ORAU TEAM 

Dose Reconstruction 

Project for NIOSH

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

Page 1 of 54

Document Title: 

Internal Dosimetry Coworker Data for the 

Hanford Site 

Document Number: ORAUT-OTIB-0039 

Revision: 00 PC-1 

Effective Date: 01/06/2006 

Type of Document: OTIB 

Supersedes: None 

Subject Expert: Donald E. Bihl 

Document Owner 

Approval: Signature on File Approval Date: 10/13/2005 

Judson L. Kenoyer, Task 3 Manager 

Concurrence: Signature on File Concurrence Date: 10/16/2005 

Richard E. Toohey, Project Director 

Approval: Signature on File Approval Date: 10/28/2005 

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-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 2 of 54 

PUBLICATION RECORD 

EFFECTIVE 

DATE 

REVISION 

NUMBER DESCRIPTION 

10/28/2005 00 New technical information bulletin for assignment of Hanford internal 

doses based on coworker bioassay data. First approved issue. 

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

Donald E. Bihl. 

01/06/2006 00 PC-1 Approved page change revision. Corrects errors in units in Table 5-

10 (page 27), Table 5-14 (page 28), Table 6-8 (page 33) and 6-10 

(page 34). Corrects a value error in Table 6-9 (311.9 instead of 300 

in the fifth column, page 33). Provides new guidance on how to 

assign radionuclides to unmonitored workers based on worker 

location, consistent with Hanford internal dosimetry TBD (Section 

6.8, page 35). Corrects errors in Table 6-13 on page 36. No 

sections were deleted. Retraining is not required. Initiated by Donald 

E. Bihl. 

Approval: 

Document Owner: 

Signature on File______________________________12/29/2005 Judson L. Kenoyer, Task 3 Manager 

Signature on File________ ________________ 12/28/2005 Kate Kimpan, Project Director 

Signature on File_________ _ ________________ 01/06/2006 James W. Neton, Associate Director for Science

TRADEMARK INFORMATION 

Microsoft and Access are registered trademarks of Microsoft Corporation in the United States and/or 

other countries. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 3 of 54 

TABLE OF CONTENTS 

SECTION TITLE PAGE

Acronyms and Abbreviations..................................................................................................................8

1.0 Introduction .................................................................................................................................9

2.0 Purpose.......................................................................................................................................9

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

4.0 Data ..........................................................................................................................................10

 4.1 Selected Bioassay Data............................................................................................... 10

 4.1.1 Plutonium Urinalysis...........................................................................................10

 4.1.2 Uranium Urinalysis.............................................................................................13

 4.1.3 Strontium Urinalysis ...........................................................................................14

 4.1.4 Promethium Urinalysis .......................................................................................15

 4.1.5 Zinc-65 in Whole-Body Counts ..........................................................................16

 4.1.6 Sodium-24 in Whole-Body Counts .....................................................................17

 4.1.7 Cesium-137 in Whole-Body Counts ....................................................................18

 4.2 Analysis........................................................................................................................ 22

5.0 Intake Modeling.........................................................................................................................22

 5.1 Assumptions................................................................................................................. 22

 5.2 Bioassay Fitting............................................................................................................ 23

 5.3 Radionuclides and Material Types............................................................................... 23

 5.3.1 Plutonium ..........................................................................................................23

 5.3.1.1 Type M ................................................................................................24

 5.3.1.2 Type S .................................................................................................24

 5.3.2 Uranium..............................................................................................................24

 5.3.2.1 Type F .................................................................................................25

 5.3.2.2 Type M ................................................................................................25

 5.3.2.3 Type S .................................................................................................25

 5.3.3 Strontium-90.......................................................................................................26

 5.3.4 Promethium-147.................................................................................................26

 5.3.4.1 Type M .................................................................................................26

 5.3.4.2 Type S ..................................................................................................26

 5.3.5 Zinc-65 ...............................................................................................................27

 5.3.5.1 Inhalation Intakes ................................................................................27

 5.3.5.2 Ingestion Intakes .................................................................................27

 5.3.6 Sodium-24..........................................................................................................28

 5.3.6.1 Inhalation Intakes ................................................................................28

 5.3.6.2 Ingestion Intakes .................................................................................28

 5.3.7 Cesium-137........................................................................................................28

6.0 Assignment of Intakes and Doses ............................................................................................29

 6.1 Plutonium ..................................................................................................................... 29

 6.2 Uranium and Thorium .................................................................................................. 30

 6.3 Strontium-90................................................................................................................. 32

 6.4 Promethium-147........................................................................................................... 32
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 6.5 Zinc-65 ......................................................................................................................... 32

 6.6 Sodium-24.................................................................................................................... 32

 6.7 Cesium-137.................................................................................................................. 33

 6.8 Additional Radionuclides.............................................................................................. 33

References ...........................................................................................................................................37

ATTACHMENT A, STATISTICAL SUMMARIES AND PLOTS........................................................38 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 5 of 54 

LIST OF TABLES 

TABLE TITLE PAGE

4-1 Time intervals for statistical analysis of plutonium urine samples..............................................13

4-2 Time intervals for statistical analysis of uranium urine samples ................................................14

4-3 Time intervals for statistical analysis of 90Sr urine samples .......................................................15

4-4 Time intervals for statistical analysis of 147Pm urine samples....................................................16

4-5 Time intervals for statistical analysis of 65Zn whole-body counts...............................................17

4-6 Time intervals for statistical analysis of 24Na whole-body counts ..............................................18

4-7 Subjective upper range for the linear distribution.......................................................................18

4-8 Time intervals for statistical analysis of 137Cs whole-body counts .............................................19

4-9 Comparison of 137Cs 50th- and 84th-percentile values between the linear 

distribution and the rank-but-not-fit methods .............................................................................20

5-1 Plutonium mixture usage ...........................................................................................................22

5-2 Type M 239+240Pu intake periods and rates .................................................................................24

5-3 Type S 239+240Pu intake period and rates....................................................................................24

5-4 Type F uranium intake periods and rates ..................................................................................25

5-5 Type M uranium intake periods and rates..................................................................................25

5-6 Type S uranium intake periods and rates ..................................................................................26

5-7 Type F 90Sr intake periods and rates .........................................................................................26

5-8 Type M 147Pm intake periods and rates .....................................................................................26

5-9 Type S 147Pm intake periods and rates......................................................................................26

5-10 Zinc-65 inhalation intake periods and rates ...............................................................................27

5-11 Zinc-65 ingestion intake periods and rates ................................................................................27

5-12 Type F 24Na inhalation intake periods and rates........................................................................28

5-13 Sodium-24 ingestion intake periods and rates...........................................................................28

5-14 Type F 137Cs intake periods and rates .......................................................................................28

6-1 Type M plutonium intake periods and rates...............................................................................30

6-2 Type S plutonium intake period and rates .................................................................................30

6-3 Uranium intake periods and rates..............................................................................................31

6-4 Thorium intake periods and rates ..............................................................................................31

6-5 Contaminants in recycled uranium (units are pCi contaminant per pCi U) ................................31

6-6 Type F 90Sr intake periods and rates .........................................................................................32

6-7 Promethium-147 intake periods and rates.................................................................................32

6-8 Zinc-65 intake periods and rates................................................................................................33

6-9 Sodium-24 intake periods and rates ..........................................................................................33

6-10 Type F cesium-137 intake periods and rates.............................................................................34

6-11 Comparison of radionuclide ratios in airborne effluents.............................................................35

6-12 Intakes for fission or activation products other than 90Sr, 65Zn, 24Na, or 

137Cs...........................................................................................................................................35

6-13 Fission or activation radionuclide chooser for unmonitored workers .........................................36

A-1 Statistical summary of 239Pu 24-hr urinary excretion rates, 1946-1988 .....................................38

A-2 Statistical summary of uranium 24-hr urinary excretion rates, 1948-1988.................................41

A-3 Statistical summary of 90Sr 24-hr urinary excretion rates, 1965-1988 .......................................45

A-4 Statistical summary of 147Pm 24-hr urinary excretion rates, 1966-1979 ....................................46

A-5 Statistical summary of 65Zn measured in whole-body counts ....................................................48

A-6 Statistical summary of 24Na measured in whole-body counts....................................................52

A-7 Statistical summary of 137Cs measured in whole-body counts...................................................53
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 6 of 54 

LIST OF FIGURES 

FIGURE TITLE PAGE

1 Production rates in tons of uranium times fuel burnup, 1944 to 1972........................................30

A-1 50th-percentile plutonium urinalysis data for intakes of Type M material, 

1946 to 1948..............................................................................................................................39

A-2 50th-percentile plutonium urinalysis data for intakes of Type M material, 

1949 to 1952..............................................................................................................................39

A-3 50th-percentile plutonium urinalysis data for intakes of Type M material, 

1953 to 1981..............................................................................................................................39

A-4 50th-percentile plutonium urinalysis data for intakes of Type M material, 

1982 to 1988..............................................................................................................................40

A-5 Predicted 50th-percentile urinary excretion of Type M plutonium from 

1946 to 1988 based on four independent intakes, compared to bioassay 

data............................................................................................................................................40

A-6 50th-percentile plutonium urinalysis data for intakes of Type S material, 

1946 to 1988..............................................................................................................................40

A-7 50th-percentile uranium urinalysis data for intakes of Type F material, 

1948 to 1988..............................................................................................................................42

A-8 50th-percentile uranium urinalysis data for intakes of Type M material, 

1948 to 1988..............................................................................................................................42

A-9 50th-percentile uranium urinalysis data for intakes of Type S material, 

1948 to 1952..............................................................................................................................42

A-10 50th-percentile uranium urinalysis data for intakes of Type S material, 

1953 to 1956..............................................................................................................................43

A-11 50th-percentile uranium urinalysis data for intakes of Type S material, 

1957 to 1961..............................................................................................................................43

A-12 50th-percentile uranium urinalysis data for intakes of Type S material, 

1962 to 1974..............................................................................................................................43

A-13 50th-percentile uranium urinalysis data for intakes of Type S material, 

1975 to 1983..............................................................................................................................44

A-14 50th-percentile uranium urinalysis data for intakes of Type S material, 

1984 to 1988..............................................................................................................................44

A-15 Predicted 50th-percentile urinary excretion of Type S uranium from 1946 

to 1988 based on six independent intakes, compared to bioassay data ...................................44

A-16 50th-percentile strontium urinalysis data for intakes of Type F material, 

1965 to 1988..............................................................................................................................45

A-17 50th-percentile promethium urinalysis data for intakes of Type M material, 

1966 to 1969..............................................................................................................................46

A-18 50th-percentile promethium urinalysis data for intakes of Type M material, 

1970 to 1979..............................................................................................................................46

A-19 Predicted 50th-percentile urinary excretion of Type M promethium from 

1966 to 1979 based on two independent intakes, compared to bioassay 

data............................................................................................................................................47

A-20 50th-percentile promethium urinalysis data for intakes of Type S material, 

1966 to 1969..............................................................................................................................47

A-21 50th-percentile promethium urinalysis data for intakes of Type S material, 

1970 to 1979..............................................................................................................................47
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 7 of 54 

A-22 Predicted 50th-percentile urinary excretion of Type S promethium from 

1966 to 1979 based on two independent intakes, compared to bioassay 

data............................................................................................................................................48

A-23 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1960 to 1963...................................................................................................49

A-24 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1964 to 1967...................................................................................................49

A-25 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1968 to 1970...................................................................................................49

A-26 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1971 to 1972...................................................................................................50

A-27 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1973 to 1977...................................................................................................50

A-28 50th-percentile zinc whole-body counting data for inhalation intakes of 

Type S material, 1978 to 1984...................................................................................................50

A-29 Predicted 50th-percentile urinary excretion of inhaled Type S zinc from 

1960 to 1984 based on six independent chronic intakes and one acute 

intake, compared to bioassay data ............................................................................................51

A-30 50th-percentile zinc whole-body counting data for ingestion intakes, 1960 

to 1984.......................................................................................................................................51

A-31 50th-percentile sodium whole-body counting data for inhalation intakes of 

Type F material, 1960 to 1984...................................................................................................52

A-32 50th-percentile sodium whole-body counting data for ingestion intakes, 

1960 to 1984..............................................................................................................................53

A-33 50th-percentile 137Cs whole-body counting data for inhalation intakes of 

Type F material, 1960 to 1988...................................................................................................54
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 8 of 54 

ACRONYMS AND ABBREVIATIONS 

dpm disintegrations per minute 

DTPA diethylenetriaminepentaacetic acid 

GM geometric mean 

GSD geometric standard deviation 

HERB Health-Related Energy Research Branch 

hr hour 

ICRP International Commission on Radiological Protection 

IMBA Integrated Modules for Bioassay Analysis 

L liter 

m meter 

MDA minimum detectable activity 

ml milliliter 

MPBB maximum permissible body burden 

nCi nanocurie 

NIOSH National Institute for Occupational Safety and Health 

pCi picocurie 

PoC Probability of Causation 

PNNL Pacific Northwest National Laboratory 

PUREX plutonium–uranium extraction 

REX Hanford Radiological Exposure Records Database 

TIB technical information bulletin 

yr year 

U.S.C. United States Code 

μCi microcurie 

μg microgram 

μm micrometer 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 9 of 54 

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 (NIOSH) 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 Energy facility” as defined in the Energy Employees 

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

2.0 PURPOSE

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 facility. In 

addition, there are incidents in which an employee’s monitoring records are incomplete or unavailable. 

In such cases, data from coworkers can be used 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 Hanford site [including the Pacific Northwest National Laboratory 

(PNNL)] for the purpose of estimating unmonitored exposures. 

3.0 OVERVIEW

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

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

Bioassay results for Hanford were obtained as a copy of the Hanford Radiological Exposure Records 

(REX) database sent to the NIOSH Health-Related Energy Research Branch (HERB) before the start 

of the dose reconstruction project. The REX data needed to generate the bioassay statistics for the 

coworker data project were converted to Microsoft Access database tables. Data in these tables were 

spot-checked against REX at Hanford, and no discrepancies were found. 

As is typical of a site with large operating reactors and spent fuel dissolution operations, there was 

potential for exposure at Hanford to many radionuclides including fission and activation products, 

plutonium, uranium, and tritium. In addition, Hanford handled thorium for part of its history. With the 

advent of in vivo counting, detection of a wide range of gamma-emitting fission and activation 

products became possible. In addition, bioassay monitoring of workers on small-scale or short-term 

projects for unusual radionuclides was performed at different times. Therefore, there are a number of 

different radionuclides in the excreta and in vivo data. For most of the radionuclides in the database, 

there were too few measurements made or too few detections (in the case of in vivo measurements) 

to allow reliable statistical evaluation. Exposure to such radionuclides was arguably rare or limited to 

only a few workers on a specific project and would not be appropriate for this general coworker study. 

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

measurements were from plutonium, uranium, radiostrontium, and promethium analyses, although the 

147Pm intakes have limited applicability (Sections 4.1.4 and 6.1.4). Before whole-body counting 

became routine in 1960, bioassay monitoring for intakes of some fission products was performed 

using a radiochemical procedure called fission product urinalysis. This procedure involves chemical 

separation and counting (gross beta) of rare-earth fission products and radioisotopes of strontium. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 10 of 54 

However, the results are difficult to interpret because the actual radionuclide or composition of the 

mixture of radionuclides in the urine was not determined and different radionuclides had different 

chemical yields and detection efficiencies. Therefore, intakes of 24Na, 65Zn, 90Sr, and 137Cs were 

extrapolated from periods when they were measured, and other fission products were accounted for 

using air concentration limits (Section 6.0). 

With the exception of naturally-occurring 40K, only three gamma-emitting radionuclides measured by 

whole-body counting were routinely reported: 137Cs, 24Na, and 65Zn. The available documentation 

does not state the reasons for choosing these three radionuclides. Other fission or activation 

products were reported only when detected above a certain level of significance determined through 

different methods at different times. A review of the in vivo database showed that there was enough 

data to warrant statistical evaluation only for these three routinely reported radionuclides. 

Dose from intakes of tritium was treated as external dose until about 1986 and reported as part of 

penetrating dose in the radiological records. Dose from tritium was included in the coworker analysis 

of penetrating external dose (ORAUT 2005b) and was therefore not duplicated in this coworker 

analysis. 

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

ORAUT (2005a). The resultant values were input to the Integrated Modules for Bioassay Analysis 

(IMBA) computer program, and a fit to the data for each of the seven radionuclides at the 50th- and 

84th-percentile values was performed to obtain intake rates for assignment of dose distributions. 

4.0 DATA

4.1 SELECTED BIOASSAY DATA 

Data for each of the electronic database codes considered were extracted from a series of Microsoft 

Access files that contained a version of the HERB database. 

Throughout most of Hanford’s history, bioassay data were truncated or censored below some level. 

Various terms can be applied to such a level, such as detection limit, less-than level, reporting level, 

lower limit of detection, decision level or minimum detectable activity (MDA). In this document, 

reporting level denotes the level below which a measurement was not recorded. Decision level and 

MDA, as best as could be determined from available documentation, are used in accordance with the 

definitions in Health Physics Society Standard N13.30 (HPS 1996). The analysis established time 

intervals for which single values for the 50th- and 84th-percentile values were calculated. These 

intervals were determined such that there was a sufficient total number of measurements and a 

sufficient number of measurements greater than the reporting level to perform meaningful statistics. 

For some data, reporting levels were not used for all samples, and there was therefore a large batch 

of samples at or just above the reporting level, a smattering of samples below the reporting level, and 

some samples with zero, blank, or null values. This mix of reporting practices led to poor curve fits 

when values at the reporting level were treated as zeros. Therefore, this analysis used the linear 

distribution (ORAUT 2005a) for values considered to represent nondetections. The following 

radionuclide-specific sections discuss exceptions to this treatment. 

4.1.1 Plutonium Urinalysis

Routine urinalysis for plutonium at Hanford began in 1946. Over the years, several factors in the 

methods for measuring and reporting plutonium urinalysis data changed: 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 11 of 54 

• Chemical method 

• Radioactivity counting method 

• Reporting units 

• Reporting levels and data censoring (that is, not reported below a certain activity) 

• Method for indicating data below the reporting level 

• Consistency of use of the previous two protocols (the data for some years show that the 

reporting level was not used consistently and/or that different methods of reporting data below 

the reporting level were used) 

Some of these changes affected how the urinalysis data were treated for the statistical analysis. The 

issues and resolutions are discussed in the following paragraphs. 

From 1946 to the third quarter of 1983, plutonium urinalysis results were measured and recorded as a 

gross alpha count on a chemically separated sample. The measured result was the total activity of 

238Pu, 239Pu, and 240Pu but did not include 241Pu nor 241Am. Since the fourth quarter of 1983, the 

chemically separated sample was measured by alpha spectrometry (for routine and priority samples). 

The recorded results were a value for 239Pu that was actually the total activity of 239Pu and 240Pu and a 

value for the 238Pu activity. The statistical analyses were conducted on the total plutonium alpha 

activity for 1946 to September 1983 and on the 239+240Pu activity for October 1983 to 1988. Because 

most plutonium exposures at Hanford would have involved a mixture of isotopes, the results of these 

different measurement techniques were normalized (Section 5). 

Routine plutonium urinalysis samples were usually simulated 24-hr samples, which were collected 

over two 12-hr periods (usually consecutive evenings). Some samples were not 24-hr samples, 

especially those collected shortly after a suspected acute intake. The collected volume of urine was 

part of the record starting partly in 1958 and consistently in 1959, so the 1959 to 1988 results with 

volumes of less than 400 ml were not used in the statistics. This criterion removed some of the 

incident samples and some samples from persons who did not follow instructions and provided less 

than simulated 24-hr samples. 

Incident samples were problematic for performing group statistics. Hanford generally collected many 

samples from a worker involved with a known large acute intake, which were referred to as special or 

follow-up samples. The number of samples varied depending on the severity of the intake, whether 

treatment was involved, the willingness of the exposed worker, and general internal dosimetry 

practices at the time. However, in many cases the number of follow-up samples ranged from tens to 

hundreds. These samples were not comparable to routine annual or semiannual samples from the 

majority of the workforce, and they tended to bias the statistics on the high side. It was too difficult to 

remove all of these samples from the database, and minor acute intakes were frequent enough at 

Hanford that they could represent the normal course of exposure to plutonium workers. However: 

• If there were a large number of samples from a single worker, usually bunched after a specific 

time, these were removed. A specific number was not rigorously applied as the definition of 

large, but it was generally greater than about 20 in 1 yr. In addition, once a person was 

selected to be removed, data for subsequent years in that worker’s history were removed until 

the excretion was near or less than the reporting level. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 12 of 54 

• If a record of an acute intake was judged to be unrepresentative, that record was removed. 

Any intake treated by diethylenetriaminepentaacetic acid (DTPA) met this criteria because 

DTPA-treated urinary excretion is enhanced. Intake through a wound or the skin was 

considered unrepresentative. Inhalations, however, were considered representative unless 

they were caused by an event judged to be unrepresentative, such as explosion, fire, or major 

contamination spread. 

Another challenge to data interpretation was results listed as “PU” or “PU239” with blank quantities. 

For most years, the meaning of a blank was not found in documentation. However, the meaning 

could be inferred from the number of blank results and how they fit with the other data for the year. 

For instance, there were many blank results each year in the early years, and it was inferred that the 

blanks meant a sample was analyzed and nothing was detected. In later years there were many 

sample results recorded exactly at the recording level but just a few blanks. It was claimant-favorable 

to leave out the blanks in those years under the assumption that a blank was a sample collected for 

which the analysis failed in some way. Each year’s distribution of sample results was scrutinized, and 

instructions were written on how to disposition blank results on a year-by-year basis. 

The method used to indicate no detection of plutonium, similar to the issue of blanks, varied over time 

and appeared not to be consistent even during a given period. For instance, zero, blank, and the 

reporting level were apparently used to indicate nondetections during some periods. In general, 

Hanford used reporting levels for plutonium urinalysis results until September 1981. Whether a value 

recorded at the reporting level meant no detection, or whether the reporting level or higher was a true 

detection and nondetections were recorded as zero or blank, was indeterminate at the broad level. 

The meanings of the reporting level, zero, and blanks had to be determined on a year-by-year basis, 

and the decision was included in the specific instructions on how to rank such sample results. For 

example, the 1966 to 1974 reporting level was 1.1 × 10-8 μCi/sample (0.244 dpm/sample) and the 

1975 to 1981 reporting level was 0.025 dpm/sample. These numbers were considered to be one-half 

of the detection level and were used to indicate no detection of plutonium. The linear distribution was 

used to distribute and rank blanks, zeros, and values at these reporting levels. For other years, 

however, the reporting level was less apparent because there were many values that were probably a 

reporting level, but other values were less than the reporting level. The latter samples were included 

in the linear fit, and the apparent reporting level was set as the top of the linear distribution. 

The following were set as the top of the linear distribution: 

1946 3.6E-7 μCi/sample 

1947–1948 3.0E-7 μCi/sample 

1949–1951 1.5E-7 μCi/sample 

1952 8.1E-8 μCi/sample 

1953–1957 2.3E-8 μCi/sample 

1958–1965 1.2E-8 μCi/sample 

1966–1974 1.1E-8 μCi/sample 

1975–Sept. 9, 1981 0.025 dpm/sample 

On September 10, 1981, the recording practice changed from recording 0.025 dpm/sample to indicate 

a nondetection to recording the exact result as measured. After September 9, 1981, therefore, any 

result greater than zero was used as recorded. Zero and negative results were included in the 

ranking of samples but not in the fitting of the line. The linear distribution was not used for data after 

September 9, 1981. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 13 of 54 

Units for plutonium analyses in the Hanford records were microcuries per sample from 1946 to 1974 

and disintegrations per minute per sample from 1975 to present. The earlier values were converted to 

disintegrations per minute before statistical analysis. 

The time interval for separate statistical analyses varied. The choice of the interval was based on the 

number of results versus the number of results over the reporting level. If there were several hundred 

sample results and 10% or more exceeded the reporting level, the basic time interval was quarterly. 

Table 4-1 lists the intervals. The unusual division of the third and fourth quarters of 1981 was applied 

because of the change in recording practice discussed above. 

Table 4-1. Time intervals for statistical 

analysis of plutonium urine samples. 

Calendar year Analysis interval 

1946 Year 

1947 Year 

1948 Half years 

1949 Year 

1950 Year 

1951 Year 

1952 Year 

1953 Half years 

1954–Jun. 1981 Quarter years 

3Q 1981 Jul. 1-Sep. 9 

4Q 1981 Sep. 10-Dec. 31 

1982–1988 Quarter years 

4.1.2 Uranium Urinalysis

Routine urinalysis for uranium began in 1947, but the results were considered unreliable until 

improvements in the procedure were made (Healy 1948). The 1947 data were analyzed but not used 

for intake modeling. Data analyzed for this study were from elemental analysis procedures. Starting 

in 1983 an alpha spectrometry procedure has been used for some workers, but these data were less 

robust and were not representative of the overall Hanford workforce. The results were recorded as 

micrograms per liter from 1947 to July 1, 1982, and as micrograms per sample from July 2, 1982, to 

present. The latter were converted to micrograms per liter using the sample volume recorded as part 

of the information in the database. Elemental uranium samples were not usually 24-hr samples; a mix 

of sample collection periods was used from 1947 to 1988 with overnight sampling being one of the 

more frequent methods. Therefore, samples of less than 400 ml were not removed from the uranium 

data. 

In general, Hanford did not have many large, acute intakes of uranium; only six samples were 

removed because they were collected after unusual acute intakes (e.g., a worker fell into a vat of 

uranyl nitrate). 

A small number of duplicate entries were found in the records from 1965 and 1968 that were true 

duplicates rather than, for instance, two analyses of the same sample; one of each pair was removed 

from the data before statistical analysis. 

Reporting levels are shown below. 

1948–74 4.0 μg/L 

1975–81 0.4 μg/L 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 14 of 54 

1982 to present Actual values were recorded as measured. 

Use of the reporting levels for uranium urinalysis appears to have been more consistent than was the 

case for plutonium, with the exception of one period. From 1958 to 1966 there were many results 

lower than 4 μg/L. It is not known if these indicated detection (i.e., whether the MDA was really 

reduced during this period). Therefore, these were treated as less-than results and included in the 

linear distribution. In 1967, Hanford returned to consistent use of the 4 μg/L reporting level. 

Through 1981, zeros, blanks, or less-than results were treated as nondetections and included in the 

linear distribution. Starting in 1982, 

• No reporting level was used. 

• The linear distribution was not used in the statistical analysis. 

• Blanks were considered invalid samples and not used in the statistical analysis. 

• Zero and negative numbers were included in the ranking of samples but not in the fitting of the 

line. 

Table 4-2 lists the time intervals for separate statistical analyses. The Plutonium–Uranium Extraction 

(PUREX) and UO3 plants were shut down during the 1970s, so there were few exposures and few 

samples. There were only 65 samples collected in 1973; the results were comparable to neighboring 

years, so the 1973 statistical parameters were included. 

Table 4-2. Time intervals for statistical 

analysis of uranium urine samples. 

Calendar year Analysis interval 

1947 Year 

1948 Half years 

1949–1969 Quarter years 

1970–1983 Year 

1984–1988 Quarter years 

4.1.3 Strontium Urinalysis

Specific urinalysis for radiostrontium began in 1965. Before that, the fission product urinalysis method 

was used to monitor for radiostrontium and some other fission product radionuclides. Both 89Sr and 

90Sr could have been counted depending on whether the sample was beta-counted before or after a 

period for ingrowth of 90Y. For this study, all the results were assumed to be 90Sr because it was 

generally more prevalent and because it produces higher (more claimant-favorable) doses per unit 

intake than 89Sr. Results were recorded as microcuries per liter for 1965 to 1974 and as 

disintegrations per minute per sample from 1975 to the present. The earlier results were converted to 

disintegrations per minute per sample before statistical analysis using the recorded volume of the 

sample. 

Most strontium urine samples were simulated 24-hr samples, so samples that were less than 400 ml 

were removed from the data before statistical analysis. Thirteen sample results were removed 

because they were follow-up samples to known large acute intakes; one sample result was removed 

because it was a recount. There were some obvious duplicates that were removed. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 15 of 54 

Reporting levels are shown below. 

1965–1969 1.67E-5 μCi//L 

1970–1974 1.00E-6 μCi/L 

1975–3/1979 2 dpm/sample 

4/1979–1981 5 dpm/sample 

1982–1988 Actual values were recorded as measured 

Blanks with volumes greater than 400 ml were rare; these were considered invalid and were not used. 

Through 1981, zero or less-than results were treated as nondetections and included in the linear 

distribution. Starting in 1982: 

• No reporting level was used. 

• The linear distribution was not used in this analysis. 

• Zero and negative numbers were included in the ranking of samples but not in the fitting of the 

line. 

Table 4-3 lists the time intervals for separate statistical analyses. Before 1970 there were few 

samples in a given year and very few samples that exceeded the reporting level, so samples were 

grouped into two 3-yr intervals. Before 1979, in general, there were only a few hundred (and 

sometimes less than a hundred) samples in a year. Whole-body counting was the primary bioassay 

method for fission products; the exception was for the workers at the Waste Encapsulation and 

Storage Facility where exposure to pure 90Sr was possible. The data from 1979 were split into two 

periods because of the change in reporting level from 2 to 5 dpm/sample on April 1. 

Table 4-3. Time intervals for statistical 

analysis of 90Sr urine samples. 

Calendar year Analysis interval 

1965, 1966, 1967 As one group 

1968, 1969, 1970 As one group 

1971–1978 Years 

1Q 1979 Quarter 

2,3,4Q 1979 As one group 

1980–1981 Years 

1982–1988 Quarters 

4.1.4 Promethium Urinalysis

Promethium-147 is a fission product with greater abundance in 1-yr-aged fuel (1 yr since removal 

from the reactor) in weapons-grade fuel than either 90Sr or 137Cs. However, it behaves in the body 

somewhat similarly to 90Sr and had an early maximum permissible body burden (MPBB) that was a 

factor of 30 (ICRP 1959) less than that for 90Sr and, later, an annual limit on intake that was a factor of 

14 (ICRP 1979, 1981) less than that for 90Sr. The presence of 147Pm would have been detected as 

part of the fission product urinalysis even though the results of the fission product urinalysis were 

calibrated for and interpreted as 90Sr. When whole-body counting and 90Sr urinalysis replaced the 

fission product urinalysis as the bioassay method of choice for fission products, 147Pm was considered 

an insignificant contributor to internal dose and 147Pm bioassay for workers exposed to general fission 

products was not performed. Promethium-147 as an unconcentrated fission product in general 

contamination is treated as a miscellaneous fission product as described in Section 6.8.
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 16 of 54 

Specific bioassay for 147Pm was initiated when the Pacific Northwest Laboratory (now PNNL) began 

manufacturing 147Pm heat sources in the 325 Building in 1966. Some exposure to 147Pm also 

occurred in the 308 Fuels Laboratory. The number of workers in the bioassay program and the 

number of samples were small in comparison to the numbers for the plutonium, uranium, or strontium 

bioassays, with a high of 65 workers in 1968. There was almost no sampling from 1972 to 1975, 

which probably indicates a cessation of the original heat source program, and only 20 workers were 

sampled from 1976 to 1979. The exact end date of the heat source program has not been 

determined. For purposes of this study, it was assumed that exposure occurred from 1966 to 1979, 

although it is likely that any exposure from 1972 to 1975 was only due to residual activity. 

Results were recorded as microcuries per liter from 1966 to 1974 and as disintegrations per minute 

per sample from 1975 to 1979. The earlier results were converted to disintegrations per minute per 

sample using the sample volume. 

Most routine samples were simulated 24-hr samples, so samples with volumes smaller than 400 ml 

were removed from the data before statistical analysis. There were a large number of duplicate 

entries in the database from 1966 to 1968, and these were removed. There was a glovebox rupture 

and large contamination spread that mainly affected three workers in 1967, and an overpressurization 

and blowback of a sampling line affected another worker in 1968; samples associated with these 

incidents were removed. 

Reporting levels are shown below. 

1966–Mar. 25, 1970 1.67E-5 μCi/L 

Mar. 31, 1970–1974 1.00E-5 μCi/L 

1975–1979 25 dpm/sample 

The linear distribution was applied to results at or below the reporting levels. There were no blanks 

with volumes greater than 400 ml. 

Table 4-4 lists the time intervals for separate statistical analyses. The split in 1970 occurred because 

of the change in reporting level on March 31. 

Table 4-4. Time intervals for statistical analysis of 147Pm urine samples. 

Calendar year Analysis interval 

1966, 1967 As one group 

1968, 1969, 1970 (through March 25,1970) As one group 

Mar. 31–Dec. 31, 1970; 1971 As one group 

1972–1974 Not enough samples for statistics 

1975, 1976, 1977, 1978, 1979 As one group 

4.1.5 Zinc-65 in Whole-Body Counts

Zinc-65 was routinely reported in whole-body counts from 1960 to 1983. There were only about 370 

recordings of 65Zn in whole-body counts in 1984, but that was considered sufficient to include in the 

statistical analysis. After 1984 there were very few detections of 65Zn in whole-body counts. Zinc-65 

was mostly a concern during the operation of the once-through-cooled reactors (through 1971) when 

large activities of 65Zn were discharged to the Columbia River. 

The three largest local cities drew their sanitary water mostly from the Columbia River, as did the 

reactors on the site. Brady (1964) shows that 65Zn passed through the purification systems in 

sufficient concentration to produce measurable body burdens in many Hanford workers. Brady also 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 17 of 54 

attributed some of the 65Zn to ingestion of fish from the Columbia River or from crops irrigated by 

Columbia River water. 

Figure A-23 shows a decrease in the median body burden of 65Zn starting in 1972 (with the exception 

of a spike in body burden in the fourth quarter of 1976), which appears to show the effect of the 

shutdown of the once-through-cooled reactors. However, it was apparent from the distribution of 

activities measured in the workers that inhalation in the workplace also had to be a viable intake 

pathway; ingestion of water cannot explain the higher body burdens at the higher percentile values of 

the quarterly distributions. Therefore, both inhalation and ingestion pathways were modeled. 

All whole-body counts were recorded in nanocuries. 

In whole-body counting, the decision level varies with every individual and every count because of the 

interperson variability in activity of 40K, the intraperson variability in activity of interfering radionuclides 

a person could have on them on any given day (especially radon and thoron progeny), and the 

day-to-day variability in the natural background in the counting cell. In addition and especially during 

the early years of the in vivo counting program, there were improvements to the program including 

type or number of detectors, counting times, and improved electronics. It was common for more than 

one whole-body counting system to be used at a time. Therefore, the stated detection limits were 

approximate and were meant to apply to a general range; little documentation on detection levels has 

been found. A single reporting level is not apparent in the recorded data. 

Because of these factors, it was impossible to state a distinct threshold value above which all results 

meant detection and below which all results meant nondetection. For 1960 to 1974, a detection level 

of 0.8 nCi for 65Zn was found in the documentation. Relative to the distribution of results in most 

years, this value was a reasonable one to use as the reporting level. Blanks and zero results were 

distributed using the linear distribution with 0.8 nCi as the upper range; values between zero and 0.79 

nCi were used as recorded and mixed in with the numbers from the distribution. 

For 1975 to 1984, the value of 0.75 nCi was distinctly used as the reporting level, with only one value 

that fell between zero and 0.75 nCi. Blanks and zeros were distributed using the linear distribution. 

Table 4-5 lists the time intervals for separate statistical analyses. 

Table 4-5. Time intervals for statistical 

analysis of 65Zn whole-body counts. 

Calendar year Analysis interval 

1960 Year 

1961–1962 Half years 

1963–1974 Quarter years 

1975 Half years 

1976–1983 Quarter years 

1984 Year 

4.1.6 Sodium-24 in Whole-Body Counts

Similar to 65Zn, 24Na was reported routinely from 1960 to 1983 with a significant but much smaller 

number of results in 1984; after 1984 there were very few recorded results. Sodium-24 was released 

to the Columbia River from the once-through-cooled reactors, but its short half-life (15 hr) prevented 

significant concentrations in local municipal drinking water systems. Its presence was correlated with 

reactor workers and was to some extent believed to be due to drinking water at the reactors (Brady 

1964). However, as with 65Zn there were body burdens that were too high to be explained by 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 18 of 54 

ingestion of drinking water. As a consequence, 24Na was modeled using both inhalation and ingestion 

pathways. 

As explained in the 65Zn section, a distinct threshold value for detection was not apparent from the 

data. For 1960 the lowest reported value was 0.56 nCi, so this value was used as the reporting level. 

Blanks and zero results were distributed using the linear distribution with 0.56 nCi as the upper range. 

For 1961 to 1974, a detection level of 0.3 nCi for 24Na was found in the documentation. This value 

was reasonable for use as the reporting level even though there were many results recorded at 

smaller values. Blanks and zero results were distributed using the linear distribution with 0.3 nCi as 

the upper range. Values between zero and 0.29 nCi were used as recorded and mixed with the 

numbers from the distribution. For 1975 to 1984, a value of 0.31 nCi was distinctly being used as the 

reporting level with no measurements recorded lower than 0.31 nCi. Blanks and zeros were 

distributed using the distribution with 0.3 nCi as the upper range. 

Table 4-6 lists the time intervals for separate statistical analyses. 

Table 4-6. Time intervals for statistical 

analysis of 24Na whole-body counts. 

Calendar year Analysis interval 

1960 Year 

1961–1962 Half years 

1963–1983 Quarter years 

1984 Half years 

4.1.7 Cesium-137 in Whole-Body Counts

Cesium-137 was recorded routinely with every whole-body count from 1960 to 1983. For 1984 to 

1988, 137Cs was generally recorded only if it was detected above a reporting level, but the database 

also shows valid whole-body counts including blank values for 137Cs. Why this occurred is not known. 

Because of its long half-life and abundance in the waste from the separations plants, 137Cs has long 

been considered one of the principal contaminants at Hanford and has often been used as an 

indicator of potential intakes. 

For 1960 to 1974, a detection level of 0.5 nCi was found in the documentation, but it is clear from the 

distribution of results that no distinct reporting level was used. Therefore, the distribution for each 

year was evaluated, and a value was chosen as the upper range of the linear distribution for 

assignment of blanks and zeroes. This value was chosen as 1) being reasonable in relation to the 

stated detection limit and 2) representing a break point in the pattern of results when ranked from 

highest to lowest (with only a few scattered results showing below the breakpoint). 

Table 4-7 lists these values. For each year, values between zero and the value given in Table 4-7 

were used as recorded and mixed with the distribution of the blank and zero results. Starting in 1976, 

0.66 nCi was the stated detection level in the database and its use as a reporting level was clear. 

From June 14, 1986, to September 19, 1986, the stated reporting level varied with each count but 

ranged mostly between 1 and 2 nCi. On September 22, 1986, a reporting level of 3 nCi was 

implemented and remained in effect until some time after 1988. 

Table 4-7. Subjective upper range for the linear 

distribution. 

Calendar year 

Upper range of the 

distribution (nCi) 

1960–1962 1.0 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 19 of 54 

1963–1964 1.4 

1965–1966 1.5 

1967–1968 1.0 

1969–Jun. 1986 0.65 

Jul. 1986–1988 3.0 

Table 4-8 lists the time intervals for separate statistical analyses. 

Table 4-8. Time intervals for statistical analysis of 137Cs 

whole-body counts. 

Calendar year Analysis interval 

1960–1974 Quarter years 

1975 Only two values reported and neither above 

the reporting level. This year was skipped. 

1976–1983 Quarter years 

1984–1988 Half years 

When the distributions for the 1960s with the linear distributions were plotted and fitted, it became 

apparent both visually and from the R2

 values that the linear distribution for the blanks and zeros did 

not match well with the distribution of the 137Cs results above the detection level. As a consequence, 

the method of including zeros and blanks in the ranking but not the fitting (used for coworker data for 

Y-12, Oak Ridge National Laboratory, K-25, and Portsmouth sites) was applied to each data set. The 

two methods were compared for each time interval. In general through 1983, the second method 

(rank-only method) provided better results in relation to three criteria: 1) the R2

 fit parameter, 2) a 

subjective visual inspection, and 3) comparison of the fitted values for the 50th-and 84th-percentile 

values versus the same values in the ranked, unfitted raw data. Table 4-9 lists the latter comparisons. 

The shaded cells highlight the method that provided the closest fit to the raw data. 

The 137Cs data could have been unusual in that all workers had body burdens of 137Cs due to fallout 

from nuclear weapons testing, and the few whole-body counts that were recorded as zero or blank 

had true values that were just barely below detection. Distributing these counts linearly between zero 

and the reporting level, therefore, did not match well with the bulk of the results that were above the 

reporting level. 

From 1984 to June 1986, 137Cs results were recorded differently than in other years. When 137Cs was 

not detected, the radionuclide was sometimes listed in the results as a blank but, more often, 137Cs 

was not listed at all. Instead, it was treated like the many other fission product radionuclides that 

could be detected by in vivo counting but are not listed if they are not detected. For this period the 

total number of whole-body counts given was determined by tallying the number of 40K counts, which 

were recorded for every valid whole-body count. Each whole-body count for which 137Cs was not 

listed was considered the same as a whole-body count with a blank or zero result for 137Cs. 

From 1984 to 1988, the rank-only method did not provide good fits. This was due in part to 

inconsistent use of the supposed 0.65-nCi reporting level, which could have been due to the use of 

three different whole-body detectors. For example, Cunningham (1984) stated, “The normal detection 

limit of two nanocuries was increased to five nanocuries at the UNC’s [a Hanford contractor at that 

time] request for whole-body counts performed at the portable whole-body counter during December 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 20 of 54 

Table 4-9. Comparison of 137Cs 50th- and 84th-percentile values between the linear distribution and 

the rank-but-not-fit methods. 

50th-percentile value 84th-percentile value 

Quarter Rank only 

linear 

distrib. Raw data 

% 

difference 

Rank/rawa

% 

difference 

Lin./rawa

 Rank only

linear 

distrib. Raw data 

% 

difference 

Rank/rawa

% 

difference 

Lin./rawa

02/15/1960 6.773 6.7049 7.100 -5 -6 9.620 9.7916 9.440 2 4 

05/15/1960 6.689 6.3078 7.000 -4 -10 9.347 10.0704 8.900 5 13 

08/15/1960 5.977 5.0141 6.250 -4 -20 9.466 11.0653 9.000 5 23 

11/15/1960 5.770 4.8916 6.100 -5 -20 8.302 9.7426 8.100 2 20 

02/15/1961 4.728 3.5971 4.950 -4 -27 6.858 8.3604 6.800 1 23 

05/15/1961 4.482 4.0306 4.550 -1 -11 6.764 7.5645 6.544 3 16 

08/15/1961 3.805 3.4611 4.000 -5 -13 6.006 6.6417 5.900 2 13 

11/15/1961 3.491 3.2782 3.700 -6 -11 5.184 5.5648 4.940 5 13 

02/15/1962 3.527 2.7622 3.700 -5 -25 5.563 6.6115 5.588 0 18 

05/15/1962 3.457 2.8695 3.400 2 -16 5.055 5.9044 5.124 -1 15 

08/15/1962 4.378 3.9146 4.500 -3 -13 6.502 7.3051 6.300 3 16 

11/15/1962 5.253 4.5092 5.300 -1 -15 7.678 8.8681 8.100 -5 9 

02/15/1963 6.691 6.4816 6.900 -3 -6 10.362 10.7872 9.764 6 10 

05/15/1963 8.922 8.4766 9.100 -2 -7 13.998 14.9786 13.000 8 15 

08/15/1963 11.218 10.7314 11.000 2 -2 16.663 17.7776 16.000 4 11 

11/15/1963 13.470 11.5633 14.000 -4 -17 19.952 23.5147 19.000 5 24 

02/15/1964 15.374 11.5565 17.000 -10 -32 23.543 29.8527 22.000 7 36 

05/15/1964 17.644 14.3843 18.500 -5 -22 26.857 32.8181 27.000 -1 22 

08/15/1964 18.129 15.6201 19.000 -5 -18 26.767 31.5749 27.000 -1 17 

11/15/1964 17.811 15.3452 19.000 -6 -19 28.334 33.3275 26.000 9 28 

02/15/1965 15.208 10.3744 17.000 -11 -39 23.287 30.3181 23.000 1 32 

05/15/1965 15.288 14.9963 16.000 -4 -6 23.190 23.9664 22.400 4 7 

08/15/1965 13.341 10.8838 14.000 -5 -22 19.881 24.1283 19.000 5 27 

11/15/1965 11.964 8.8597 13.000 -8 -32 18.931 23.7735 18.000 5 32 

02/15/1966 10.544 7.9454 12.000 -12 -34 16.593 20.5504 16.000 4 28 

05/15/1966 8.526 7.0335 9.300 -8 -24 13.837 16.4036 13.000 6 26 

08/15/1966 8.198 8.0457 8.700 -6 -8 13.210 13.6153 12.000 10 13 

11/15/1966 6.417 5.2622 7.200 -11 -27 12.039 14.0325 11.000 9 28 

02/15/1967 5.877 5.4974 6.300 -7 -13 9.856 10.7179 9.644 2 11 

05/15/1967 5.417 4.8662 5.800 -7 -16 9.242 10.3839 9.000 3 15 

08/15/1967 4.770 4.1398 5.300 -10 -22 8.025 9.1841 7.900 2 16 

11/15/1967 4.049 3.1439 4.700 -14 -33 7.580 8.9436 6.900 10 30 

02/15/1968 3.195 1.9707 3.500 -9 -44 6.012 6.9889 6.000 0 16 

05/15/1968 2.574 2.1498 3.000 -14 -28 4.939 5.5300 4.740 4 17 

08/15/1968 2.667 2.0480 3.000 -11 -32 5.467 6.2850 5.260 4 19 

11/15/1968 2.824 2.3593 3.100 -9 -24 5.511 6.2571 5.100 8 23 

02/15/1969 3.022 2.3924 3.300 -8 -28 5.516 6.5052 5.200 6 25 

05/15/1969 2.176 1.7451 2.400 -9 -27 4.728 5.3988 4.300 10 26 

08/15/1969 2.222 1.6440 2.400 -7 -31 4.332 5.0581 4.300 1 18 

11/15/1969 2.354 1.4820 2.550 -8 -42 5.610 6.3480 4.700 19 35 

02/15/1970 2.302 1.5264 2.500 -8 -39 4.695 5.1308 4.400 7 17 

05/15/1970 2.074 1.6764 2.300 -10 -27 4.580 5.2044 3.900 17 33 

08/15/1970 2.152 1.6640 2.500 -14 -33 4.536 5.1995 4.100 11 27 

11/15/1970 2.642 1.9784 2.900 -9 -32 4.874 5.8021 4.500 8 29 

02/15/1971 2.161 1.6815 2.400 -10 -30 4.107 4.7771 4.000 3 19 

05/15/1971 2.429 2.1680 2.600 -7 -17 4.501 4.9822 4.168 8 20 

08/15/1971 2.527 2.2540 2.600 -3 -13 4.389 4.9210 4.000 10 23 

11/15/1971 2.674 2.4173 2.700 -1 -10 4.727 5.2469 4.200 13 25 

02/15/1972 2.368 1.9827 2.600 -9 -24 4.295 4.9311 4.000 7 23 

05/15/1972 2.324 2.1229 2.500 -7 -15 4.995 5.4094 4.200 19 29 

08/15/1972 2.325 2.1214 2.400 -3 -12 4.530 4.9716 4.000 13 24 

11/15/1972 2.200 1.7517 2.500 -12 -30 5.052 5.7898 4.400 15 32 

02/15/1973 2.054 1.6426 2.300 -11 -29 4.504 5.1906 3.900 15 33 

05/15/1973 1.848 1.5758 2.000 -8 -21 3.468 3.9319 3.300 5 19 

08/15/1973 1.830 1.5869 2.000 -9 -21 3.345 3.7805 3.300 1 15 

11/15/1973 1.640 1.3787 1.800 -9 -23 3.300 3.7405 3.000 10 25 

02/15/1974 1.251 1.0530 1.400 -11 -25 3.020 3.3523 2.700 12 24 

05/15/1974 0.919 0.7600 0.945 -3 -20 2.184 2.4080 2.100 4 15 

08/15/1974 1.089 0.9004 1.100 -1 -18 2.462 2.7476 2.400 3 14 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 21 of 54 

Table 4-9. (Continued). Comparison of 137Cs 50th- and 84th-percentile values between the linear 

distribution and the rank-but-not-fit methods.

50th-percentile value 84th-percentile value 

Quarter Rank only 

linear 

distrib. Raw data 

% 

difference 

Rank/rawa

% 

difference 

Loch/rawa Rank only

linear 

distrib. Raw data 

% 

difference 

Rank/rawa

% 

difference 

Loch/rawa

11/15/1974 1.109 0.9124 1.100 1 -17 2.702 2.9827 2.600 4 15 

02/15/1976 1.049 0.8155 1.100 -5 -26 2.165 2.4371 2.200 -2 11 

05/15/1976 1.120 0.9374 1.200 -7 -22 2.695 2.9798 2.300 17 30 

08/15/1976 0.932 0.7885 0.970 -4 -19 2.182 2.4143 2.100 4 15 

11/15/1976 1.618 1.3848 1.700 -5 -19 3.974 4.4145 3.700 7 19 

02/15/1977 1.365 1.0991 1.400 -2 -21 2.988 3.3717 2.900 3 16 

05/15/1977 1.469 1.2989 1.500 -2 -13 3.426 3.7779 2.800 22 35 

08/15/1977 1.122 0.9515 1.200 -7 -21 2.924 3.2178 2.600 12 24 

11/15/1977 0.868 0.7054 0.785 11 -10 2.247 2.4277 2.220 1 9 

02/15/1978 1.052 0.8522 1.100 -4 -23 2.643 2.9030 2.500 6 16 

05/15/1978 0.788 0.7319 0.860 -8 -15 2.380 2.5618 2.100 13 22 

08/15/1978 0.779 0.6937 0.800 -3 -13 2.234 2.4145 2.100 6 15 

11/15/1978 1.082 0.8820 1.100 -2 -20 2.681 2.9578 2.600 3 14 

02/15/1979 1.178 1.0128 1.300 -9 -22 2.958 3.2641 2.700 10 21 

05/15/1979 0.867 0.6959 0.840 3 -17 2.052 2.2602 2.100 -2 8 

08/15/1979 0.922 0.7524 0.940 -2 -20 2.198 2.4296 2.200 0 10 

11/15/1979 1.239 0.9935 1.300 -5 -24 2.654 3.0002 2.604 2 15 

02/15/1980 1.152 0.9653 1.200 -4 -20 2.820 3.1273 2.700 4 16 

05/15/1980 0.818 0.8072 0.880 -7 -8 2.912 3.0825 2.400 21 28 

08/15/1980 0.669 0.6006 0.635 5 -5 1.897 2.0524 1.800 5 14 

11/15/1980 0.732 0.6364 0.720 2 -12 1.940 2.1137 1.900 2 11 

02/15/1981 0.828 0.6995 0.820 1 -15 1.096 2.3033 2.100 0 10 

05/15/1981 0.499 0.4194 0.487 3 -14 1.348 1.3065 1.200 -1 9 

08/15/1981 0.335 0.3650 0.435 -23 -16 1.247 1.1101 1.000 -5 11 

11/15/1981 0.474 0.3995 0.474 0 -16 1.027 1.2101 1.188 -8 2 

02/15/1982 0.565 0.4809 0.556 2 -13 1.295 1.4869 1.300 4 14 

05/15/1982 0.470 0.4335 0.496 -5 -13 1.124 1.3749 1.300 -4 6 

08/15/1982 0.436 0.3836 0.460 -5 -17 0.815 1.1464 1.100 -7 4 

11/15/1982 0.532 0.4545 0.521 2 -13 0.905 1.4185 1.300 0 9 

02/15/1983 0.426 0.4016 <.65 1.119 1.2493 1.200 -6 4 

05/15/1983 0.302 0.3348 <.65 0.02194 0.9809 0.840 -3 17 

08/15/1983 0.371 0.3528 <.65 0.06501 1.0379 0.920 -2 13 

11/15/1983 0.435 0.3978 <.65 0.02014 1.2350 1.200 -7 3 

04/01/1984 0.00080 0.2487 <.65 4.686 0.6537 <.65 

10/01/1984 0.00786 0.2461 <.65 0.00089 0.6285 <.65 

04/01/1985 0.00140 0.2430 <.65 3.781 0.6134 <.65 

10/01/1985 3.785 0.2398 <.65 0.124 0.5927 <.65 

04/01/1986 0.00001 0.2450 <.65 1.075 0.6327 <.65 

10/01/1986 2.786 1.1416 <3.0 0.469 2.7971 <3.0 

04/01/1987 0.0123 1.1220 <3.0 0.152 2.8167 <3.0 

10/01/1987 0.409 1.1235 <3.0 1.096 2.8170 <3.0 

04/01/1988 0.131 1.1169 <3.0 1.348 2.7720 <3.0 

10/01/1988 0.0274 1.1106 <3.0 1.247 2.7455 <3.0 

a. Shaded cells denote which of the two methods was closer to the raw distribution. 

1983 at 100-N Area.” This implies that the detection limit for the portable whole-body counter was 

usually 2 nCi, although the letter does not state to which radionuclide that applied. It is possible that 

the sensitivity for the portable counter was not as good as for the detectors used at the whole-body 

counting facility. In addition, the sensitivities of the two counters at the fixed facility were not the same 

(Palmer, Rieksts, and Spitz 1984). Because of the different sensitivities, it is likely that not all counts 

recorded as blanks for 137Cs were really less than 0.65 nCi. Another reason for the poor fits is that the 

numbers of results recorded as greater than the reporting level (0.65 nCi for 1984 to September 19, 

1986, and 3 nCi for September 22, 1986, to 1988) were very small (generally less than 2% of the total 

counts during each half-year period). The rank-only method forces a fit to these small numbers of 

detected results and extrapolates the fits to the almost 4,000 counts in each half-year period that had 

no detection. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 22 of 54 

This analysis used the linear distribution for 1984 to 1988 because it provides better fits (visually and 

by the R2

 values) and is less biased under the circumstances mentioned above. 

4.2 ANALYSIS 

For each of the seven radionuclides, a lognormal distribution for the data in the intervals specified in 

Tables 4-1 to 4-6 and Table 4-8 was assumed. The 50th- and 84th-percentile values were calculated 

using the method described in ORAUT (2005a). Tables A-1 to A-7 in Attachment A show the 

statistical analysis results for plutonium, uranium, 90Sr, 147Pm, 65Zn, 24Na, and 137Cs. 

5.0 INTAKE MODELING

5.1 ASSUMPTIONS 

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

either eliminated or normalized to be representative of a full day before creating the lognormal plots. 

Each result used in the intake calculation was assumed to have a normal distribution, and a uniform 

absolute error of 1 was applied to all results, which weighted all results equally. A chronic exposure 

pattern was assumed, even though this is unlikely for most exposures at Hanford, because it 

approximates a series of acute intakes with unknown dates. Intakes were assumed to be from 

inhalation using a default breathing rate of 1.2 m3

/hr and a 5-μm activity median aerodynamic 

diameter particle size distribution unless otherwise specified. Intakes of 65Zn and 24Na were 

determined using whole-body counting results. As discussed in Sections 4.1.5 and 4.1.6, both 

inhalation and ingestion intakes were possible, so both were modeled. 

The results for 147Pm and 90Sr urinalysis were taken directly from the statistical analysis of the 

database, as were the results for 65Zn, 24Na, and 137Cs whole-body counting. 

For plutonium, 239Pu was used for the IMBA intake modeling, but the database results were presumed 

to be gross plutonium alpha measurements through the third quarter of 1983. To convert from gross 

plutonium alpha to 239Pu, fresh fuel-grade plutonium was assumed for 1945 to 1949, 5-yr-aged 

fuel-grade plutonium was assumed for 1950 to 1954, and 10-yr-aged fuel-grade plutonium was 

assumed for 1955 and after. Table 5-1 lists the percentages of 239Pu used. Starting in October 1, 

1983, alpha spectrometry was used in the analysis to specifically identify the 239Pu; therefore, no 

correction factor was used. 

Table 5-1. Plutonium mixture usage. 

Time period Plutonium grade 

Percentage 239Pu of 

plutonium alpha emitters 

1946-1949 Fresh fuel-grade 82.4% 

1950-1954 5-yr-aged fuel-grade 83.0% 

1955-09/30/1983 10-yr-aged fuel-grade 83.5% 

10/01/83+ 10-yr-aged fuel-grade 100% (isotopic analysis) 

For uranium, because the IMBA program requires urine results in units of activity per day, the total 

uranium values in micrograms per liter were multiplied by 1.4 to normalize them to the Reference Man 

excretion rate of 1,400 ml/d. Because a variety of enrichments was possible, the intake modeling 

used mass concentration units and 234U was assumed for all the IMBA intake modeling. This did not 

affect the data fits for intake determination (i.e., the same total intakes would be obtained for any 

enrichment that was assumed) because all uranium isotopes have the same biokinetic behavior and 

the isotopes considered in this analysis have long half-lives relative to the assumed intake period. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 23 of 54 

To convert to units of activity for dose calculation, the 0.7054 pCi/μg specific activity of natural 

uranium was assumed through 1952, and the 0.9099 pCi/μg specific activity of recycled uranium was 

used for later years (ORAUT 2004). Like the intake modeling, 234U was used to calculate the doses. 

The 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 1993). Because of the isotopic 

compositions of the source terms, the 234U dose conversion factor yields claimant-favorable doses. 

5.2 BIOASSAY FITTING 

The IMBA computer program was used to fit the bioassay results to a series of chronic inhalation or 

ingestion intakes. The exception is that one acute intake was used in the modeling of 24Na exposure 

because that resulted in the best fit. Modeling was performed only for intervals when data were 

available. Having been based on whole-body counts, the data for 65Zn and 24Na were available for 

1960 to 1984. The least amount of available data was for 147Pm from 1966 to 1979. Plutonium data 

was from 1946 to 1988, uranium data was from 1948 to 1988, and 90Sr data was from 1965 to 1988. 

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

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

were of similar magnitudes. A new chronic intake period was started where the data indicated a 

significant sustained change in the results. 

5.3 RADIONUCLIDES AND MATERIAL TYPES 

For each considered radionuclide or group of radionuclides, the bioassay results were entered into 

IMBA with assumed material types in terms of lung absorption type or uptake factor from the 

gastrointestinal tract. The types were chosen to be consistent with International Commission on 

Radiological Protection (ICRP) Publication 68 (ICRP 1993) and the Hanford internal dosimetry 

technical basis document (ORAUT 2004). Attachment A shows the resultant 50th-percentile intakes 

as plots. The annual bioassay data used in the fits are shown as solid blue dots (●) (dark spots when 

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

The type S compounds present at Hanford have very long radiological half-lives, and the materials are 

retained in the body for long periods. Therefore, the excretion results for different chronic intake 

periods are not independent for type S materials. For example, an intake in the 1950s could 

contribute to urinary excretion in the 1980s and later. To avoid potential underestimation of intakes 

for people who worked at Hanford for relatively short periods, each chronic intake of type S material 

was independently fit using only the bioassay results from the single intake period. This same 

process was used for type M plutonium and 147Pm as well. This method likely results in an 

overestimate of intakes, particularly for assumed type S exposures extending through multiple 

assumed intake periods. However, this approach was not used for type S plutonium. See Section 6.1 

for an explanation on how to use the type S plutonium intake. 

5.3.1 Plutonium

Both type M and S materials were present at Hanford and were common enough to apply to general 

workers, hence, both types were modeled. Tables 5-2 and 5-3 provide intakes for 239+240Pu. Dose 

reconstructions must also include intakes of other plutonium isotopes and 241Am as shown in Table 

5-1. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 24 of 54 

5.3.1.1 Type M 

This section shows intakes when the plutonium urinalysis results were fit as type M material. As 

discussed above, each chronic intake period was fit independently. Figures A-1 to A-4 show the fits 

to the 50th-percentile values for each intake period. The same intake periods were applied to the 

84th-percentile values because the values followed a similar pattern. Table 5-2 summarizes the 

intake periods and corresponding intake rates for the 50th- and 84th-percentile values. 

Table 5-2. Type M 239+240Pu intake periods and rates. 

Plutonium intake rate (dpm/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1946 12/31/1948 57.7 149.2 2.59 

01/01/1949 12/31/1952 21.1 54.11 2.56 

01/01/1953 12/31/1981 1.003 3.196 3.19 

01/01/1982 12/31/1988 0.1336 1.132 8.47 

Figure A-5 depicts the predicted excretion rates from all 50th-percentile type M intakes. 

The large decrease in 50th-percentile bioassay results and intakes after 1981 resulted from a switch 

in reporting practices from a reporting level of 0.025 dpm to reporting all results. The MDA also 

decreased from 0.05 dpm to 0.02 dpm in 1984. 

5.3.1.2 Type S 

Because type S plutonium clears slowly from the body, the plutonium exposure was fit as a single 

chronic intake based on the bioassay measurements from 1982 to 1988. This period was used 

because the measurements were relatively consistent; in addition, because these are the most recent 

measurements, they had the lowest MDA and, therefore, were presumably the most accurate. See 

Section 6.1 for special instructions for using the type S intake. 

Figure A-6 shows the predicted excretion rates for the 50th-percentile values based on a chronic 

intake for the entire set of years fitted to the bioassay data for the last 7 yr (1982 to 1988). The same 

intake period was applied to the 84th-percentile values because the values followed a similar pattern. 

Table 5-3 summarizes the intake period and corresponding intake rate for the 50th- and 

84th-percentile values. 

Table 5-3. Type S 239+240Pu intake period and rates. 

Plutonium intake rate (dpm/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1946 12/31/1988 0.5169 4.382 8.48 

5.3.2 Uranium

Uranium at Hanford existed as mostly type F or S, but neither classification should be considered a 

perfect match to the uranium compounds, and type M cannot be ruled out. Therefore, all three types 

should be considered possible. Thorium exposure was associated with uranium exposure in 300 

Area facilities from 1950 to 1970. Section 6.1.2 contains guidance for adding thorium to uranium 

intakes. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 25 of 54 

5.3.2.1 Type F 

This section shows intakes when uranium urinalysis results were fit using a type F material. Figure 

A-7 shows the fit to the 50th-percentile values from all intakes. The figure depicts the expected 

excretion rate from an individual exposed for all the periods at the 50th-percentile intake rate. The 

same intake periods were applied to the 84th-percentile values because the values followed a similar 

pattern. Table 5-4 summarizes the intake periods and corresponding intake rates for the 50th- and 

84th-percentile values. 

Table 5-4. Type F uranium intake periods and rates. 

Uranium intake rate (μg/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1948 12/31/1952 17.42 58.35 3.35 

01/01/1953 12/31/1956 12.3 39.45 3.21 

01/01/1957 12/31/1961 17.73 61.65 3.48 

01/01/1962 12/31/1974 10.61 31.09 2.93 

01/01/1975 12/31/1983 1.281 7.037 5.49 

01/01/1984 12/31/1988 0.4903 1.895 3.86 

The decrease in intake rate in 1975 resulted from a decrease in the reporting level from 4 μg/L to 

0.4 μg/L. That decrease may have also resulted in part from the shut downs of the PUREX and UO3 

plants from 1973 to 1983. 

5.3.2.2 Type M 

The intake periods used in the type F fits were applied to the type M material fits. Figure A-8 shows 

the fit to the 50th-percentile values from all intakes. The same intake periods were applied to the 

84th-percentile values because the values followed a similar pattern. Table 5-5 summarizes the 

intake periods and corresponding intake rates for the 50th- and 84th-percentile values. 

5.3.2.3 Type S 

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

discussed, each chronic intake period for type S material was fit independently. Figures A-9 to A-14 

show the individual fits for the 50th-percentile values. The 84th–percentile values were fit similarly. 

Table 5-6 summarizes the intake rates for the 50th- and 84th-percentile values. 

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

Uranium intake rate (μg/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1948 12/31/1952 73.12 244.5 3.34 

01/01/1953 12/31/1956 49.35 159 3.22 

01/01/1957 12/31/1961 72.79 252.6 3.47 

01/01/1962 12/31/1974 42.78 124.9 2.92 

01/01/1975 12/31/1983 4.414 25.99 5.89 

01/01/1984 12/31/1988 1.919 7.043 3.67 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 26 of 54 

Table 5-6. Type S uranium intake periods and rates. 

Uranium intake rate (μg/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1948 12/31/1952 1,308 4,373 3.34 

01/01/1953 12/31/1956 1,035 3,321 3.21 

01/01/1957 12/31/1961 1,349 4,660 3.45 

01/01/1962 12/31/1974 665.1 1,953 2.94 

01/01/1975 12/31/1983 83.67 403.3 4.82 

01/01/1984 12/31/1988 46.84 171.6 3.66 

Figure A-15 shows the predicted excretion rates from all 50th-percentile value type S intakes. 

5.3.3 Strontium-90

Only type F solubility was analyzed for 90Sr. Figure A-16 shows the fit to the 50th-percentile values 

from all intakes. Table 5-7 summarizes the intake rates for the 50th- and 84th-percentile values. 

Table 5-7. Type F 90Sr intake periods and rates. 

Sr-90 intake rate (dpm/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1965 12/31/1967 90.47 241.5 2.67 

01/01/1968 12/31/1970 60.5 241.5 3.99 

01/01/1971 12/31/1988 3.698 9.405 2.54 

5.3.4 Promethium-147

5.3.4.1 Type M 

Each chronic intake period for type M 147Pm was fit independently. Figures A-17 and A-18 show the 

individual fits for the 50th-percentile values. The 84th-percentile values were fit similarly. Table 5-8 

summarizes the intake rates for the 50th- and 84th-percentile values. 

Table 5-8. Type M 147Pm intake periods and rates. 

147Pm intake rate (dpm/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1966 12/31/1969 4,976 15,620 3.14 

01/01/1970 12/31/1979 1,720 4,483 2.61 

Figure A-19 shows the predicted excretion rates from all 50th-percentile value type M intakes. 

5.3.4.2 Type S 

Each chronic intake period for type S 147Pm was fit independently. Figures A-20 and A-21 show the 

individual fits for the 50th-percentile values. The 84th–percentile values were fit similarly. Table 5-9 

summarizes the intake rates for the 50th- and 84th-percentile values. 

Table 5-9. Type S 147Pm intake periods and rates. 

Pm-147 intake rate (dpm/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1966 12/31/1969 131,500 411,400 3.13 

01/01/1970 12/31/1979 34,810 90,850 2.61 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 27 of 54 

Figure A-22 shows the predicted excretion rates from all 50th-percentile value type S intakes. 

5.3.5 Zinc-65

Intakes of 65Zn include a single acute intake in addition to the normal chronic intakes modeled. This 

acute intake was included to optimize the fit of the modeling results to the data. The data show a 

sudden increase in the last quarter of 1976 followed by a steady decrease over the next several 

quarters, which is indicative of an acute intake during the last quarter of 1976. 

5.3.5.1 Inhalation Intakes 

Absorption type S was used for 65Zn inhalation intakes. Each chronic intake period for type S 65Zn 

was fit independently. However, the acute intake on October 1, 1976, was modeled with the 

contemporaneous chronic intake. Figures A-23 to A-28 show the individual fits for the 50th-percentile 

values. The 84th-percentile values were fit similarly. Table 5-10 summarizes the intake rates for the 

50th- and 84th-percentile values. 

Table 5-10. Type S zinc-65 inhalation intake periods and rates. 

Zinc-65 intake rate (pCi/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1960 12/31/1963 44.56 181.2 4.07 

01/01/1964 12/31/1967 53.68 199.6 3.72 

01/01/1968 12/31/1970 35.29 124.2 3.52 

01/01/1971 12/31/1972 29.88 94.31 3.16 

01/01/1973 12/31/1977 12.58 42.59 3.39 

01/01/1978 12/31/1984 7.411 21.83 2.95 

10/01/1976a - 2555b 14260b 5.58 

a. This is the date of the acute intake. 

b. This intake has units of pCi for an acute intake rather than pCi/d. 

Figure A-29 shows the predicted excretion rates from all 50th-percentile value type S intakes. 

The once-through-cooled reactors were being shutdown from 1964 to 1971. 

5.3.5.2 Ingestion Intakes 

The ingestion intakes of 65Zn were modeled together. Figure A-30 shows the fit to the 50th-percentile 

values from all intakes. The 84th–percentile values were fit similarly. Table 5-11 summarizes the 

intake rates for the 50th- and 84th-percentile values. Ingestion intakes after the once-through-cooled 

reactors were shut down (after 1972) were not considered plausible. 

Table 5-11. Zinc-65 ingestion intake periods and rates. 

Zn-65 intake rate (pCi/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1960 12/31/1963 26.21 105.0 4.01 

01/01/1964 12/31/1967 27.64 103.4 3.74 

01/01/1968 12/31/1970 16.69 57.34 3.44 

01/01/1971 12/31/1972 13.06 39.86 3.05 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 28 of 54 

5.3.6 Sodium-24

5.3.6.1 Inhalation Intakes 

Absorption type F was used for 24Na inhalation intakes. Figure A-31 shows the fit to the 

50th-percentile values from all intakes. The 84th–percentile values were fit similarly. Table 5-12 

summarizes the intake rates for the 50th- and 84th-percentile values. 

Table 5-12. Type F 24Na inhalation intake periods and rates. 

Na-24 intake rate (pCi/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1960 09/30/1963 310.3 942.6 3.04 

10/01/1963 12/31/1963 1921 6939 3.61 

01/01/1964 09/30/1964 452.7 1410 3.11 

10/01/1964 03/31/1965 1037.6 3654 3.52 

04/01/1965 12/31/1973 452.7 1410 3.11 

01/01/1974 12/31/1984 250.8 680.7 2.71 

5.3.6.2 Ingestion Intakes 

The ingestion intakes of 24Na were modeled together. Figure A-32 shows the fit to the 50th-percentile 

values from all intakes. These depict the expected excretion rates from an individual exposed for all 

the periods at the 50th- and 84th-percentile intake rates. Table 5-13 summarizes the intake rates for 

the 50th- and 84th-percentile values. Ingestion intakes after the once-through-cooled reactors were 

shut down (by 1971 because of the very short half-life of 24Na) were not considered plausible. 

Table 5-13. Sodium-24 ingestion intake periods and rates. 

Na-24 intake rate (pCi/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1960 09/30/1963 205.6 624.7 3.04 

10/01/1963 12/31/1963 1274 4599 3.61 

01/01/1964 09/30/1964 311.9 986.3 3.16 

10/01/1964 03/31/1965 687.6 2421 3.52 

04/01/1965 12/31/1971 311.9 986.3 3.16 

5.3.7 Cesium-137

Only absorption type F was analyzed for 137Cs. Figure A-33 shows the fit to the 50th-percentile values 

from all intakes. Table 5-14 summarizes the intake rates for the 50th- and 84th-percentile values. 

Table 5-14. Type F 137Cs intake periods and rates. 

Cs-137 intake rate (pCi/d) 

Start date Stop date 50th-percentile 84th-percentile GSD 

01/01/1960 12/31/1960 118.6 173.7 1.46 

01/01/1961 12/31/1961 39.08 61.74 1.58 

01/01/1962 12/31/1962 55.23 81.79 1.48 

01/01/1963 12/31/1964 246.8 374.8 1.52 

01/01/1965 12/31/1966 132.6 213.9 1.61 

01/01/1967 12/31/1967 44.34 85.13 1.92 

01/01/1968 12/31/1976 28.38 58.36 2.06 

01/01/1977 12/31/1988 10.13 26.08 2.57 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 29 of 54 

6.0 ASSIGNMENT OF INTAKES AND DOSES

Tables 6-1 to 6-3 and 6-6 to 6-10 summarize the 50th-percentile intake rates and GSDs for each 

primary radionuclide over their respective periods and solubility classes. Table 6-4 lists the potential 

intake rates and GSDs for thorium. When calculating doses to individuals from bioassay data, a GSD 

of 3 has been used to account for biological variation and uncertainty in the models. It was 

considered inappropriate to assign a value less than 3 for the coworker data. Therefore, a GSD of at 

least 3 was assigned for each of the intake periods. The GSDs for different intake periods have also 

been conservatively adjusted for consistency between intake periods for calculational efficiency. 

Bioassay results used to establish coworker intakes did not cover all the years of possible exposure at 

Hanford. Extrapolation from monitored years to unmonitored years is discussed as part of the overall 

discussion of intakes for each radionuclide. The history of production at Hanford is relevant to those 

discussions. Figure 1 shows how a figure of merit for production (tons of uranium processed in the 

reactors times the burnup) varied from 1944 to 1972. This unit is especially relevant for the 

production of fission products and to a reasonable extent for production of activation products. The 

figure shows that the period of highest production at Hanford was from about 1958 to 1968, which 

overlaps with the period of whole-body counting and 90Sr urinalysis. 

6.1 PLUTONIUM 

Tables 6-1 and 6-2 list the plutonium intakes and associated GSDs for each period for types M and S 

solubility classes, respectively. A small amount of plutonium was produced in 1944 (T Plant started 

operations in December 1944), and more was produced in 1945. A tolerance air concentration level 

was implemented at least by October 1945, which was reduced by a factor of 25 sometime between 

1945 and 1948 (Cantril 1945; Parker 1947). Because production from 1946 to 1948 was comparable 

to that in 1945, and allowing for the higher tolerance air concentration, an intake at 25 times the rate 

for 1946 to 1948 should be assigned to the period from December 1944 to December 1945. Type S 

plutonium would not have been likely during those first 12 months of operation. 

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. For non-systemic (respiratory and GI tracts) organs, the following 

shall be done: 

1. Run the type M intakes. If this does not result in a draft PoC >50% [final PoC is determined by 

the Department of Labor], 

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

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; 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, note that lognormal distributions with different GSDs cannot 

be summed in a single IREP line. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 30 of 54 

0

1000000

2000000

3000000

4000000

5000000

6000000

1940 1945 1950 1955 1960 1965 1970 1975

Year

Tons U times burnup

Production

Figure 1. Production rates in tons of uranium times fuel burnup, 1944 to 1972. 

Table 6-1. Type M plutonium intake periods and rates. 

Plutonium intake rate (dpm/d) 

Start date Stop date 50th-percentile GSD 

12/01/1944 12/31/1945 1,440a 3.00 

01/01/1946 12/31/1948 57.7 3.00 

01/01/1949 12/31/1952 21.1 3.00 

01/01/1953 12/31/1981 1.003 3.19 

01/01/1982 12/31/1988 0.1336 8.47 

a. Assumed to be 25 times the 1946-48 rate. 

Table 6-2. Type S plutonium intake period and rates. 

Plutonium intake rate (dpm/d) 

Start date Stop date 50th-percentile GSD 

01/01/1946 12/31/1988 0.5169 8.48 

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

6.2 URANIUM AND THORIUM 

Table 6-3 lists the uranium intakes and associated GSDs for each period. The values were adjusted 

from micrograms per day to picocuries per day for input into IMBA. Uranium bioassay started in 1947, 

but the early results were not considered reliable. Exposure to uranium in the 300 Area started in 

March 1944. The tolerance air concentration in 1945 was three times higher than the required 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 31 of 54 

respiratory protection level implemented sometime between 1945 and 1947 (Cantril 1945; Parker 

1947). Because production quantities were similar or smaller from 1944 to 1947 than for 1948 and 

later and the tolerance concentration was three times greater, intakes for 1944 to 1947 were assumed 

to be 3 times higher than for 1948 to 1952. 

Table 6-3. Uranium intake periods and rates. 

Uranium intake, pCi/d 

Type F Type M Type S 

Start date Stop date Intake GSD Intake GSD Intake GSD 

03/01/1944 12/31/1947a 36.87 3.48 154.7 3.47 2,768 3.45 

01/01/1948 12/31/1951 12.29 3.48 51.58 3.47 922.7 3.45 

01/01/1952 12/31/1952 15.85 3.48 66.53 3.47 1,190 3.45 

01/01/1953 12/31/1956 11.19 3.48 44.90 3.47 941.7 3.45 

01/01/1957 12/31/1961 16.13 3.00 66.23 3.00 1,227 3.00 

01/01/1962 12/31/1974 9.654 5.49 38.93 5.89 605.2 4.82 

01/01/1975 12/31/1983 1.166 3.86 4.016 3.67 76.13 3.66 

01/01/1984 12/31/1988 0.446 3.86 1.746 3.67 42.62 3.66 

a. Intakes in this period assumed to be 3 times the 1948-51 intakes. 

If the energy employee worked in the 300 Area and was associated with uranium in any way, then 

exposure to thorium cannot be ruled out. Exposure could have occurred as early as 1950. The same 

would apply to workers at the PUREX Plant from 1966 to 1971. Although there was less thorium than 

uranium by mass handled at Hanford, the potential for intake could have been similar on an individual 

worker basis. Therefore, the same intake rates were assumed. Table 6-4 shows thorium intake 

periods and rates. The degree of equilibrium between 232Th and decay products including 228Th is not 

known. Similar processes at Y-12 caused separation between thorium and the radium and lead 

decay products resulting in disequilibrium between 232Th and 228Th with the activity ratio 228/232 

remaining around 0.6 for about 4 to 10 years after purification. A ratio generally-applicable over most 

years is 0.8, which is being used for the Y-12 thorium exposures, and hence, is recommended for this 

application also. 

Table 6-4. Thorium intake periods and rates. 

Thorium intake, pCi/d 

Type M Type S 

Exposure area Start date Stop date Intake GSD Intake GSD 

01/01/1950 12/31/1951 51.58 3.47 922.7 3.45 

01/01/1952 12/31/1952 66.53 3.47 1,190 3.45 

01/01/1953 12/31/1956 44.90 3.47 941.7 3.45 

01/01/1957 12/31/1961 66.23 3.00 1,227 3.00 

300 Area, 

uranium facilities 

01/01/1962 12/31/1970 38.93 5.89 605.2 4.82 

PUREX 01/01/1966 12/31/1971 66.23 3.00 1,227 3.00 

Starting in 1952, uranium at Hanford was recycled uranium with contaminants. Table 6-5 shows the 

activities of contaminants to apply to the uranium intakes in Table 6-3 from 1952 to 1988. 

Table 6-5. Contaminants in recycled uranium (units are pCi contaminant per pCi U). 

Pu-239 Np-237 Th-232 Tc-99 Ru-106 Zr-95 Nb-95 

4.4 E-4 4.4 E-4 5.5 E-6 2.2E-1 4.4 E-2 1.1 E-2 1.1 E-2 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 32 of 54 

6.3 STRONTIUM-90 

Table 6-6 lists the 90Sr intakes and associated GSDs for each period. Production of fission products 

in general from 1965 to 1967 was as great as any time in the history of Hanford, and build-up of 90Sr 

as a contamination source had occurred over 20 yr of operation. Air concentration limits were 

essentially unchanged from 1947 to the present (Parker 1947; Patterson 1949). The tolerance air 

concentration in 1945 was 10 times the 1947 value. Therefore, it is reasonable to apply the 90Sr 

intake rates from the 1965 to 1967 period to the 1947 to 1964 period and to apply 10 times those 

rates to the 1944 to 1946 period. 

Table 6-6. Type F 90Sr intake periods and rates. 

Sr-90 intake rate (dpm/d) 

Start date Stop date Intake GSD 

12/01/1944 12/31/1946 904.7a 3.00 

01/01/1947 12/31/1964 90.47b 3.00 

01/01/1965 12/31/1967 90.47 3.00 

01/01/1968 12/31/1970 60.5 3.99 

01/01/1971 12/31/1988 3.698 3.00 

a. Intake rate assumed to be 10 times the rate for 1965 to 1967. 

b. Intake rate assumed to be the same as the rate for 1965 to 1967. 

6.4 PROMETHIUM-147 

Table 6-7 lists the 147Pm intakes and associated GSDs for each period. Promethium-147 intakes 

should be applied only to workers who were in the 325 or 308 Buildings from 1966 to 1979. 

Table 6-7. Promethium-147 intake periods and rates. 

Pm-147 intake (dpm/d) 

Type M Type S 

Start date Stop date Intake GSD Intake GSD 

01/01/1966 12/31/1969 4,976 3.14 131,500 3.13 

01/01/1970 12/31/1979 1,720 3.00 34,810 3.00 

6.5 ZINC-65 

Table 6-8 lists the zinc intakes and associated GSDs for each period. Similar to 90Sr, the intake rates 

before 1960 were assumed based on smaller production and similar air concentration limits, with the 

exception of the 1944 to 1946 period. Because the intakes are based on whole-body counting, which 

measures activity in the body from all intake pathways, the dose reconstructor should apply the more 

claimant-favorable of the inhalation or ingestion intake but not both in the same year. If ingestion is 

used and the exposure period continues to 1973 or later, then the intake mode will have to be 

switched from ingestion to inhalation for the latter years. Since ingestion was determined to not be 

plausible after 1972, the intakes for inhalation must be assumed after this date, even when ingestion 

has been assumed prior to this date. 

6.6 SODIUM-24 

Table 6-9 lists the 24Na intakes and associated GSDs for each period. As a claimant-favorable 

assumption, the highest intake rate within a given year was used to set the intake rate for the entire 

year. Similar to 90Sr, the intake rates before 1960 were assumed based on smaller production and 

similar air concentration limits with the exception of the 1944 to 1946 period. Because the intakes 

were based on whole-body counting, which measures activity in the body from all intake pathways, 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 33 of 54 

Table 6-8. Zinc-65 intake periods and rates. 

Zn-65 intake (pCi/d) 

Inhalation Ingestion 

Start date Stop date Intake GSD Intake GSD 

12/01/1944 12/31/1946a 445.6 4.07 262 4.01 

01/01/1947 12/31/1959b 44.56 4.07 26.2 4.01 

01/01/1960 12/31/1963 44.56 4.07 26.2 4.01 

01/01/1964 12/31/1967 53.68 4.07 27.64 4.01 

01/01/1968 12/31/1970 35.29 3.52 16.69 3.44 

01/01/1971 12/31/1972 29.88 3.52 13.06 3.05 

01/01/1973 12/31/1977 12.58 3.52 NAc 

01/01/1978 12/31/1984 7.411 3.00 NA 

10/1/1976d - 2555e 5.58 NA 

a. Intake rates assumed to be 10 times the rates for 1960 to 1963. 

b. Intake rates assumed to be the same as the rates for 1960 to 1963. 

c. NA = not applicable. 

d. This is the date of the acute intake. 

e. This intake has units of pCi for an acute intake rather than pCi/d. 

the dose reconstructor should apply the more claimant-favorable of the inhalation or ingestion intakes, 

but not both in the same year. If ingestion is used and the exposure period continues to 1972 or 

later, then the intake mode will have to be switched from ingestion to inhalation for the latter years, 

that is, the intakes for inhalation must be assumed after 1971, even when ingestion has been 

assumed prior to this date. 

Table 6-9. Sodium-24 intake periods and rates. 

Na-24 intake (pCi/d) 

Inhalation 

Type F Ingestion 

Start date Stop date Intake GSD Intake GSD 

12/1/1944 12/31/1946a 3,103 3.04 2,056 3.04 

01/01/1947 12/31/1959b 310.3 3.04 205.6 3.04 

01/01/1960 12/31/1962 310.3 3.04 205.6 3.04 

01/01/1963 12/31/1963 1,921 3.61 1,274 3.61 

01/01/1964 12/31/1965 1,038 3.72 687.6 3.61 

01/01/1966 12/31/1971 452.7 3.11 311.9 3.61 

01/01/1972 12/31/1973 452.7 3.11 NAc NA 

01/01/1974 12/31/1984 250.8 3.11 NA NA 

a. Intake rates assumed to be 10 times the rates for 1960 to 1962. 

b. Intake rates assumed to be the same as the rates for 1960 to 

1962. 

c. NA = not applicable.

6.7 CESIUM-137 

Table 6-10 lists the 137Cs intakes and associated GSDs for each period. Similar to 90Sr, the intake 

rates before 1960 were assumed based on smaller production and similar air concentration limits, with 

the exception of the period from 1944 to 1946. 

6.8 ADDITIONAL RADIONUCLIDES 

A large number of different radionuclides were present at Hanford at various times, but the available 

bioassay data for radionuclides in addition to those considered in this report were considered to be 

too few to be statistically reliable for intake estimation. Workers exposed to 137Cs, 90Sr, 24Na, and 65Zn 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 34 of 54 

Table 6-10. Type F cesium-137 intake periods and rates. 

Cs-137 intake rate (pCi/d) 

Start date Stop date Intake GSD 

12/1/1944 12/31/1946 1,186a 3.00 

01/01/1947 12/31/1959 118.6b 3.00 

01/01/1960 12/31/1960 118.6 3.00 

01/01/1961 12/31/1961 39.08 3.00 

01/01/1962 12/31/1962 55.23 3.00 

01/01/1963 12/31/1964 246.8 3.00 

01/01/1965 12/31/1966 132.6 3.00 

01/01/1967 12/31/1967 44.34 3.00 

01/01/1968 12/31/1976 28.38 3.00 

01/01/1977 12/31/1988 10.13 3.00 

a. Intake rate assumed to be 10 times the rate for 1960. 

b. Intake rate assumed to be the same as the rate for 1960. 

could also have been exposed to other fission and activation products. From 1960 to 1988, intakes of 

most fission or activation products would have been detectable in whole-body counts. However, the 

recording practice for fission and activation products other than 137Cs, 24Na, and 65Zn was not 

amenable to statistical analysis. Measured body burdens less than 1% of the MPBBs were often 

simply listed as a trace. For 51Cr, 60Co, 106Ru, and 144Ce, for instance, 1% of the MPBBs are 8,000, 

100, 30, and 50 nCi, respectively. It is clear from the database that body burdens less than these 

values were often reported, but it is not known with certainty how to interpret a whole-body count that 

lists, for example, 60Co but has a blank result field. Therefore, other methods were investigated for 

the assignment of intakes of unmeasured or unquantified fission and activation products. 

Use of the ratios of fission products in irradiated fuel was one evaluated approach. Limitations to this 

approach include: 

• Excludes activation products. 

• Dependent on assumed cooling time before fuel is dissolved. 

• Ignores how radionuclides in fuel become contamination. Ratios of contamination would be 

different at the various facilities; for instance, reactors versus reactor fuel storage pools versus 

separations plants versus waste management facilities. In accessible contaminated areas, 

ratios of long-lived radionuclides would have increased over time relative to short-lived 

radionuclides due to chronic build-up. 

Another investigated approach was to assign intakes based on ratios in airborne effluents. Limitations 

to this approach include: 

• Data were available for effluents from the separations plants only, and these were not 

representative of the contamination ratios at the reactors or waste management facilities. 

• Activation products were underrepresented. 

• This method favors volatile radionuclides, whereas workers were more likely exposed to the 

less volatile radionuclides (i.e., the ones that were not vented through the stack). 

• The removal efficiencies of the effluent clean-up systems might not have been the same for all 

radionuclides (which is clearly true for radioiodines, but could also be true for particulates). 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 35 of 54 

The two methods did not produce consistent results. For instance, Table 6-11 shows the range and 

average ratios in airborne effluents from Hanford’s separations plants for the 1945 to 1971 period for 

several principal radionuclides versus the range in the fuel for discharge versus 3 yr of cooling. In 

general, the average ratios in the effluents were equal to or greater than the ratios in the fuel at 

discharge. One might expect the average in the effluents to fall between the ratio in the fuel at 

discharge versus after three years of cooling. 

Table 6-11. Comparison of radionuclide ratios in airborne effluents. 

Range in effluents, 

1945-71a Average in effluents, 

1944-71a In N-reactor fuel at dischargeb In N-reactor fuel, 3-yr cooling timeb

Ce-144/Cs-137 8.40-270 110 29 2.1 

Ru-106/Cs-137 2.90-830 59 8.7 0.62 

Nb+Zr-95/Cs-137 1.10-200 23 164 0.0024 

Ce-144/Sr-90 7.40- 58 33 33 2.4 

Ru-106/Sr-90 1.00-720 50 5.6 0.72 

Zr+Nb-95/Sr-90 0.28- 61 19 120 0.0028 

a. Based on data in (Heeb 1994) for airborne effluents from Hanford’s separations plants. 

b. Based on ORIGEN 2 computer calculations for N-Reactor MKIV 6% fuel. 

Because a method of determining ratios of other fission and activation products to 137Cs or 90Sr was 

not considered reliable, the approach in the Hanford internal dosimetry technical basis document 

(ORAUT 2004) for unmonitored workers was adapted to cover the unmonitored fission and activation 

products. Table 5.7-1 in ORAUT (2004) establishes intakes for workers with external monitoring but 

no bioassay based on limiting air concentrations or air concentrations for which respiratory protection 

was required. Table 6-12 lists the parts of that table applicable to fission and activation products not 

covered by coworker bioassay measurements. Which particulate fission or activation radionuclide the 

intakes apply to depends on the organ of concern. Table 6-13 lists the radionuclide and absorption 

type that produce the highest dose to the organs listed (from Table 5.7-2 in ORAUT 2004). 

It is unlikely that an unmonitored worker had chronic intakes of a large number of radionuclides in any 

1 yr. Intakes of 65Zn should be given to all workers for the periods covered because of its presence in 

city drinking water; 24Na should be assigned to the reactor workers for the periods covered; plutonium, 

uranium 90Sr, and 137Cs should be assigned to workers according to guidance at the end of Section 

5.7 in ORAUT 2004; intakes of thorium should be assigned per Table 6-4; and 147Pm should be added 

for workers involved in the 147Pm heat source program. One additional (remainder) radionuclide 

should be added to the list to cover the unmonitored fission or activation products in accordance with 

the guidance in Tables 6-12 and 6-13. The distribution for the remainder radionuclide should be 

triangular with a minimum of zero, the mode from Table 6-12, and a maximum of twice the mode. 

Table 6-12. Intakes for fission or activation products other than 90Sr, 65Zn, 24Na, or 137Cs. 

Period Radioactive material 

Limiting air 

concentration 

(μCi/cm3) 

Daily intake 

(dpm/d) 

Particulate fission/activation products other than Sr-90, Cs-137, Zn-65, Na-24 1 × 10-8 14,700b 1944-47a

I-131 vaporc,d NAe

 166,000 

Particulate fission/activation products other than Sr-90, Cs-137, Zn-65, Na-24 1 × 10-9 733b 1948-52a

I-131 vaporc,d NA 166,000 

Particulate fission/activation products other than Sr-90, Cs-137, Zn-65, Na-24 3 × 10-10 22.2b 1953-67 

I-131 vaporc

 9 × 10-9 1,310 

Particulate fission/activation products other than Sr-90, Cs-137, Zn-65, Na-24 1 × 10-9 73.3b 1968-88 

I-131 vaporc

 9 × 10-9 1,310 

a. Based on air concentrations that required respiratory protection. 

b. One-half of values in ORAUT (2004) to account for 90Sr, 137Cs, 65Zn, and 24Na. 

c. From ORAUT 2004; reactor or separations plant workers only. 

d. Based on tolerance thyroid burden. 

e. NA = not applicable. 
Document No. ORAUT-OTIB-0039 Revision No. 00 PC-1 Effective Date: 01/06/2006 Page 36 of 54 

Table 6-13. Fission or activation radionuclide chooser for unmonitored 

workers. 

Beta/gamma radionuclide and absorption type 

Organ of concern Operating reactors 

Fuel separation plants, waste 

management facilitiesa

 

Adrenals Co-60 Sb Ru-106 F 

Bone surface Zr-95 Fb Zr-95 F 

Brain Ru-106 F Ru-106 F 

Breast Ru-106 F Ru-106 F 

Colon Ru-106 S Ru-106 S 

Esophagus Ru-106 F Ru-106 F 

Extra thoracic Co-60 S Ru-106 S 

Gall bladder Ru-106 Fb Ru-106 F 

Heart Co-60 S Ru-106 F 

Kidneys Ru-106 Fb Ru-106 F 

Liver Ce-144 Mb Ce-144 M 

Lower large intestine Ru-106 Sb Ru-106 S 

Lung Ru-106 S Ru-106 S 

Muscle Ru-106 F Ru-106 F 

Ovaries Ru-106 F Ru-106 F 

Pancreas Ru-106 F Ru-106 F 

Red bone marrow Ce-144 Mb Ce-144 M 

Small intestine Ru-106 Fb Ru-106 F 

Skin Ru-106 F Ru-106 F 

Spleen Ru-106 F Ru-106 F 

Stomach Ru-106 Fb Ru-106 F 

Testes Ru-106 F Ru-106 F 

Thymus Co-60 S Ru-106 F 

Thyroid Ru-106 F Ru-106 F 

Upper large intestine Ru-106 F Ru-106 F 

Urinary bladder Ru-106 F Ru-106 F 

Uterus Ru-106 F Ru-106 F 

a. Or any other facilities where workers might have been exposed to older fission products. 

b. Substitute Eu-154 M if individual worked at N Reactor. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 37 of 54 

REFERENCES 

Brady, D. N., editor, 1964, Hanford Whole Body Counter Activities for 1961-1963, HW-82409, Hanford 

Atomic Products Operation, Richland, Washington. 

Cunningham, D. S., 1984, “Temporary Detection Limit Increase for WBC’s at 100-N,” letter to M. J. 

Sula (Pacific Northwest Laboratory), February 8, UNC Nuclear Industries, Richland, 

Washington. 

Cantril, S. T., 1945, “Tolerance Limits,” letter to file, October 18, 1945, Hanford Works, Richland, 

Washington. 

Healy, J. W., 1948, Bioassay at Hanford, HW-10522, Hanford Works, Richland, Washington. 

Heeb, C. M., 1994, Radionuclide Releases to the Atmosphere from Hanford Operations, 1944-1972, 

PNWD-2222 HEDR, Pacific Northwest National Laboratory, Richland, Washington. 

HPS (Health Physics Society), 1996, An American National Standard – Performance Criteria for 

Radiobioassay, HPS N13.30-1996, Health Physics Society, McLean, Virginia. 

ICRP (International Commission on Radiological Protection), 1959, Report of ICRP Committee II on 

Permissible Dose for Internal Radiation, Publication 2, Pergamon Press, Oxford, England. 

ICRP (International Commission on Radiological Protection), 1979, Limits for Intakes of Radionuclides 

by Workers, Publication 30, Part 1, Pergamon Press, Oxford, England. 

ICRP (International Commission on Radiological Protection), 1981, Limits for Intakes of Radionuclides 

by Workers, Publication 30, Part 3, Pergamon Press, Oxford, England. 

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

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

Pergamon Press, Oxford, England. 

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

Site – Occupational Internal Dose, ORAUT-TKBS-0006-5, Rev. 01, Oak Ridge, Tennessee. 

ORAUT (Oak Ridge Associated Universities Team), 2005b, External Coworker Dosimetry Data for the 

Hanford Site, ORAUT-OTIB-0030, Rev. 00, Oak Ridge, Tennessee. 

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

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

Palmer, H. E., G. A. Rieksts, and H. B. Spitz, 1984, Hanford Whole Body Counter 1983 Activities, 

Pacific Northwest Laboratory, Richland, Washington. 

Parker, H. M., 1947, Introductory Lecture Series in HI, HW-7184 Pt 2, Lecture 16-21, Hanford Works, 

Richland, Washington. 

Patterson, C. M., 1949, “General Operating Tolerances,” HW-12710, letter to Lauriston S. Taylor 

(National Bureau of Standards), March 11, 1949, Hanford Works, Richland, Washington. 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 38 of 54 

Table A-1. Statistical summary of 239Pu 24-hr urinary excretion rates, 1946-1988.a

Effective 

bioassay 

date 

GMb 

(50th) 

dpm/d 

GM*GSDc 

(84th) 

dpm/d 

07/01/1946 0.25402 0.66092 

07/01/1947 0.20476 0.50991 

04/01/1948 0.21047 0.53721 

10/1/1948 0.22645 0.60437 

07/01/1949 0.10752 0.28933 

07/01/1950 0.10249 0.25412 

07/01/1951 0.10358 0.26263 

07/01/1952 0.05707 0.14968 

04/01/1953 0.01647 0.04436 

10/1/1953 0.01724 0.04873 

02/15/1954 0.01704 0.04637 

05/15/1954 0.01746 0.04932 

08/15/1954 0.01765 0.05080 

11/15/1954 0.01697 0.04609 

02/15/1955 0.01671 0.04478 

05/15/1955 0.01695 0.04624 

08/15/1955 0.01746 0.05021 

11/15/1955 0.01681 0.04538 

02/15/1956 0.01703 0.04723 

05/15/1956 0.01716 0.04803 

08/15/1956 0.01724 0.04828 

11/15/1956 0.01756 0.04956 

02/15/1957 0.01659 0.04369 

05/15/1957 0.01699 0.04599 

08/15/1957 0.01663 0.04360 

11/15/1957 0.01712 0.04671 

02/15/1958 0.01576 0.06661 

05/15/1958 0.01089 0.03745 

08/15/1958 0.01001 0.03106 

11/15/1958 0.01240 0.05037 

02/15/1959 0.01265 0.05288 

05/15/1959 0.01163 0.04018 

08/15/1959 0.01058 0.03276 

11/15/1959 0.01098 0.03388 

02/15/1960 0.01237 0.04317 

05/15/1960 0.01002 0.02983 

08/15/1960 0.00980 0.02880 

11/15/1960 0.00980 0.02931 

02/15/1961 0.00977 0.02866 

05/15/1961 0.00984 0.02971 

08/15/1961 0.01022 0.03099 

11/15/1961 0.00990 0.02813 

02/15/1962 0.00948 0.02621 

05/15/1962 0.01091 0.03307 

08/15/1962 0.01235 0.04221 

11/15/1962 0.01061 0.03407 

02/15/1963 0.01100 0.03651 

05/15/1963 0.01276 0.04553 

08/15/1963 0.01166 0.03917 

11/15/1963 0.01479 0.05371 

02/15/1964 0.01826 0.06779 

Effective 

bioassay 

date 

GMb

(50th) 

dpm/d 

GM*GSDc 

(84th) 

dpm/d 

05/15/1964 0.02133 0.08054 

08/15/1964 0.02435 0.08191 

11/15/1964 0.02067 0.07232 

02/15/1965 0.01409 0.04706 

05/15/1965 0.01380 0.04542 

08/15/1965 0.01248 0.03685 

11/15/1965 0.01556 0.04811 

02/15/1966 0.01197 0.03675 

05/15/1966 0.01152 0.03613 

08/15/1966 0.01354 0.04801 

11/15/1966 0.01200 0.04220 

02/15/1967 0.01330 0.05292 

05/15/1967 0.02204 0.11370 

08/15/1967 0.01175 0.04248 

11/15/1967 0.01338 0.05001 

02/15/1968 0.01216 0.04585 

05/15/1968 0.01078 0.03891 

08/15/1968 0.01397 0.06615 

11/15/1968 0.01192 0.04489 

02/15/1969 0.01321 0.04680 

05/15/1969 0.00952 0.02753 

08/15/1969 0.01101 0.03788 

11/15/1969 0.01095 0.03868 

02/15/1970 0.00974 0.03019 

05/15/1970 0.0888 0.02567 

08/15/1970 0.00980 0.03067 

11/15/1970 0.01307 0.05338 

02/15/1971 0.00933 0.02895 

05/15/1971 0.00993 0.03206 

08/15/1971 0.01126 0.03955 

11/15/1971 0.01089 0.03976 

02/15/1972 0.01179 0.04290 

05/15/1972 0.01013 0.03254 

08/15/1972 0.00973 0.03035 

11/15/1972 0.01073 0.03642 

02/15/1973 0.01107 0.03977 

05/15/1973 0.00948 0.02877 

08/15/1973 0.00945 0.02812 

11/15/1973 0.00875 0.02403 

02/15/1974 0.00885 0.02454 

05/15/1974 0.00900 0.02532 

08/15/1974 0.00911 0.02602 

11/15/1974 0.01119 0.03852 

02/15/1975 0.00910 0.02516 

05/15/1975 0.00953 0.02738 

08/15/1975 0.00802 0.02030 

11/15/1975 0.00838 0.02233 

02/15/1976 0.00857 0.02433 

05/15/1976 0.00835 0.02245 

08/15/1976 0.00801 0.02006 

11/15/1976 0.00898 0.02764 

Effective 

bioassay 

date 

GMb

(50th) 

dpm/d 

GM*GSDc 

(84th) 

dpm/d 

02/15/1977 0.00871 0.02336 

05/15/1977 0.00875 0.02371 

08/15/1977 0.00835 0.02161 

11/15/1977 0.00812 0.02061 

02/15/1978 0.00878 0.02468 

05/15/1978 0.00906 0.02664 

08/15/1978 0.00836 0.02192 

11/15/1978 0.00825 0.02180 

02/15/1979 0.00871 0.02373 

05/15/1979 0.00849 0.02278 

08/15/1979 0.00851 0.02273 

11/15/1979 0.00818 0.02095 

02/15/1980 0.00821 0.02140 

05/15/1980 0.00865 0.02388 

08/15/1980 0.00870 0.02426 

11/15/1980 0.00900 0.02488 

02/15/1981 0.00799 0.02036 

05/15/1981 0.00827 0.02204 

8/5/1981 0.00851 0.02341 

11/5/1981 0.00109 0.00644 

02/15/1982 0.00069 0.00973 

05/15/1982 0.00053 0.00572 

08/15/1982 0.00083 0.00647 

11/15/1982 0.00149 0.01120 

02/15/1983 0.00113 0.00661 

05/15/1983 0.00087 0.00497 

08/15/1983 0.00094 0.00738 

11/15/1983 0.00083 0.00589 

02/15/1984 0.00132 0.00760 

05/15/1984 0.00062 0.01534 

08/15/1984 0.00090 0.00810 

11/15/1984 0.00099 0.00860 

02/15/1985 0.00116 0.01028 

05/15/1985 0.00056 0.00531 

08/15/1985 0.00076 0.00541 

11/15/1985 0.00073 0.00389 

02/15/1986 0.00065 0.00635 

05/15/1986 0.00069 0.01717 

08/15/1986 0.00099 0.00725 

11/15/1986 0.00050 0.00463 

02/15/1987 0.00069 0.00551 

05/15/1987 0.00065 0.00471 

08/15/1987 0.00086 0.00488 

11/15/1987 0.00048 0.00411 

02/15/1988 0.00080 0.00395 

05/15/1988 0.00052 0.00312 

08/15/1988 0.00064 0.00339 

11/15/1988 0.00020 0.00203 

a. For 1946 through 1949, the Pu-239 values were calculated as 0.824 of the total Pu alpha values; for 1950 through 1954, the Pu-239 values were 

calculated as 0.830 of the total Pu alpha values, for 1951 through 08/15/1983, the Pu-239 values were calculated as 0.835 of the total Pu alpha values. 

b. GM = geometric mean or 50th-percentile value of the fitted line. 

c. GSD = geometric standard deviation; GM*GSD is the 84th-percentile value of the fitted line. 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 1 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 39 of 54 

Figure A-1. 50th-percentile plutonium urinalysis data for intakes of Type M material, 1946 to 1948. 

Figure A-2. 50th-percentile plutonium urinalysis data for intakes of Type M material, 1949 to 1952. 

Figure A-3. 50th-percentile plutonium urinalysis data for intakes of Type M material, 1953 to 1981. 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 1 of 16 Page 2 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 40 of 54 

Figure A-4. 50th-percentile plutonium urinalysis data for intakes of Type M material, 1982 to 1988. 

Figure A-5. Predicted 50th-percentile urinary excretion of Type M plutonium from 1946 to 1988 based 

on four independent intakes, compared to bioassay data. 

Figure A-6. 50th-percentile plutonium urinalysis data for intakes of Type S material, 1946 to 1988. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 2 of 16 Page 3 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 41 of 54 

Table A-2. Statistical summary of uranium 24-hr urinary excretion rates, 1948-1988a. Effective 

bioassay 

date 

GMb 

(50th) 

μg/d 

GM*GSDc

(84th) μg/d 

04/01/1948 3.88 12.48 

10/1/1948 5.50 21.41 

02/15/1949 4.20 15.22 

05/15/1949 3.32 10.87 

08/15/1949 7.02 20.71 

11/15/1949 4.65 15.47 

02/15/1950 6.97 23.35 

05/15/1950 4.57 15.20 

08/15/1950 4.71 13.26 

11/15/1950 3.62 11.81 

02/15/1951 3.97 13.61 

05/15/1951 4.15 14.93 

08/15/1951 4.51 16.53 

11/15/1951 4.15 13.99 

02/15/1952 5.71 20.24 

05/15/1952 4.84 16.17 

08/15/1952 4.48 14.71 

11/15/1952 5.15 16.08 

02/15/1953 4.89 15.49 

05/15/1953 4.07 12.44 

08/15/1953 3.39 10.92 

11/15/1953 3.62 12.79 

02/15/1954 3.02 9.77 

05/15/1954 3.02 9.26 

08/15/1954 3.16 10.11 

11/15/1954 3.78 12.74 

2/14/1955 3.17 9.87 

05/15/1955 3.44 11.06 

08/15/1955 2.77 8.14 

11/15/1955 3.21 10.35 

2/14/1956 2.61 7.45 

05/15/1956 3.55 11.48 

08/15/1956 4.20 14.94 

11/15/1956 2.88 8.92 

02/15/1957 4.28 15.51 

05/15/1957 5.70 21.26 

08/15/1957 6.23 23.63 

11/51/1957 6.88 24.31 

02/15/1958 6.65 22.18 

05/15/1958 5.34 18.07 

08/15/1958 4.34 14.70 

Effective 

bioassay 

date 

GMb

(50th) 

μg/d 

GM*GSDc

(84th) μg/d

11/15/1958 3.96 12.54 

02/15/1959 3.94 12.97 

05/15/1959 4.59 15.29 

08/15/1959 5.54 19.18 

11/15/1959 4.48 16.23 

02/15/1960 4.20 14.36 

05/15/1960 5.82 20.97 

08/15/1960 4.47 14.79 

11/15/1960 4.34 15.45 

02/15/1961 4.76 18.96 

05/15/1961 4.85 17.54 

08/15/1961 3.76 11.26 

11/15/1961 3.86 11.32 

02/15/1962 3.68 11.21 

05/15/1962 3.05 8.70 

08/15/1962 2.78 7.73 

11/15/1962 2.74 7.69 

02/15/1963 3.77 10.83 

05/15/1963 3.19 8.55 

08/15/1963 2.73 7.43 

11/15/1963 2.76 7.37 

02/15/1964 2.39 6.25 

05/15/1964 2.54 6.79 

08/15/1964 2.89 9.30 

11/15/1964 2.66 7.54 

02/15/1965 3.56 11.55 

05/15/1965 3.82 13.26 

08/15/1965 4.39 16.82 

11/15/1965 3.72 11.94 

02/15/1966 3.09 10.22 

05/15/1966 3.02 9.28 

08/15/1966 3.56 12.10 

11/15/1966 3.13 9.35 

02/15/1967 2.85 8.54 

05/15/1967 2.97 8.84 

08/15/1967 2.71 7.71 

11/15/1967 2.77 8.13 

02/15/1968 3.06 9.14 

05/15/1968 3.73 11.62 

08/15/1968 2.96 8.82 

11/15/1968 3.21 9.10 

Effective 

bioassay 

date 

GMb

(50th) 

μg/d 

GM*GSDc

(84th) μg/d

02/15/1969 2.38 5.98 

05/15/1969 2.73 7.06 

08/15/1969 2.48 6.26 

11/15/1969 2.27 5.67 

07/01/1970 2.24 5.65 

07/01/1971 2.61 6.88 

07/01/1972 3.10 8.19 

07/01/1973 2.27 5.34 

07/01/1974 2.86 8.96 

07/01/1975 0.97 5.99 

07/01/1976 0.79 4.84 

07/01/1977 0.39 1.42 

07/01/1978 0.25 0.76 

07/01/1979 0.29 0.96 

07/01/1980 0.25 0.74 

07/01/1981 0.41 2.02 

07/01/1982 0.36 2.11 

07/01/1983 0.13 0.64 

02/15/1984 0.14 0.82 

05/15/1984 0.20 0.78 

08/15/1984 0.25 1.15 

11/15/1984 0.32 1.34 

02/15/1985 0.31 1.25 

05/15/1985 0.28 0.89 

08/15/1985 0.23 0.71 

11/15/1985 0.15 0.45 

02/15/1986 0.13 0.38 

05/15/1986 0.27 1.36 

08/15/1986 0.21 0.78 

11/15/1986 0.18 0.62 

02/15/1987 0.12 0.43 

05/15/1987 0.15 0.50 

08/15/1987 0.14 0.42 

11/15/1987 0.15 0.43 

02/15/1988 0.14 0.41 

05/15/1988 0.09 0.23 

08/15/1988 0.09 0.29 

11/15/1988 0.02 0.30 

a. Through 1981, excretion was converted to μg/d from μg/L assuming 1.4L/d excretion. 

b. GM = geometric mean or 50th-percentile value of the fitted line. 

c. GSD = geometric standard deviation; GM*GSD is the 84th-percentile value of the fitted line. 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 4 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 42 of 54 

Figure A-7. 50th-percentile uranium urinalysis data for intakes of Type F material, 1948 to 1988. 

Figure A-8. 50th-percentile uranium urinalysis data for intakes of Type M material, 1948 to 1988. 

Figure A-9. 50th-percentile uranium urinalysis data for intakes of Type S material, 1948 to 1952. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___ fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 5 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 43 of 54 

Figure A-10. 50th-percentile uranium urinalysis data for intakes of Type S material, 1953 to 1956. 

Figure A-11. 50th-percentile uranium urinalysis data for intakes of Type S material, 1957 to 1961. 

Figure A-12. 50th-percentile uranium urinalysis data for intakes of Type S material, 1962 to 1974. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 6 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 44 of 54 

Figure A-13. 50th-percentile uranium urinalysis data for intakes of Type S material, 1975 to 1983. 

Figure A-14. 50th-percentile uranium urinalysis data for intakes of Type S material, 1984 to 1988. 

Figure A-15. Predicted 50th-percentile urinary excretion of Type S uranium from 1946 to 1988 based 

on six independent intakes, compared to bioassay data. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 7 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 45 of 54 

Table A-3. Statistical summary of 90Sr 24-hr urinary excretion rates, 1965-1988. 

Effective 

bioassay 

date 

GM 

(50th) 

dpm/d 

GM*GSD 

(84th) 

dpm/d 

07/01/1966 20.74 56.46 

07/01/1969 14.53 55.88 

07/01/1971 1.76 4.56 

07/01/1972 2.33 12.27 

07/01/1973 1.64 4.51 

07/01/1974 1.38 3.82 

07/01/1975 0.923 2.57 

07/01/1976 1.20 3.40 

07/01/1977 0.835 2.12 

07/01/1978 1.009 3.82 

02/15/1979 0.882 2.55 

08/15/1979 2.00 5.58 

07/01/1980 1.92 4.92 

07/01/1981 2.33 7.60 

02/15/1982 0.289 1.43 

05/15/1982 0.322 1.58 

08/15/1982 0.350 1.72 

11/15/1982 0.802 7.91 

02/15/1983 0.665 2.60 

05/15/1983 0.387 3.13 

08/15/1983 0.743 3.78 

Effective 

bioassay 

date 

GM 

(50th) 

dpm/d 

GM*GSD 

(84th) 

dpm/d 

11/15/1983 0.410 2.73 

02/15/1984 0.807 1.76 

05/15/1984 1.04 2.70 

08/15/1984 1.00 1.66 

11/15/1984 1.06 1.87 

02/15/1985 1.30 2.88 

05/15/1985 1.18 2.38 

08/15/1985 1.06 1.69 

11/15/1985 1.11 2.20 

02/15/1986 1.12 2.26 

05/15/1986 1.05 1.88 

08/15/1986 1.14 2.05 

11/15/1986 1.27 2.29 

02/15/1987 1.28 2.02 

05/15/1987 1.43 2.28 

08/15/1987 1.43 2.18 

11/15/1987 1.47 2.21 

02/15/1988 1.79 2.79 

05/15/1988 1.53 2.57 

08/15/1988 1.32 2.02 

11/15/1988 0.327 0.993 

Figure A-16. 50th-percentile strontium urinalysis data for intakes of Type F material, 1965 to 1988. 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 8 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 46 of 54 

Table A-4. Statistical summary of 147Pm 

24-hr urinary excretion rates, 1966-1979. 

Effective 

bioassay 

date 

GM (50th) 

dpm/d 

GM*GSD 

(84th) dpm/d

01/01/1967 25.7 82.9 

2/12/1969 28.6 88.5 

02/15/1971 13.7 35.6 

07/01/1977a 10.5 27.4 

a. Very few bioassays were obtained during 1972 

through 1974 so no statistics were developed. A 

single intake rate was fit for 1970 through 1979, 

using the 1971 and 1977 statistical values. 

Figure A-17. 50th-percentile promethium urinalysis data for intakes of Type M material, 1966 to 1969. 

Figure A-18. 50th-percentile promethium urinalysis data for intakes of Type M material, 1970 to 1979. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 9 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 47 of 54 

Figure A-19. Predicted 50th-percentile urinary excretion of Type M promethium from 1966 to 1979 

based on two independent intakes, compared to bioassay data. 

Figure A-20. 50th-percentile promethium urinalysis data for intakes of Type S material, 1966 to 1969. 

Figure A-21. 50th-percentile promethium urinalysis data for intakes of Type S material, 1970 to 1979. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 10 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 48 of 54 

Figure A-22. Predicted 50th-percentile urinary excretion of Type S promethium from 1966 to 1979 

based on two independent intakes, compared to bioassay data. 

Table A-5. Statistical summary of 65Zn measured in whole-body counts. 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi 

07/01/1960 2.45 7.80 

04/01/1961 2.16 9.58 

10/1/1961 2.13 7.78 

04/01/1962 2.04 8.73 

10/1/1962 2.15 12.08 

02/15/1963 2.11 8.44 

05/15/1963 1.60 6.25 

08/15/1963 1.34 4.70 

11/15/1963 3.40 12.52 

02/15/1964 2.40 9.02 

05/15/1964 2.12 7.22 

08/15/1964 1.92 6.79 

11/15/1964 4.20 16.06 

02/15/1965 2.93 12.17 

05/15/1965 3.11 10.80 

08/15/1965 2.348 9.40 

11/15/1965 2.56 10.10 

02/15/1966 2.82 9.32 

05/15/1966 2.87 10.10 

08/15/1966 1.84 6.32 

11/15/1966 1.86 8.03 

02/15/1967 1.78 6.06 

05/15/1967 3.35 12.02 

08/15/1967 2.13 8.26 

11/15/1967 1.50 5.91 

02/15/1968 1.53 6.61 

05/15/1968 1.38 5.45 

08/15/1968 1.41 6.18 

11/15/1968 1.83 6.78 

02/15/1969 2.35 7.89 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi

05/15/1969 1.28 4.63 

08/15/1969 1.05 3.66 

11/15/1969 1.45 5.37 

02/15/1970 1.45 5.56 

05/15/1970 1.27 4.31 

08/15/1970 1.56 5.11 

11/15/1970 2.10 5.87 

02/15/1971 1.52 5.06 

05/15/1971 1.55 4.69 

08/15/1971 1.29 3.81 

11/15/1971 1.24 3.55 

02/15/1972 1.18 3.92 

05/15/1972 0.963 3.01 

08/15/1972 1.17 3.74 

11/15/1972 1.18 3.98 

02/15/1973 1.18 4.21 

05/15/1973 1.04 3.44 

08/15/1973 0.612 1.99 

11/15/1973 0.678 2.27 

02/15/1974 0.497 1.61 

05/15/1974 0.431 1.33 

08/15/1974 0.456 1.41 

11/15/1974 0.507 1.64 

04/01/1975 0.405 1.23 

10/1/1975 0.613 2.00 

02/15/1976 0.647 2.19 

05/15/1976 0.712 3.25 

08/15/1976 0.673 2.46 

11/15/1976 1.21 5.39 

02/15/1977 0.964 3.74 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi

05/15/1977 0.788 2.83 

08/15/1977 0.688 2.67 

11/15/1977 0.388 1.27 

02/15/1978 0.371 1.16 

05/15/1978 0.369 1.15 

08/15/1978 0.373 1.19 

11/15/1978 0.396 1.28 

02/15/1979 0.401 1.28 

05/15/1979 0.415 1.37 

08/15/1979 0.348 1.02 

11/15/1979 0.406 1.31 

02/15/1980 0.384 1.19 

05/15/1980 0.403 1.32 

08/15/1980 0.372 1.15 

11/15/1980 0.348 1.01 

02/15/1981 0.372 1.09 

05/15/1981 0.354 1.04 

08/15/1981 0.306 0.817 

11/15/1981 0.316 0.854 

02/15/1982 0.340 0.947 

05/15/1982 0.338 0.944 

08/15/1982 0.334 0.934 

11/15/1982 0.331 0.909 

02/15/1983 0.323 0.884 

05/15/1983 0.334 0.922 

08/15/1983 0.314 0.843 

11/15/1983 0.337 0.937 

04/01/1984 0.354 1.03 

10/01/1984 0.391 1.09 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 11 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 49 of 54 

Figure A-23. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1960 to 1963. 

Figure A-24. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1964 to 1967. 

Figure A-25. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1968 to 1970. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 12 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 50 of 54 

Figure A-26. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1971 to 1972. 

Figure A-27. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1973 to 1977. 

Figure A-28. 50th-percentile zinc whole-body counting data for inhalation intakes of Type S material, 

1978 to 1984. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 13 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 51 of 54 

Figure A-29. Predicted 50th-percentile urinary excretion of inhaled Type S zinc from 1960 to 1984 

based on six independent chronic intakes and one acute intake, compared to bioassay data. 

Figure A-30. 50th-percentile zinc whole-body counting data for ingestion intakes, 1960 to 1984. 

● bioassay value 

● not used in fit 

___

 fit 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 14 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 52 of 54 

Table A-6. Statistical summary of 24Na measured in whole-body counts. 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi 

07/01/1960 0.221 0.587 

04/01/1961 0.174 0.610 

10/1/1961 0.187 0.616 

02/15/1962 0.142 0.421 

05/15/1962 0.182 0.609 

08/15/1962 0.150 0.413 

11/15/1962 0.145 0.414 

02/15/1963 0.180 0.562 

05/15/1963 0.185 0.515 

08/15/1963 0.231 0.713 

11/15/1963 1.11 4.02 

02/15/1964 0.388 1.35 

05/15/1964 0.355 1.16 

08/15/1964 0.316 0.993 

11/15/1964 0.647 2.06 

02/15/1965 0.555 2.17 

05/15/1965 0.295 0.983 

08/15/1965 0.286 0.930 

11/15/1965 0.292 0.891 

02/15/1966 0.347 1.09 

05/15/1966 0.233 0.650 

08/15/1966 0.257 0.834 

11/15/1966 0.218 0.687 

02/15/1967 0.288 0.904 

05/15/1967 0.428 1.740 

08/15/1967 0.247 0.701 

11/15/1967 0.346 0.998 

02/15/1968 0.405 1.610 

05/15/1968 0.269 0.887 

08/15/1968 0.229 0.728 

11/15/1968 0.256 0.805 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi 

02/15/1969 0.194 0.570 

05/15/1969 0.204 0.649 

08/15/1969 0.268 0.915 

11/15/1969 0.285 0.979 

02/15/1970 0.218 0.623 

05/15/1970 0.228 0.605 

08/15/1970 0.193 0.543 

11/15/1970 0.196 0.559 

02/15/1971 0.260 0.711 

05/15/1971 0.234 0.591 

08/15/1971 0.224 0.589 

11/15/1971 0.220 0.591 

02/15/1972 0.245 0.715 

05/15/1972 0.255 0.760 

08/15/1972 0.206 0.608 

11/15/1972 0.243 0.673 

02/15/1973 0.244 0.756 

05/15/1973 0.196 0.556 

08/15/1973 0.220 0.614 

11/15/1973 0.176 0.501 

02/15/1974 0.144 0.401 

05/15/1974 0.147 0.431 

08/15/1974 0.149 0.418 

11/15/1974 0.139 0.369 

02/15/1975 0.128 0.331 

05/15/1975 0.131 0.340 

08/15/1975 0.140 0.383 

11/15/1975 0.131 0.342 

02/15/1976 0.139 0.371 

05/15/1976 0.148 0.404 

08/15/1976 0.166 0.459 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi 

11/15/1976 0.158 0.434 

02/15/1977 0.168 0.465 

05/15/1977 0.166 0.466 

08/15/1977 0.162 0.449 

11/15/1977 0.162 0.458 

02/15/1978 0.138 0.368 

05/15/1978 0.148 0.401 

08/15/1978 0.139 0.368 

11/15/1978 0.150 0.414 

02/15/1979 0.134 0.356 

05/15/1979 0.155 0.421 

08/15/1979 0.147 0.396 

11/15/1979 0.145 0.387 

02/15/1980 0.139 0.369 

05/15/1980 0.140 0.372 

08/15/1980 0.131 0.346 

11/15/1980 0.140 0.370 

02/15/1981 0.139 0.372 

05/15/1981 0.138 0.366 

08/15/1981 0.147 0.403 

11/15/1981 0.133 0.348 

02/15/1982 0.134 0.352 

05/15/1982 0.149 0.407 

08/15/1982 0.140 0.375 

11/15/1982 0.143 0.387 

02/15/1983 0.145 0.399 

05/15/1983 0.142 0.385 

08/15/1983 0.142 0.390 

11/15/1983 0.150 0.414 

04/01/1984 0.144 0.377 

10/01/1984 0.171 0.495 

Figure A-31. 50th-percentile sodium whole-body counting data for inhalation intakes of Type F 

material, 1960 to 1984. 

● bioassay value 

● not used in fit 

___ fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 15 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 53 of 54 

Figure A-32. 50th-percentile sodium whole-body counting data for ingestion intakes, 1960 to 1984. 

Table A-7. Statistical summary of 137Cs measured in whole-body counts. 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi 

02/15/1960 6.773 9.620 

05/15/1960 6.689 9.347 

08/15/1960 5.977 9.466 

11/15/1960 5.770 8.302 

02/15/1961 4.728 6.858 

05/15/1961 4.482 6.764 

08/15/1961 3.805 6.006 

11/15/1961 3.491 5.184 

02/15/1961 3.527 5.563 

05/15/1961 3.457 5.055 

08/15/1961 4.378 6.502 

11/15/1961 5.253 7.678 

02/15/1963 6.691 10.362 

05/15/1963 6.773 9.620 

08/15/1963 6.689 9.347 

11/15/1963 5.977 9.466 

02/15/1964 5.770 8.302 

05/15/1964 4.728 6.858 

08/15/1964 4.482 6.764 

11/15/1964 3.805 6.006 

02/15/1965 3.491 5.184 

05/15/1965 3.527 5.563 

08/15/1965 3.457 5.055 

11/15/1965 4.378 6.502 

02/15/1966 5.253 7.678 

05/15/1966 6.691 10.362 

08/15/1966 8.922 13.998 

11/15/1966 11.218 16.663 

02/15/1967 13.470 19.952 

05/15/1967 15.374 23.543 

08/15/1967 17.644 26.857 

11/15/1967 18.129 26.767 

02/15/1968 17.811 28.334 

05/15/1968 15.208 23.287 

08/15/1968 15.288 23.190 

11/15/1968 13.341 19.881 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi

02/15/1969 11.964 18.931 

05/15/1969 10.544 16.593 

08/15/1969 8.526 13.837 

11/15/1969 8.198 13.210 

02/15/1970 6.417 12.039 

05/15/1970 5.877 9.856 

08/15/1970 5.417 9.242 

11/15/1970 4.770 8.025 

02/15/1971 4.049 7.580 

05/15/1971 3.195 6.012 

08/15/1971 2.574 4.939 

11/15/1971 2.667 5.467 

02/15/1972 2.824 5.511 

05/15/1972 3.022 5.516 

08/15/1972 2.176 4.728 

11/15/1972 2.222 4.332 

02/15/1973 2.0544 4.5035 

05/15/1973 1.8482 3.4682 

08/15/1973 1.8296 3.3453 

11/15/1973 1.6404 3.3004 

02/15/1974 1.2505 3.0204 

05/15/1974 0.9186 2.1838 

08/15/1974 1.0889 2.4621 

11/15/1974 1.1091 2.7017 

02/15/1976 1.0488 2.1653 

05/15/1976 1.1197 2.6952 

08/15/1976 0.9322 2.1818 

11/15/1976 1.6176 3.9736 

02/15/1977 1.3651 2.9877 

05/15/1977 1.4688 3.4256 

08/15/1977 1.1219 2.9244 

11/15/1977 0.8683 2.2466 

02/15/1978 1.0525 2.6430 

05/15/1978 0.7876 2.3797 

08/15/1978 0.7788 2.2337 

11/15/1978 1.0824 2.6808 

Effective 

bioassay 

date 

GM 

(50th) 

nCi 

GM*GSD 

(84th) nCi

02/15/1979 1.1775 2.9579 

05/15/1979 0.8671 2.0518 

08/15/1979 0.9219 2.1979 

11/15/1979 1.2393 2.6536 

02/15/1980 1.1519 2.8199 

05/15/1980 0.8175 2.9124 

08/15/1980 0.6695 1.8971 

11/15/1980 0.7321 1.9398 

02/15/1981 0.8278 2.1018 

05/15/1981 0.4992 1.1927 

08/15/1981 0.3353 0.9534 

11/15/1981 0.4740 1.0964 

02/15/1982 0.5655 1.3484 

05/15/1982 0.4695 1.2468 

08/15/1982 0.4364 1.0269 

11/15/1982 0.5316 1.2952 

02/15/1983 0.4257 1.1238 

05/15/1983 0.3023 0.8154 

08/15/1983 0.3705 0.9053 

11/15/1983 0.4354 1.1195 

02/15/1984 0.2487 0.6537 

05/15/1984 0.2461 0.6285 

08/15/1984 0.2430 0.6134 

11/15/1984 0.2398 0.5927 

02/15/1985 0.2450 0.6327 

05/15/1985 1.1416 2.7971 

08/15/1985 1.1220 2.8167 

11/15/1985 1.1235 2.8170 

04/01/1986 1.1169 2.7720 

10/1/1986 1.1106 2.7455 

04/01/1987 0.9186 2.1838 

10/01/1987 1.0889 2.4621 

04/01/1988 1.1091 2.7017 

10/01/1988 1.0488 2.1653 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 16 of 17 
Document No. ORAUT-OTIB-0039 Revision No. 00 Effective Date: 10/28/2005 Page 54 of 54 

Figure A-33. 50th-percentile 137Cs whole-body counting data for inhalation intakes of Type F material, 

1960 to 1988. 

● bioassay value 

● not used in fit 

___

 fit 

ATTACHMENT A: STATISTICAL SUMMARIES AND PLOTS 

Page 17 of 17