show the individual fits to the 50th-percentile 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.

Plutonium Type S 

The solid lines in Figures B-20 to B-25 show the individual fits to the 50th-percentile 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 [9]. Figure B-33 shows the 84th-percentile predicted excretion rates from all 

type S intakes.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 15 of 60

Plutonium-238 Type MHI

The solid lines in Figures B-34 to B-39 show the individual fits to the 50th-percentile excretion rates 

for type MHI materials. Figure B-40 shows the 50th-percentile predicted excretion rates from all type 

MHI intakes. The solid lines in Figures B-41 to B-46 show the individual fits to the 84th-percentile 

excretion rates for type MHI materials [10]. Figure B-47 shows the 84th-percentile predicted excretion 

rates from all type MHI intakes.

Plutonium-239 Type SS

The solid lines in Figures B-48 to B-53 show the individual fits to the 50th-percentile excretion rates 

for type SS materials. Figure B-54 shows the 50th-percentile predicted excretion rates from all 

type SS intakes. The solid lines in Figures B-55 to B-60 show the individual fits to the 84th-percentile 

excretion rates for type S materials [11]. Figure B-61 shows the 84th-percentile predicted excretion 

rates from all type SS intakes.

4.0 ASSIGNING INTAKES AND DOSES

The derived intake rates were used to determine co-exposure doses to individuals. Worker-specific 

dates and information are used to calculate the doses. This section tabulates the derived intake rates 

and provides guidance for assigning doses. For tritium, the doses to assign are provided rather than 

intake rates.

The 50th- and 95th-percentile intake rates are presented in the tables. The GSD, as calculated from 

the ratio of the 50th- and 84th-percentile intake rates, is included with the 50th-percentile intake rate 

so that the full distribution can be assigned when appropriate. The 95th percentile was calculated 

based on the GM (50th percentile) and GSD of the distribution. Note that there is an exception to the 

use of the GSD calculated from the 50th- and 84th-percentile intake rates. A value of 3 is assigned in 

ORAUT-OTIB-0060, Internal Dose Reconstruction [ORAUT 2018], to account for the uncertainty in 

the bioassay measurements and biokinetic models, so a minimum value of 3 is assigned to the coexposure intake rates. This includes the calculation of the 95th-percentile intake rate.

Workers with a significant potential for intake should be assigned doses at the 95th percentile with a 

constant distribution, while those with less potential should be assigned the full distribution (i.e., 50th 

percentile with a lognormal distribution). Section 3.3.5 of ORAUT [2018] contains additional guidance 

on which intake rate to assign. The lognormal distribution should be selected in the Interactive 

RadioEpidemiological 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 should be applied to all 

annual doses that are determined from the intake period.

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

ORAUT [2017] for more information on determining the material type for assignment of dose.

4.1 POLONIUM

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

many of the GSDs were relatively similar, they were combined and the largest value in a given period 

was assigned for simplicity [12].

The intake rates, GSDs, and periods to which they are applicable are given in Table A-3 for type M 

210Po and Table A-4 for type F 210Po. In most cases, doses for individuals with potential routine 

exposure should be calculated from the 50th-percentile intake rates by assuming the absorption type 

that results in the largest dose. Table 4-1 summarizes the derived polonium intake rates that 

produced the data-fitting results in Attachment B. Note that the results on the left hand side of Table 
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 16 of 60

4-1 are in becquerels per day because the original data were recorded as such [13]. The values in

picocuries per day are provided on the right hand side of the table.

Table 4-1. Derived polonium intake rates for types F and M 210Po, 1944 to 1973. 

Type F Po-210

Period

Type F

50th percentile

(Bq/d)

Type F

GSD

Type F

95th percentile 

(Bq/d)

Type F

50th percentile

(pCi/d)

Type F 

GSD

Type F

95th percentile 

(pCi/d)

07/1944–03/1946 1,189.5 3.89 11,113 32,149 3.89 300,351

04/1946–03/1949 254.96 5.56 4,287 6,891 5.56 115,865

04/1949–03/1960 12.192 7.99 372 329.5 7.99 10,054

04/1960–03/1965 2.0696 6.70 47.3 55.94 6.7 1,278

04/1965–12/1973 0.10303 8.88 3.74 2.785 8.88 101.1

Type M Po-210

Period

Type M

50th percentile

(Bq/d)

Type M

GSD

Type M

95th percentile 

(Bq/d)

Type M

50th percentile

(pCi/d)

Type M

GSD

Type M

95th percentile 

(pCi/d)

07/1944–03/1946 4,097.6 3.9 38,444 110,746 3.9 1,039,027

04/1946–03/1949 800.19 5.8 14,422 21,627 5.8 389,784

04/1949–03/1960 39.851 8.0 1,219 1077 8 32,946

04/1960–03/1965 5.7883 6.2 116 156.4405405 6.2 3,135

04/1965–12/1973 0.34853 8.8 12.5 9.420 8.8 337.8

4.2 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 types S and SS material. Six intake periods were fit to the derived 50th- and 84thpercentile plutonium excretion data for type MHI 238Pu. If the GSD was less than 3, the value was set 

to 3 to account for biological variation when determining dose [14].

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

Table A-6 for type S plutonium, Table A-7 for type MHI 238Pu, and Table A-8 for type SS 239Pu. In most 

cases, doses for individuals with potential routine exposure should be calculated from the 50thpercentile intake rates by assuming the absorption type that results in the largest probability of 

causation. Table 4-2 summarizes the derived plutonium intake rates that produced the data-fitting 

results in Attachment B. Note that the results in Table 4-2 are in picocuries per day because the 

original data were recorded as such [15]. If becquerels per day are preferred, multiply the Table 4-2 

values by 0.037.

To calculate doses from plutonium, the intakes of total plutonium should be classified as either 

weapons-grade plutonium (WGPu) or heat-source plutonium (HSPu) using the established protocol 

for Mound. HSPu is assumed to be 100% 238Pu by activity. For HSPu, absorption types M, S, and MHI 

should be considered. Determining the isotopic mix of WGPu is more complex. Table 4-3 lists three 

WGPu mixes aged 1, 3.2, and 10 years. These values are taken from the technical basis document 

[ORAUT 2017]. If the age of the isotopic mix is not known, the 10-year-aged material should be 

selected to be favorable to claimants in relation to the ingrowth of 241Am from 241Pu [16]. For WGPu, 

absorption types M, S, and SS intake rates should be evaluated. 
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 17 of 60

Table 4-2. Derived plutonium intake rates for types M, S, MHI, and SS plutonium, 1956 to 2002. 

Type M Pu

Period

50th percentile

(pCi/d) GSD

95th percentile 

(pCi/d)

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

1998–2002 0.04092 12.31 2.54

Type S Pu

Period

50th percentile

(pCi/d) GSD

95th percentile 

(pCi/d)

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

Type MHI (Pu-238 only)

Period

50th percentile

(pCi/d) GSD

95th percentile 

(pCi/d)

1956–1957 2,161 3.00a 13,168

1958–1960 1,121 4.02 11,053

1961–1969 26.47 4.85 355.1

1970–1984 4.681 5.11 68.55

1985–1997 0.8675 7.30 22.80

1998–2002 0.09004 12.33 5.61

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

Type SS (Pu-239 only)

Period

50th percentile

(pCi/d) GSD

95th percentile 

(pCi/d)

1956–1957 99,300 3.00a 605,081

1958–1960 59,300 3.71 512,466

1961–1969 1,630 4.88 22,138

1970–1984 286 5.10 4,178

1985–1997 54.2 7.36 1,446

1998–2002 5.71 12.28 353.3

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

Table 4-3. Dose calculations for WGPu intakes. 

Material age 

(yr)

% alpha activity 

Pu-239/240

% alpha activity 

Pu-238

% alpha activity 

Am-241

Beta activity 

(times APu-239/240) 

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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 18 of 60

4.3 TRITIUM

Tritium doses rather than intake rates were calculated. Table 4-4 lists the tritium doses and GSDs to 

be used for each year of potential tritium exposure. These doses apply to exposure to tritiated water 

vapor (HTO), and do not apply to exposure to stable metal tritides. Refer to ORAUT [2017] for dose 

from stable metal tritides.

Table 4-4. 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

5.0 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 (SRDB).

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.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 19 of 60

[1] Lochamy, Joseph C. Oak Ridge Associated Universities (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.

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 example, OCAS-IG-002, Internal Dose 

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

Respiratory Tract Model for Radiological Protection (ICRP 1994).

[4] 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 

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.

[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.

[6] Mahathy, Michael, and Lochamy, Joseph C. ORAU Team. Co-exposure Statistics Analyst and 

Senior Health Physicist. February 2007.

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

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

Attachment B figures were generated by LaBone from IMBA results.

[8] 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.

[9] 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.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 20 of 60

[10] 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.

[11] 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.

[12] 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.

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

Principal Internal Dosimetrist, Co-exposure 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.

[14] 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 2018). 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 co-exposure 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.

[15] 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.

[16] 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.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 21 of 60

REFERENCES

ICRP [1994]. Human respiratory tract model for radiological protection. ICRP Publication 66. Ann.

ICRP 24(4). [SRDB Ref ID: 22732]

MJW Corporation [2002]. Pre-1989 dose assessment project, phase I final report, volume I (non-SUD

version). Williamsville, NY. April. [SRDB Ref. ID: 8745]

Mound [no date a]. Polonium database – PORECON. Miamisburg, OH. [SRDB Ref ID: 12462]

Mound [no date b]. Plutonium analysis database – PURECON_MERGED. Miamisburg, OH. [SRDB

Ref ID: 12457]

NIOSH [2002]. Internal dose reconstruction implementation guideline. OCAS-IG-002 Rev. 0.

Cincinnati, OH: U.S. Department of Health and Human Services, Centers for Disease Control and

Prevention, National Institute for Occupational Safety and Health. August. [SRDB Ref ID: 22402]

NIOSH [2016]. Alternative dissolution models for insoluble Pu-238. DCAS-RPT-005 Rev. 00. 

Cincinnati, OH: U.S. Department of Health and Human Services, Centers for Disease Control and

Prevention, National Institute for Occupational Safety and Health. June 30. [SRDB Ref ID: 161248]

ORAUT [2004a]. Coworker data exposure profile development. ORAUT-PLAN-0014 Rev. 00. Oak

Ridge, TN: Oak Ridge Associated Universities Team. November 24. [SRDB Ref ID: 166559]

ORAUT [2004b]. Technical information bulletin: tritium calculated and missed dose estimates.

ORAUT-OTIB-0011 Rev. 00. Oak Ridge, TN: Oak Ridge Associated Universities Team. June 29.

[SRDB Ref ID: 19430]

ORAUT [2005]. Analysis of coworker bioassay data for internal dose assignment. ORAUT-OTIB-0019

Rev. 01. Oak Ridge, TN: Oak Ridge Associated Universities Team. October 7. [SRDB Ref ID: 19438]

ORAUT [2006]. Generating summary statistics for coworker bioassay data. ORAUT-PROC-0095 Rev.

00. Oak Ridge, TN: Oak Ridge Associated Universities Team. June 5. [SRDB Ref ID: 73397]

ORAUT [2017]. Mound Site – occupational internal dose. ORAUT-TKBS-0016-5 Rev. 03. Oak Ridge,

TN: Oak Ridge Associated Universities Team. March 3. [SRDB Ref ID: 165903]

ORAUT [2018]. Internal dose reconstruction. ORAUT-OTIB-0060 Rev. 02. Oak Ridge, TN: Oak Ridge 

Associated Universities Team. April 20. [SRDB Ref ID: 171554]

ORAUT [2020]. Estimating doses for plutonium strongly retained in the lung. ORAUT-OTIB-0049 Rev. 

02. Oak Ridge, TN: Oak Ridge Associated Universities Team. September 1. [SRDB Ref ID: 178329]
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 22 of 60

ATTACHMENT A 

CO-EXPOSURE DATA TABLES

LIST OF TABLES

TABLE TITLE PAGE

A-1 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1973................................ 23

A-2 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 2002 ................. 25

A-3 Type M 210Po intake rates and dates ...................................................................................... 27

A-4 Type F 210Po intake rates and dates....................................................................................... 28

A-5 Type M plutonium intake rates and dates............................................................................... 28

A-6 Type S plutonium intake rates and dates ............................................................................... 28

A-7 Type MHI 238Pu intake rates and dates ................................................................................... 28

A-8 Type SS 238Pu intake rates and dates .................................................................................... 28
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 23 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

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

Effective 50th percentile 84th percentile Number of samples Number 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

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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 24 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

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

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

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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 25 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

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

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. 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 2002 (pCi/d). 

Effective 50th percentile 84th percentile Number of samples Number 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

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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 26 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

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

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

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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 27 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

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

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

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

07/01/1991 2.83E−03 1.44E−02 1,612 712

07/01/1992 1.94E−03 1.08E−02 2,211 1,131

07/01/1993 1.07E−03 5.51E−03 2,108 915

07/01/1994 9.79E−04 4.55E−03 2,404 1,149

07/01/1995 1.64E−03 7.26E−03 1799 797

07/01/1996 2.18E−03 8.09E−03 678 255

07/01/1997 1.30E−03 6.60E−03 834 233

07/01/1998 3.18E−04 3.67E−03 847 205

07/01/1999 1.92E−04 2.77E−03 756 256

07/01/2000 2.02E−04 2.31E−03 1,033 329

07/01/2001 1.95E−04 2.26E−03 787 258

07/01/2002 1.32E−04 1.73E−03 577 321

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

Start End 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 4,097.6 15,796 3.9

04/01/1946 03/31/1949 800.19 4,602.3 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
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 28 of 60

ATTACHMENT A

CO-EXPOSURE DATA TABLES (continued)

Table A-4. Type F 210Po intake rates (Bq/d) and dates. 

Start End 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 1,189.5 4,628 3.89

04/01/1946 03/31/1949 254.96 1,416.8 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-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

01/01/1998 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

01/01/1958 12/31/1960 12,880 53,000 4.11

01/01/1961 12/31/1969 209.9 1,301 4.91

01/01/1970 12/31/1984 31.31 160.2 5.12

01/01/1985 12/31/1997 6.141 43.77 7.13

01/01/1998 12/31/2002 0.8638 10.64 12.32

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

Table A-7. Type MHI 238Pu intake rates (pCi/d) and dates. 

Start End 50th percentile 84th percentile GSD

01/01/1956 12/31/1957 2,161 4,143 1.92a

01/01/1958 12/31/1960 1,121 4,506 4.02

01/01/1961 12/31/1969 26.47 128.3 4.85

01/01/1970 12/31/1984 4.681 23.93 5.11

01/01/1985 12/31/1997 0.8675 6.329 7.30

01/01/1998 12/31/2002 0.09004 1.11 12.33

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

Table A-8. Type SS 238Pu intake rates (pCi/d) and dates. 

Start End 50th percentile 84th percentile GSD

01/01/1956 12/31/1957 99,300 198,000 1.99a

01/01/1958 12/31/1960 59,300 220,000 3.71

01/01/1961 12/31/1969 1,630 7,960 4.88

01/01/1970 12/31/1984 286 1,460 5.10

01/01/1985 12/31/1997 54.2 399 7.36

01/01/1998 12/31/2002 5.71 70.1 12.28

a. Actual. Adjust all GSD <3 to 3 for dose calculations.
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 29 of 60

 

ATTACHMENT B 

CO-EXPOSURE DATA FIGURES

LIST OF FIGURES

FIGURE TITLE PAGE

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

type M 210Po...........................................................................................................................32

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

type M 210Po...........................................................................................................................32

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

type F 210Po............................................................................................................................33

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

type F 210Po............................................................................................................................33

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

type M plutonium, 1956 to 1957 ............................................................................................. 34

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

type M plutonium, 1958 to 1960 ............................................................................................. 34

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

type M plutonium, 1961 to 1969 ............................................................................................. 35

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

type M plutonium, 1970 to 1984 ............................................................................................. 35

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

type M plutonium, 1985 to 1997 ............................................................................................. 36

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

type M plutonium, 1998 to 2002 ............................................................................................. 36

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

type M plutonium, 1956 to 2002 ............................................................................................. 37

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

type M plutonium, 1956 to 1960 ............................................................................................. 37

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

type M plutonium, 1961 to 1967 ............................................................................................. 38

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

type M plutonium, 1968 to 1969 ............................................................................................. 38

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

type M plutonium, 1970 to 1977 ............................................................................................. 39

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

type M plutonium, 1978 to 1984 ............................................................................................. 39

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

type M plutonium, 1985 to 1997 ............................................................................................. 40

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

type M plutonium, 1998 to 2002 ............................................................................................. 40

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

type M plutonium, 1956 to 2002 ............................................................................................. 41

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

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 41

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

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 42

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

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 42

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

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 43
Document No. ORAUT-OTIB-0061 Revision No. 04 Effective Date: 09/01/2020 Page 30 of 60

ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 43

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

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 44

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

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 44

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

inhalation intake of type S plutonium, 1956 to 1957 ............................................................... 45

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

inhalation intake of type S plutonium, 1958 to 1960 ............................................................... 45

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

inhalation intake of type S plutonium, 1961 to 1969 ............................................................... 46

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

inhalation intake of type S plutonium, 1970 to 1984 ............................................................... 46

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

inhalation intake of type S plutonium, 1985 to 1997 ............................................................... 47

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

inhalation intake of type S plutonium, 1998 to 2002 ............................................................... 47

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

inhalation intake of type S plutonium, 1956 to 2002 ............................................................... 48

B-34 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 1957 .................................................................. 48

B-35 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1958 to 1960 .................................................................. 49

B-36 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1961 to 1969 .................................................................. 49

B-37 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1970 to 1984 .................................................................. 50

B-38 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1985 to 1997 .................................................................. 50

B-39 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1998 to 2002 .................................................................. 51

B-40 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 2002 .................................................................. 51

B-41 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238

Pu, 1956 to 1957 .................................................................. 52

B-42 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1958 to 1960 .................................................................. 52

B-43 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1961 to 1969 .................................................................. 53

B-44 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1970 to 1984 .................................................................. 53

B-45 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1985 to 1997 .................................................................. 54

B-46 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1998 to 2002 .................................................................. 54

B-47 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type MHI 238Pu, 1956 to 2002 .................................................................. 55

B-48 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 1957............................................................. 55
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

B-49 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1958 to 1960............................................................. 56

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

inhalation intake of type SS plutonium, 1961 to 1969............................................................. 56

B-51 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1970 to 1984 ............................................................. 56

B-52 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1985 to 1997............................................................. 57

B-53 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1998 to 2002............................................................. 57

B-54 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 2002............................................................. 57

B-55 Predicted and observed 84th-percentile urinary excretion assuming a single chronic

inhalation intake of type SS plutonium, 1956 to 1957............................................................. 58

B-56 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1958 to 1960............................................................. 58

B-57 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1961 to 1969............................................................. 58

B-58 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1970 to 1984............................................................. 59

B-59 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1985 to 1997............................................................. 59

B-60 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1998 to 2002............................................................. 59

B-61 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type SS plutonium, 1956 to 2002............................................................. 60
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

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. 

Figure B-34. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1956 to 1957. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-35. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1958 to 1960. 

Figure B-36. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1961 to 1969. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-37. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1970 to 1984. 

Figure B-38. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1985 to 1997. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-39. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1998 to 2002. 

Figure B-40. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1956 to 2002. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-41. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1956 to 1957. 

Figure B-42. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1958 to 1960. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-43. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1961 to 1969. 

Figure B-44. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1970 to 1984. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-45. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1985 to 1997. 

Figure B-46. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1998 to 2002. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-47. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type MHI 238Pu, 1956 to 2002. 

Figure B-48. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type SS plutonium, 1956 to 1957. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-49. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

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

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

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

Figure B-51. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type SS plutonium, 1970 to 1984. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-52. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

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

Figure B-53. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

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

Figure B-54. Predicted (line) and observed (dots) 50th-percentile urinary excretion assuming a single 

chronic inhalation intake of type SS plutonium, 1956 to 2002. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-55. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

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

Figure B-56. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

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

Figure B-57. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type SS plutonium, 1961 to 1969. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-58. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

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

Figure B-59. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

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

Figure B-60. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

chronic inhalation intake of type SS plutonium, 1998 to 2002. 
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ATTACHMENT B

CO-EXPOSURE DATA FIGURES (continued)

Figure B-61. Predicted (line) and observed (dots) 84th-percentile urinary excretion assuming a single 

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