ORAU TEAM

Dose Reconstruction

Project for NIOSH

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

Page 1 of 16

Document Title:

Internal Dosimetry Coworker Data for 

Portsmouth Gaseous Diffusion Plant

Document Number: ORAUT-OTIB-0036

Revision: 00

Effective Date: 07/29/2005

Type of Document: OTIB

Supersedes: None

Subject Expert: Tracy A. Ikenberry

Document Owner

Approval: Signature on File Approval Date: 07/20/2005

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 07/26/2005

Richard E. Toohey, Project Director

Approval: Signature on File Approval Date: 07/29/2005

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

DOCUMENTS MA RKED AS A TOTAL REWRITE, REV ISION, OR PA GE CHANGE REPLA CE THE PRIOR REV ISION. 

PLEASE DISCARD / DESTROY ALL COPIES OF THE PRIOR REV ISION.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 2 of 16

PUBLICATION RECORD

EFFECTIVE

DATE

REVISION 

NUMBER DESCRIPTION

04/26/2005 00-A New technical information bulletin for assignment of Portsmouth 

Gaseous Diffusion Plant internal doses based on coworker 

bioassay data. Initiated by Tracy A. Ikenberry.

05/27/2005 00-B Incorporates internal review comments. Initiated by Tracy A. 

Ikenberry.

07/15/2005 00-C Incorporates NIOSH review comments. Initiated by Tracy A.

Ikenberry.

07/29/2005 00 First approved issue. Training required: As determined by the 

Task Manager. Initiated by Tracy A. Ikenberry.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 3 of 16

TABLE OF CONTENTS

Section

Publication Record............................................................................................................................

Page

2

1.0 Purpose ...................................................................................................................................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 ..................................................................................................................6

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

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

4.3.2 Type M.......................................................................................................................7

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-0036 Revision No. 00 Effective Date: 07/29/2005 Page 4 of 16

LIST OF TABLES

Table

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

Page

7

4-2 Type M uranium intake periods and rates...............................................................................7

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

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

5-2 Type M uranium intake periods and rates...................................................................................8

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

A-1 Summary of quarterly uranium 24-hour urinary excretion rate analyses, 1955-

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

LIST OF FIGURES

Figure

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

uranium occurring 1/1/55 to 12/31/88...................................................................................

Page

12

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

uranium occurring 1/1/55 to 12/31/88...................................................................................12

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

uranium occurring 1/1/55 to 12/31/88...................................................................................13

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

uranium occurring 1/1/55 to 12/31/88...................................................................................13

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

uranium occurring 1/1/55 to 12/31/56...................................................................................14

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

uranium occurring 1/1/57 to 12/31/58...................................................................................14

A-7 50th-percentile uranium urinalysis data used to estimate intakes of Type S 

uranium occurring 1/1/59 to 6/30/61.....................................................................................15

A-8 50th-percentile uranium urinalysis data used to estimate intakes of Type S 

uranium occurring 7/1/61 to 12/31/88...................................................................................15

A-9 Predicted 50th- percentile urinary excretion of Type S uranium from 1955-

1988 based on four independent intakes, compared to bioassay data...................................16

A-10 Predicted 84th-percentile urinary excretion of Type S uranium from 1955-1988 

based on four independent intakes, compared to bioassay data ...........................................16
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 5 of 16

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 Portsmouth (Ohio) Gaseous Diffusion Plant (PORTS) 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

Bioassay results from 1955 to 1988 were obtained from the Health Physics Department at PORTS.

The urinalysis data were derived from an Oracle 7.1 database (DEC/VMS operating system) that had 

been maintained by health physics personnel at the site for several years. Database information was

reviewed for extraneous data and cleared by an authorized derivative classifier. 

There were nearly a quarter million data records provided, which included gross alpha measurements 

with units of gross alpha disintegrations per minute per 100 milliliters (dpm/100 mL) and total uranium 

measurements with units of milligrams per liter (mg/L). Fewer than 4% of the data records included a 

nonzero uranium entry, while approximately 30% of the gross alpha records were nonzero. The gross 

alpha records provide a more robust data set for statistical analysis; therefore the gross alpha 

measurements were used as the indicator for uranium rather than the relatively few nonzero uraniumspecific measurements in the database. 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 OCAS-Edition computer program. It was assumed the data 

represented excretion of 234U and a data fit was performed to obtain intake rates for assigning dose

distributions.

3.0

3.1 SELECTED BIOASSAY DATA

DATA

Data were extracted from the urinalysis table in “HR_prior_1993,” a Microsoft® Access version of the 

PORTS database. Sample dates were taken from the Sample Date field. Gross alpha urinalysis 
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 6 of 16

results were taken from the RES_Alpha field in the database, which contains gross alpha bioassay 

results in units of dpm/100 mL. 

3.2 ANALYSIS

Because of the number of sample results, data were analyzed by quarter, with the exception of 1955, 

when the analysis was for the entire year. 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 (year for 1955), 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 gross alpha results are in units of dpm/100 mL; therefore, the results were multiplied by 14 

in order to normalize them to the Reference Man excretion rate of 1400 mL per day. 

Each result used in the intake calculation was assumed to be normally distributed, and a uniform 

absolute error of 1 was applied to all results, thereby weighting all results equally. A chronic exposure

pattern was assumed; while this is unlikely for workers at PORTS it 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 modeled results as “gross alpha,” which this analysis conservatively 

assumed to be all uranium. Because a variety of enrichments occurred at PORTS, 234U was assumed 

for the IMBA intake modeling. This assumption does not affect the fitting of the data for intake 

determination (i.e., the same total intakes would be obtained for any enrichment that was assumed) 

because all uranium isotopes behave the same biokinetically and the isotopes considered in this 

analysis have long half-lives in relation to the assumed intake period. 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 234U dose conversion factor will yield 

claimant-favorable doses.

Although PORTS began enrichment operations in September 1954, there are no gross alpha 

bioassay results before 1955 in the database. Intake modeling was based on the 1955 and later data;

however uranium intakes should be considered possible as early as September 1, 1954. 

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 1955 through 1988 were fit as a series of chronic intakes. 

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

constant chronic intake rates were chosen by selecting time spans for which the bioassay results are 

of similar magnitudes. A new chronic intake period was started if the data indicated a significant 

sustained change in the bioassay results. By this method, the period from 1955 through 1988 was 

divided into four chronic intake periods. 
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4.3 URANIUM MATERIAL TYPES

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

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

rates. Therefore, all three material types were evaluated. The bioassay results were entered into 

IMBA and the assumed 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 PORTS have very long radiological half-lives, and the 

body retains the material 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 PORTS 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 multiple 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 (dpm/day)

50th percentile 84th percentile GSD

1/1/1955 12/31/1956 115.6 504.8 4.37

1/1/1957 12/31/1958 73.75 239.6 3.25

1/1/1959 6/30/1961 155.4 565.8 3.64

7/1/1961 12/31/1988 33.37 111 3.33

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 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 (dpm/day)

50th percentile 84th percentile GSD

1/1/1955 12/31/1956 497.4 2161 4.34

1/1/1957 12/31/1958 275.7 809.1 2.93

1/1/1959 6/30/1961 664.9 2,449 3.68

7/1/1961 12/31/1988 132.8 440.9 3.32
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 8 of 16

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 to 

A-8 show the individual fits for the 50th-percentile values. The 84th-percentile values are not shown 

but 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 (dpm/day)

50th percentile 84th percentile GSD

1/1/1955 12/31/1956 11,990 51,429 4.29

1/1/1957 12/31/1958 8,344 27,002 3.24

1/1/1959 6/30/1961 16,423 61,616 3.75

7/1/1961 12/31/1988 1,644 5,233 3.18

Figures A-9 and A-10 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 different time periods from 1954 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 September 1, 1954. Type F material 

during the period from 1957 through 1988 had intake rate GSDs within 10% of each other; for 

simplicity the largest intake rate GSD was assigned to all three intake rates during the period, as listed 

in Table 5-1. Similarly, with Type M material, the largest GSD for the period from 1959 through 1988 

was assigned to both of the intake rates during the period, as indicated in Table 5-2. Table 5-2 also 

has one GSD value adjusted from 2.93 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. No changes were 

made for the Type S material listed in Table 5-3; it is identical to Table 4-3 but presented here for 

completeness. 

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

Start date Stop date

Uranium intake rate (dpm/day)

50th percentile 84th percentile GSD

9/1/1954 12/31/1956 115.6 504.8 4.4

1/1/1957 12/31/1958 73.75 239.6 3.6

1/1/1959 6/30/1961 155.4 565.8 3.6

7/1/1961 12/31/1988 33.37 111 3.6

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

Start date Stop date

Uranium intake rate (dpm/day)

50th percentile 84th percentile GSD

9/1/1954 12/31/1956 497.4 2161 4.3

1/1/1957 12/31/1958 275.7 809.1 3

1/1/1959 6/30/1961 664.9 2,449 3.7

7/1/1961 12/31/1988 132.8 440.9 3.7
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 9 of 16

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

Start date Stop date

Uranium intake rate (dpm/day)

50th percentile 84th percentile GSD

9/1/1954 12/31/1956 11,990 51,429 4.3

1/1/1957 12/31/1958 8,344 27,002 3.2

1/1/1959 6/30/1961 16,423 61,616 3.8

7/1/1961 12/31/1988 1,644 5,233 3.2

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 PORTS 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-0036 Revision No. 00 Effective Date: 07/29/2005 Page 10 of 16

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 Portsmouth 

Gaseous Diffusion Plant – Occupational Internal Dose, ORAUT-TKBS-0015-5, Oak Ridge, 

Tennessee.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 11 of 16

ATTACHMENT A

Table A-1. Summary of quarterly uranium 24-hour urinary excretion rate analyses, 1955-1988.

Effective 

sample date

50th 

percentile 

(dpm/d)

84th 

percentile 

(dpm/d)

Effective 

sample date

50th 

percentile 

(dpm/d)

84th 

percentile 

(dpm/d)

Effective

sample date

50th 

percentile 

(dpm/d)

84th 

percentile 

(dpm/d)

7/1/1955* 28.95 150.76 8/15/1966 2.36 12.36 11/15/1977 13.75 36.39

2/15/1956 28.42 128.17 11/15/1966 3.03 13.65 2/15/1978 14.76 38.34

5/15/1956 36.58 152.73 2/15/1967 3.91 25.02 5/15/1978 3.58 15.68

8/15/1956 36.09 143.76 5/15/1967 6.07 23.81 2/15/1979 2.18 10.12

11/15/1956 26.66 107.93 2/15/1968 3.13 15.49 5/15/1979 11.86 28.42

2/15/1957 24.96 93.31 5/15/1968 3.44 14.25 8/15/1979 11.04 34.86

5/15/1957 22.03 83.84 8/15/1968 3.54 15.65 11/15/1979 9.68 21.07

8/15/1957 22.33 60.55 11/15/1968 3.91 18.95 2/15/1980 11.25 22.64

11/15/1957 19.39 62.82 2/15/1969 14.06 103.20 5/15/1980 12.70 22.87

2/15/1958 18.60 55.84 5/15/1969 5.50 29.89 8/15/1980 12.86 24.34

5/15/1958 21.89 70.35 8/15/1969 4.74 21.70 11/15/1980 13.43 23.67

8/15/1958 13.74 48.28 11/15/1969 7.50 33.38 2/15/1981 13.17 25.28

11/15/1958 21.07 64.17 2/15/1970 6.58 51.85 5/15/1981 12.65 24.97

2/15/1959 29.45 91.09 5/15/1970 8.67 37.69 8/15/1981 10.78 22.94

5/15/1959 44.64 139.88 8/15/1970 4.87 18.97 11/15/1981 10.58 22.79

8/15/1959 26.51 89.44 11/15/1970 5.22 20.81 2/15/1982 6.07 19.98

11/15/1959 31.04 111.51 2/15/1971 6.86 36.73 5/15/1982 9.11 18.76

2/15/1960 58.01 175.95 5/15/1971 9.89 41.37 8/15/1982 8.68 25.29

5/15/1960 55.25 192.36 8/15/1971 8.68 32.76 11/15/1982 8.76 22.90

8/15/1960 53.58 174.45 11/15/1971 8.51 28.29 2/15/1983 6.25 19.42

11/15/1960 48.61 197.29 2/15/1972 5.39 22.11 5/15/1983 9.11 23.11

2/15/1961 38.73 175.27 5/15/1972 8.46 25.16 8/15/1983 9.47 23.21

5/15/1961 36.27 187.36 8/15/1972 5.13 18.02 11/15/1983 9.84 27.32

8/15/1961 21.39 59.48 11/15/1972 7.18 30.52 2/15/1984 7.85 21.06

11/15/1961 14.43 42.94 2/15/1973 8.09 37.98 5/15/1984 10.50 21.44

2/15/1962 7.39 32.13 5/15/1973 4.22 22.53 8/15/1984 12.07 25.75

5/15/1962 7.68 34.96 8/15/1973 4.22 21.70 11/15/1984 7.84 27.94

8/15/1962 14.81 43.17 11/15/1973 6.79 76.22 2/15/1985 7.26 20.19

11/15/1962 9.47 44.79 2/15/1974 4.26 27.83 5/15/1985 10.36 23.48

2/15/1963 4.07 31.74 5/15/1974 6.79 22.55 8/15/1985 13.33 30.05

5/15/1963 6.49 17.55 8/15/1974 6.08 19.07 11/15/1985 8.43 17.77

8/15/1963 6.70 25.84 11/15/1974 8.89 22.37 2/15/1986 8.09 14.61

11/15/1963 11.68 62.28 2/15/1975 10.51 30.95 5/15/1986 11.92 18.22

2/15/1964 9.45 45.78 5/15/1975 11.72 30.17 8/15/1986 13.31 23.32

5/15/1964 10.19 23.24 8/15/1975 13.54 60.73 11/15/1986 13.38 25.30

8/15/1964 8.14 30.99 11/15/1975 10.15 40.65 2/15/1987 12.29 25.60

11/15/1964 13.04 49.30 2/15/1976 11.36 29.62 5/15/1987 13.85 31.03

2/15/1965 23.92 176.43 5/15/1976 13.86 26.81 8/15/1987 9.15 25.24

5/15/1965 13.88 88.81 8/15/1976 16.72 40.62 11/15/1987 7.04 21.65

8/15/1965 10.92 58.95 11/15/1976 19.89 62.78 2/15/1988 5.06 18.42

11/15/1965 8.21 38.71 2/15/1977 17.04 37.21 5/15/1988 11.93 29.26

2/15/1966 7.02 25.13 5/15/1977 16.79 36.86 8/15/1988 14.59 29.91

5/15/1966 3.35 23.23 8/15/1977 17.44 40.72 11/15/1988 7.13 18.78

*Due to the low number of urinalysis samples in 1955, only the annual summary w as analyzed.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 12 of 16

Type F Uranium

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

occurring 1/1/55 to 12/31/88.

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

occurring 1/1/55 to 12/31/88.

● quarterly bioassay value

___ fit

● quarterly bioassay value 

___ fit
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 13 of 16

Type M Uranium

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

occurring 1/1/55 to 12/31/88. 

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

occurring 1/1/55 to 12/31/88.

● quarterly bioassay value 

___ fit

● quarterly bioassay value 

___ fit
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 14 of 16

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 1/1/55 to 12/31/56. 

● 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 1/1/57 to 12/31/58.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 15 of 16

● quarterly bioassay value 

● not used in fit

___ fit

Figure A-7. 50th-percentile uranium urinalysis data used to estimate intakes of Type S uranium

occurring 1/1/59 to 6/30/61.

● quarterly bioassay value 

● not used in fit

___ fit

not used in fit

used in fit

Figure A-8. 50th-percentile uranium urinalysis data used to estimate intakes of Type S uranium

occurring 7/1/61 to 12/31/88.
Document No. ORAUT-OTIB-0036 Revision No. 00 Effective Date: 07/29/2005 Page 16 of 16

Figure A-9. Predicted 50th- percentile urinary excretion of Type S uranium from 1955 to 1988 based 

on four independent intakes, compared to bioassay data.

Figure A-10. Predicted 84th-percentile urinary excretion of Type S uranium from 1955 to 1988 based 

on four independent intakes, compared to bioassay data.

● not used in fit

___ 4-intake estimate

● not used in fit

___ 4-intake estimate