ORAU TEAM 

Dose Reconstruction 

Project for NIOSH

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

Page 1 of 35

Document Title: 

Internal Dosimetry Coworker Data for 

Rocky Flats Environmental Technology 

Site 

Document Number: ORAUT-OTIB-0038 

Revision: 00 

Effective Date: 08/03/2006 

Type of Document: OTIB 

Supersedes: None 

Subject Experts: Matthew Arno, Robert N. Cherry, and Joseph C. Lochamy 

Document Owner 

Approval: Signature on File Approval Date: 07/26/2006 

John M. Byrne, Task 3 Manager 

Concurrence: Signature on File Concurrence Date: 07/26/2006 

Edward F. Maher, Task 5 Manager 

 

Concurrence: Signature on File Concurrence Date: 07/27/2006 

Kate Kimpan, Project Director 

Approval: Signature on File Approval Date: 08/03/2006 

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-0038 Revision No. 00 Effective Date: 08/03/2006 Page 2 of 35 

PUBLICATION RECORD 

EFFECTIVE 

DATE 

REVISION 

NUMBER DESCRIPTION 

08/03/2006 00 New technical information bulletin for assigning Rocky Flats 

Environmental Technology Site internal doses based on coworker 

bioassay data. First approved issue. There is no change to the 

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

determined by the Task Manager. Initiated by Robert M. Cherry, 

Matthew Arno, and Joseph C. Lochamy. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 3 of 35 

TABLE OF CONTENTS 

SECTION TITLE PAGE

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

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

2.0 Purpose .........................................................................................................................................8

3.0 Data Overview ...............................................................................................................................9

3.1 Bioassay Data Selection ......................................................................................................... 9

3.2 Analysis................................................................................................................................. 10

4.0 Intake Modeling ...........................................................................................................................10

4.1 Assumptions ......................................................................................................................... 10

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

4.3 Material Types ...................................................................................................................... 11

4.3.1 Uranium.........................................................................................................................11

4.3.2 Plutonium ......................................................................................................................12

5.0 Assigning Intakes and Doses.......................................................................................................13

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

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

References ...........................................................................................................................................15

LIST OF TABLES 

TABLE TITLE PAGE

5-1 Derived uranium intake rate, 1953 to 1988...............................................................................13

5-2 Derived plutonium intake rates, 1952 to 1988 ..........................................................................13

A-1 Summary of annual uranium urinary excretion rate analyses, 1953 to 1989............................16

A-2 Summary of annual plutonium urinary excretion rate analyses, 1952 to 1988 .........................17

A-2 Summary of annual plutonium urinary excretion rate analyses, 1952 to 1988 .........................18

A-3 241Am lung count bioassay data for individualized 239Pu Type S fits.........................................18

B-1 IMBA-derived uranium intake rates, dpm/day...........................................................................28

B-2 IMBA-derived plutonium/americium intake rates, Type M ........................................................33

B-3 IMBA-derived plutonium/americium intake rates, Type S .........................................................35
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 4 of 35 

LIST OF FIGURES 

FIGURE TITLE PAGE

B-1 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1976, 50th-percentile, Type F......................................................................19

B-2 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type F......................................................................19

B-3 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots) from all 

intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type F..........................................................20

B-4 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1988, 84th-percentile, Type F......................................................................20

B-5 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1976, 50th-percentile, Type M .....................................................................21

B-6 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type M .....................................................................21

B-7 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots) from all 

intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type M.........................................................22

B-8 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1988, 84th-percentile, Type M .....................................................................22

B-9 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1958, 50th-percentile, Type S......................................................................23

B-10 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1959 to 12/31/1960, 50th-percentile, Type S......................................................................23

B-11 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1961 to 12/31/1963, 50th-percentile, Type S......................................................................24

B-12 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1964 to 12/31/1976, 50th-percentile, Type S......................................................................24

B-13 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type S......................................................................25

B-14 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1958, 84th-percentile, Type S......................................................................25

B-15 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1959 to 12/31/1960, 84th-percentile, Type S......................................................................26
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 5 of 35 

B-16 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1961 to 12/31/1963, 84th-percentile, Type S......................................................................26

B-17 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1964 to 12/31/1976, 84th-percentile, Type S......................................................................27

B-18 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 84th-percentile, Type S......................................................................27

B-19 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots) from all 

intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type S .........................................................28

B-20 Predicted uranium bioassay results (line) calculated using IMBA-derived U 

intake rates compared with measured uranium-in-urine results (dots) from all 

intakes 1/1/1953 to 12/31/1988, 84th-percentile, Type S .........................................................28

B-21 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1952 to 

12/31/1961, 50th-percentile, Type M ........................................................................................29

B-22 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1962 to 

12/31/1969, 50th-percentile, Type M ........................................................................................29

B-23 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1970 to 

12/31/1979, 50th-percentile, Type M ........................................................................................30

B-24 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1980 to 

12/31/1988, 50th-percentile, Type M ........................................................................................30

B-25 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1952 to 

12/31/1961, 84th-percentile, Type M ........................................................................................31

B-26 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1962 to 

12/31/1969, 84th-percentile, Type M ........................................................................................31

B-27 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1970 to 

12/31/1979, 84th-percentile, Type M ........................................................................................32

B-28 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1980 to 

12/31/1988, 84th-percentile, Type M ........................................................................................32

B-29 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), from all 

intakes 1/1/1952 to 12/31/1988, 50-percentile, Type M............................................................33

B-30 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), from all 

intakes 1/1/1952 to 12/31/1988, 84th-percentile, Type M.........................................................33

B-31 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1952 to 

12/31/1988, 50-percentile, Type S............................................................................................34

B-32 Predicted plutonium bioassay results (line) calculated using IMBA-derived Pu 

intake rates compared with measured Pu-in-urine results (dots), 1/1/1952 to 

12/31/1988, 84th-percentile, Type S.........................................................................................34
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 6 of 35 

B-33 Predicted Am bioassay results (line) calculated using IMBA-derived Am 

intake rates compared with measured Am lung burden results (dots), 

1/1/1952 to 12/31/1988, 50th-percentile, Type S......................................................................35

B-34 Predicted Am bioassay results (line) calculated using IMBA-derived Am 

intake rates compared with measured Am lung burden results (dots), 

1/1/1952 to 12/31/1988, 84th-percentile, Type S......................................................................35
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 7 of 35 

ACRONYMS AND ABBREVIATIONS 

CEDR Comprehensive Epidemiologic Data Resource 

d day 

DOE Department of Energy 

dpm disintegrations per minute 

GSD geometric standard deviation 

hr hour 

ICRP International Commission on Radiological Protection 

IMBA Integrated Modules for Bioassay Analysis 

IREP NIOSH Interactive RadioEpidemiological Program 

mL milliliter 

μg microgram 

nCi nanocurie 

NIOSH National Institute for Occupational Safety and Health 

OCAS Office of Compensation and Analysis 

pCi picocurie 

PoC Probability of Causation 

ppm parts per million 

RFETS Rocky Flats Environmental Technology Site 

TIB Technical Information Bulletin (also OTIB) 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 8 of 35 

1.0 INTRODUCTION

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. 

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 Energy1

 [DOE] facility” as defined in the Energy Employees 

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

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

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

results. Coworker Data Exposure Profile Development (ORAUT 2004b) describes the approach and 

processes to be used to develop reasonable exposure profiles based on available dosimetric 

information for workers at DOE sites. 

Bioassay results were obtained through the Comprehensive Epidemiologic Data Resource (CEDR), 

formerly a DOE public-use repository of data from occupational and environmental health studies of 

workers at DOE facilities and nearby communities. In 1990, the Department of Health and Human 

Services assumed responsibility for many aspects of the epidemiology programs and now provides 

CEDR data. The CEDR database used here contains approximately 300,000 bioassay records from 

Rocky Flats Environmental Technology Site (RFETS) and includes measurements for uranium, 

plutonium, and americium for the years 1952 through 1988. Based on a spot check, this data set 

coincides well with original RFETS paper records. It is appropriate for use only at RFETS. 

Furthermore, the database is representative of worker bioassay results at RFETS during a substantial 

part of the operating cycle at this site. However, its use is only appropriate for the specific time 

periods and radionuclides discussed later in this document. 

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

techniques, and measurement period. These units usually were disintegrations per minute per 24 hr 

but, for example, depleted uranium bioassay results were reported in units of micrograms per 24 hr 

from 1952 until April 1964. The specific units for each radionuclide are provided in the appropriate 

sections of this document. 

A statistical analysis of the data was performed according to ORAUT (2004a) and its implementing 

procedure, ORAUT (2005). The results were entered in the Integrated Modules for Bioassay Analysis 

(IMBA) ExpertTM Office of Compensation and Analysis (OCAS)-Edition computer software to obtain 

intake rates for assigning dose distributions. 

2.0 PURPOSE

Some employees at DOE sites were not monitored for internal ionizing radiation exposure or the 

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

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

 

1

 References to DOE in this document include DOE and its predecessor agencies: the Manhattan Engineer District (1942 to 

1946), the U.S. Atomic Energy Commission (1947 to 1975), the Energy Research and Development Administration (1975 to 

1977), and DOE (1977 to the present). 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 9 of 35 

provide monitored coworker information for calculating and assigning occupational internal doses to 

employees at RFETS for whom no or insufficient bioassay monitoring records exist. 

3.0 DATA OVERVIEW

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

of analysis. More detailed radionuclide-specific information is provided in section 4. 

3.1 BIOASSAY DATA SELECTION 

Urinalysis data for uranium and plutonium from 1952 to 1988 were extracted from a Microsoft®

Access table named “RFFACW02_BIOASSAY.” There were just over 300,000 records in the 

urinalysis database. Four cases had a date prior to 1952: one each in 1950 and 1951 and two that 

appeared to be date errors (years incorrectly entered as 1911 and 1923). 

In most cases, both the uranium and plutonium results were recorded as dpm/24 hr. However, the 

depleted uranium units are date-dependent: through April 1964 the units were μg/24 hr; from May 

1964 to 1988, the units were dpm/24 hr. Micrograms of uranium were converted to dpm by a 0.89 

multiplier determined from the isotopic abundances specified for depleted uranium in IMBA. Once 

converted to dpm, the uranium data were assumed to be entirely U-234. See section 4.1 for 

additional discussion on using U-234 for the analyses. 

All of the uranium and plutonium urinalysis results were recorded either as positive numbers or zeros. 

In general, a zero entry meant the result was less than some reporting level; however, after April 6, 

1970, actual results were reported according to Technical Basis Document for the Rocky Flats Plant – 

Occupational Internal Dose (ORAUT 2004c). Zeros were reported in 176,900 records, a little over 

half of the results for all measurements. The technical basis document (TBD; ORAUT 2004c) states 

that uranium and plutonium urinalysis data with a “1” flag in the “nocalc” column of the database 

(about 2,500 records out of roughly 300,000) should be (and were) excluded from analysis because 

the data did not meet quality objectives. 

In vivo 241Am lung data from 1965 to 1988 were extracted from a Microsoft® Access table named 

“RFFACW02_RFWB.” There were just fewer than 80,000 241Am records in the lung database. From 

1965 through 1971, all results (about 4,000) were reported as zero, with no explanation of what those 

values might have meant. Therefore, no analyses were performed on those data. Furthermore, the 

TBD (ORAUT 2004c) mentions that the 241Am activities were quantified only if a known plutonium 

incident occurred. However, the TBD also says that results were sometimes recorded (in counts per 

minute) when no known incident had occurred. Some results were also recorded in micrograms or 

nanocuries. Thus, careful interpretation of the data units was imperative. After 1971, positive values 

began to appear but there still were no exclusion instructions for when 0 values were reported. (See 

the “nocalc” discussion above.) Therefore, 0 results were treated as zeros because no better 

information was available. Calculations of the lung plutonium values recorded with the 241Am lung 

data were determined by using the 241Am data and an assumed concentration of 100 ppm (by weight) 

of 241Am in the plutonium. 

In both the urinalysis and lung counting data sets, badge numbers (column “ID”) are associated with 

most records. However, in the urinalysis data, 55,200 records had a “0” in the badge-number column. 

It was not determined what a “0” badge ID meant other than, perhaps, to identify unbadged personnel. 

For the urinalysis data, about 34,000 of the “0” badges were plutonium records; 15,000 were gross 

alpha, "A;" and 6,000 were "U". It was decided to treat “0” badge numbers as one individual when 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 10 of 35 

counting the number of unique individuals in any period. The “sdate” column provided the date of 

each analysis in YYMMDD order. 

3.2 ANALYSIS 

Bioassay data were analyzed by quarter or year, depending on the amount of data available during 

the periods. A lognormal distribution was assumed. As mentioned in the previous section, a large 

fraction of the uranium and plutonium urinalysis data were entered as zeros. In many cases, this fact 

made analysis of the data difficult, since so few positive values were reported. Thus, where a 

reporting level was specified in the site Technical Basis Document (ORAUT 2004c) and where zeros 

were inserted for the actual values (below the reporting level) in the original data, a linear distribution 

between zero and the reporting level was substituted for the zeros. The linear distribution had the 

form, c/n, 2c/n, 3c/n,..., nc/n, where n is the number of zero values less than the reporting level, c. 

Using R2

 as the goodness-of-fit criterion, this linear distribution (alone) fits a lognormal transformation 

by better than 80% and typically significantly improves the goodness of fit for the entire data set. 

Furthermore, the linear distribution has an average equal to half of the reporting value, consistent with 

the general dose reconstruction practice of assigning half of the lower limit of detection for missed 

dose calculations. Consequently, substituting a linear distribution for these zero entries appears 

reasonable. 

Whenever a linear distribution was substituted for values below a reporting level, the reporting levels 

given in the version of ORAUT (2004c) used to develop this document were used. For enriched 

uranium, these reporting levels were 8.8 dpm/24 hr through 1963, and 20-28 dpm/24 hr after 1963. 

For depleted uranium, the reporting levels were 5.8 dpm/24 hr through April 1964, 20-28 dpm for May 

1964-79, and actual measured values thereafter. For plutonium, these reporting levels were 0.88 

dmp/24 hr through 1961, 0.2 dpm/24 hr for 1962-April 1970, and actual measured values after April 

1970. The reporting level fro gross alpha through 1963 was 8.8 dpm/24 hr (assigned as enriched 

uranium) and 0.9 dpm/24 hr thereafter (assigned as plutonium). No reporting level was given for 

americium-in-lung measurements. 

After log transforming the data, the 50th and 84th percentiles were determined for each period using 

the method described in ORAUT (2004a). Tables A-1, A-2, and A-3 in Attachment A show the 

statistical analysis results for uranium, plutonium, and 241Am, respectively. 

4.0 INTAKE MODELING

This section discusses intake modeling assumptions, intake fitting, and the intake materials (uranium 

and plutonium). 

4.1 ASSUMPTIONS 

Each result used in the intake calculations was assumed to be normally distributed. A uniform 

absolute error of 1 was applied to all results, thus assigning the same weight to each result. IMBA 

requires results to be in units of activity per day; therefore, all urinalysis results were normalized, as 

needed, to 24-hr samples, using 1,400 mL, the volume of urine excreted by Reference Man in a 24-hr 

period. 

Because of the nature of work at RFETS, it is possible that intakes could have been either chronic or 

acute. However, a series of acute intakes can be approximated as a chronic intake. Therefore, 

intakes were assumed to be chronic and were assumed to occur through inhalation, using a default 

breathing rate of 1.2 m3

/hr and a 5-μm activity median aerodynamic diameter particle size distribution. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 11 of 35 

For intake modeling purposes, all uranium activity was assumed to be 234U. This assumption does not 

affect the fitting of the data for intake determination because all uranium isotopes behave the same 

biokinetically and the isotopes considered in this analysis all have long half-lives in relation to the 

assumed intake period. 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). Therefore, the assumption that the intake is 100% 234U 

provides a claimant-favorable result. 

For plutonium, 239Pu was assumed for the intake modeling. Prior to the mid-1970s, plutonium 

urinalysis was performed by chemical separation followed by the counting of all alpha-emitting 

isotopes of plutonium (i.e., 238Pu, 239Pu, and 240Pu). In the mid-1970s, alpha spectroscopy was used 

to differentiate between the various alpha-emitting plutonium isotopes. For this modeling, the grossplutonium alpha results are assumed to represent only alphas from 239Pu, which results in 

approximately a 2% overestimate of the modeled intakes. This assumption is made to enable 

consistent modeling of data from both types of urinalysis. 

Starting in 1972, lung counts were performed to determine the lung burden of 241Am. These lung 

counts can be used to determine the intake of plutonium. For each plutonium material type, the more 

limiting value of the intakes as determined by the americium lung counts or plutonium urinalysis was 

used. Use of the higher value (from the less sensitive bioassay method for a given material type) 

would be inconsistent with the available bioassay records since a higher intake would result in higherthan-observed bioassay results from the more sensitive bioassay method. 

4.2 BIOASSAY FITTING 

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

inhalation intakes. 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. Periods with 

constant chronic intake rates were chosen by selecting periods where the bioassay results were 

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

the bioassay results. By this method, 1952 through 1988 was divided into multiple chronic intake 

periods. 

4.3 MATERIAL TYPES 

ORAUT (2004c) discusses Rocky Flats internal dosimetry data for the dose reconstructor, including 

guidance for the appropriate use of that information. Workers at Rocky Flats had the potential to 

receive intakes of plutonium, americium, enriched uranium, and depleted uranium. Site-specific 

internal dosimetry information for other radionuclides is rare or not available (ORAU 2004c). 

4.3.1 Uranium

Because the uranium isotopes present at RFETS have very long radiological half-lives, and the 

material is retained in the body for long periods, excretion results are not independent. 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 RFETS for relatively short periods, each chronic 

intake was fit independently, using only the bioassay results from the single intake period for Type S 

solubility. For Type M and F solubility, this approach was used where it was determined that earlier 

intake rates significantly biased later intake rates. This method will result in an overestimate of 

intakes for exposures extending through multiple assumed intake periods. Only the results within the 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 12 of 35 

intake period were selected for use in fitting each period. Excluded results are shown in light gray in 

the figures in Attachment B. 

Uranium urinalysis results were analyzed with IMBA to derive intake rates for 1953 to 1988. Excretion 

data are shown in Table A-1. The solid lines in Figures B-1 and B-2 show the individual fits to the 

50th-percentile excretion rates for type F material. Figure B-3 is the combined fit for all the intake 

periods. Figure B-4 shows the overall fit to the 84th-percentile excretion rates for type F material. 

The same intake periods were applied for both percentiles because the values followed a similar 

pattern. Similarly, Figures B-5 and B-6 show the individual fits to the 50th-percentile excretion rates 

for type M material. Figure B-7 is the combined fit for all the intake periods. Figure B-8 shows the 

overall fit to the 84th-percentile excretion rates for type M material. Figures B-9 to B-13 and B-14 to 

B-18 show the individual fits to the 50th-and 84th- percentile excretion rates for type S material, 

respectively. Figures B-19 and B-20 show the 50th- and 84th-percentile predicted excretion rates, 

respectively, from all type S intakes. Table B-1 tabulates the derived intake rates for Types F, M, and 

S materials at both the 50th and 84th percentiles levels along with the associated GSDs. 

4.3.2 Plutonium

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

rates for 1952 to 1988. Type M intakes should be applied to all systemic organs. Type S must be 

considered for non-systemic (i.e., lung and GI tract) cancers. 

Plutonium Type M—The solid lines in Figures B-21 to B-24 and B-25 to B-28 show the individual fits 

to the 50th- and 84th-percentile excretion rates for type M materials, respectively. The same intake 

periods were applied for both percentiles because the values followed a similar pattern. Figures B-29 

and B-30 show the 50th- and 84th-percentile predicted excretion rates, respectively, from all type M 

intakes. In addition, intake rates for Type M plutonium based on lung counting measurements of the 

associated americium-241 were also derived. The plutonium urinalysis results were determined to be 

more limiting and thus were used for the final values. Table B-2 lists the 50th percentile and 84th

percentile intake rates along with the associated GSD determined from plutonium urinalysis. For 

comparison, the intake rate determined from the americium lung counts at the 50th percentile level 

are also given. 

Plutonium Type S—Because type S plutonium clears slowly from the lungs, the plutonium exposure 

was fit as a single chronic intake based on the bioassay measurements from 1983 through 1988. 

This period was used because the measurements were relatively consistent; in addition, as the most 

recent measurements, they had the lowest minimum detectable activity and, therefore, are 

presumably the most accurate. During this time, the plutonium urinalysis results were more limiting 

for type S intakes and were, therefore, used to determine these intakes. Figures B-31 and B-32 show 

the 50th- and 84th-percentile predicted plutonium 50th- and 84th-percentile excretion rates, 

respectively. Figures B-33 and B-34 show the corresponding predicted 241Am lung burdens, 

respectively, for comparison to the lung count data. Table B-3 lists the 50th percentile and 84th

percentile intake rates along with the associated GSD determined from the plutonium urinalysis. For 

comparison, the intake rate determined from the americium lung count results at the 50th percentile 

level are also given. 

The type S intake rate can only be used as an underestimate. If an overestimate or best estimate is 

needed for type S material, an individualized fit to the bioassay data for the specific work period of the 

energy employee being evaluated must be performed. Tables A-2 and A-3 provide the bioassay data 

to be used to perform the individualized fit. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 13 of 35 

5.0 ASSIGNING INTAKES AND DOSES

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

5.1 INTAKE RATE SUMMARY 

Five intake periods were fit to the derived 50th- and 84th-percentile uranium excretion data. Table 5-1 

summarizes the derived uranium intake rates that produced the fits. Where the geometric standard 

deviation was less than 3, the value was set to a minimum of 3 to account for biological variation 

when determining dose. Subsequently, because many of the GSDs were relatively similar, they were 

further combined and the largest value within a given timeframe was assigned for simplicity. Actual 

GSDs are provided in Tables B-1 through B-3 located in Appendix B after Figures B-20, B-30, and B34 respectively. 

Table 5-1. Derived uranium intake rates, 1953 to 1988. 

Type F material Type M material Type S material 

Period 

50th 

percentile 

(dpm/d) 

Geometric 

standard 

deviation 

50th 

percentile

(dpm/d) 

Geometric 

standard 

deviation 

50th 

percentile 

(dpm/d)

Geometric 

standard 

deviation 

1953-1958 13.37 3.48 54.8 3.38 937 3.36 

1959 19.7 3.48 103 3.38 2,770 3.36 

1960 27.23 3.48 103 3.38 2,770 3.36 

1961 21.62 3.48 71.9 3.38 1,680 3.36 

1962 16.27 4.05 71.9 3.38 1,680 3.36 

1963 16.27 3.48 71.9 3.38 1,680 3.36 

1964 27.26 3.48 113 3.38 1,630 3.36 

1965-1976 27.26 3.48 113 3.38 1,630 3.36 

1977-1988 0.597 5.03 2.44 3.38 28.6 5.4 

Four intake periods were fit to the data for type M material and one was fit for type S material to the 

derived 50th- and 84th-percentile plutonium excretion and americium lung burden data. Table 5-2 

summarizes the derived plutonium intake rates that produced the fits. Where the geometric standard 

deviation was less than 3, the value was set to 3. Because of the interdependence between the 

bioassay results, it is not possible to fit type S plutonium to the data in a manner that would be 

representative of all individuals for all time periods. Therefore, only a minimizing intake has been 

calculated for type S plutonium. Type M plutonium should be applied for all systemic organs. 

Table 5-2. Derived plutonium intake rates, 1952 to 1988. 

Type M material 

Period 

50th percentile 

(dpm/d)

Geometric standard 

deviation 

1952-1961 121 3 

1962-1969 43.5 3 

1970-1979 7.05 4.23 

1980-1988 1.62 5.49 

Type S material (underestimate)

Period

50th percentile 

(dpm/d)

Geometric standard 

deviation 

1952-1988 8.142 5.39 

For non-systemic (respiratory and GI tracts) organs, the following shall be done: 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 14 of 35 

1. Run the type M intakes. If this action does not result in a PoC >50% (which is determined by 

the Department of Labor), 

2. Run the minimizing type S intake. If this action still does not yield a PoC >50% then 

3. Manually fit the coworker bioassay data for the time frame of interest for the employee, using 

the assumption of type S material. 

Standard fitting techniques should be used to fit the plutonium urinalysis and americium lung 

count data from the employee’s work period contained in Tables A-2 and A-3. Acute or 

chronic intakes can be assigned, depending on the patterns in the data. Both the 50th- and 

84th-percentile data must be fit using the same intake dates or periods; the 50th-percentile 

intakes are used to assign the intake and the 84th-percentile is used to determine the GSD for 

each intake. For input into IREP, the dose from each intake must be determined separately. 

4. The more claimant-favorable doses from the type M and S fits should be assigned. 

5.2 DOSE ASSIGNMENT 

For most cases, doses to be assigned to individuals are calculated from the 50th-percentile intake 

rates. Dose reconstructors should select the material type that is the most claimant-favorable. 

The lognormal distribution is selected in the NIOSH 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-0038 Revision No. 00 Effective Date: 08/03/2006 Page 15 of 35 

REFERENCES 

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

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

ORAUT (Oak Ridge Associated Universities Team), 2004a, Analysis of Coworker Bioassay Data for 

Internal Dose Assignment, ORAUT-OTIB-0019, Rev. 00, Oak Ridge, Tennessee. 

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

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

ORAUT (Oak Ridge Associated Universities Team), 2004c, Technical Basis Document for the Rocky 

Flats Plant – Occupational Internal Dose, ORAUT-TKBS-0011-5, Oak Ridge, Tennessee. 

ORAUT (Oak Ridge Associated Universities Team), 2005, Generating Summary Statistics for 

Coworker Bioassay Data, ORAUT-PROC-0095, Rev. 00, Oak Ridge, Tennessee. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 16 of 35 

ATTACHMENT A. COWORKER DATA TABLES 

Table A-1. Summary of uranium urinary excretion rate analyses, 1953 to 1988. 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 

hr) 

84th 

percentile 

(dpm/24 hr) 

7/1/1953 3.727 10.008 

2/15/1954 3.866 10.362 

5/15/1954 4.161 11.472 

8/15/1954 3.732 10.074 

11/15/1954 3.409 9.389 

2/15/1955 3.225 9.019 

5/15/1955 3.333 9.487 

8/15/1955 3.434 9.406 

11/15/1955 3.442 9.875 

2/15/1956 3.310 9.039 

5/15/1956 3.497 9.843 

8/15/1956 3.635 10.213 

11/15/1956 3.302 9.121 

2/15/1957 3.460 9.894 

5/15/1957 3.492 10.173 

8/15/1957 3.655 10.781 

11/15/1957 3.700 10.996 

2/15/1958 4.089 12.575 

5/15/1958 3.739 10.593 

8/15/1958 3.907 11.266 

11/15/1958 4.705 14.316 

2/15/1959 4.381 13.159 

5/15/1959 5.518 17.908 

8/15/1959 5.544 16.566 

11/15/1959 5.887 19.134 

2/15/1960 8.806 33.071 

5/15/1960 6.856 22.227 

8/15/1960 7.476 24.214 

11/15/1960 6.602 23.668 

2/15/1961 5.944 20.258 

5/15/1961 5.722 18.628 

8/15/1961 5.574 18.290 

11/15/1961 6.598 22.669 

2/15/1962 5.862 20.451 

5/15/1962 4.692 15.380 

8/15/1962 5.654 16.742 

11/15/1962 4.397 13.827 

2/15/1963 4.166 13.230 

5/15/1963 4.175 13.154 

8/15/1963 3.841 12.283 

11/15/1963 3.601 11.507 

2/15/1964 6.354 18.506 

5/15/1964 8.368 23.389 

8/15/1964 8.161 22.172 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 

hr) 

84th 

percentile 

(dpm/24 hr) 

11/15/1964 8.297 23.535 

7/1/1965 7.823 20.789 

7/1/1966 7.432 18.360 

7/1/1967 7.445 18.440 

7/1/1968 7.430 18.459 

7/1/1969 7.509 18.518 

7/1/1970 7.440 18.275 

7/1/1971 7.421 18.131 

7/1/1972 7.316 18.176 

7/1/1973 7.403 18.059 

7/1/1974 7.388 18.084 

7/1/1975 7.378 18.104 

7/1/1976 7.418 18.037 

7/1/1977 0.172 0.538 

7/1/1978 0.893 2.355 

7/1/1979 0.444 2.037 

7/1/1980 0.241 1.049 

7/1/1981 0.178 1.109 

2/15/1982 0.237 1.152 

5/15/1982 0.062 0.677 

8/15/1982 0.016 0.211 

11/15/1982 0.112 0.741 

2/15/1983 0.221 1.062 

5/15/1983 0.432 1.330 

8/15/1983 0.327 1.576 

11/15/1983 0.072 0.646 

2/15/1984 0.273 1.400 

5/15/1984 0.221 1.330 

8/15/1984 0.133 0.997 

11/15/1984 0.065 0.464 

2/15/1985 0.034 0.410 

5/15/1985 0.030 0.281 

8/15/1985 0.040 0.511 

11/15/1985 0.037 0.415 

2/15/1986 0.029 0.357 

5/15/1986 0.033 0.339 

8/15/1986 0.018 0.207 

11/15/1986 0.022 0.316 

7/1/1987 0.057 0.467 

7/1/1988 0.059 0.412 

All results shown in bold are annual averages rather than quarterly averages. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 17 of 35 

Table A-2. Summary of plutonium urinary excretion rate analyses, 1952 to 1988. 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 hr) 

84th 

percentile 

(dpm/24 hr) 

7/1/1952 2.514 8.198 

7/1/1953 0.716 1.046 

7/1/1954 0.575 1.053 

7/1/1955 0.469 0.919 

7/1/1956 0.615 1.264 

7/1/1957 2.610 12.006 

2/15/1958 2.173 10.041 

5/15/1958 1.037 2.872 

8/15/1958 1.295 3.801 

11/15/1958 0.919 2.581 

2/15/1959 0.709 1.542 

5/15/1959 0.942 2.276 

8/15/1959 0.945 2.482 

11/15/1959 0.560 1.211 

2/15/1960 0.614 1.353 

5/15/1960 0.596 1.221 

8/15/1960 0.453 0.955 

11/15/1960 0.573 1.528 

2/15/1961 0.728 1.625 

5/15/1961 0.691 1.377 

8/15/1961 0.754 2.035 

11/15/1961 0.656 1.645 

2/15/1962 0.337 0.809 

5/15/1962 0.326 0.735 

8/15/1962 0.271 0.589 

11/15/1962 0.220 0.431 

2/15/1963 0.250 0.467 

5/15/1963 0.248 0.496 

8/15/1963 0.238 0.432 

11/15/1963 0.252 0.562 

2/15/1964 0.296 0.810 

5/15/1964 0.249 0.483 

8/15/1964 0.379 1.668 

11/15/1964 0.334 1.066 

2/15/1965 0.283 0.757 

5/15/1965 0.348 1.085 

8/15/1965 0.221 0.417 

11/15/1965 0.266 0.646 

2/15/1966 0.293 0.821 

5/15/1966 0.237 0.554 

8/15/1966 0.213 0.430 

11/15/1966 0.252 0.625 

2/15/1967 0.251 0.622 

5/15/1967 0.240 0.565 

8/15/1967 0.199 0.413 

11/15/1967 0.236 0.535 

2/15/1968 0.228 0.526 

5/15/1968 0.205 0.461 

8/15/1968 0.252 0.585 

11/15/1968 0.278 0.724 

2/15/1969 0.292 0.692 

5/15/1969 0.266 0.606 

8/15/1969 0.240 0.519 

11/15/1969 0.264 0.558 

2/15/1970 0.242 0.515 

5/15/1970 0.165 0.623 

8/15/1970 0.100 0.423 

11/15/1970 0.120 0.470 

2/15/1971 0.091 0.366 

5/15/1971 0.055 0.209 

8/15/1971 0.073 0.293 

11/15/1971 0.061 0.249 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 hr) 

84th 

percentile 

(dpm/24 hr) 

2/15/1972 0.046 0.398 

5/15/1972 0.046 0.442 

8/15/1972 0.029 0.199 

11/15/1972 0.028 0.168 

2/15/1973 0.024 0.145 

5/15/1973 0.033 0.180 

8/15/1973 0.067 0.305 

11/15/1973 0.061 0.268 

2/15/1974 0.060 0.224 

5/15/1974 0.049 0.189 

8/15/1974 0.033 0.144 

11/15/1974 0.016 0.109 

2/15/1975 0.021 0.104 

5/15/1975 0.019 0.095 

8/15/1975 0.022 0.200 

11/15/1975 0.015 0.097 

2/15/1976 0.016 0.144 

5/15/1976 0.021 0.102 

8/15/1976 0.015 0.104 

11/15/1976 0.043 0.184 

2/15/1977 0.083 0.262 

5/15/1977 0.092 0.245 

8/15/1977 0.072 0.190 

11/15/1977 0.062 0.188 

2/15/1978 0.095 0.307 

5/15/1978 0.060 0.199 

8/15/1978 0.056 0.201 

11/15/1978 0.033 0.134 

2/15/1979 0.062 0.237 

5/15/1979 0.013 0.100 

8/15/1979 0.013 0.087 

11/15/1979 0.029 0.139 

2/15/1980 0.017 0.106 

5/15/1980 0.017 0.064 

8/15/1980 0.013 0.061 

11/15/1980 0.004 0.035 

2/15/1981 0.006 0.037 

5/15/1981 2.25E-04 0.006 

8/15/1981 0.005 0.036 

11/15/1981 0.008 0.056 

2/15/1982 1.43E-04 0.007 

5/15/1982 3.11E-04 0.011 

8/15/1982 1.37E-04 0.004 

11/15/1982 2.90E-04 0.006 

2/15/1983 0.001 0.017 

5/15/1983 3.99E-04 0.008 

8/15/1983 0.002 0.016 

11/15/1983 0.004 0.029 

2/15/1984 0.008 0.050 

5/15/1984 0.053 0.222 

8/15/1984 0.011 0.071 

11/15/1984 0.054 0.196 

2/15/1985 0.010 0.080 

5/15/1985 0.025 0.100 

8/15/1985 0.014 0.081 

11/15/1985 0.017 0.100 

2/15/1986 0.005 0.033 

5/15/1986 0.004 0.038 

8/15/1986 0.007 0.038 

11/15/1986 0.008 0.042 

2/15/1987 0.004 0.030 

5/15/1987 0.005 0.036 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 18 of 35 

Table A-2 (Continued). Summary of plutonium urinary excretion rate analyses, 1952 to 

1988. 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 hr) 

84th 

percentile 

(dpm/24 hr) 

8/15/1987 0.008 0.051 

11/15/1987 0.008 0.050 

2/15/1988 0.003 0.032 

Effective 

sample 

date 

50th 

percentile 

(dpm/24 hr) 

84th 

percentile 

(dpm/24 hr) 

5/15/1988 0.002 0.033 

8/15/1988 0.005 0.034 

11/15/1988 0.006 0.038 

All results shown in bold are annual averages rather than quarterly averages. Very large results for: badge 395943 excluded from 

1964-1965; badges 164455 and 184168 excluded from quarter 3, 1971; 164455 and 184169 excluded from quarter 4, 1971; badge 

184106 excluded from quarter 2, 1976. 

Results for quarter 2, 1981, all of 1982, and quarter 2, 1983 were not used in calculations—too few results. 

Table A-3. 241Am lung count bioassay data for individualized 239Pu Type S fits. 

Effective 

Sample date 

50th percentile 

(nCi) 

84th percentile 

(nCi) 

7/1/1972 6.73E-05 0.003 

2/15/1973 0.005 0.059

5/15/1973 0.010 0.107

8/15/1973 0.025 0.188

11/15/1973 0.009 0.095

2/15/1974 0.005 0.067

5/15/1974 0.007 0.080 

8/15/1974 0.007 0.079 

11/15/1974 0.007 0.079 

2/15/1975 0.017 0.150 

5/15/1975 0.027 0.180 

8/15/1975 0.039 0.244 

11/15/1975 0.048 0.278 

2/15/1976 0.043 0.261 

5/15/1976 0.044 0.254 

8/15/1976 0.017 0.133 

11/15/1976 0.012 0.111 

2/15/1977 0.010 0.097 

5/15/1977 0.008 0.082 

8/15/1977 0.007 0.061 

11/15/1977 0.004 0.051 

2/15/1978 0.008 0.083 

5/15/1978 0.007 0.070 

8/15/1978 0.007 0.066 

11/15/1978 0.004 0.045 

7/1/1979 0.012 0.108

2/15/1980 0.026 0.195 

5/15/1980 0.020 0.159 

8/15/1980 0.021 0.171 

11/15/1980 0.027 0.207 

2/15/1981 0.018 0.151 

5/15/1981 0.016 0.140 

Effective 

Sample date

50th percentile 

(nCi) 

84th percentile 

(nCi) 

8/15/1981 0.016 0.138 

11/15/1981 0.016 0.136 

2/15/1982 0.013 0.126 

5/15/1982 0.011 0.111 

8/15/1982 0.010 0.102 

11/15/1982 0.009 0.081 

2/15/1983 0.006 0.066 

5/15/1983 0.002 0.031 

8/15/1983 0.005 0.055 

11/15/1983 0.008 0.063 

2/15/1984 0.005 0.058 

5/15/1984 0.006 0.058 

8/15/1984 0.005 0.054 

11/15/1984 0.008 0.067 

2/15/1985 0.004 0.042 

5/15/1985 0.005 0.051 

8/15/1985 0.003 0.035 

11/15/1985 0.003 0.037 

2/15/1986 0.004 0.049 

5/15/1986 0.007 0.054 

8/15/1986 0.005 0.057 

11/15/1986 0.004 0.043 

2/15/1987 0.008 0.072 

5/15/1987 0.005 0.051 

8/15/1987 0.009 0.091 

11/15/1987 0.009 0.072 

2/15/1988 0.006 0.061 

5/15/1988 0.008 0.073 

8/15/1988 0.005 0.043 

11/15/1988 0.004 0.042 

All results shown in bold are annual averages rather than quarterly averages. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 19 of 35 

ATTACHMENT B. COWORKER DATA FIGURES 

Figure B-1. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1976, 50th-percentile, Type F. 

Figure B-2. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type F. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 20 of 35 

Figure B-3. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots) 

from all intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type F. 

Figure B-4. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1988, 84th-percentile, Type F. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 21 of 35 

Figure B-5. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1976, 50th-percentile, Type M. 

Figure B-6. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 22 of 35 

Figure B-7. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots) 

from all intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type M. 

Figure B-8. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1988, 84th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 23 of 35 

Figure B-9. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1958, 50th-percentile, Type S. 

Figure B-10. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1959 to 12/31/1960, 50th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 24 of 35 

Figure B-11. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1961 to 12/31/1963, 50th-percentile, Type S. 

Figure B-12. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1964 to 12/31/1976, 50th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 25 of 35 

Figure B-13. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 50th-percentile, Type S. 

Figure B-14. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1953 to 12/31/1958, 84th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 26 of 35 

Figure B-15. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1959 to 12/31/1960, 84th-percentile, Type S. 

Figure B-16. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1961 to 12/31/1963, 84th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 27 of 35 

Figure B-17. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1964 to 12/31/1976, 84th-percentile, Type S. 

Figure B-18. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots), 

1/1/1977 to 12/31/1988, 84th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 28 of 35 

Figure B-19. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots) 

from all intakes 1/1/1953 to 12/31/1988, 50th-percentile, Type S. 

Figure B-20. Predicted uranium bioassay results (line) calculated using IMBAderived U intake rates compared with measured uranium-in-urine results (dots) 

from all intakes 1/1/1953 to 12/31/1988, 84th-percentile, Type S. 

Table B-1. IMBA-derived uranium intake rates, dpm/day. 

Type F Type M Type S 

Years 50% 84% GSD 50% 84% GSD 50% 84% GSD

1953-1958 13.37 37.91 2.84 54.75 154.8 2.83 936.9 2,676 2.86

1959 19.7 61.99 3.15 102.7 347.5 3.38 2,768 9,300 3.36

1960 27.23 94.74 3.48 102.7 347.5 3.38 2,768 9,300 3.36

1961 21.62 65.97 3.05 71.85 234.2 3.26 1,680 5,438 3.24

1962 16.27 65.97 4.05 71.85 234.2 3.26 1,680 5,438 3.24

1963 16.27 44.36 2.73 71.85 234.2 3.26 1,680 5,438 3.24 

1964 27.26 80.39 2.95 112.8 284.2 2.52 1,630 4,086 2.51 

1965-1976 27.26 66.26 2.43 112.8 284.2 2.52 1,630 4,086 2.51 

1977-1988 0.597 3.004 5.03 2.443 6.263 2.56 28.6 154.3 5.40 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 29 of 35 

Figure B-21. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1952 to 12/31/1961, 50th-percentile, Type M. 

Figure B-22. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1962 to 12/31/1969, 50th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 30 of 35 

Figure B-23. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1970 to 12/31/1979, 50th-percentile, Type M. 

Figure B-24. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1980 to 12/31/1988, 50th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 31 of 35 

Figure B-25. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1952 to 12/31/1961, 84th-percentile, Type M. 

Figure B-26. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1962 to 12/31/1969, 84th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 32 of 35 

Figure B-27. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1970 to 12/31/1979, 84th-percentile, Type M. 

Figure B-28. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1980 to 12/31/1988, 84th-percentile, Type M. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 33 of 35 

Figure B-29. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), from 

all intakes 1/1/1952 to 12/31/1988, 50-percentile, Type M. 

Figure B-30. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), from 

all intakes 1/1/1952 to 12/31/1988, 84th-percentile, Type M. 

Table B-2. IMBA-derived plutonium/americium intake rates, Type M. 

Plutonium urinalysisbased results, dpm/day Americium lung count-based 

results, 50th percentile 

Year Pu 50% Pu 84% GSD Am, pCi/day Pu, dpm/day 

1952-1961 121 357.3 2.95 

1962-1969 43.5 106.5 2.45 

1970-1971 7.05 29.82 4.23 

1972-1976 7.05 29.82 4.23 1.845 871.5 

1977-1979 7.05 29.82 4.23 1.154 545.1 

1980-1982 1.622 8.907 5.49 1.154 545.1 

1983-1988 1.622 8.907 5.49 0.513 242.5 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 34 of 35 

Figure B-31. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1952 to 12/31/1988, 50-percentile, Type S. 

Figure B-32. Predicted plutonium bioassay results (line) calculated using IMBAderived Pu intake rates compared with measured Pu-in-urine results (dots), 

1/1/1952 to 12/31/1988, 84th-percentile, Type S. 
Document No. ORAUT-OTIB-0038 Revision No. 00 Effective Date: 08/03/2006 Page 35 of 35 

Figure B-33. Predicted Am bioassay results (line) calculated using IMBA-derived 

Am intake rates compared with measured Am lung burden results (dots), 

1/1/1952 to 12/31/1988, 50th-percentile, Type S. 

Figure B-34. Predicted Am bioassay results (line) calculated using IMBA-derived 

Am intake rates compared with measured Am lung burden results (dots), 

1/1/1952 to 12/31/1988, 84th-percentile, Type S. 

Table B-3. IMBA-derived plutonium/americium intake rates, Type S. 

Intake rate modeling type 50% 84% GSD 

Plutonium from Am lung counts, dpm/day 11.83 113.4 9.58 

Americium from Am lung counts, pCi/day 0.025 0.240 9.58 

Plutonium from Pu urinalysis dpm/day 8.142 43.87 5.39 

Americium from Pu urinalysis, pDi/day 0.017 0.093 5.39