ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 23

Document Title:

Internal Dosimetry Coworker Data for 

Lawrence Livermore National Laboratory

Document Number: ORAUT-OTIB-0065

Revision: 00

Effective Date: 02/16/2007

Type of Document: OTIB

Supersedes: None

Subject Expert(s): Donald E. Bihl, Thomas R. LaBone, and Joseph C. Lochamy

Site Expert(s): N/A

Approval: Signature on File Approval Date: 02/14/2007

Donald E. Bihl, Document Owner

Concurrence: Signature on File Concurrence Date: 02/13/2007

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 02/13/2007

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 02/15/2007

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 02/16/2007

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 2 of 23

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

02/13/2007 00 First approved issue. New technical information bulletin for 

assignment of LLNL internal doses based on coworker bioassay 

data. Revised second to last sentence in Section 5.2.1 to indicate 

that workers exposed to uranium in 1952 through 1957 were not 

unmonitored if they had uranium bioassay in more recent years. 

Other minor changes occurred in response to internal review. 

Incorporates NIOSH formal review comments. Added dates of 

operation of AVLIS to Section 4.1. Deleted “1981” from the second 

sentence, 5th paragraph under Section 4.1. In same paragraph, 

indicated that “all” samples were excluded for persons with more 

than 20 samples. Added Attributions and Annotations section. 

There is no change to the assigned dose and no PER is required. 

Training required: As determined by the Task Manager. Initiated by 

Donald E. Bihl. 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 3 of 23

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

6

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

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

3.0 Overview..................................................................................................................................7

4.0 Discussion of the Datasets.......................................................................................................8

4.1 Uranium........................................................................................................................8

4.2 Plutonium (reserved) ....................................................................................................9

4.3 Gross Alpha (reserved).................................................................................................9

4.4 Gross Beta and MFP (reserved)...................................................................................9

4.5 Analysis........................................................................................................................9

5.0 Intake Modeling........................................................................................................................9

5.1 Assumptions.................................................................................................................9

5.2 Bioassay Fitting and Intakes.......................................................................................10

5.2.1 Uranium ....................................................................................................... 10

5.3 Plutonium (reserved) ..................................................................................................11

5.4 Gross Alpha (reserved)...............................................................................................11

5.5 Gross Beta/MFP (reserved)........................................................................................11

6.0 Attributions and Annotations .................................................................................................. 11

References ........................................................................................................................................14

Attachment A, Statistical Summaries and Plots ................................................................................15

LIST OF TABLES

TABLE TITLE

4-1 Time intervals for statistical analysis of uranium urine samples.................................................

PAGE

9

5-1 Uranium mass and activity intake rates for four different time periods..................................... 11

A-1 Uranium urine bioassay data for 50th and 84th percentiles in units of μg/L and 

mg/day along with the time period and effective bioassay date, 1958 through 1996................ 15
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 4 of 23

LIST OF FIGURES

FIGURE TITLE

A-1 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1958 to 12/31/1973 (blue dots)..............

PAGE

16

A-2 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1974 to 12/31/1987 (blue dots).............. 16

A-3 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1988 to 12/31/1996 (blue dots).............. 16

A-4 Predicted and observed 50th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type F natural uranium............................................................... 17

A-5 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1958 to 12/31/1973 (blue dots).............. 17

A-6 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1974 to 12/31/1987 (blue dots).............. 17

A-7 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1988 to 12/31/1996 (blue dots).............. 18

A-8 Predicted and observed 84th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type F natural uranium............................................................... 18

A-9 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1958 to 12/31/1973 (blue dots)............. 18

A-10 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1974 to 12/31/1987 (blue dots)............. 19

A-11 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1988 to 12/31/1996 (blue dots)............. 19

A-12 Predicted and observed 50th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type M natural uranium.............................................................. 19

A-13 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1958 to 12/31/1973 (blue dots)............. 20

A-14 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1974 to 12/31/1987 (blue dots)............. 20

A-15 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type M natural uranium from 1/1/1988 to 12/31/1996 (blue dots)............. 20

A-16 Predicted and observed 84th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type M natural uranium (blue dots) ............................................ 21

A-17 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1959 to 12/31/1973 (blue dots).............. 21

A-18 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1974 to 12/31/1987 (blue dots).............. 21

A-19 Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1988 to 12/31/1996 (blue dots).............. 22

A-20 Predicted and observed 50th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type S natural uranium .............................................................. 22

A-21 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1958 to 12/31/1973 (blue dots).............. 22

A-22 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1974 to 12/31/1987 (blue dots).............. 23

A-23 Predicted and observed 84th-percentile urinary excretion assuming a chronic 

inhalation intake of Type S natural uranium from 1/1/1988 to 12/31/1996 (blue dots).............. 23
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 5 of 23

A-24 Predicted and observed 84th-percentile urinary excretion assuming three separate 

chronic inhalation intakes of Type S natural uranium .............................................................. 23
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 6 of 23

ACRONYMS AND ABBREVIATIONS

AVLIS Atomic Vapor Laser Isotope Separation

DOE U.S. Department of Energy

GSD geometric standard deviation

hr hour

ICRP International Commission on Radiological Protection

IMBA Integrated Modules for Bioassay Analysis

L liter

LLNL Lawrence Livermore National Laboratory

MDA minimum detectable activity

NIOSH National Institute for Occupational Safety and Health

ORAUT Oak Ridge Associated Universities team

pCi picocurie

TBD technical basis document

TIB technical information bulletin

U.S.C. United States Code

μm micrometer

yr year

§ Section
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 7 of 23

1.0

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

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

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

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

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

individual dose reconstructions.

INTRODUCTION

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

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

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

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

2.0

Some employees at DOE sites were either not monitored for intakes of radioactive material or the 

records of such monitoring are missing or incomplete. In such cases, data from monitored coworkers 

can be used to estimate an individual’s possible exposure. The purpose of this document is to 

provide monitored coworker information for calculating and assigning intakes to employees of the 

Lawrence Livermore National Laboratory (LLNL) for whom no or insufficient bioassay monitoring 

records exist. 

PURPOSE

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

justification, or clarification of the associated information, are presented in Section 6.0.

3.0

Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAUT 2005a) describes the 

general process for analyzing bioassay data for the assignment of doses based on coworker results.

OVERVIEW

Bioassay results for LLNL were obtained as a copy of the site’s MAPPER database converted to an 

Excel spreadsheet along with a cover letter explaining characteristics of the database and pointing out 

possibilities of data recording errors that might exist in the database (Mansfield 2006a). As sent to 

Oak Ridge Associated Universities Project Team (ORAUT), the MAPPER database had 

approximately 34,900 records. It contained no in vivo counting results and had only a few of the many 

tritium urinalysis results obtained throughout the operation of the Laboratory. The in vivo counting 

results were not available electronically and, therefore, were not analyzed as a coworker database. 

(In vivo results for individual Energy Employees are included in the files sent to NIOSH from LLNL.) It 

also proved infeasible to obtain the rest of the tritium urinalyses results from LLNL; discussion of the 

tritium dose database is reserved. 

The principal radionuclides with potential for intakes at LLNL were tritium, isotopes of plutonium in a 

weapons-grade mixture, isotopes of uranium in mixtures typical of depleted uranium, natural uranium 

or slightly enriched uranium (to 5%), various transuranic radionuclides, activation products, and fission 

products (ORAUT 2005b). The MAPPER database had small numbers of analyses for other 

radionuclides, such as 241Am, curium, “TRU;” however, the numbers were too small for statistical 

analysis. Generally, LLNL used the gross alpha analysis to screen for intakes of transuranic

radionuclides with follow-up analyses being more specific for the radionuclide of concern. 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 8 of 23

The urinalysis data chosen for this coworker study because of general applicability and number of 

measurements were for plutonium, uranium, gross alpha, gross beta, and an analysis labeled MFP. 

Two previous bioassay laboratory managers confirmed that the gross beta results and the MFP 

results were from the same procedure and should be treated as the same (Bihl 2006, Mansfield 

2006b). The tritium dose data were also analyzed. For revision zero of this document, the analyses 

of the plutonium, gross alpha, gross beta, and tritium datasets were reserved. 

The statistical analyses of the bioassay data for each radionuclide were performed in accordance with 

the internal dosimetry coworker TIB (ORAUT 2005a) and the procedure, Generating Summary 

Statistics for Coworker Bioassay Data, (ORAUT 2006a). The resultant values were input to the 

Integrated Modules for Bioassay Analysis (IMBA) computer program and a fit to the data for each of 

the five analyzed groups at the 50th- and 84th-percentile values was performed to obtain intake rates 

for assignment of dose distributions. 

4.0

4.1 URANIUM

DISCUSSION OF THE DATASETS

MAPPER had uranium urinalysis data from 1958 to 1996. Nearly all of the results were reported as 

U238 in units of μg/L. The LLNL cover letter indicates that the results actually represent total uranium 

(Mansfield 2006a). According to the technical basis document (TBD), most uranium exposure was to 

depleted or natural uranium. The Atomic Vapor Laser Isotope Separation (AVLIS) project converted 

kilogram quantities of natural uranium to slightly enriched uranium, up to 5%, as a demonstration 

plant. AVLIS operated in 1998 and 1999. There was another project involving highly enriched 

uranium in the 1990s. When identified in MAPPER, results from workers on these projects were 

excluded from the uranium dataset because of the higher specific activity of uranium on that project

(31 results). Uranium results were left in the units of μg/L for the statistical analysis and curve fitting. 

The uranium dataset has no negative (i.e., <0) results. Minimum detectable activities (MDAs) for the 

uranium analysis methods were not provided in the LLNL cover letter. The TBD lists the MDA as 4 

μg/L through 1975, 1 μg/L for 1976 through 1986, and 0.04 μg/L for 1987 through 1999; however, 

these MDAs came from industry-wide norms rather than LLNL specific documentation (ORAUT 

2006b). Most of the results less than 1 μg/L were recorded as zero prior to 1974. In 1974, the 

database shows a distinctly different pattern, with an overall decrease in the general magnitude of the 

results, a lower reporting level at around 0.01 μg/L, and sufficient results between 0.01 to 1 μg/L to 

support a reasonably normal or lognormal pattern implying that a change to a more sensitive analysis 

technique took place. The MDA in 1985 was stated in one document as about 0.3 μg/L (Gibson 

1985). 

The zero results were included in the ranking of the data but not the curve fitting. In several years 

prior to 1974, there were a few results recorded with values between 1 and zero μg/L. Because there 

were just a few of these and not in all years, they seemed to be anomalous recordings relative to the 

1 μg/L reporting level. Because they might have been misrecorded data, such as misplaced decimals 

or incorrect unit conversion, and because they were clearly anomalous when included in the 

lognormal plots of the results, these results were excluded from the final annual datasets. There were 

37 of these results throughout the period 1962 through 1973. Excluding these results had only small 

effects on the 50th and 84th percentiles. 

The uranium dataset had entries from recounts on the same sample and entries showing multiple 

same-day samples from a given worker. The recounted samples were identified as having identical 

information, including sample number, but different results and different uncertainty. The multiple
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 9 of 23

same-day samples were indicated by having the same worker identification and sample dates,

however, the sample numbers were different, often by one digit. Because two counts on a single 

sample or two samples from a given worker on the same day produces a bias when compared to 

other workers’ samples that were given only a single count, the multi-counted samples were replaced 

by the average of the multiple counts. 

Duplicate entries that were obvious and samples marked by LLNL as baselines or quality control

samples were excluded [1]. 

Table 4-1 lists the time intervals for separate statistical analyses. Intervals were chosen to obtain 

approximately 100 results or more per interval; however, 1967 had only 51 results and 1971 had only 

34 results. (The median and 84th-percentile values for 1971 were also much lower than surrounding 

years, perhaps indicating that there was little work with uranium at the site in 1971.) The statistical 

parameters for each interval, e.g., 50th and 84th percentiles, were assigned to the midpoint of the 

interval. 

Table 4-1. Time intervals for statistical analysis of

uranium urine samples.

Calendar year Analysis interval

1958 Year

1959−1961 Treated as a single interval 

1962–1964 Treated as a single interval

1965–1974 Year

1975–1986 Six months

1987−1996 Three months

4.2 PLUTONIUM (RESERVED)

4.3 GROSS ALPHA (RESERVED)

4.4 GROSS BETA AND MFP (RESERVED)

4.5 ANALYSIS

For each of the radionuclide groups above, a lognormal distribution for the data in the intervals 

specified in Tables 4-1 to 4-4 was assumed [2]. (Tables 4-2 through 4-4 are reserved.) The 50th- and 

84th-percentile values were calculated using the method described in ORAUT (2006a). Table A-1 in 

Attachment A shows the statistical analysis results for uranium.

5.0

5.1 ASSUMPTIONS

INTAKE MODELING

All urinalysis results were assumed to be representative of a full-day (24-hr) urinary excretion or were 

normalized to be representative of a full day before creating the lognormal plots with the exception of 

the uranium data, which were normalized to daily excretion prior to intake modeling [3]. Each result 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 10 of 23

used in the intake calculation was assumed to have a normal distribution and a uniform absolute error 

of 1 was applied to all results, which weighted all results equally [4]. A chronic exposure pattern was 

assumed unless the data clearly showed a sharp, short-term, increase in excretion [5]. Intakes were 

assumed to be from inhalation using a default breathing rate of 1.2 m3

/hr and a 5-μm activity median 

aerodynamic diameter particle size distribution [6].

When calculating doses to individuals from bioassay data, a GSD of 3 has been used to account for 

biological variation and uncertainty in the models. It was considered inappropriate to assign a value 

less than 3 for the coworker data. Therefore, a GSD of 3 was assigned for any intake period where 

the calculated GSD was <3 [7].

5.2 BIOASSAY FITTING AND INTAKES

The IMBA Expert ORAU-Edition, Version 4.0.9 computer program was used to fit the bioassay results 

to a series of chronic inhalations. The intake assumptions were based on observed patterns in the 

bioassay data. Intervals with constant chronic intake rates were chosen by selecting periods during

which the bioassay results were of similar magnitudes. A new chronic intake period was started 

where the data indicated a significant sustained change in the results [8]. The effective bioassay 

dates used in IMBA to calculate the intake rates were the midpoints of the sampling time periods [9]. 

The 50th- and 84th-percentile excretion values were fit as independent datasets producing separate 

50th- and 84th-percentile intakes [10]. The geometric standard deviations were calculated as the ratio 

of the 84th- to the 50th-percentile intakes for each intake interval [11].

The TBD does not specify inhalation absorption types for the various radionuclide or group of 

radionuclides; therefore, the bioassay results were entered into IMBA with assumed lung absorption 

types chosen to be consistent with International Commission on Radiological Protection (ICRP)

Publication 68 (ICRP 1993). Attachment A shows the resultant 50th-percentile intakes as plots. The

bioassay data used in the fits are shown as solid blue dots (●) (dark spots when printed) and data that 

are not used in the fits are shown as red dots (●) (light dots when printed). 

Type S compounds have very long radiological half-lives and the materials are retained in the body for 

long periods; therefore, the excretion results for different chronic intake periods are not independent 

for type S materials. For example, an intake in the 1950s could contribute to urinary excretion in the 

1980s and later. To avoid potential underestimation of intakes for people who worked at LLNL for 

relatively short periods, each chronic intake of type S material was independently fit using only the 

bioassay results from the single intake period. This results in an overestimate of intake rates for 

workers who were exposed to type S compounds for long periods. 

5.2.1

The 50th- and 84th-percentile uranium urinary excretion concentrations in μg/L were converted to 

mg/day assuming a daily urine volume of 1.4 liter per day (ICRP 1974). These data are shown in 

Table A-1. The intakes were determined from the mg/d excretion values. For ease of use by dose 

reconstructors, the intakes were also converted to activity using the specific activity of natural uranium 

(682 pCi/mg), which is favorable to claimants relative to using the specific activity of depleted 

uranium. While workers at LLNL may not have been chronically exposed to natural uranium, chronic 

intakes will approximate a series of acute intakes with unknown intake dates. Plots of the fits of 

models to urinary excretion are shown in Figures A-1 through A-24. 

Uranium
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 11 of 23

The intake rates, geometric standard deviations, and time periods in which they are applicable are 

given in Table 5-1. Use the intakes in pCi/d assuming all the activity is from 234U, which is favorable to 

claimants. 

Table 5-1. Uranium mass and activity intake rates for four different time periods.

Type Dates

50th

Percentile

(mg/day)

84th

Percentile

(mg/day)

50th

Percentile

(pCi/day)

84th

Percentile

(pCi/day) GSD

F 1/1/58-12/31/73 2.51E-02 5.81E-02 1.71E+01 3.96E+01 2.32a

F 1/1/74-12/31/87 1.65E-04 8.52E-04 1.13E-01 5.81E-01 5.16

F 1/1/88-12/31/96 2.87E-04 3.73E-04 1.96E-01 2.54E-01 1.30a

M 1/1/58-12/31/73 1.03E-01 2.39E-01 7.04E+01 1.65E+02 2.32a

M 1/1/74-12/31/87 6.76E-04 3.49E-03 4.61E-01 2.38E+00 5.16

M 1/1/88-12/31/96 1.20E-03 1.582E-03 8.16E-01 1.08E+00 1.32a

S 1/1/58-12/31/73 1.24E+00 2.93E+00 8.49E+02 1.99E+03 2.35a

S 1/1/74-12/31/87 8.55E-03 4.19E-02 5.83E+00 2.86E+01 4.90

S 1/1/88-12/31/96 1.75E-02 3.01E-02 1.19E+01 2.05E+01 1.72a

a. Use the default GSD of 3.0 instead of the calculated GSD.

There were no bioassay results for uranium prior to 1958 in the MAPPER database and, according to 

the laboratory manager circa 1958, few or none may have been obtained, so workers exposed to 

uranium during 1952 through 1957 who did not have subsequent uranium bioassay would be 

considered unmonitored. Guidance for how to assign intakes of uranium during that period is 

reserved. 

5.3 PLUTONIUM (RESERVED)

5.4 GROSS ALPHA (RESERVED)

5.5 GROSS BETA/MFP (RESERVED)

6.0

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.

ATTRIBUTIONS AND ANNOTATIONS

[1] Bihl, Donald E. ORAU Team. Principal Health Physicist. January 2007.

Duplicate entries bias the dataset and provide no useful information concerning coworker 

exposures. Quality control samples are spiked samples used to monitor laboratory 

performance against known quantities of the analyte; they are not excreta samples from 

workers. See also ORAUT-PROC-0095, “Generating Summary Statistics for Coworker 

Bioassay Data.” 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 12 of 23

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

Per ORAUT-PROC-0095, “Generating Summary Statistics for Coworker Bioassay Data.”

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

The uranium results were recorded as μg/L 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; hence, the statistical parameters were converted to excretion per day 

before intake calculations were made using IMBA. 

[4] Brackett, Elizabeth M. ORAU Team. 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 any one interval over another. 

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

Per ORAUT-OTIB-019, “Analysis of Coworker Bioassay Data for Internal Dose Assignment.”

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

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 concerning 

intakes at LLNL that shows that the default values should not be used. See, for instance, 

OCAS-IG-002, “Internal Dose Reconstruction Implementation Guide,” and ICRP Publication 

66, “Human Respiratory Tract Model for Radiological Protection.”

[7] Bihl, Donald E. ORAU Team. Principal Health Physicist. February 2007.

The minimum GSD of 3 is established in ORAUT-OTIB-0060, “Internal Dose Reconstruction.” 

It reflects the overall uncertainty associated with biokinetic modeling as well as usual 

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

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

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

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

The first four sentences of this paragraph explain how the intakes were calculated. The choice 

of intervals and resulting fits were peer reviewed by the Principal Internal Dosimetrist. 

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

Use of the midpoint of the time period represented by the excreta data point is established in 

ORAUT-OTIB-019, “Analysis of Coworker Bioassay Data for Internal Dose Assignment,” and 

is standard practice for assigning chronic intakes or acute intakes with unknown dates. See, 

for instance, HPS-N13.39-2001, “Design of Internal Dosimetry Programs.”

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

Per ORAUT-OTIB-019, “Analysis of Coworker Bioassay Data for Internal Dose Assignment.” 

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

Per ORAUT-OTIB-019, “Analysis of Coworker Bioassay Data for Internal Dose Assignment.” 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 13 of 23

[12] Lochamy, Joseph C. and Bihl, Donald E. ORAU Team. Senior Health Physicist and Principal 

Health Physicist. February 2007.

Table was compiled by Don Bihl from data generated by Joe Lochamy as explained in Section 

4.5 and ORAUT-PROC-095. 
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/16/2007 Page 14 of 23

REFERENCES

Bihl, D. E., 2006, “Notes from September 29, 2006 Conference Call on LLNL 

Radiochemistry/Bioassay,” October 2. [SRDB Ref. ID: 26883]

Gibson, T., 1985, Discipline Action Plan; Radiation Safety Program for Site 300. [SRDB Ref. ID: 

16037]

ICRP (International Commission on Radiological Protection), 1974, Report of the Task Group on 

Reference Man, Publication 23, Pergamon Press, Oxford, England.

ICRP (International Commission on Radiological Protection), 1993, Report of a Task Group of ICRP 

Committee II on Dose Coefficients for Intakes of Radionuclides by Workers, Publication 68,

Pergamon Press, Oxford, England.

Mansfield, W. G., 2006a, Letter from W. Gary Mansfield, LLNL, to Jennifer L. Hoff, ORAUT, “Copy of 

LLNL ‘MAPPER’ Bioassay Results Database,” May 17. [SRDB Ref. ID 28120]

Mansfield, W. G., 2006b, “Fwd; Re; Fwd; Questions for Gary Mansfield,” electronic mail message 

from W. Gary Mansfield, LLNL, to Don E. Bihl, PNNL, September 28. [SRDB Ref. ID 26886]

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

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

ORAUT (Oak Ridge Associated Universities Team), 2005b, Lawrence Livermore National Laboratory

– Site Description, ORAUT-TKBS-0035-2, Rev. 00, Oak Ridge, Tennessee.

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

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

ORAUT (Oak Ridge Associated Universities Team), 2006b, Lawrence Livermore National Laboratory

– Occupational Internal Dose, ORAUT-TKBS-0035-5, Rev. 01, Oak Ridge, Tennessee.
Document No. ORAUT-OTIB-0065 Revision No. 00 Effective Date: 02/1

6/2007 Page 15 of 23

ATTACHMENT A

STATISTICAL SUMMARIES AND PLOTS

Page 1 of 9

Table A-1. Uranium urine bioassay data for 50th and 84th percentiles in units of μg/L and mg/day along with the time period and 

effective bioassay date, 1958 through 1996 [12].

Year

Effective

bioassay date

50tha

(ug/L)

84thb

(ug/L)

50tha

(mg/day)

84thb

(mg/day) Year

Effective

bioassay date

50tha

(ug/L)

84thb

(ug/L)

50tha

(mg/day)

84thb

(mg/day)

1958 6/30/1958 6.886E+00 1.391E+01 9.640E-03 1.948E-02 1987 Q2c 5/15/1987 1.115E-02 6.624E-02 1.561E-05 9.273E-05

1959-61 6/30/1960 6.128E+00 1.479E+01 8.580E-03 2.070E-02 1987 Q3c 8/15/1987 2.036E-02 1.049E-01 2.850E-05 1.469E-04

1962-64 6/30/1963 5.773E+00 1.350E+01 8.082E-03 1.890E-02 1987 Q4c 11/15/1987 1.902E-02 1.228E-01 2.663E-05 1.719E-04

1965 6/30/1965 7.611E+00 1.539E+01 1.066E-02 2.155E-02 1988 Q1c 2/15/1988 1.381E-02 1.152E-01 1.934E-05 1.613E-04

1966 6/30/1966 1.615E+00 6.241E+00 2.261E-03 8.737E-03 1988 Q2c 5/15/1988 6.777E-02 1.583E-01 9.487E-05 2.217E-04

1967 6/30/1967 6.910E+00 1.401E+01 9.674E-03 1.961E-02 1988 Q3c 8/15/1988 6.883E-02 1.656E-01 9.636E-05 2.318E-04

1968 6/30/1968 5.415E+00 9.337E+00 7.581E-03 1.307E-02 1988 Q4c 11/15/1988 1.036E-01 2.746E-01 1.450E-04 3.844E-04

1969 6/30/1969 3.676E+00 7.727E+00 5.146E-03 1.082E-02 1989 Q1c 2/15/1989 7.946E-02 1.877E-01 1.112E-04 2.628E-04

1970 6/30/1970 1.913E+00 5.412E+00 2.678E-03 7.577E-03 1989 Q2c 5/15/1989 1.044E-01 2.581E-01 1.462E-04 3.614E-04

1971 6/30/1971 9.164E-01 3.893E+00 1.283E-03 5.450E-03 1989 Q3c 8/15/1989 7.688E-02 2.156E-01 1.076E-04 3.019E-04

1972 6/30/1972 8.316E+00 2.025E+01 1.164E-02 2.835E-02 1989 Q4c 11/15/1989 1.041E-01 2.834E-01 1.457E-04 3.968E-04

1973 6/30/1973 4.312E+00 1.332E+01 6.036E-03 1.865E-02 1990 Q1c 2/15/1990 5.557E-02 1.424E-01 7.780E-05 1.994E-04

1974 6/30/1974 4.574E-02 2.614E-01 6.405E-05 3.660E-04 1990 Q2c 5/15/1990 4.668E-02 1.194E-01 6.536E-05 1.672E-04

1975 S1c 3/31/1975 6.246E-02 1.869E-01 8.745E-05 2.617E-04 1990 Q3c 8/15/1990 4.637E-02 1.017E-01 6.492E-05 1.424E-04

1975 S2c 9/30/1975 7.562E-02 2.951E-01 1.059E-04 4.132E-04 1990 Q4c 11/15/1990 5.328E-02 8.954E-02 7.459E-05 1.254E-04

1976 S1c 3/31/1976 3.083E-02 2.092E-01 4.317E-05 2.928E-04 1991 Q1c 2/15/1991 7.233E-02 1.348E-01 1.013E-04 1.887E-04

1976 S2c 9/30/1976 2.754E-02 1.786E-01 3.856E-05 2.500E-04 1991 Q2c 5/15/1991 8.435E-02 1.587E-01 1.181E-04 2.222E-04

1977 S1c 3/31/1977 2.109E-02 1.026E-01 2.953E-05 1.436E-04 1991 Q3c 8/15/1991 6.278E-02 1.109E-01 8.789E-05 1.552E-04

1977 S2c 9/30/1977 2.419E-02 1.898E-01 3.386E-05 2.657E-04 1991 Q4c 11/15/1991 3.915E-02 7.684E-02 5.481E-05 1.076E-04

1978 S1c 3/31/1978 3.272E-02 1.654E-01 4.581E-05 2.316E-04 1992 Q1c 2/15/1992 3.836E-02 7.151E-02 5.371E-05 1.001E-04

1978 S2c 9/30/1978 3.315E-02 1.716E-01 4.641E-05 2.402E-04 1992 Q2c 5/15/1992 3.665E-02 6.038E-02 5.131E-05 8.453E-05

1979 S1c 3/31/1979 2.137E-02 1.069E-01 2.988E-05 1.497E-04 1992 Q3c 8/15/1992 4.188E-02 7.383E-02 5.863E-05 1.034E-04

1979 S2c 9/30/1979 3.709E-02 1.743E-01 5.193E-05 2.440E-04 1992 Q4c 11/15/1992 3.108E-02 4.560E-02 4.351E-05 6.383E-05

1980 S1c 3/31/1980 2.477E-02 2.750E-01 3.468E-05 3.850E-04 1993 Q1c 2/15/1993 3.576E-02 5.452E-02 5.006E-05 7.633E-05

1980 S2c 9/30/1980 8.372E-03 6.439E-02 1.172E-05 9.015E-05 1993 Q2c 5/15/1993 4.383E-02 6.672E-02 6.136E-05 9.340E-05

1981 S1c 3/31/1981 9.337E-03 8.276E-02 1.307E-05 1.159E-04 1993 Q3c 8/15/1993 4.338E-02 6.845E-02 6.073E-05 9.583E-05

1981 S2c 9/30/1981 8.418E-02 3.658E-01 1.179E-04 5.121E-04 1993 Q4c 11/15/1993 5.259E-02 7.099E-02 7.362E-05 9.939E-05

1982 S1c 3/31/1982 3.963E-02 1.981E-01 5.548E-05 2.773E-04 1994 Q1c 2/15/1994 4.764E-02 6.450E-02 6.670E-05 9.030E-05

1982 S2c 9/30/1982 8.179E-02 3.613E-01 1.145E-04 5.058E-04 1994 Q2c 5/15/1994 4.321E-02 6.539E-02 6.049E-05 9.155E-05

1983 S1c 3/31/1983 2.842E-02 2.227E-01 3.976E-05 3.118E-04 1994 Q3c 8/15/1994 5.066E-02 7.457E-02 7.093E-05 1.044E-04

1983 S2c 9/30/1983 3.694E-02 2.037E-01 5.172E-05 2.852E-04 1994 Q4c 11/15/1994 5.338E-02 7.858E-02 7.473E-05 1.100E-04

1984 S1c 3/31/1984 2.784E-02 1.550E-01 3.898E-05 2.170E-04 1995 Q1c 2/15/1995 6.468E-02 9.702E-02 9.055E-05 1.358E-04

1984 S2c 9/30/1984 4.755E-02 1.589E-01 6.657E-05 2.224E-04 1995 Q2c 5/15/1995 5.128E-02 7.838E-02 7.180E-05 1.097E-04

1985 S1c 3/31/1985 3.331E-02 2.177E-01 4.663E-05 3.048E-04 1995 Q3c 8/15/1995 4.628E-02 6.613E-02 6.480E-05 9.258E-05

1985 S2c 9/30/1985 2.855E-02 1.097E-01 3.996E-05 1.536E-04 1995 Q4c 11/15/1995 4.706E-02 7.429E-02 6.588E-05 1.040E-04

1986 S1c 3/31/1986 2.012E-02 1.371E-01 2.817E-05 1.919E-04 1996 Q1c 2/15/1996 5.239E-02 9.028E-02 7.335E-05 1.264E-04

1986 S2c 9/30/1986 5.117E-03 5.037E-02 7.164E-06 7.051E-05 1996 Q2c 5/15/1996 4.861E-02 8.392E-02 6.806E-05 1.175E-04

1987 Q1c 2/15/1987 6.010E-03 5.424E-02 8.414E-06 7.594E-05 1996 Q3c 8/15/1996 5.534E-02 8.901E-02 7.747E-05 1.246E-04

a. 50th-percentile value of the fitted line.

b. 84th-percentile value of the fitted line.

c. S1 means 1st 6 months of the year, S2 means 2nd 6 months of the year, Q1 means months 1-3 of the year, Q2 means months 4-6 of the year, Q3 means months 7-9 of the year, Q4 means months 10-

12 of the year. 
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Figure A-1. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type F natural uranium from 1/1/1958 to 12/31/1973 (blue 

dots).

Figure A-2. Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1974 to 12/31/1987 (blue dots).

Figure A-3. Predicted and observed 50th-percentile urinary excretion assuming a chronic 

inhalation intake of Type F natural uranium from 1/1/1988 to 12/31/1996 (blue dots).
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Figure A-4. Predicted and observed 50th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type F natural uranium.

Figure A-5. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type F natural uranium from 1/1/1958 to 12/31/1973 (blue 

dots).

Figure A-6. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type F natural uranium from 1/1/1974 to 12/31/1987 (blue 

dots).
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Figure A-7. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type F natural uranium from 1/1/1988 to 12/31/1996 (blue 

dots).

Figure A-8. Predicted and observed 84th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type F natural uranium.

Figure A-9. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1958 to 12/31/1973 (blue 

dots).
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Figure A-10. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1974 to 12/31/1987 (blue 

dots).

Figure A-11. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1988 to 12/31/1996 (blue 

dots).

Figure A-12. Predicted and observed 50th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type M natural uranium.
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STATISTICAL SUMMARIES AND PLOTS

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Figure A-13. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1958 to 12/31/1973 (blue 

dots).

Figure A-14. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1974 to 12/31/1987 (blue 

dots).

Figure A-15. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type M natural uranium from 1/1/1988 to 12/31/1996 (blue 

dots).
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Figure A-16. Predicted and observed 84th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type M natural uranium (blue dots).

Figure A-17. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1959 to 12/31/1973 (blue 

dots).

Figure A-18. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1974 to 12/31/1987 (blue 

dots).
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Figure A-19. Predicted and observed 50th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1988 to 12/31/1996 (blue 

dots).

Figure A-20. Predicted and observed 50th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type S natural uranium.

Figure A-21. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1958 to 12/31/1973 (blue 

dots).
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Figure A-22. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1974 to 12/31/1987 (blue 

dots).

Figure A-23. Predicted and observed 84th-percentile urinary excretion assuming a 

chronic inhalation intake of Type S natural uranium from 1/1/1988 to 12/31/1996 (blue 

dots).

Figure A-24. Predicted and observed 84th-percentile urinary excretion assuming three 

separate chronic inhalation intakes of Type S natural uranium.