ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 15

Document Title:

Internal Dosimetry Coworker Data for 

Paducah Gaseous Diffusion Plant

Document Number: ORAUT-OTIB-0037

Revision: 00

Effective Date: 09/20/2005

Type of Document: OTIB

Supersedes: None

Subject Expert: Tracy A. Ikenberry

Document Owner

Approval: Signature on File Approval Date: 08/29/2005

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 08/29/2005

Richard E. Toohey, Project Director

Approval: Signature on File Approval Date: 09/20/2005

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REV ISION.
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 2 of 15

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

05/12/2005 00-A New technical information bulletin for assignment of Paducah 

Gaseous Diffusion Plant internal doses based on coworker bioassay 

data. Initiated by Tracy A. Ikenberry.

06/29/2005 00-B Incorporates internal review comments. Initiated by Tracy A. 

Ikenberry.

07/21/2005 00-C Incorporates NIOSH review comments. Initiated by Tracy A. 

Ikenberry.

08/05/2005 00-D Incorporates additional NIOSH review comments. Initiated by Tracy 

A. Ikenberry.

09/20/2005 00 First approved issue. Training required: As determined by the Task 

Manager. Initiated by Tracy A. Ikenberry.
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 3 of 15

TABLE OF CONTENTS

Section

1.0 Purpose ...................................................................................................................................

Page

5

2.0 Overview ..................................................................................................................................5

3.0 Data.........................................................................................................................................5

3.1 Selected Bioassay Data......................................................................................................5

3.2 Analysis..............................................................................................................................6

4.0 Intake Modeling........................................................................................................................6

4.1 Assumptions.......................................................................................................................6

4.2 Bioassay Fitting ..................................................................................................................7

4.3 Uranium Material Types......................................................................................................7

4.3.1 Type F .......................................................................................................................7

4.3.2 Type M.......................................................................................................................8

4.3.3 Type S.......................................................................................................................8

5.0 Assignment of Intakes and Doses.............................................................................................8

 5.1 Intake Rate Summary.............................................................................................................. 8

5.2 Contribution from Contaminants in Recycled Uranium .........................................................9

5.3 Dose Assignment................................................................................................................9

References.....................................................................................................................................10

Attachment A..................................................................................................................................11
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 4 of 15

LIST OF TABLES

Table

4-1 Type F uranium intake periods and rates................................................................................

Page

7

4-2 Type M uranium intake periods and rates...............................................................................8

4-3 Type S uranium intake periods and rates ...............................................................................8

5-1 Type F uranium intake periods....................................................................................................8

5-2 Type M uranium intake periods and rates...................................................................................9

5-3 Type S uranium intake periods and rates................................................................................... 9 

A-1 Summary of quarterly uranium 24-hr urinary excretion rate analyses, 1952-

1988....................................................................................................................................11

LIST OF FIGURES

Figure

A-1 50th-percentile uranium urinalysis data used to estimate intakes of Type F 

uranium occurring 6/1/52 to 12/31/88...................................................................................

Page

12

A-2 84th-percentile uranium urinalysis data used to estimate intakes of Type F 

uranium occurring 6/1/52 to 12/31/88...................................................................................12

A-3 50th-percentile uranium urinalysis data used to estimate intakes of Type M 

uranium occurring 6/1/52 to 12/31/88...................................................................................13

A-4 84th-percentile uranium urinalysis data used to estimate intakes of Type M 

uranium occurring 6/1/52 to 12/31/88...................................................................................13

A-5 50th-percentile uranium urinalysis data used to estimate intakes of Type S 

uranium occurring 6/1/52 to 3/31/80.....................................................................................14

A-6 50th-percentile uranium urinalysis data used to estimate intakes of Type S 

uranium occurring 4/1/80 to 12/31/88...................................................................................14

A-7 Predicted 50th-percentile urinary excretion of Type S uranium from 1955 to 

1988 based on two independent intakes, compared to bioassay data ...................................15

A-8 Predicted 84th-percentile urinary excretion of Type S uranium from 1955 to 

1988 based on two independent intakes, compared to bioassay data ...................................15
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 5 of 15

1.0

Technical Information Bulletins (TIBs) are general working documents that provide 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. TIBs may be used to assist the 

National Institute for Occupational Safety and Health in the completion of individual dose 

reconstructions. 

PURPOSE

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 facility” as defined in the Energy Employees 

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

There are instances of energy employees who, for a variety of reasons, were not monitored for 

internal exposure during the course of their employment at a U.S. Department of Energy (DOE) 

facility, or whose records of such monitoring are incomplete or unavailable. In such cases, dose 

reconstructors can use data from coworkers to approximate an individual’s possible exposure. The 

purpose of this document is to provide the details of the calculation and assignment of intakes based 

on coworker data from the Paducah (Kentucky) Gaseous Diffusion Plant (PGDP) for the purpose of 

estimating unmonitored exposures or where records of monitoring are incomplete or unavailable. 

2.0

Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAU 2004a) describes the 

general process used to analyze bioassay data for assigning doses to individuals based on coworker 

results. 

OVERVIEW

Uranium urine bioassay results from 1952 through 1988 were obtained from the PGDP Dosimetry 

Section. The data were copied from working files that are the basis for the PGDP annual dose reports 

and dose histories. Some of the bioassay data were taken from handwritten logs and then added to 

the electronic data base. 

The database results are in units of micrograms or milligrams of total uranium per liter (μg/L or mg/L, 

respectively). All results were converted to μg/L for data analysis. There were a limited number of 

“beta” results in one of the files used (about 11%) which likely reflects measurement for technitium-99 

(

99Tc). The decision was made not to use these data, because most of the results (> 97%) were 

reported as zero. The uranium records provide a more robust data set for statistical analysis. 

A statistical analysis of these data was performed in accordance with ORAU (2004a). The resultant

values were input to the Integrated Modules for Bioassay Analysis (IMBA) Expert Office of 

Compensation Analysis and Support (OCAS)-Edition computer program. The bioassay data were 

assumed to represent excretion of 234U which is biokinetically identical to other uranium isotopes and 

would result in the highest dose; a data fit was performed to obtain intake rates for assigning dose

distributions. Bioassay results were converted from mass to activity before fitting.

3.0

3.1 SELECTED BIOASSAY DATA

DATA

PGDP urinalysis data were extracted from two separate Microsoft® Access files provided by the 

PGDP Dosimetry Section. File “PGDP_Historical_Urine” was the source of urinalysis data from 1977
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 6 of 15

through 1988. Sample dates were taken from the Sample_Date field. Total uranium urinalysis results

were taken from the Result field in the database; the Units field identified result units as micrograms 

per liter.

File “Historical_Urinalysis_Data_(unverified)” was the source of urinalysis data from October 1952 to 

mid-1977. Sample dates were taken from the Date_Sample field. Total uranium urinalysis results 

were taken from the Urinalysis_Result field in the database; there were no units associated with

urinalysis results in this file. Comparison to results with identified units in file “PGDP_Historical_Urine” 

and with information presented in Technical Basis Document for Paducah Gaseous Diffusion Plant – 

Occupational Internal Dose (ORAU 2004b) determined the results in this file were in units of 

milligrams per liter. Results in this file were converted to micrograms per liter for analysis.

Because both of the above files included PGDP uranium urinalysis data from 1977, the data were 

evaluated to identify and eliminate duplicate entries. 

3.2 ANALYSIS

Because of the number of sample results, data were analyzed by quarter from the final quarter of 

1952 through 1988. The effective bioassay date was set equal to the midpoint of the analysis period. 

A lognormal distribution was assumed, and the 50th and 84th percentiles were calculated for each 

quarter, using the method described in ORAU (2004a). Table A-1 in Attachment A lists the statistical 

analysis results.

4.0

4.1 ASSUMPTIONS

INTAKE MODELING

The IMBA Expert OCAS-Edition computer program requires urine results to be in units of activity per 

day. The total uranium results are in units of μg/L; therefore the results were multiplied by 1.4 in order 

to normalize them to the Reference Man excretion rate of 1400 mL per day. Bioassay results were 

converted from mass to activity before fitting assuming 0.0389 Bq/μg, characteristic of low-enrichment 

(2 percent) uranium. Low-enrichment uranium feed is the default value in ORAU (2004b) when the 

specific location where a claimant worked is not available. 

The uncertainty for each result in the intake calculation was assumed to be normally distributed. All 

results were equally weighted by applying a uniform absolute error of 1, indicating to IMBA that all 

results are (assumed to be) equally precise. A chronic exposure pattern was assumed for PGDP 

workers; this pattern also approximates a series of acute intakes with unknown intake dates. Intakes 

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

/hr and a 5-μm activity 

median aerodynamic diameter (AMAD) particle size distribution.

The database reported all results as “uranium.” The bioassay data were assumed to represent 

excretion of 234U. All uranium isotopes considered have long half-lives in relation to the assumed 

intake period so radioactive decay is not a consideration. Also, all uranium isotopes are biokinetically 

identical so there is no effect on the fitting of the data for intake determination. 234U was the isotope 

selected because it would result in the highest internal dose; the International Commission on 

Radiological Protection (ICRP) Publication 68 dose coefficients (also referred to as dose conversion 

factors) for 234U are 7% to 31% larger than those for 235U, 236U, and 238U (ICRP 1995). Because of the 

isotopic compositions of the source terms, the assumption of 234U will yield claimant-favorable doses. 
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 7 of 15

PGDP received uranium and began enrichment operations during June 1952 and first withdrew 

enriched uranium during November 1952. The November 1952 period is consistent with uranium 

urinalysis data; however, the first intake period was conservatively assumed to begin on June 1, 1952. 

4.2 BIOASSAY FITTING

The IMBA Expert OCAS-Edition computer program was used to fit the bioassay results to a series of 

inhalation intakes. Quarterly data from 1952 through 1988 were fit as a series of chronic intakes. 

The intake assumptions were based on patterns observed in the bioassay data. The analysis for this 

TIB used periods with constant chronic intake rates by selecting time spans for which the bioassay 

results are of similar magnitudes. The analysis started a new chronic intake period if the data 

indicated a significant sustained change in the bioassay results. By this method, the period from 1952 

through 1988 was divided into two chronic intake periods. 

4.3 URANIUM MATERIAL TYPES

Section 5.1.2.6 of the PGDP Technical Basis Document on Occupational Internal Dose (ORAU 

2004b) indicates uranium could be present in material with all three lung clearance rates (F, M, and 

S). Therefore, all three material types were evaluated. The bioassay results were entered into IMBA 

and the 50th-percentile intakes that resulted are shown in the figures in Attachment A. In these 

figures, quarterly bioassay data used in the fits are shown as blue dots (●), and data that are not used 

in the fits are shown as red dots (●). 

The Type S uranium compounds present at PGDP have very long radiological half-lives, and the body 

retains the compounds 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 PGDP for relatively short periods, each chronic intake of Type S material 

was fit independently, using only the bioassay results from the single intake period. This will result in 

an overestimate of intakes for assumed Type S exposures extending through both assumed intake 

periods. 

4.3.1

Uranium urine results were fit using a Type F material. Figure A-1 in Attachment A shows the fits to 

the 50th-percentile values from all intakes. The same intake periods were applied to the 84thpercentile values because the values followed a similar pattern, as shown in Figure A-2. These depict 

the expected excretion rates from an individual exposed for all the periods at the 50th- and 84thpercentile intake rates, respectively. Table 4-1 summarizes the intake periods and corresponding 

intake rates for the 50th and 84th percentiles. The geometric standard deviations (GSDs) were 

determined by dividing the 84th-percentile intake rates by the 50th-percentile intake rates. 

Type F

Table 4-1. Type F uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 1.11 3.05 2.75

4/1/1980 12/31/1988 0.279 0.862 3.09
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 8 of 15

4.3.2

The intake periods used in the Type F fits were applied to the Type M material fits. Figures A-3 and 

A-4 show the fits to the 50th- and 84th-percentile values, respectively, from all intakes. Table 4-2 

summarizes the intake periods and corresponding intake rates for the 50th and 84th percentiles. The 

GSDs were determined as described for the Type F intake rates. 

Type M

Table 4-2. Type M uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 4.53 12.42 2.74

4/1/1980 12/31/1988 1.07 3.35 3.13

4.3.3

The intake periods used in the Type F and M fits were applied to the Type S material fits. As 

discussed above, each chronic intake period for Type S material was fit independently. Figures A-5 

and A-6 show the individual fits for the 50th-percentile values. The 84th-percentile values were fit 

similarly. Table 4-3 summarizes the intake rates for the 50th- and 84th-percentile values. The GSDs 

were determined as described for the Type F intake rates.

Type S 

Table 4-3. Type S uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 51.45 138.3 2.69

4/1/1980 12/31/1988 18.91 59.11 3.13

Figures A-7 and A-8 show the 50th- and 84th-percentile predicted excretion rates, respectively, from 

all Type S intakes. 

5.0

5.1 INTAKE RATE SUMMARY

ASSIGNMENT OF INTAKES AND DOSES

A summary of uranium intake rates and GSDs for time periods from 1952 to 1988 is presented in 

Tables 5.1, 5.2, and 5.3 for Type F, M, and S material, respectively. These tables include potential 

intakes that may have occurred as early as June 1, 1952. Each of these tables has one GSD value 

adjusted from approximately 2.7 to 3. When calculating doses to individuals from their own bioassay 

data, a GSD of 3 is assigned to account for biological variation and uncertainty in the models. A GSD 

of at least 3 is assigned for intake rates based on coworker data. 

Table 5-1. Type F uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 1.11 3.05 3

4/1/1980 12/31/1988 0.279 0.862 3.1

Table 5-2. Type M uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 4.53 12.42 3

4/1/1980 12/31/1988 1.07 3.35 3.1
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 9 of 15

Table 5-3. Type S uranium intake periods and rates. 

Start date Stop date

Uranium intake rate (Bq/day)

50th percentile 84th percentile GSD

6/1/1952 3/31/1980 51.45 138.3 3

4/1/1980 12/31/1988 18.91 59.11 3.1

5.2 CONTRIBUTION FROM CONTAMINANTS IN RECYCLED URANIUM

Throughout the DOE complex, spent fuel from fission reactors has been processed to recover 

uranium for recycling. Because the uranium streams at PGDP could have contained recycled 

uranium, the dose from the added constituents, including plutonium, 237Np, and 99Tc, must be 

included. See ORAU (2004b) for information about intake values in relation to the uranium intake 

amounts. 

5.3 DOSE ASSIGNMENT

Doses to be assigned to individuals are calculated from the 50th-percentile intake rates; the material 

type resulting in the largest probability of causation, which is determined by the Department of Labor,

is selected. A comparison of the intake rates shows that the intake rate substantially increases as the 

material solubility decreases. However, because lower solubility materials remain in the lungs for 

longer periods, while higher solubility materials are transferred to the systemic organs, it is necessary 

to compare the annual doses on a case-by-case basis to determine which will deliver the larger dose 

to the organ of interest. Recycled uranium contaminants, when appropriate for the period, are a factor 

in this comparison.

The lognormal distribution is 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 is applied to all annual doses determined from the intake period.
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 10 of 15

REFERENCES

ICRP (International Commission on Radiological Protection), 1995, Dose Coefficients for Intakes by 

Workers, Publication 68, Pergamon Press, Oxford, England.

ORAU (Oak Ridge Associated Universities), 2004a, Analysis of Coworker Bioassay Data for Internal 

Dose Assignment, ORAUT-OTIB-0019, Oak Ridge, Tennessee.

ORAU (Oak Ridge Associated Universities), 2004b, Technical Basis Document for Paducah Gaseous 

Diffusion Plant – Occupational Internal Dose, ORAUT-TKBS-0019-5, Oak Ridge, Tennessee.
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 11 of 15

ATTACHMENT A

Table A-1. Summary of quarterly uranium 24-hr urinary excretion rate analyses, 1952-1988. 

Effective 

sample 

date

50th

percentile 

(Bq/d)

84th

percentile 

(Bq/d)

Effective 

sample 

date

50th

percentile 

(Bq/d)

84th

percentile 

(Bq/d)

Effective 

sample 

date

50th

percentile 

(Bq/d)

84th

percentile 

(Bq/d)

11/14/1952 0.599 3.246 5/15/1965 0.196 0.441 5/15/1977 0.334 0.972

8/15/1953 0.205 0.980 8/15/1965 0.242 0.467 8/15/1977 0.321 0.964

11/15/1953 0.362 1.373 11/15/1965 0.279 0.520 11/15/1977 0.432 1.189

2/15/1954 0.578 2.023 2/15/1966 0.326 0.672 2/15/1978 0.418 1.037

5/15/1954 0.466 1.643 5/15/1966 0.336 0.683 5/15/1978 0.330 0.862

8/15/1954 0.383 0.951 8/15/1966 0.293 0.598 8/15/1978 0.245 0.603

11/15/1954 0.330 1.010 11/15/1966 0.318 0.558 11/15/1978 0.209 0.621

2/15/1955 0.331 1.327 2/15/1967 0.305 0.612 2/15/1979 0.071 0.376

5/15/1955 0.471 1.419 5/15/1967 0.289 0.689 5/15/1979 0.159 0.577

8/15/1955 0.411 1.185 8/15/1967 0.275 0.503 8/15/1979 0.170 0.447

11/15/1955 0.468 1.465 11/15/1967 0.224 0.561 11/15/1979 0.258 0.658

2/15/1956 0.466 1.454 2/15/1968 0.241 0.523 2/15/1980 0.229 0.674

5/15/1956 0.407 0.800 5/15/1968 0.241 0.449 5/15/1980 0.117 0.330

8/15/1956 0.323 0.739 8/15/1968 0.293 0.647 8/15/1980 0.120 0.318

11/15/1956 0.328 0.930 11/15/1968 0.421 0.981 11/15/1980 0.109 0.232

2/15/1957 0.377 0.866 2/15/1969 0.529 1.165 2/15/1981 0.100 0.297

5/15/1957 0.453 1.063 5/15/1969 0.394 0.840 5/15/1981 0.081 0.243

8/15/1957 0.316 0.886 8/15/1969 0.278 0.677 8/15/1981 0.097 0.236

11/15/1957 0.351 0.900 11/15/1969 0.344 0.847 11/15/1981 0.083 0.207

2/15/1958 0.415 1.028 2/15/1970 0.218 0.661 2/15/1982 0.106 0.279

5/15/1958 0.353 0.859 5/15/1970 0.228 0.636 5/15/1982 0.061 0.199

8/15/1958 0.425 1.040 8/15/1970 0.223 0.764 8/15/1982 0.086 0.267

11/15/1958 0.365 0.857 11/15/1970 0.254 0.912 11/15/1982 0.081 0.250

2/15/1959 0.380 1.046 2/15/1971 0.260 0.797 2/15/1983 0.107 0.291

5/15/1959 0.277 0.770 5/15/1971 0.208 0.634 5/15/1983 0.116 0.307

8/15/1959 0.243 0.655 8/15/1971 0.253 0.746 8/15/1983 0.060 0.214

11/15/1959 0.311 0.930 11/15/1971 0.341 0.947 11/15/1983 0.098 0.276

2/15/1960 0.260 0.737 2/15/1972 0.298 0.875 2/15/1984 0.088 0.275

5/15/1960 0.197 0.581 5/15/1972 0.163 0.570 5/15/1984 0.069 0.245

8/15/1960 0.195 0.558 8/15/1972 0.176 0.548 8/15/1984 0.051 0.193

11/15/1960 0.287 1.119 11/15/1972 0.216 0.736 11/15/1984 0.062 0.222

2/15/1961 0.297 1.083 2/15/1973 0.175 0.632 2/15/1985 0.086 0.384

5/15/1961 0.190 0.551 5/15/1973 0.248 0.624 5/15/1985 0.055 0.249

8/15/1961 0.176 0.529 8/15/1973 0.212 0.630 8/15/1985 0.052 0.157

11/15/1961 0.340 0.977 11/15/1973 0.275 0.735 11/15/1985 0.053 0.156

2/15/1962 0.447 1.284 2/15/1974 0.221 0.665 2/15/1986 0.054 0.250

5/15/1962 0.412 0.950 5/15/1974 0.177 0.546 5/15/1986 0.039 0.106

8/15/1962 0.302 0.797 8/15/1974 0.232 0.695 8/15/1986 0.072 0.240

11/15/1962 0.369 0.911 11/15/1974 0.354 0.980 11/15/1986 0.055 0.185

2/15/1963 0.343 0.929 2/15/1975 0.422 1.185 2/15/1987 0.088 0.259

5/15/1963 0.327 0.807 5/15/1975 0.347 0.818 5/15/1987 0.061 0.213

8/15/1963 0.228 0.597 8/15/1975 0.307 0.698 8/15/1987 0.107 0.282

11/15/1963 0.274 0.678 11/15/1975 0.362 0.890 11/15/1987 0.091 0.229

2/15/1964 0.316 0.720 2/15/1976 0.401 0.869 2/15/1988 0.114 0.425

5/15/1964 0.305 0.917 5/15/1976 0.321 0.876 5/15/1988 0.119 0.341

8/15/1964 0.286 0.616 8/15/1976 0.329 0.906 8/15/1988 0.089 0.257

11/15/1964 0.233 0.540 11/15/1976 0.384 0.965 11/15/1988 0.110 0.358

2/15/1965 0.213 0.461 2/15/1977 0.260 0.879
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 12 of 15

Type F Uranium

Figure A-1. 50th-percentile uranium urinalysis data used to estimate intakes of Type F uranium

occurring 6/1/52 to 12/31/88. 

Figure A-2. 84th-percentile uranium urinalysis data used to estimate intakes of Type F uranium

occurring 6/1/52 to 12/31/88. 

● quarterly bioassay value

___ fit

● quarterly bioassay value 

___ fit
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 13 of 15

Type M Uranium

Figure A-3. 50th-percentile uranium urinalysis data used to estimate intakes of Type M uranium

occurring 6/1/52 to 12/31/88. 

Figure A-4. 84th-percentile uranium urinalysis data used to estimate intakes of Type M uranium

occurring 6/1/52 to 12/31/88. 

● quarterly bioassay value 

___ fit

● quarterly bioassay value 

___ fit
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 14 of 15

Type S Uranium

● quarterly bioassay value 

● not used in fit

___ fit

Figure A-5. 50th-percentile uranium urinalysis data used to estimate intakes of Type S uranium

occurring 6/1/52 to 3/31/80. 

● quarterly bioassay value 

● not used in fit

___ fit

Figure A-6. 50th-percentile uranium urinalysis data used to estimate intakes of Type S uranium

occurring 4/1/80 to 12/31/88. 
Document No. ORAUT-OTIB-0037 Revision No. 00 Effective Date: 09/20/2005 Page 15 of 15

Figure A-7. Predicted 50th-percentile urinary excretion of Type S uranium from 1952 to 1988 based 

on two independent intakes, compared to bioassay data. 

Figure A-8. Predicted 84th-percentile urinary excretion of Type S uranium from 1952 to 1988 based 

on two independent intakes, compared to bioassay data. 

● not used in fit

___ 2-intake estimate

● not used in fit

___ 2-intake estimate