ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 104

DOE Review Release 10/27/2009

Document Title:

Internal Dosimetry Coworker Data for Los Alamos 

National Laboratory

Document Number: ORAUT-OTIB-0062

Revision: 00

Effective Date: 10/15/2009

Type of Document OTIB

Supersedes: None

Subject Expert(s): Matthew Arno

Site Expert(s): N/A

Approval: Signature on File Approval Date: 09/28/2009

Matthew Arno, Document Owner

Concurrence: Signature on File Concurrence Date: 09/24/2009

John M. Byrne, Objective 1 Manager

Concurrence: Keith A. McCartney Signature on File for Concurrence Date: 09/28/2009

Edward F. Maher, Objective 3 Manager

Concurrence: Signature on File Concurrence Date: 09/28/2009

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 10/15/2009

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-0062 Revision No. 00 Effective Date: 10/15/2009 Page 2 of 104

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

10/15/2009 00 New technical information bulletin for internal dosimetry coworker 

data for Los Alamos National Laboratory. Incorporates formal 

internal and NIOSH review comments. Analysis of plutonium-239 

and cesium-137 lung counts updated and new guidance added for 

Type Super S plutonium-239. Training required: As determined by 

the Objective Manager. Initiated by Matthew Arno.

TRADEMARK INFORMATION

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

and/or other countries.

All trademarks are the property of their respective owners.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 3 of 104

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

10

1.0 Introduction ............................................................................................................................11

2.0 Purpose .................................................................................................................................11

3.0 Data Overview .......................................................................................................................11

3.1 Bioassay Data Selection.............................................................................................12

3.2 Analysis......................................................................................................................12

3.3 Tritium ........................................................................................................................12

3.4 Plutonium-238 ............................................................................................................13

3.5 Plutonium-239 ............................................................................................................14

3.5.1 Pu-239 In-Vitro Data ....................................................................................... 14

3.5.2 Pu-239 In-Vivo Data........................................................................................ 16

3.6 Polonium-210 .............................................................................................................16

3.7 Uranium......................................................................................................................17

3.8 Cesium-137................................................................................................................17

4.0 Intake Modeling......................................................................................................................18

4.1 Assumptions...............................................................................................................18

4.2 Bioassay Fitting ..........................................................................................................18

4.3 Material Types............................................................................................................19

4.3.1 Tritium............................................................................................................. 19

4.3.2 Plutonium-238................................................................................................. 19

4.3.3 Plutonium-239................................................................................................. 20

4.3.4 Polonium......................................................................................................... 20

4.3.5 Uranium .......................................................................................................... 21

4.3.6 Cesium-137 .................................................................................................... 21

5.0 Assigning Intakes and Doses ................................................................................................. 21

5.1 Intake Rate Summary.................................................................................................22

5.2 Tritium ........................................................................................................................22

5.3 Plutonium-238 ............................................................................................................22

5.4 Plutonium-239 ............................................................................................................23

5.5 Polonium ....................................................................................................................24

5.6 Uranium......................................................................................................................25

5.7 Cesium-137................................................................................................................25

6.0 Attibutions and Annotations ....................................................................................................25

References ........................................................................................................................................26

ATTACHMENT A, COWORKER DATA TABLES............................................................................... 27

ATTACHMENT B, COWORKER DATA FIGURES ............................................................................ 34
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 4 of 104

LIST OF TABLES

TABLE TITLE

3-1 High bioassay readings for 238Pu............................................................................................

PAGE

13

3-2 High bioassay readings for 239Pu............................................................................................ 15

5-1 Tritium annual doses and GSDs............................................................................................. 22

5-2 Plutonium-238 intake rates..................................................................................................... 23

5-3 Plutonium-239 Type M intake rates........................................................................................ 23

5-4 Plutonium-239 Type S lung burden-based intake rates .......................................................... 24

5-5 Polonium intake rates............................................................................................................. 24

5-6 August 1, 1955 incident polonium intakes .............................................................................. 25

5-7 Uranium intake rates.............................................................................................................. 25

5-8 Type F 137Cs intake rates ....................................................................................................... 25

A-1 Statistical summary of 238Pu urinary excretion rates, 1968 to 2008......................................... 28

A-2 Statistical summary of 239Pu urinary excretion rates, 1945 to 2008......................................... 29

A-3 Statistical summary of 239Pu lung burdens, 1969 to 1979 ....................................................... 30

A-4 Statistical summary of polonium urinary excretion rates, 1947 to 1956 .................................. 31

A-5 Statistical summary of uranium urinary excretion rates from 1950 to 2008............................. 32

A-6 Statistical summary of cesium whole-body counts, 1970 to 1993........................................... 33

B-1 Summary of 238Pu type M intake rates and dates ................................................................... 48

B-2 Summary of 238Pu type S intake rates and dates.................................................................... 56

B-3 Summary of 239Pu type M intake rates and dates ................................................................... 66

B-4 Summary of 239Pu type S intake rates and dates.................................................................... 76

B-5 Summary of 239Pu type S lung burden-based intake rates and dates ..................................... 81

B-6 Summary of polonium type F intake rates and dates.............................................................. 83

B-7 Summary of polonium type M intake rates and dates ............................................................. 83

B-8 Summary of polonium acute intakes type F and M................................................................. 91

B-9 Summary of uranium type F intake rates and dates ............................................................... 93

B-10 Summary of uranium type M intake rates and dates............................................................... 94

B-11 Summary of uranium type S intake rates and dates ............................................................. 103

B-12 Summary of type F 137Cs intake rates and dates .................................................................. 104
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 5 of 104

LIST OF FIGURES

FIGURE TITLE

B-1 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 50th percentile, type M .................................

PAGE

40

B-2 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 50th percentile, type M.............................................. 40

B-3 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 50th percentile, type M ................................. 41

B-4 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1977, 50th percentile, type M ................................. 41

B-5 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1978 to 1981, 50th percentile, type M ................................. 42

B-6 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 50th percentile, type M ................................. 42

B-7 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 50th percentile, type M ................................. 43

B-8 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type M ................................. 43

B-9 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 84th percentile, type M ................................. 44

B-10 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 84th percentile, type M.............................................. 44

B-11 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973-1974, 84th percentile, type M..................................... 45

B-12 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 84th percentile, type M ................................. 45

B-13 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 84th percentile, type M ................................. 46

B-14 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 84th percentile, type M ................................. 46

B-15 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type M ................................. 47

B-16 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type M............................... 47

B-17 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type M............................... 48

B-18 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 50th percentile, type S.................................. 48

B-19 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 50th percentile, type S .............................................. 49

B-20 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 50th percentile, type S.................................. 49

B-21 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 50th percentile, type S.................................. 50

B-22 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 50th percentile, type S.................................. 50

B-23 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 50th percentile, type S.................................. 51
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 6 of 104

B-24 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type S.................................. 51

B-25 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 84th percentile, type S.................................. 52

B-26 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 84th percentile, type S .............................................. 52

B-27 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 84th percentile, type S.................................. 53

B-28 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 84th percentile, type S.................................. 53

B-29 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 84th percentile, type S.................................. 54

B-30 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 84th percentile, type S.................................. 54

B-31 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type S.................................. 55

B-32 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type S................................ 55

B-33 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type S................................ 56

B-34 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1945, 50th percentile, type M.............................................. 56

B-35 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1946, 50th percentile, type M.............................................. 57

B-36 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1947-1953, 50th percentile, type M..................................... 57

B-37 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1954 to 1956, 50th percentile, type M ................................. 58

B-38 Predicted 239

Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1957 to 1966, 50th percentile, type M ................................. 58

B-39 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1967 to 1972, 50th percentile, Type M................................ 59

B-40 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1973 to 1975, 50th percentile, type M ................................. 59

B-41 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1976 to 1993, 50th percentile, type M ................................. 60

B-42 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type M ................................. 60

B-43 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1945, 84th percentile, type M.............................................. 61

B-44 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1946, 84th percentile, type M.............................................. 61

B-45 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1947 to 1954, 84th percentile, type M ................................. 62

B-46 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1954 to 1956, 84th percentile, type M ................................. 62

B-47 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1957 to 1966, 84th percentile, type M ................................. 63

B-48 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1967 to 1972, 84th percentile, type M ................................. 63
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 7 of 104

B-49 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1973 to 1975, 84th percentile, type M ................................. 64

B-50 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1976 to 1993, 84th percentile, type M ................................. 64

B-51 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type M ................................. 65

B-52 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type M............................... 65

B-53 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type M............................... 66

B-54 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1945, 50th percentile, type S ........................... 67

B-55 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1946, 50th percentile, type S ........................... 67

B-56 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1947 to 1953, 50th percentile, type S............... 68

B-57 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1954 to 1956, 50th percentile, type S............... 68

B-58 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1957 to 1958, 50th percentile, type S............... 69

B-59 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1967 to 1972, 50th percentile, type S............... 69

B-60 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1973 to 1975, 50th percentile, type S............... 70

B-61 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1993, 50th percentile, type S............... 70

B-62 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1994 to 2008, 50th percentile, type S............... 71

B-63 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1945, 84th percentile, type S ........................... 71

B-64 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1946, 84th percentile, type S ........................... 72

B-65 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1947 to 1954, 84th percentile, type S............... 72

B-66 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1955 to 1956, 84th percentile, type S............... 73

B-67 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1957 to 1966, 84th percentile, type S............... 73

B-68 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1967 to 1972, 84th percentile, type S............... 74

B-69 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1973 to 1975, 84th percentile, type S............... 74

B-70 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1993, 84th percentile, type S............... 75

B-71 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1994 to 2008, 84th percentile, type S............... 75

B-72 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results from all intakes, 50th percentile, type S ............ 76

B-73 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results from all intakes, 84th percentile, type S ............ 76
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 8 of 104

B-74 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1969 to 1971, 50th percentile, type S............... 77

B-75 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1972 to 1974, 50th percentile, type S............... 77

B-76 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1975, 50th percentile, type S ........................... 78

B-77 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1977, 50th percentile, type S............... 78

B-78 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1978 to 1979, 50th percentile, type S............... 79

B-79 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1969 to 1971, 84th percentile, type S............... 79

B-80 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1972 to 1974, 84th percentile, type S............... 80

B-81 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1975, 84th percentile, type S ........................... 80

B-82 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1977, 84th percentile, type S............... 81

B-83 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1978 to 1979, 84th percentile, type S............... 81

B-84 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F....................... 82

B-85 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F....................... 82

B-86 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 50th percentile, type M ...................... 83

B-87 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 84th percentile, type M ...................... 83

B-88 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “A,” type F ...................... 84

B-89 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “B,” type F ...................... 84

B-90 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “C,” type F ...................... 85

B-91 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “D,” type F ...................... 85

B-92 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “E,” type F ...................... 86

B-93 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “F,” type F....................... 86

B-94 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “G,” type F...................... 87

B-95 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “A,” type M..................... 87

B-96 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “B,” type M...................... 88

B-97 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “C,” type M ..................... 88

B-98 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “D,” type M ..................... 89
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 9 of 104

B-99 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “E,” type M...................... 89

B-100 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “F,” type M...................... 90

B-101 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “G,” type M ..................... 90

B-102 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F....................... 92

B-103 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F....................... 92

B-104 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 50th percentile, type M ...................... 93

B-105 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 84th percentile, type M ...................... 94

B-106 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1950 to 1955, 50th percentile, type S......................... 95

B-107 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1956 to 1957, 50th percentile, type S......................... 95

B-108 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1958 to 1965, 50th percentile, type S......................... 96

B-109 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1966 to 1973, 50th percentile, type S......................... 96

B-110 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1974 to 1982, 50th percentile, type S......................... 97

B-111 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1983 to 1989, 50th percentile, type S......................... 97

B-112 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1990 to 2008, 50th percentile, type S......................... 98

B-113 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1950 to 1955, 84th percentile, type S......................... 98

B-114 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1956 and 1957, 84th percentile, type S...................... 99

B-115 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1958 to 1965, 84th percentile, type S......................... 99

B-116 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1966 to 1973, 84th percentile, type S....................... 100

B-117 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1974 to 1982, 84th percentile, type S....................... 100

B-118 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1983 to 1989, 84th percentile, type S....................... 101

B-119 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1990 to 2008, 84th percentile, type S....................... 101

B-120 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, all intake periods, 50th percentile, type S................. 102

B-121 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, all intake periods, 84th percentile, type S................. 102

B-122 Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F..................... 103

B-123 Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F..................... 104
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 10 of 104

ACRONYMS AND ABBREVIATIONS

d day

DOE U.S. Department of Energy

GI gastrointestinal

GM geometric mean

GSD geometric standard deviation

hr hour

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

L liter

LANL Los Alamos National Laboratory

m meter

MDA minimum detectable activity

mL milliliter

nCi nanocurie

NIOSH National Institute for Occupational Safety and Health

pCi picocurie

POC probability of causation

TIB technical information bulletin

U.S.C. United States Code

μCi microcurie

μg microgram

μm micrometer

§ section or sections
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 11 of 104

1.0 

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

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

historic background information and guidance to assist in the preparation of dose reconstructions at 

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

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

individual dose reconstructions.

INTRODUCTION

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

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

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

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

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

general process used to analyze bioassay data for the assignment of doses to individuals based on 

coworker results. Coworker Data Exposure Profile Development (ORAUT 2004a) describes the 

approach and processes to develop reasonable exposure profiles based on available dosimetric 

information for workers at DOE sites.

Bioassay results were obtained directly from the Los Alamos National Laboratory (LANL) In-Vivo 

Measurements Laboratory and from the LANL Bioassay Repository for in vitro bioassay results. The 

combined databases used here contain more than half a million bioassay records from LANL and 

include measurements for 238Pu, plutonium, tritium, polonium, and cesium for the years 1945 to 2008.

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

techniques, and measurement periods. These units usually were disintegrations per minute, counts 

per minute, or picocuries per 24 hr or per liter. The specific units for each radionuclide are provided in 

the appropriate sections of this document.

A statistical analysis of the data was performed according to ORAUT (2005) and its implementing 

procedure ORAUT (2006). The results were entered in the Integrated Modules for Bioassay Analysis 

(IMBA) ExpertTM Oak Ridge Associated Universities (ORAU)-Edition computer software to obtain 

intake rates for the assignment of dose distributions.

2.0 

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

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

coworkers can be used to assign an internal dose to address potential intakes of radioactive material. 

The purpose of this TIB is to provide monitored coworker information for calculating and assigning 

occupational internal doses to employees at LANL for whom no or insufficient monitoring records 

exist.

PURPOSE

3.0 

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

of analysis. More detailed radionuclide-specific information is provided in Section 4.0.

DATA OVERVIEW
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 12 of 104

3.1 BIOASSAY DATA SELECTION

Urinalysis data for 238Pu, plutonium, polonium, uranium, and tritium from 1945 to 2004 were extracted 

from a Microsoft® Access® database named “LANL CO-Worker Data – Rev 1.mdb.” There were more 

than 400,000 records in the urinalysis database. There were also six measurements for 239Pu in 1944 

that were not used because the low number of measurements does not permit reliable statistical 

analysis. The same data for 2005 through 2008 was extracted from a Microsoft® Access® database 

named “LANL_invitro_dataset_feb2009.mdb,” which contains an additional 55,000+ urinalysis 

results. The units used are dependent on both the analyte and the era. The specific units used are 

discussed in more detail below in the discussion of each radionuclide. 

In vivo data from 1965 to 2004 were extracted from a Microsoft® Access® database named 

“2007_10_08-LANL_IN_VIVO_DATA-Access2003.mdb.” There are approximately 100,000 records in 

this database. Most of the records are for chest or whole-body counts, although a few counts of 

specific organs or body regions (hand, skull, etc.) are included. Only the chest and whole-body 

counts were used. Bioassay data were available for in vivo measurements of 238

Pu, 239Pu, 241Am, and 

137Cs. Beyond these four nuclides, very limited data were available, primarily for the late 1980s when 

the use of high-resolution germanium detectors became more widespread, which allowed

identification of a wide selection of other radionuclides. However, insufficient data were available to 

perform any analysis for these other radionuclides. Even for the four primary radionuclides, sufficient 

non-zero data for analysis were available only for 239Pu and 137Cs. 

3.2 ANALYSIS

Bioassay data were analyzed by quarter, year, or multiyear span dependent on the amount of data 

available for each radionuclide during a given period and the expected biokinetics of each 

radionuclide. A lognormal distribution was assumed. After log-transforming the data, the 50th and 

84th percentiles were determined for each period through the use of the method described in ORAUT 

(2005). A large fraction of the data for every radionuclide was entered as zero bioassay results. 

These zeros were retained in the analysis to rank the results. The acute intake of polonium in 1955 

was addressed differently as discussed below in the sections regarding polonium.

3.3 TRITIUM

Tritium urine bioassay data were extracted from the “LANL CO-Worker Data – Rev 1.mdb” database. 

The “co_worker_data” table in this database was queried to identify all records with a nuclide type of 

“H-3” and collection dates ranging from the earliest recorded through the end of 2004. The 

“coll_date,” “z_number,” and “activity” fields were extracted and exported to a spreadsheet. All activity 

results are in microcuries per liter. No other codes or fields with useful information were identified. 

For the period from the start of data (June 23, 1950) through approximately 1991, no records had 

fields that contained information that would permit the sorting or exclusion of any data points. Later 

data (post-1991) identified samples as routine or special, but all pre-1989 data were identified as 

historical spot samples. All data were used. A total of 72,153 distinct records were identified.

Visual examination of the data indicates that almost all of the high bioassay values are clearly the 

result of acute intakes. Involved employees were regularly monitored while the tritium was excreted, 

which resulted in well-defined decaying exponential excretion curves. No attempt was made to 

exclude the bioassay data resulting from these acute intakes. 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 13 of 104

The minimum detectable activity (MDA) for the entire period was 1 μCi/L until late 1987, when the 

MDA decreased to 0.1 μCi/L. Prior to 1991, MDAs are reported in the database separately from the 

analytical result. Analytical results <MDA were recorded as zero, except for December 1968 through 

January 1971, when the actual result was recorded. Starting in 1991, the actual result, regardless of 

whether it was above or below the MDA, was reported and the MDA was not reported separately.

Activities recorded in site records as less than the MDA were input as one-half of the MDA for this 

analysis. 

For 2005 through 2008, tritium urine bioassay data were extracted from the “LANL IN VITRO DATA 

FEB 2009” table in the “LANL_invitro_dataset_feb2009.mdb” database. All records with a nuclide 

type of “H-3” and collection dates ranging from 2005 through 2008 inclusive were identified. The 

“ZNO,” “COLLECTED_DATE,” and “ACTIVITY” fields were extracted and exported to a spreadsheet.

All activity results are in microcuries per liter. No other codes or fields with useful information were 

identified. A total of 5,186 distinct records were identified. The actual result, regardless of whether it 

was above or below the MDA was reported. In addition, the MDA was reported.

3.4 PLUTONIUM-238

The “co_worker_data” table in the “LANL CO-Worker Data – Rev 1.mdb” database was queried to 

identify all records with a nuclide type of “PU-238” and collection dates that ranged from the beginning 

of 1968 through the end of 2004. Predominantly pure 238Pu was not encountered at LANL prior to 

1968 (ORAUT 2004c). The “coll_date,” “z_number,” and “activity” fields were extracted and exported 

to a spreadsheet. All activity results were in units of picocuries per 24 hr. For the period from the 

start of data (1968) through the end of 1990, all the data had the same information available in the 

database with no fields that contained information that would permit the sorting or exclusion of any 

data points. Later data (post-1991) identified samples as routine or special, but all pre-1991 data 

were identified as simply historical samples. All data were used.

It appears that values less than the MDA were reported beginning in 1971 with negative results 

reported as zero. Negative results were reported beginning in 1973 except for two results in 1971. All 

activity values, including zero, less than zero, and less-than MDA, were used without modification for 

all years.

The statistical analysis was performed on an annual basis. A total of 77,739 distinct records were 

used for the statistical analysis. Table A-1 in Attachment A lists the statistical analysis results for 

238

Pu.

Examination of the reported activities revealed that a relatively small number of individuals accounted

for the majority of the highest bioassay results. These results tended to skew the curve fit. The 

bioassay results for these individuals were filtered out for the years indicated to eliminate this skew of 

the curve fit. Table 3-1 lists the individuals whose results were filtered out and for which years. 

Additional detail, with personally identifiable information removed, for filtering out these individuals is 

provided below. 

 Table 3-1. High bioassay readings

 for 238Pu.

Individual Years filtered out

1 1972 through 1988

2 1972 through 1988

3 1972 through 1988

4 1977 through 1988

5 1981 through 1988
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 14 of 104

Individuals 1 through 3: These individuals were involved in the Wing-9 incident in 1971, which has 

been the subject of multiple studies (Hickman et al 1995, James et al 2003). Their bioassay data is 

well-studied and associated with a known incident. Their data was removed for 1972 through 1988.

Individual 4: In 1977, this individual had an acute intake on February 10, 1977 and was bioassayed a 

total of 96 times during 1977 and was treated with DTPA (ORISE 2009). The bioassay 

measurements exhibit a clear exponential decay and the initial data were extreme outliers and 

skewed the fit. All data for this individual for 1977 through 1988 were removed. The same pattern 

was seen in this individual’s 239

Pu bioassay measurements.

Individual 5: This individual had an acute intake in mid April 1981 (Inkret and Miller 1995). He was

sampled numerous times and the bioassay data exhibits an exponential decay trend. All data for this

individual for 1981 through 1988 were removed. This individual also had high 239Pu bioassay 

measurements starting at same time.

For 2005 through 2008, the “LANL IN VITRO DATA FEB 2009” table in the 

“LANL_invitro_dataset_feb2009.mdb” database was queried to identify all records with a nuclide type 

of “PU-238” and collection dates that ranged from the beginning of 2005 through the end of 2008. 

The “ZNO,” “COLLECTED_DATE,” “SAMPLE_ID,” “ACTIVITY_PS” and “ACTIVITY” fields were 

extracted and exported to a spreadsheet. For a given “SAMPLE_ID,” the “ACTIVITY_PS” field was 

used as the sample activity unless it was blank, in which case the value in the “ACTIVITY” field was 

used as the result. All samples are 24-hour or simulated 24-hour samples and were in units of pCi 

per sample or pCi per 24-hours. Thus all results were treated as pCi/day. All data were used.

3.5 PLUTONIUM-239

3.5.1 Pu-239 In-Vitro Data

The “co_worker_data” table in the “LANL CO-Worker Data – Rev 1.mdb” database was queried to 

identify all urinalysis records with a nuclide type of “PU-239” and collection dates that ranged from the 

beginning of 1945 through the end of 2004. The “coll_date,” “z_number,” and “activity” fields were 

extracted and exported to a spreadsheet. All activity results were in units of picocuries per 24 hr. For 

the period from the start of data (1944) through approximately 1991, all the data had the same

information available in the database with no fields that contained information that would permit the 

sorting or exclusion of any data points. Later data (post-1991) identified samples as routine or 

special, but all pre-1989 data were identified as simply historical samples. All data were used.

Values less than the MDA and negative results were reported as such from 1945 through 1957 and 

from 1971 onward. For 1958 through 1970, values less than zero were reported as zero. All activity 

values, including zero, less than zero, and above-MDA, were used without modification for all years.

Prior to 1967, plutonium urinalysis measured gross plutonium alpha activity rather than 239/240Pu 

activity. However, the pre-1967 data has been treated as measuring the 239/240Pu count rate, which 

overestimates the actual 239/240Pu activity by 10 to 12% for weapons-grade plutonium depending on 

the fuel age. The statistical analysis was performed on an annual basis. A total of 85,752 distinct 

records were used for the statistical analysis. Table A-2 in Attachment A lists the statistical analysis 

results for in vitro 239Pu.

Examination of the reported activities revealed that, for a few years, a few individuals were 

responsible for the vast majority of the highest bioassay results. These results tended to skew the 

curve fit. The bioassay results for these individuals were filtered out for the specific year listed to 

eliminate this skew of the curve fit. Table 3-2 lists the individuals whose results were filtered out and 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 15 of 104

for which years. The justification for filtering out these individuals is the same as given for Pu-238 

above.

 Table 3-2. High bioassay readings

 for 239

Pu.

Individual Years filtered out

4 1977 through 1988

5 1981 through 1988

For 2005 through 2008, the “LANL IN VITRO DATA FEB 2009” table in the 

“LANL_invitro_dataset_feb2009.mdb” database was queried to identify all records with a nuclide type 

of “PU-239,” “PU-240,” or “PU-239+PU-240” and collection dates that ranged from the beginning of 

2005 through the end of 2008. The “ZNO,” “COLLECTED_DATE,” “SAMPLE_ID,” 

“ANALYSIS_TYPE,” “ACTIVITY_PS” and “ACTIVITY” fields were extracted and exported to a 

spreadsheet. All samples are 24-hour or simulated 24-hour samples and were in units of pCi per 

sample or pCi per 24-hours. Thus all results were treated as pCi/day. 

Pu-239/240 results were obtained by both alpha spectrometry, “RAS,” and by mass spectrometry, 

“TIMS.” The TIMS results report a concentration separately for Pu-239 and for Pu-240. RAS results 

do not distinguish between Pu-239 and Pu-240 since the alpha particle energies for these two 

radionuclides are very similar and report the combined activity as “PU-239.” The TIMS results have a 

lower limit of detection and are generally more reliable. For this study, the combined Pu-239/240 

activity is the desired quantity. A single sample ID in the database may have as many as 8 records 

associated with it. To determine the single quantity to use for this study, the following priority order 

was used: 

For a given “sample_ID” #, use the record(s) highest in the following priority list:

1 “NUCLIDE” field = “PU-239+PU-240”, “ANALYSIS_TYPE” = “TIMS”, recorded value in the 

“ACTIVITY_PS” field

2 “NUCLIDE” field = “PU-239+PU-240”, “ANALYSIS_TYPE” = “TIMS”, “ACTIVITY_PS” field 

blank, with a recorded value in the “ACTIVITY” field 

3 Sum the “ACTIVITY_PS” fields of:

a. “NUCLIDE” field = “PU-239”, “ANALYSIS_TYPE” = “TIMS”, recorded value in the 

“ACTIVITY_PS” field plus

b. “NUCLIDE” field = “PU-240”, “ANALYSIS_TYPE” = “TIMS”, recorded value in the 

“ACTIVITY_PS” field.

4 Sum the “ACTIVITY” fields of:

a. “NUCLIDE” field = “PU-239”, “ANALYSIS_TYPE” = “TIMS”, “ACTIVITY_PS” field blank, 

recorded value in the “ACTIVITY” field plus

b. “NUCLIDE” field = “PU-240”, “ANALYSIS_TYPE” = “TIMS”, “ACTIVITY_PS” field blank, 

recorded value in the “ACTIVITY” field

5 “NUCLIDE” field = “PU-239”, “ANALYSIS_TYPE” = “RAS”, recorded value in the 

“ACTIVITY_PS” field.

6 “NUCLIDE” field = “PU-239”, “ANALYSIS_TYPE” = “RAS”, “ACTIVITY_PS” field blank, 

recorded value in the “ACTIVITY” field

A single value for each sample ID was used. All sample IDs with reported Pu-239 and/or Pu-240 

results were used. In 2007, one individual had the 67 largest results. All of this person’s bioassay 

data in 2007 was excluded from the analysis.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 16 of 104

3.5.2 Pu-239 In-Vivo Data

The “TBL_NIOSH_REPORT_2007_V2” table in the “2007_10_08-LANL_IN_VIVO_DATAAccess2003.mdb” database was queried to identify all lung count records with a nuclide type of “Pu239,” organ type of “Chest,” count reason other than “new hire,” “rehire,” or “baseline,” and collection 

dates ranging from the beginning of 1969 through the end of 2004. The “count_date,” “zno” and 

“abundance_nCi” fields were extracted and exported to Excel. The “zno” field was used as the 

employee identifier and the “abundance_nCi” field was used as the value of the chest count.

Records with no abundance value given were entered with an abundance of “0,” based on the 

assumption that the result was less than the MDA and the fact that the recorded MDAs were much 

higher than the typical recorded positive values. Only 1969 through 1979 were analyzed since there 

were few positive results after 1979. Table A-3 in Attachment A lists the statistical analysis results for 

in-vivo 239Pu.

3.6 POLONIUM-210

The “co_worker_data” table in the “LANL CO-Worker Data – Rev 1.mdb” database was queried to 

identify all records with a nuclide type of “Po” and collection dates that ranged from the beginning of 

1947 through the end of 2004. The “coll_date,” “z_number,” and “activity” fields were extracted and 

exported to Excel®. The activity results are reported in units of picocuries per liter or counts per 

minute per liter. Results reported in counts per minute were converted to disintegrations per minute 

using a detector efficiency of 50% based on the assumption that a 2-π detector was used in the 

absence of any other information and a recovery fraction of 10%. The results in disintegrations per 

minute were then converted to picocuries for consistency with the other data. Results reported in 

picocuries per liter were adjusted assuming a recovery fraction of 10% rather than 100% (ORAUT 

2009). All the data had the same information available in the database with no fields that contained 

information that would permit the sorting or exclusion of any data points. Therefore, all data were 

used.

Examination of the data indicated several anomalies. Several individuals had acute intakes in 

January 1953. Because more than one individual was involved (even though a limited number), these 

data were left in the data set for the entire year. In August 1954, one employee had an acute intake 

that resulted in all of the highest 20% of bioassay results for the year. All bioassay results for this 

employee for the third and fourth quarters of 1954 were excluded from the analysis.

Another acute intake involving a large number of individuals occurred in late July or early August 

1955. To separate the urinalysis results due to this acute intake, urinalysis results for seven

employees were excluded from the fits performed for the last two quarters of 1955. Although these 

seven individuals were not the only ones involved in the incident, these seven had the majority of the 

highest readings. The bioassay data for these seven individuals as a result of this incident have been 

analyzed separately as an acute intake. Dose reconstruction for individuals who were involved in this 

incident and who do not have relevant bioassay data should also be assigned this intake. This 

applies only to individuals for whom there is evidence or reason to believe that they were involved in 

this incident. An incident date of August 1, 1955 was chosen as the best fit to the available data.

All activity values, including zero, less than zero, and less-than MDA, were used without modification 

for all years. The normal statistical analysis was performed on a quarterly basis. For the seven 

identified individuals involved in the incident, the bioassay data for each individual was fit separately 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 17 of 104

to determine the intake of material that occurred in the incident. Table A-4 in Attachment A lists the 

statistical analysis results for 210Po. A total of 5,121 distinct records were used for the quarterly and 

incident analyses.

3.7 URANIUM

The “co_worker_data” table in the “LANL CO-Worker Data – Rev 1.mdb” database was queried to 

identify all records with a nuclide type of “U-234,” “U-235” or “U-238” and collection dates ranging from 

1950 through the end of 2004. The “coll_date,” “z_number,” “activity,” and “MDA” fields were 

extracted and exported to a spreadsheet. All activity results are in units of picocuries per 24 hr. For 

the period from the start of data (1950) through approximately 1991, all the data had the same 

information available in the database with no fields that contained information that would permit the 

sorting or exclusion of any data points. Later data (post-1991) identified samples as routine or 

special, but all pre-1989 data were identified as historical spot samples. All data were used.

Prior to July, 1991, the bioassay records identified the results as being specific for either 238U or 235U. 

However, both techniques truly measured the same quantity but reported the results in different units. 

A single measurement technique was used during any given time frame (See Table 5-13 in ORAUT 

2004c) for analysis of uranium in urine prior to 1991. The analytical results were interpreted based on 

the materials to which an individual was presumed to have been exposed. Therefore, the two data 

sets were merged to create an overall uranium data set. The 238U data were converted to activity 

units assuming an activity of 0.4673 pCi/μg based on the specific activity of D-38 uranium (ORAUT 

2004c) and merged with the 235U data. All activity values, including zero, less than zero, and lessthan MDA, were used without modification for all years.

Beginning in July, 1991, alpha spectrometry was used to analyze the urine samples for uranium, at 

which time results for U-234, U-235, and U238 were reported. Since all uranium activity is assumed 

to be U-234 for the purposes of calculating dose, the activities of all three isotopes were summed and 

used as the total uranium activity.

The statistical analysis was performed on an annual basis. A total of 126,523 records were used for 

the statistical analysis. Table A-5 in Attachment A lists the statistical analysis results for uranium. 

For 2005 through 2008, the “LANL IN VITRO DATA FEB 2009” table in the

“LANL_invitro_dataset_feb2009.mdb” database was queried to identify all records with a nuclide type 

of “U-234,” “U-235,” or “U-238” and collection dates that ranged from the beginning of 2005 through 

the end of 2008. The “ZNO,” “COLLECTED_DATE,” “SAMPLE_ID,” “ACTIVITY_PS” and “ACTIVITY” 

fields were extracted and exported to a spreadsheet. For a given “SAMPLE_ID,” the “ACTIVITY_PS” 

field was used as the sample activity unless it was blank, in which case the value in the “ACTIVITY” 

field was used as the result. All samples are 24-hour or simulated 24-hour samples and were in units 

of pCi per sample or pCi per 24-hours. Thus all results were treated as pCi/day. The U-234, U-235, 

and U238 activities for a given sample ID were summed and used as the total uranium activity. All 

data were used.

3.8 CESIUM-137

The “TBL_NIOSH_REPORT_2007_V2” table in the “2007_10_08-LANL_IN_VIVO_DATAAccess2003.mdb” database was queried to identify all records with a nuclide type of “Cs-137,” organ 

type of “Whole Body,” collection dates that ranged from the beginning of 1970 through the end of 

2004, and count reason other than “new hire.” The “count_date,” “zno,” and “abundance_nCi” fields 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 18 of 104

were extracted and exported to a spreadsheet. The “zno” field was used as the employee identifier 

and the “abundance_nCi” field was used as the value of the whole-body count.

Records with no abundance value were entered with an abundance equal to the MDA based on the 

assumption that the result was less than the MDA and since the MDA was typically less than the 

positive values recorded.

Due to the small number of records (301 distinct records), the statistical analysis was performed in 5-

or 4-yr blocks: 1970 to 1974, 1975 to 1979, 1980 to 1984, 1985 to 1989, and 1990 to 1993. Table A6 in Attachment A lists the statistical analysis results for 137Cs. Insufficient data is available after 1993 

to permit analysis.

4.0 

This section discusses intake modeling assumptions, intake fitting, and intake materials.

INTAKE MODELING

4.1 ASSUMPTIONS

Each result used in the intake calculations was assumed to have a normal distribution. A uniform 

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

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

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

period).

Because of the nature of work at LANL, intakes could have been either chronic or acute. However, a 

series of acute intakes can be approximated as a chronic intake. Therefore, intakes were assumed to 

be chronic and were assumed to occur through inhalation with a default breathing rate of 1.2 m3

/hr 

and a 5-μm activity median aerodynamic diameter particle size distribution. 

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

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

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

the assumed intake period. International Commission on Radiological Protection (ICRP) Publication 

68 dose coefficients (also referred to as dose conversion factors) for 234U are 7% to 31% larger than 

the dose coefficients for 235U, 236U, and 238U (ICRP 1995). Therefore, the assumption that the intake is 

100% 234U provides a result that is favorable to claimants.

4.2 BIOASSAY FITTING

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

inhalation intakes. Data from 1945 through 2008 were fit as a series of chronic intakes. 

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

constant chronic intake rates were chosen by the selection of periods in which the bioassay results 

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

change in the bioassay results. By this method, the years from 1945 through 2008 were divided 

independently into multiple chronic intake periods for each radionuclide.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 19 of 104

4.3 MATERIAL TYPES

ORAUT (2004c) discussed LANL internal dosimetry data for the dose reconstructor and included 

guidance for the appropriate use of that information. Workers at LANL had the potential to receive 

intakes of 238

Pu, 239Pu, uranium, polonium, tritium, and cesium. Site-specific internal dosimetry 

information for other radionuclides is rare or not available (ORAUT 2004c).

4.3.1 

The data set discussed in the previous section for tritium was condensed into a file for the period from 

January 1, 1950, to December 31, 2008, with the following columns:

Tritium

Days Post Conc MDA

Z Number ID Number Name 1/1/1950 uCi/L uCi/L

Duplicate records (i.e., lines that had all six fields the same as another line) were deleted to leave 

unique records. The doses were calculated by individual for each calendar year from 1950 to 2008.

Any person who had only a single urine result of <MDA μCi/L for a given period was not included in 

the calculations of the dose distribution for that period because they were not considered part of the 

routine monitoring program. All remaining concentrations of <MDA μCi/L were replaced with one-half 

of the appropriate MDA. Any person with a single measurement in a period was assigned a second 

measurement 40 days later of one-half of the MDA of the first measurement.

The protocol given in Technical Information Bulletin: Tritium Calculated and Missed Dose Estimates

(ORAUT 2004b) was used to calculate the dose for each individual with the following rules concerning 

the elapsed time between consecutive samples: 

• Type 1 calculations were performed for samples separated by 40 or fewer days.

• Type 3 calculations were performed if there were no other samples within 90 days of a 

sample.

• Type 2 calculations were performed in all other situations.

The doses for a period are plotted on a lognormal probability plot and the typical parameters 

[geometric mean (GM), geometric standard deviation (GSD), and R2

] are determined from a linear 

regression. The plotting positions were calculated with i/n – 1/(2n) convention specified in ORAUTPROC-0095 (ORAUT 2006).

4.3.2 

Plutonium-238 urinalysis results were analyzed with IMBA using type M and S materials to derive 

intake rates for 1968 to 2008. Note that solubility Type Super S is not applicable to 238Pu (ORAUT 

2008). 

Plutonium-238

Plutonium-238 Type M: The solid lines in Figures B-1 to B-8 and B-9 to B-15 in Attachment B show 

the individual fits to the 50th- and 84th-percentile excretion rates, respectively, for type M materials. 

Figures B-16 and B-17 show the 50th- and 84th-percentile predicted excretion rates, respectively, 

from all type M intakes. Table B-1 lists the 50th- and 84th-percentile intake rates along with the 

associated GSD determined from 238Pu urinalysis. 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 20 of 104

Plutonium-238 Type S: The solid lines in Figures B-18 to B-24 and B-25 to B-31 in Attachment B 

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

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

similar pattern. Figures B-32 and B-33 show the 50th- and 84th-percentile predicted excretion rates, 

respectively, from all type S intakes. Table B-2 lists the 50th- and 84th-percentile intake rates along 

with the associated GSD determined from 238Pu urinalysis. 

4.3.3 

Plutonium-239 urinalysis results were analyzed with IMBA using type M and S materials to derive 

intake rates for 1944 to 2008. 

Plutonium-239

Plutonium-239 Type M Urinalysis: The solid lines in Figures B-34 to B-42 and B-43 to B-51 in 

Attachment B show the individual fits to the 50th- and 84th-percentile excretion rates, respectively, for 

type M materials. The same intake periods were applied for both percentiles because the values 

followed a similar pattern. Figures B-52 and B-53 show the 50th- and 84th-percentile predicted 

excretion rates, respectively, from all type M intakes. Table B-3 lists the 50th- and 84th-percentile 

intake rates along with the associated GSD determined from 239Pu urinalysis. 

Plutonium-239 Type S Urinalysis: The solid lines in Figures B-54 to B-62 and B-63 to B-71 in 

Attachment B show the individual fits to the 50th- and 84th-percentile excretion rates, respectively, for 

type S materials. Figures B-72 and B-73 show the 50th- and 84th-percentile predicted excretion 

rates, respectively, from all type S intakes. Table B-4 lists the 50th- and 84th-percentile intake rates 

along with the associated GSD determined from 239Pu urinalysis. 

Plutonium-239 Type S Lung Counts: The solid lines in Figures B-74 to B-78 and B-79 to B-83 in 

Attachment B show the individual fits to the 50th- and 84th-percentile lung burdens, respectively, for 

type S materials. The same intake periods were applied for both percentiles as the values followed a 

similar pattern. Table B-5 lists the 50th- and 84th-percentile intake rates along with the associated 

GSD determined from 239Pu lung burdens.

4.3.4 

Polonium urinalysis results were analyzed with IMBA using type F and M materials to derive intake 

rates for 1947 to 1956.

Polonium 

Polonium Type F: The solid lines in Figures B-84 and B-85 in Attachment B show the fit to the 50thand 84th-percentile excretion rates, respectively, for type F materials. Table B-6 lists the 50th- and 

84th percentile intake rates along with the associated GSD determined from the polonium urinalysis. 

Polonium Type M: The solid lines in Figures B-86 and B-87 in Attachment B show the fit to the 50thand 84th-percentile excretion rates, respectively, for type M materials. Table B-7 lists the 50th- and 

84th-percentile intake rates along with the associated GSD determined from the polonium urinalysis. 

August 1, 1955 Incident: The bioassay data for the seven individuals positively identified as having 

been involved in this incident were analyzed separately using standard dose reconstruction bioassay 

fitting methods assuming both Type F and Type M material types. Figures B-88 through B-94 and B95 through B-101 show the fits for each individual for Type F and M material types respectively. 

Table B-8 lists the calculated intakes from these fits.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 21 of 104

1944 to 1946: Polonium bioassay data to evaluate coworker intakes is not available for this time 

period. To approximate intakes during this time period, which falls within a SEC definition, the intake 

rate for each solubility class for 1947 to 1949 was applied.

4.3.5 

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

the material is retained in the body for long periods, excretion results are not independent. For 

example, an intake in the 1950s could contribute to urinary excretion in the 1980s and later. To avoid 

potential underestimation of intakes for people who worked at LLNL for relatively short periods, each 

chronic intake was fit independently using only the bioassay results from the single intake period for 

type S solubility. This method results in an overestimate of intakes for exposures that extended

through multiple assumed intake periods. Only the results in the intake period were selected for use 

in the fitting of each period. Excluded results are shown in light gray in the figures in Attachment B. 

For type M and F solubility, this approach was not used. 

Uranium

Uranium Type F: The solid lines in Figures B-102 and B-103 in Attachment B show the fit to the 

50th- and 84th-percentile excretion rates, respectively, for type F materials. Table B-9 lists the 50thand 84th-percentile intake rates along with the associated GSD determined from the uranium

urinalysis. 

Uranium Type M: The solid lines in Figures B-104 and B-105 in Attachment B show the fit to the 

50th- and 84th-percentile excretion rates, respectively, for type M materials. Table B-10 lists the 50thand 84th-percentile intake rates along with the associated GSD determined from the uranium

urinalysis. 

Uranium Type S: The solid lines in Figures B-106 to B-112 and B-113 to B-119 in Attachment B 

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

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

similar pattern. Figures B-120 and B-121 show the 50th- and 84th-percentile predicted excretion 

rates, respectively, from all type S intakes. Table B-11 lists the 50th- and 84th-percentile intake rates 

along with the associated GSD determined from the uranium urinalysis. 

1947 to 1949: Uranium bioassay data to evaluate coworker intakes is not available for this time 

period. To approximate intakes during this time period, which falls within a SEC definition, the intake 

rate for each solubility class for 1950 to 1955 was applied

4.3.6 

Cesium whole-body count results were analyzed with IMBA using type F materials to derive intake 

rates for 1970 through 1993. The solid lines in Figures B-122 and B-123 in Attachment B show the fit 

to the 50th- and 84th-percentile excretion rates, respectively, for type F materials. Table B-12 lists the 

50th- and 84th-percentile intake rates along with the associated GSD determined from the cesium 

whole-body counts. 

Cesium-137 

5.0 

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

ASSIGNING INTAKES AND DOSES
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 22 of 104

5.1 INTAKE RATE SUMMARY

For the calculation of 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 been conservatively adjusted for 

consistency between intake periods for calculational efficiency.

The following subsections list the intake rates that should be used for each radionuclide and the 

period of applicability of each intake rate except that for tritium. For tritium, the actual dose that 

should be used is provided.

5.2 TRITIUM

Table 5-1 lists the tritium doses and GSDs to be used for each year of potential tritium exposure.

 Table 5-1. Tritium annual doses (mrem) and GSDs. 

Year Dose GSD Year Dose GSD

1950 33 7.2 1980 15 4.1

1951 36 5.9 1981 17 4.1

1952 25 4.2 1982 21 4.5

1953 26 6.7 1983 18 4.8

1954 16 6.2 1984 16 3.4

1955 43 6.5 1985 18 3.3

1956 33 6.9 1986 21 3.8

1957 35 6.9 1987 17 4.3

1958 26 5.7 1988 7 4.4

1959 22 5.5 1989 7 3.5

1960 27 5.2 1990 6 3.2

1961 20 4.7 1991 2 3.0

1962 17 4.7 1992 5 3.5

1963 18 3.7 1993 6 3.4

1964 17 3.5 1994 3 3.0

1965 18 3.5 1995 5 3.0

1966 19 4.2 1996 5 3.0

1967 23 6.0 1997 4 3.0

1968 16 4.6 1998 7 3.0

1969 21 5.0 1999 4 3.0

1970 25 7.0 2000 9 4.1

1971 16 4.9 2001 6 3.0

1972 14 5.4 2002 6 3.5

1973 16 5.3 2003 5 3.3

1974 25 6.7 2004 3 3.0

1975 19 6.2 2005 3 3.0

1976 13 4.1 2006 4 3.0

1977 20 5.5 2007 4 3.0

1978 20 5.2 2008 6 3.3

1979 12 4.9

5.3 PLUTONIUM-238

Intakes of 238

Pu should be assigned if the energy employee is known or believed to have been

exposed to heat source plutonium. For heat source plutonium, solubility Type Super S is not 
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 23 of 104

applicable. If the energy employee was only exposed to weapons-grade plutonium (239

Pu), then the 

intake of 238

Pu should be based on the isotope mixture for weapons-grade 239Pu and the 239Pu intakes 

given in Section 5.4 and not on the intakes in this section. Table 5-2 lists the 238

Pu intakes and 

associated GSDs to be used for each year of potential 238

Pu exposure for both Type M and Type S 

material. Solubility Type Super S is not applicable to plutonium-238 (ORAUT 2008).

Table 5-2. Plutonium-238 intake rates (pCi/d).

Start End

Type M Type S

50th percentile GSD 50th percentile GSD

1/1/1968 12/31/1971 1.8 5.63 43 5.74

1/1/1972 12/31/1972 14. 3.13 765 3.13

1/1/1973 12/31/1974 2.0 4.31 72 4.17

1/1/1975 12/31/1977 0.67 3.59 5.2 8.47

1/1/1978 12/31/1981 0.32 7.56 5.2 8.47

1/1/1982 12/31/1988 0.084 8.73 1.8 8.47

1/1/1989 12/31/1993 0.44 4.31 9.7 4.17

1/1/1994 12/31/2008 0.048 6.82 0.72 6.58

5.4 PLUTONIUM-239

Intakes of 239

Pu should be assigned if the energy employee is known or believed to have been 

exposed to weapons-grade plutonium. For weapons-grade plutonium, solubility Type Super S must 

be considered. If the energy employee was only exposed to heat source plutonium (238

Pu), then the 

plutonium intake should be based on the 238

Pu intakes in Section 5.3 and not on the intakes in this 

section. Table 5-3 lists the 239Pu urine-based intakes and associated GSDs to be used for each year 

of potential 239Pu exposure for Type M material. Intakes of the associated isotopes as given in Table 

5-9 of the LANL internal TBD (ORAUT 2009) must also be assigned.

 Table 5-3. Plutonium-239 Type M intake rates (pCi/d).

Start End

Type M

50th percentile GSD

1/1/1944 12/31/1945 248 5.05

1/1/1946 12/31/1946 95 6.24

1/1/1947 12/31/1953 10 5.16

1/1/1954 12/31/1954 3.1 17.2

1/1/1955 12/31/1956 3.1 12.4

1/1/1957 12/31/1966 0.38 12.4

1/1/1967 12/31/1972 3.3 4.81

1/1/1973 12/31/1975 1.5 6.21

1/1/1976 12/31/1993 0.16 6.83

1/1/1994 12/31/2008 0.013 12.2

 

Table 5-4 lists the 239Pu urinalysis and lung burden-based intakes and associated GSDs to be used 

for each year of potential 239Pu exposure for Type S and Super S material. Intakes of the associated 

isotopes as given in Table 5-9 of the LANL internal TBD (ORAUT 2009) must also be assigned.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 24 of 104

Table 5-4. Plutonium-239 Type S and Super S intake rates (pCi/d).

Systemic intake rates Non-systemic intake rates

Start End 50th percentile GSD Start End 50th percentile GSD

1/1/1944 12/31/1945 8,651 a 5.05 1/1/1944 12/31/1945 8,651 a 5.05

1/1/1946 12/31/1946 5,125 a 6.24 1/1/1946 12/31/1946 5,125 a 6.24

1/1/1947 12/31/1953 200 a 4.87 1/1/1947 12/31/1953 200 a 4.87

1/1/1954 12/31/1954 88a 11.12 1/1/1954 12/31/1954 88a 11.12

1/1/1955 12/31/1956 88a 15.3 1/1/1955 12/31/1956 88a 15.3

1/1/1957 12/31/1966 6.3a 11.91 1/1/1957 12/31/1966 6.3a 11.91

1/1/1967 12/31/1972 73a 4.62 1/1/1967 12/31/1968 73a 4.62

1/1/1969 12/31/1971 27.66b 4.50

1/1/1973 12/31/1975 41 a 6.34 1/1/1972 12/31/1974 29.43b 4.50

1/1/1975 12/31/1975 505.4b 3.00

1/1/1976 12/31/1993 2.3 a 6.34 1/1/1976 12/31/1977 96.07b 3.90

1/1/1978 12/31/1979 19.55b 6.24

1/1/1980 12/31/1993 2.3 a 6.34

1/1/1994 12/31/2008 0.14 a 12.8 1/1/1994 12/31/2008 0.14 a 12.8

a. Urinalysis-based intake rates.

b. Lung count-based intake rates. 

The Table 5-4 intake rates should be used as follows:

• For doses to systemic organs, only the urinalysis-based intakes should be used in accordance

 with the guidance in ORAUT-OTIB-0049 (ORAUT 2008).

• Doses to the lungs and thoracic lymph nodes, gastrointestinal tract, and extrathoracic regions

 (non-systemic organs) should be based on the lung counts when available in accordance with

 the guidance in ORAUT-OTIB-0049 (ORAUT 2008).

• Type S doses should be calculated using the lung count-based intakes for 1969 through

1974 and urinalysis-based intakes for all other time periods.

• Type Super S doses should be calculated using the lung count-based intakes for 1969 

through 1979 and urinalysis-based intakes for all other time periods.

5.5 POLONIUM

Table 5-5 lists the polonium intakes and associated GSDs to be used for each year of potential 

polonium exposure. 

Table 5-5. Polonium intake rates (pCi/d).

Start End

Type F Type M

50th percentile GSD 50th percentile GSD

1/1/1944 12/31/1946 592.8a 6.96 2013a 7.01

1/1/1947 03/31/1949 592.8 6.96 2013 7.01

4/1/1949 12/31/1956 592.8 3.00 2013 3.00

a. Intakes for 1944 through 1946 are based on the 1947 to March 31, 1949 intakes.

Dose reconstruction for individuals who were involved in the polonium incident that occurred at or 

near the beginning of August 1955 and who do not have relevant bioassay data should be assigned 

the intakes in Table 5-6. The most favorable to claimant material type should be used. This intake 

should be applied only to individuals for whom there is evidence or reason to believe that they were 

involved in this incident.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 25 of 104

Table 5-6. August 1, 1955 incident polonium intakes (pCi).

Date

Type F Type M

50th percentile GSD 50th percentile GSD

8/1/1955 2.8E6 3.00 1.2E7 3.00

5.6 URANIUM

Table 5-7 lists the uranium intakes and associated GSDs to be used for each year of potential 

uranium exposure.

Table 5-7. Uranium intake rates (pCi/d).

Start End

Type F Type M Type S

50th percentile GSD 50th percentile GSD 50th percentile GSD

1/1/1947 12/31/1949 21.3a 3.36 88.7a 3.36 1,520a 3.24

1/1/1950 12/31/1955 21.3 3.36 88.7 3.36 1,520 3.24

1/1/1956 12/31/1957 5.36 3.36 16.0 3.36 656 3.24

1/1/1958 12/31/1965 1.98 4.81 7.95 4.90 141 4.71

1/1/1966 12/31/1973 0.909 6.84 3.53 7.03 59.3 6.59

1/1/1974 12/31/1982 0.227 11.31 1.03 10.6 19.7 9.27

1/1/1983 12/31/1989 1.53 4.81 6.29 4.90 105 4.44

1/1/1990 12/31/2000 0.201 4.03 0.756 4.06 11.0 4.57

1/1/2001 12/31/2001 1.019 3.00 4.70 3.00 92.0 3.00

1/1/2002 12/31/2008 0.201 4.03 0.756 4.06 11.0 4.57

a. Intakes for 1947 through 1949 are based on the 1950 through 1955 intakes.

5.7 CESIUM-137

Table 5-8 lists the cesium intakes and associated GSDs to be used for each year of potential cesium 

exposure.

Table 5-8. Type F 137Cs intake rates (pCi/d).

Start End 50th percentile GSD

1/1/1970 12/31/1974 185.5 3.00

1/1/1975 12/31/1979 130.7 3.28

1/1/1980 12/31/1984 69.47 3.00

1/1/1985 12/31/1989 47.36 3.00

1/1/1990 12/31/1993 30.16 3.00

6.0 ATTRIBUTIONS AND ANNOTATIONS

All information requiring identification was addressed via references integrated into the reference 

section of this document.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 26 of 104

REFERENCES

Hickman, A. W., et al., 1995, “Application of a Canine 238Pu Biokinetics/Dosimetry Model to Human 

Bioassay Data,” Health Physics, (68) 3, pp 359-370.

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

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

Inkret B, G. Miller, 1995, “On the Front Lines - Plutonium Workers Past and Present Share Their 

Experiences.” Los Alamos Science, (23)pp. 125-173. Los Alamos, NM. 1995. [SRDB Ref ID: 

43568] 

James, A. C., et al, 2003, “USTUR Case 0259 Whole Body Donation: A Comprehensive Test of the 

Current ICRP Models for the Behavior of Inhaled Pu-238 OxideCeramic Particles, (84) 1, pp. 

2-33

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

Development, ORAUT-PLAN-0014, Rev. 00, Oak Ridge, Tennessee, November 24.

ORAUT (Oak Ridge Associated Universities Team), 2004b, Technical Information Bulletin: Tritium 

and Missed Dose Estimates, ORAUT-OTIB-0011, Rev. 00, Oak Ridge, Tennessee, June 29.

ORAUT (Oak Ridge Associated Universities Team), 2004c, Los Alamos National Laboratory –

Occupational Internal Dose, ORAUT-TKBS-0010-5, Rev 00, Oak Ridge, Tennessee, 

December 21.

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

Internal Dose Assignment, ORAUT-OTIB-0019, Rev. 01, Oak Ridge, Tennessee, October 7.

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

Coworker Bioassay Data, ORAUT-PROC-0095, Rev. 00, Oak Ridge, Tennessee, June 5.

ORAUT (Oak Ridge Associated Universities Team), 2008, Estimating Doses for Plutonium Strongly 

Retained in the Lung, ORAUT-OTIB-0049, Rev 01 PC-1, Oak Ridge, Tennessee, September 

26.

ORAUT (Oak Ridge Associated Universities Team), 2009, Mound Site – Occupational Internal Dose, 

ORAUT-TKBS-0016-5, Rev 00 PC-1, Oak Ridge, Tennessee, March 13.

ORISE (Oak Ridge Institute for Science and Education), 2009, Chelation DTPA data for DOE 

Employees. Oak Ridge, Tennessee, August 8. [SRDB Ref ID: 71439].
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 27 of 104

LIST OF TABLES

TABLE TITLE

A-1 Statistical summary of 238Pu urinary excretion rates, 1968 to 2008.........................................

PAGE

28

A-2 Statistical summary of 239Pu urinary excretion rates, 1945 to 2008......................................... 29

A-3 Statistical summary of 239Pu lung burdens, 1969 to 1979 ....................................................... 30

A-4 Statistical summary of polonium urinary excretion rates, 1947 to 1956 .................................. 31

A-5 Statistical summary of uranium urinary excretion rates from 1950 to 2008............................. 32

A-6 Statistical summary of cesium whole-body counts, 1970 to 1993........................................... 33

ATTACHMENT A

COWORKER DATA TABLES

Page 1 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 28 of 104

Table A-1. Statistical summary of 238Pu

urinary excretion rates (pCi/d), 1968 to 2008.

Effective 

bioassay date GM (50th) GM*GSD (84th)

7/1/1968 0.00823 0.0339

7/1/1969 0.00486 0.0332

7/1/1970 0.00147 0.0062

7/1/1971 0.00815 0.0466

7/1/1972 0.02683 0.0840

7/1/1973 0.00581 0.0308

7/1/1974 0.00571 0.0214

7/1/1975 0.00261 0.0154

7/1/1976 0.00224 0.0164

7/1/1977 0.00232 0.0182

7/1/1978 0.00101 0.0143

7/1/1979 0.00162 0.0118

7/1/1980 0.00126 0.0091

7/1/1981 0.00124 0.0118

7/1/1982 0.00010 0.0027

7/1/1983 0.00010 0.0019

7/1/1984 0.00011 0.0026

7/1/1985 0.00028 0.0038

7/1/1986 0.00079 0.0053

7/1/1987 0.00056 0.0047

7/1/1988 0.00072 0.0048

7/1/1989 0.0017 0.0079

7/1/1990 0.0021 0.0081

7/1/1991 0.0025 0.0091

7/1/1992 0.0022 0.0079

7/1/1993 0.0016 0.0078

7/1/1994 0.0006 0.0046

7/1/1995 0.0003 0.0049

7/1/1996 0.0006 0.0035

7/1/1997 0.0004 0.0035

7/1/1998 0.0004 0.0029

7/1/1999 0.0002 0.0013

7/1/2000 0.0002 0.0028

7/1/2001 0.0002 0.0017

7/1/2002 0.0002 0.0012

7/1/2003 0.0002 0.0011

7/1/2004 0.0003 0.0016

7/1/2005 0.0005 0.0022

7/1/2006 0.0007 0.0031

7/1/2007 0.0004 0.0042

7/1/2008 0.0005 0.0029

ATTACHMENT A

COWORKER DATA TABLES

Page 2 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 29 of 104

 Table A-2. Statistical summary of 239Pu urinary excretion rates (μCi/L), 1945 to

 2008.

Effective 

bioassay 

date

GM 

(50th)

GM*GSD 

(84th)

Effective 

bioassay 

date

GM 

(50th)

GM*GSD 

(84th)

7/1/1945 0.8332 4.2106 7/1/1980 0.0018 0.0154

7/1/1946 0.1793 1.1191 7/1/1981 0.0014 0.0137

7/1/1947 0.1065 0.4876 7/1/1982 0.0003 0.0057

7/1/1948 0.0571 0.4084 7/1/1983 0.0006 0.0093

7/1/1949 0.0301 0.2028 7/1/1984 0.0003 0.0053

7/1/1950 0.0434 0.2118 7/1/1985 0.0017 0.0111

7/1/1951 0.0574 0.2595 7/1/1986 0.0013 0.0108

7/1/1952 0.0628 0.4073 7/1/1987 0.0013 0.0084

7/1/1953 0.0703 0.4009 7/1/1988 0.0012 0.0071

7/1/1954 0.0153 0.1779 7/1/1989 0.0017 0.0077

7/1/1955 0.0119 0.0978 7/1/1990 0.0021 0.0083

7/1/1956 0.0115 0.0979 7/1/1991 0.0023 0.0084

7/1/1957 0.0042 0.052 7/1/1992 0.0017 0.0076

7/1/1958 0.0040 0.0537 7/1/1993 0.0015 0.0083

7/1/1959 0.0020 0.0322 7/1/1994 0.0004 0.0045

7/1/1960 0.0022 0.0306 7/1/1995 0.0003 0.0043

7/1/1961 0.0019 0.0201 7/1/1996 0.0007 0.0040

7/1/1962 0.0016 0.0232 7/1/1997 0.0002 0.0038

7/1/1963 0.002 0.0306 7/1/1998 0.0002 0.0026

7/1/1964 0.0026 0.0265 7/1/1999 0.00010 0.00120

7/1/1965 0.0023 0.0253 7/1/2000 0.00009 0.00136

7/1/1966 0.0037 0.0380 7/1/2001 0.00004 0.00094

7/1/1967 0.0066 0.0471 7/1/2002 0.00003 0.00064

7/1/1968 0.0093 0.0584 7/1/2003 0.00002 0.00034

7/1/1969 0.0145 0.0814 7/1/2004 0.00002 0.00041

7/1/1970 0.0066 0.0422 7/1/2005 0.00004 0.00049

7/1/1971 0.0157 0.1008 7/1/2006 0.00002 0.00035

7/1/1972 0.0341 0.1136 7/1/2007 0.00004 0.00051

7/1/1973 0.0083 0.0446 7/1/2008 0.00006 0.00068

7/1/1974 0.0061 0.0350

7/1/1975 0.0037 0.0265

7/1/1976 0.0022 0.0201

7/1/1977 0.0023 0.0292

7/1/1978 0.0012 0.0157

7/1/1979 0.0011 0.0116

ATTACHMENT A

COWORKER DATA TABLES

Page 3 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 30 of 104

Table A-3. Statistical summary of 239Pu lung burdens

(pCi), 1969 to 1979.

Measurement 

data date 

range

Effective 

bioassay date GM (50th) GM*GSD (84th)

1969-1970 7/1/1970 473 2033

1971-1974 7/1/1973 504 2268

1975 7/1/1975 3712 6922

1976-1977 1/1/1977 1221 4319

1978-1979 1/1/1979 248 1290

ATTACHMENT A

COWORKER DATA TABLES

Page 4 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 31 of 104

Table A-4. Statistical summary of polonium 

urinary excretion rates (pCi/d), 1947 to 1956.

Effective 

bioassay date GM (50th) GM*GSD (84th)

2/15/1947 54.51 219.82

5/15/1947 76.59 343.47

8/15/1947 25.15 240.80

11/15/1947 50.89 200.17

2/15/1948 48.88 252.94

5/15/1948 52.76 294.13

8/15/1948 98.45 507.63

11/15/1948 53.79 189.88

2/15/1949 79.84 364.04

5/15/1949 49.10 148.29

8/15/1949 32.53 86.43

11/15/1949 29.78 120.96

2/15/1950 20.90 63.53

5/15/1950 41.23 90.29

8/15/1950 25.93 79.71

11/15/1950 31.89 119.93

2/15/1951 42.18 115.02

5/15/1951 33.14 111.07

8/15/1951 41.25 144.68

11/15/1951 36.96 125.69

2/15/1952 45.76 142.02

5/15/1952 32.36 157.48

8/15/1952 27.83 105.86

11/15/1952 27.15 84.03

2/15/1953 76.61 299.93

5/15/1953 33.87 127.48

8/15/1953 51.79 138.64

11/15/1953 65.50 225.54

2/15/1954 43.99 122.20

5/15/1954 46.75 120.15

8/15/1954 39.35 89.36

11/15/1954 34.75 76.77

2/15/1955 33.08 77.69

5/15/1955 16.99 52.10

8/15/1955 55.54 200.24

11/15/1955 30.19 54.61

7/1/1956 14.44 52.33

ATTACHMENT A

COWORKER DATA TABLES

Page 5 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 32 of 104

Table A-5. Statistical summary of uranium urinary excretion rates (pCi/d) from 1950 to 2008.

Effective 

bioassay date GM (50th)

GM*GSD 

(84th)

Effective bioassay 

date GM (50th)

GM*GSD 

(84th)

7/1/1950 6.941 24.394 7/1/1980 0.002 0.054

7/1/1951 5.035 15.898 7/1/1981 0.003 0.060

7/1/1952 6.764 19.354 7/1/1982 0.016 0.274

7/1/1953 3.979 11.575 7/1/1983 0.438 2.136

7/1/1954 5.656 20.846 7/1/1984 0.410 1.788

7/1/1955 6.536 18.864 7/1/1985 0.215 1.045

7/1/1956 1.447 5.702 7/1/1986 0.482 1.723

7/1/1957 1.518 4.324 7/1/1987 0.286 1.893

7/1/1958 0.410 2.087 7/1/1988 0.348 1.543

7/1/1959 0.090 1.110 7/1/1989 0.317 1.351

7/1/1960 0.083 0.660 7/1/1990 0.030 0.240

7/1/1961 0.206 1.498 10/1/1991 0.058 0.231

7/1/1962 0.723 4.006 7/1/1992 0.024 0.168

7/1/1963 0.471 2.691 7/1/1993 0.033 0.223

7/1/1964 1.009 3.153 7/1/1994 0.074 0.346

7/1/1965 0.722 3.779 7/1/1995 0.084 0.399

7/1/1966 0.467 2.249 7/1/1996 0.088 0.366

7/1/1967 0.356 3.554 7/1/1997 0.072 0.292

7/1/1968 0.065 0.919 7/1/1998 0.070 0.291

7/1/1969 0.204 1.287 7/1/1999 0.064 0.307

7/1/1970 0.224 1.370 7/1/2000 0.066 0.383

7/1/1971 0.001 0.044 7/1/2001 0.285 0.746

7/1/1972 0.150 1.046 7/1/2002 0.070 0.231

7/1/1973 0.233 1.501 7/1/2003 0.053 0.164

7/1/1974 0.070 0.876 7/1/2004 0.059 0.197

7/1/1975 0.080 0.784 7/1/2005 0.114 0.312

7/1/1976 0.040 0.529 7/1/2006 0.078 0.230

7/1/1977 0.023 0.391 7/1/2007 0.103 0.288

7/1/1978 0.034 0.513 7/1/2008 0.074 0.216

7/1/1979 0.055 0.590

ATTACHMENT A

COWORKER DATA TABLES

Page 6 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 33 of 104

Table A-6. Statistical summary of cesium whole-body counts

(pCi), 1970 to 1993.

Measurement data 

date range

Effective 

bioassay date GM (50th)

GM*GSD 

(84th)

1970–1974 7/1/1972 12740 37156

1975–1979 7/1/1977 9013 29573

1980–1984 7/1/1982 4799 9442

1985–1989 1/1/1987 3277 6896

1990-1993 1/1/1992 2089 4354

ATTACHMENT A

COWORKER DATA TABLES

Page 7 of 7
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 34 of 104

LIST OF TABLES

TABLE TITLE

B-1 Summary of 238Pu type M intake rates and dates ...................................................................

PAGE

48

B-2 Summary of 238Pu type S intake rates and dates.................................................................... 56

B-3 Summary of 239Pu type M intake rates and dates ................................................................... 66

B-4 Summary of 239Pu type S urinalysis-based intake rates and dates ......................................... 76

B-5 Summary of 239Pu type S lung burden-based intake rates and dates ..................................... 81

B-6 Summary of polonium type F intake rates and dates.............................................................. 83

B-7 Summary of polonium type M intake rates and dates ............................................................. 83

B-8 Summary of polonium acute intakes type F and M................................................................. 91

B-9 Summary of uranium type F intake rates and dates ............................................................... 93

B-10 Summary of uranium type M intake rates and dates............................................................... 94

B-11 Summary of uranium type S intake rates and dates ............................................................. 103

B-12 Summary of type F 137Cs intake rates and dates .................................................................. 104

LIST OF FIGURES

FIGURE TITLE

B-1 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 50th percentile, type M .................................

PAGE

40

B-2 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 50th percentile, type M.............................................. 40

B-3 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 50th percentile, type M ................................. 41

B-4 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1977, 50th percentile, type M ................................. 41

B-5 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1978 to 1981, 50th percentile, type M ................................. 42

B-6 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 50th percentile, type M ................................. 42

B-7 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 50th percentile, type M ................................. 43

B-8 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type M ................................. 43

B-9 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 84th percentile, type M ................................. 44

B-10 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 84th percentile, type M.............................................. 44

B-11 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973-1974, 84th percentile, type M..................................... 45

B-12 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 84th percentile, type M ................................. 45

ATTACHMENT B

COWORKER DATA FIGURES

Page 1 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 35 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 2 of 71

B-13 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 84th percentile, type M ................................. 46

B-14 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 84th percentile, type M ................................. 46

B-15 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type M ................................. 47

B-16 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type M............................... 47

B-17 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type M............................... 48

B-18 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 50th percentile, type S.................................. 48

B-19 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 50th percentile, type S .............................................. 49

B-20 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 50th percentile, type S.................................. 49

B-21 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 50th percentile, type S.................................. 50

B-22 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 50th percentile, type S.................................. 50

B-23 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 50th percentile, type S.................................. 51

B-24 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type S.................................. 51

B-25 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1968 to 1971, 84th percentile, type S.................................. 52

B-26 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1972, 84th percentile, type S .............................................. 52

B-27 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1973 to 1974, 84th percentile, type S.................................. 53

B-28 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1975 to 1981, 84th percentile, type S.................................. 53

B-29 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1982 to 1988, 84th percentile, type S.................................. 54

B-30 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1989 to 1993, 84th percentile, type S.................................. 54

B-31 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type S.................................. 55

B-32 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type S................................ 55

B-33 Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type S................................ 56

B-34 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1945, 50th percentile, type M.............................................. 56

B-35 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1946, 50th percentile, type M.............................................. 57
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 36 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 3 of 71

B-36 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1947-1953, 50th percentile, type M..................................... 57

B-37 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1954 to 1956, 50th percentile, type M ................................. 58

B-38 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1957 to 1966, 50th percentile, type M ................................. 58

B-39 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1967 to 1972, 50th percentile, Type M................................ 59

B-40 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1973 to 1975, 50th percentile, type M ................................. 59

B-41 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1976 to 1993, 50th percentile, type M ................................. 60

B-42 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1994 to 2008, 50th percentile, type M ................................. 60

B-43 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1945, 84th percentile, type M.............................................. 61

B-44 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1946, 84th percentile, type M.............................................. 61

B-45 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1947 to 1954, 84th percentile, type M ................................. 62

B-46 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1954 to 1956, 84th percentile, type M ................................. 62

B-47 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1957 to 1966, 84th percentile, type M ................................. 63

B-48 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1967 to 1972, 84th percentile, type M ................................. 63

B-49 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1973 to 1975, 84th percentile, type M ................................. 64

B-50 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1976 to 1993, 84th percentile, type M ................................. 64

B-51 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results, 1994 to 2008, 84th percentile, type M ................................. 65

B-52 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results from all intakes, 50th percentile, type M............................... 65

B-53 Predicted 239Pu bioassay results calculated using IMBA-derived 239Pu intake rates 

compared with bioassay results from all intakes, 84th percentile, type M............................... 66

B-54 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1945, 50th percentile, type S ........................... 67

B-55 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1946, 50th percentile, type S ........................... 67

B-56 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1947 to 1953, 50th percentile, type S............... 68

B-57 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1954 to 1956, 50th percentile, type S............... 68

B-58 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1957 to 1958, 50th percentile, type S............... 69
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 37 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 4 of 71

B-59 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1967 to 1972, 50th percentile, type S............... 69

B-60 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1973 to 1975, 50th percentile, type S............... 70

B-61 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1993, 50th percentile, type S............... 70

B-62 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1994 to 2008, 50th percentile, type S............... 71

B-63 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1945, 84th percentile, type S ........................... 71

B-64 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1946, 84th percentile, type S ........................... 72

B-65 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1947 to 1954, 84th percentile, type S............... 72

B-66 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1955 to 1956, 84th percentile, type S............... 73

B-67 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1957 to 1966, 84th percentile, type S............... 73

B-68 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1967 to 1972, 84th percentile, type S............... 74

B-69 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1973 to 1975, 84th percentile, type S............... 74

B-70 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1993, 84th percentile, type S............... 75

B-71 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1994 to 2008, 84th percentile, type S............... 75

B-72 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results from all intakes, 50th percentile, type S ............ 76

B-73 Predicted 239Pu urinalysis bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results from all intakes, 84th percentile, type S ............ 76

B-74 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1969 to 1971, 50th percentile, type S............... 77

B-75 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1972 to 1974, 50th percentile, type S............... 77

B-76 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1975, 50th percentile, type S ........................... 78

B-77 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1977, 50th percentile, type S............... 78

B-78 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1978 to 1979, 50th percentile, type S............... 79

B-79 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1969 to 1971, 84th percentile, type S............... 79

B-80 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1972 to 1974, 84th percentile, type S............... 80

B-81 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1975, 84th percentile, type S ........................... 80
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 38 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 5 of 71

B-82 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1976 to 1977, 84th percentile, type S............... 81

B-83 Predicted 239Pu lung burden bioassay results calculated using IMBA-derived 239Pu 

intake rates compared with bioassay results, 1978 to 1979, 84th percentile, type S............... 81

B-84 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F....................... 82

B-85 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F....................... 82

B-86 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 50th percentile, type M ...................... 83

B-87 Predicted polonium bioassay results calculated using IMBA-derived polonium intake 

rates compared with bioassay results from all intakes, 84th percentile, type M ...................... 83

B-88 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “A,” type F ...................... 84

B-89 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “B,” type F ...................... 84

B-90 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “C,” type F ...................... 85

B-91 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “D,” type F ...................... 85

B-92 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “E,” type F ...................... 86

B-93 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “F,” type F....................... 86

B-94 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “G,” type F...................... 87

B-95 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “A,” type M..................... 87

B-96 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “B,” type M...................... 88

B-97 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “C,” type M ..................... 88

B-98 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “D,” type M ..................... 89

B-99 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “E,” type M...................... 89

B-100 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “F,” type M...................... 90

B-101 Predicted polonium acute intake bioassay fit calculated using an IMBA-derived 

polonium intake rate compared with bioassay results for individual “G,” type M ..................... 90

B-102 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F....................... 92

B-103 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F....................... 92

B-104 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 50th percentile, type M ...................... 93
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 39 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 6 of 71

B-105 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results from all intakes, 84th percentile, type M ...................... 94

B-106 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1950 to 1955, 50th percentile, type S......................... 95

B-107 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1956 to 1957, 50th percentile, type S......................... 95

B-108 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1958 to 1965, 50th percentile, type S......................... 96

B-109 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1966 to 1973, 50th percentile, type S......................... 96

B-110 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1974 to 1982, 50th percentile, type S......................... 97

B-111 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1983 to 1989, 50th percentile, type S......................... 97

B-112 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1990 to 2008, 50th percentile, type S......................... 98

B-113 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1950 to 1955, 84th percentile, type S......................... 98

B-114 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1956 and 1957, 84th percentile, type S...................... 99

B-115 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1958 to 1965, 84th percentile, type S......................... 99

B-116 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1966 to 1973, 84th percentile, type S....................... 100

B-117 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1974 to 1982, 84th percentile, type S....................... 100

B-118 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1983 to 1989, 84th percentile, type S....................... 101

B-119 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, 1990 to 2008, 84th percentile, type S....................... 101

B-120 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, all intake periods, 50th percentile, type S................. 102

B-121 Predicted uranium bioassay results calculated using IMBA-derived uranium intake 

rates compared with bioassay results, all intake periods, 84th percentile, type S................. 102

B-122 Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates compared with bioassay results from all intakes, 50th percentile, type F..................... 103

B-123 Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates compared with bioassay results from all intakes, 84th percentile, type F..................... 104
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 40 of 104

Figure B-1. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1968 to 1971, 50th

percentile, type M.

Figure B-2. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1972, 50th percentile, 

type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 7 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 41 of 104

Figure B-3. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1973 to 1974, 50th

percentile, type M.

Figure B-4. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1975 to 1977, 50th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 8 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 42 of 104

Figure B-5. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1978 to 1981, 50th

percentile, type M.

Figure B-6. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1982 to 1988, 50th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 9 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 43 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 10 of 71

Figure B-7. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu 

intake rates (line) compared with bioassay results (dots), 1989 to 1993, 50th 

percentile, type M.

Figure B-8. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu 

intake rates (line) compared with bioassay results (dots), 1994 to 2008, 50th 

percentile, type M.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 44 of 104

Figure B-9. Predicted 238Pu bioassay results calculated using IMBA-derived 238Pu

intake rates (line) compared with bioassay results (dots), 1968 to 1971, 84th

percentile, type M.

Figure B-10. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1972, 84th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 11 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 45 of 104

Figure B-11. Predicted 238Pu bioassay results calculated using IMBA-derived 

238

Pu intake rates (line) compared with bioassay results (dots), 1973-1974, 84th

percentile, type M.

Figure B-12. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1975 to 1981, 84th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 11 of 71

ATTACHMENT B

COWORKER DATA FIGURES

Page 12 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 46 of 104

ATTACHMENT B

COWORKER DATA FIGURES

Page 13 of 71

Figure B-13. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1982 to 1988, 84th

percentile, type M.

Figure B-14. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1989 to 1993, 84th 

percentile, type M.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 47 of 104

Figure B-15. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1994 to 2008, 84th 

percentile, type M.

Figure B-16. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

Page 14 of 71
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 48 of 104

Figure B-17. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type M.

Table B-1. Summary of 238

Pu type M intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1968 12/31/1971 1.774 9.981 5.63

1/1/1972 12/31/1972 14.12 44.22 3.13

1/1/1973 12/31/1974 2.038 8.793 4.31

1/1/1975 12/31/1977 0.666 2.394 3.59

1/1/1978 12/31/1981 0.317 2.394 7.56

1/1/1982 12/31/1988 0.084 0.737 8.74

1/1/1989 12/31/1993 0.439 1.764 4.02

1/1/1994 12/31/2008 0.048 0.326 6.82

Figure B-18. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1968 to 1971, 50th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-19. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1972, 50th 

percentile, type S.

Figure B-20. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1973 to 1974, 50th 

percentile, type S.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 50 of 104

Figure B-21. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1975 to 1981, 50th 

percentile, type S.

Figure B-22. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1982 to 1988, 50th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-23. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1989 to 1993, 50th 

percentile, type S.

Figure B-24. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1994 to 2008, 50th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-25. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1968 to 1971, 84th 

percentile, type S.

Figure B-26. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1972, 84th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-27. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1973 to 1974, 84th 

percentile, type S.

Figure B-28. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1975 to 1981, 84th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-29. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1982 to 1988, 84th 

percentile, type S.

Figure B-30. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1989 to 1993, 84th 

percentile, type S.
Document No. ORAUT-OTIB-0062 Revision No. 00 Effective Date: 10/15/2009 Page 55 of 104

Figure B-31. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots), 1994 to 2008, 84th 

percentile, type S.

Figure B-32. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-33. Predicted 238Pu bioassay results calculated using IMBA-derived 

238Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type S.

Table B-2. Summary of 238

Pu type S intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1968 12/31/1971 42.95 246.5 5.74

1/1/1972 12/31/1972 764.7 2394 3.13

1/1/1973 12/31/1974 72.28 301.3 4.17

1/1/1975 12/31/1981 5.235 44.34 8.47

1/1/1982 12/31/1988 1.818 15.02 8.26

1/1/1989 12/31/1993 9.708 39.21 4.04

1/1/1994 12/31/2008 0.717 4.72 6.58

Figure B-34. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1944 to 1945, 50th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-35. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1946, 50th

percentile, type M.

Figure B-36. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1947-1953, 50th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-37. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1954 to 1956, 50th

percentile, type M.

Figure B-38. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1957 to 1966, 50th

percentile, Type M.

ATTACHMENT B

COWORKER DATA FIGURES

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COWORKER DATA FIGURES

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Figure B-39. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1967 to 1972, 50th

percentile, Type M.

Figure B-40. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1973 to 1975, 50th

percentile, type M.
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Figure B-41. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1976 to 1993, 50th

percentile, type M.

Figure B-42. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1994 to 2008, 50th 

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-43. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1944 to 1945, 84th

percentile, type M.

Figure B-44. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1946, 84th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-45. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1947 to 1954, 84th

percentile, type M.

Figure B-46. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1955 to 1956, 84th

percentile, type M.
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Figure B-47. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1957 to 1966, 84th

percentile, type M.

Figure B-48. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1967 to 1972, 84th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-49. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1973 to 1975, 84th

percentile, type M.

Figure B-50. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1976 to 1993, 84th

percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-51. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots), 1994 to 2008, 84th 

percentile, type M.

Figure B-52. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-53. Predicted 239Pu bioassay results calculated using IMBA-derived 

239Pu intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type M.

Table B-3. Summary of 239Pu type M intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1944 12/31/1945 247.9 1253 5.05

1/1/1946 12/31/1946 94.53 590 6.24

1/1/1947 12/31/1953 10.46 53.96 5.16

1/1/1954 12/31/1954 3.146 53.96 17.15

1/1/1955 12/31/1956 3.146 39.05 12.41

1/1/1957 12/31/1966 0.379 4.62 12.19

1/1/1967 12/31/1972 3.267 15.71 4.81

1/1/1973 12/31/1975 1.535 9.54 6.21

1/1/1976 12/31/1993 0.164 1.12 6.83

1/1/1994 12/31/2008 0.013 0.15 12.20

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COWORKER DATA FIGURES

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Figure B-54. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1944 to 

1945, 50th percentile, type S.

Figure B-55. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1946, 50th 

percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-56. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1947 to 

1953, 50th percentile, type S.

Figure B-57. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1954 to 

1956, 50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-58. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1957 to 

1966, 50th percentile, type S.

Figure B-59. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1967 to 

1972, 50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

Page 33 of 71

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-60. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1973 to 

1975, 50th percentile, type S.

Figure B-61. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1976 to 

1993, 50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-62. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1994 to 

2008, 50th percentile, type S.

Figure B-63. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1944 to 

1945, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-64. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1946, 84th 

percentile, type S.

Figure B-65. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1947 to 

1954, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-66. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1955 to 

1956, 84th percentile, type S.

Figure B-67. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1957 to 

1966, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-68. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1967 to 

1972, 84th percentile, type S.

Figure B-69. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1973 to 

1975, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-70. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1976 to 

1993, 84th percentile, type S.

Figure B-71. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots), 1994 to 

2008, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-72. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots) from all 

intakes, 50th percentile, type S.

Figure B-73. Predicted 239Pu urinalysis bioassay results calculated using IMBAderived 239Pu intake rates (line) compared with bioassay results (dots) from all 

intakes, 84th percentile, type S.

Table B-4. Summary of 239Pu type S urinalysis-based intake rates

(pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1944 12/31/1945 8651 43270 5.05

1/1/1946 12/31/1946 5125 31990 6.24

1/1/1947 12/31/1953 200.2 975 4.87

1/1/1954 12/31/1954 87.71 975 11.12

1/1/1955 12/31/1956 87.71 1342 15.30

1/1/1957 12/31/1966 6.27 74.67 11.91

1/1/1967 12/31/1972 73.47 339.2 4.62

1/1/1973 12/31/1975 40.56 257 6.34

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COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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1/1/1976 12/31/1993 2.303 14.51 6.30

1/1/1994 12/31/2008 0.1402 1.798 12.82

Figure B-74. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1969 to 1971, 50th percentile, type S.

Figure B-75. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1972 to 1974, 50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-76. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1975, 50th percentile, type S.

Figure B-77. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1976 to 1977, 50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-78. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1978 to 1979, 50th percentile, type S.

Figure B-79. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1969 to 1971, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-80. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1972 to 1974, 84th percentile, type S.

Figure B-81. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1975, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-82. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1976 to 1977, 84th percentile, type S.

Figure B-83. Predicted 239Pu lung burden bioassay results calculated using 

IMBA-derived 239Pu intake rates (line) compared with bioassay results (dots), 

1978 to 1979, 84th percentile, type S.

Table B-5. Summary of 239Pu type S lung burden-based intake 

rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1969 12/31/1971 27.66 118.9 4.30

1/1/1972 12/31/1974 29.43 132.5 4.50

1/1/1975 12/31/1975 505.4 942.5 1.86

1/1/1976 12/31/1977 96.07 339.8 3.54

1/1/1978 12/31/1979 19.55 101.7 5.20

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-84. Predicted polonium bioassay results calculated using IMBA-derived 

polonium intake rates (line) compared with bioassay results (dots) from all 

intakes, 50th percentile, type F.

Figure B-85. Predicted polonium bioassay results calculated using IMBA-derived 

polonium intake rates (line) compared with bioassay results (dots), from all 

intakes, 84th percentile, type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-6. Summary of polonium type F intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1947 03/31/1949 592.8 4126 6.96

4/1/1949 12/31/1956 592.8 1587 2.68

Figure B-86. Predicted polonium bioassay results calculated using IMBA-derived 

polonium intake rates (line) compared with bioassay results (dots) from all 

intakes, 50th percentile, type M.

Figure B-87. Predicted polonium bioassay results calculated using IMBA-derived 

polonium intake rates (line) compared with bioassay results (dots) from all 

intakes, 84th percentile, type M.

Table B-7. Summary of polonium type M intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1947 3/31/1949 2013 14120 7.01

4/1/1949 12/31/1956 2013 5346 2.65

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-88. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “A,” type F.

Figure B-89. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “B,” type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-90. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “C,” type F.

Figure B-91. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “D,” type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-92. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “E,” type F.

Figure B-93. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “F,” type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-94. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “G,” type F.

Figure B-95. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “A,” type M.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-96. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “B,” type M.

Figure B-97. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “C,” type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-98. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “D,” type M.

Figure B-99. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “E,” type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-100. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “F,” type M.

Figure B-101. Predicted polonium acute intake bioassay fit calculated using an 

IMBA-derived polonium intake rate (line) compared with bioassay results (dots) 

for individual “G,” type M.

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-8. Summary of polonium acute intakes

(pCi) type F and M.

Individual Type F Type M

A 1.07E+06 4.55E+06

B 1.06E+07 4.22E+07

C 2.85E+06 1.21E+07

D 2.61E+06 1.12E+07

E 6.44E+06 2.56E+07

F 2.16E+06 9.30E+06

G 1.29E+06 5.36E+06

Geometric 

mean

2.84E+06 1.19E+07

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-102. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type F.

Figure B-103. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-9. Summary of uranium type F intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1950 12/31/1955 21.28 67.25 3.16

1/1/1956 12/31/1957 5.358 17.99 3.36

1/1/1958 12/31/1965 1.981 9.535 4.81

1/1/1966 12/31/1973 0.9086 6.218 6.84

1/1/1974 12/31/1982 0.2270 2.567 11.31

1/1/1983 12/31/1989 1.526 6.768 4.44

1/1/1990 12/31/2008 0.201 0.8091 4.03

1/1/2001 12/31/2001 0.818 1.794 2.19

Note: the 2001 intake is additive to the 1990-2008 intake.

Figure B-104. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type M.

ATTACHMENT B

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Figure B-105. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type M.

Table B-10. Summary of uranium type M intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1950 12/31/1955 88.72 279.9 3.15

1/1/1956 12/31/1957 15.96 53.6 3.36

1/1/1958 12/31/1965 7.946 38.94 4.90

1/1/1966 12/31/1973 3.528 24.8 7.03

1/1/1974 12/31/1982 1.029 10.91 10.60

1/1/1983 12/31/1989 6.285 27.74 4.41

1/1/1990 12/31/2008 0.7555 3.065 4.06

1/1/2001 12/31/2001 3.944 8.644 2.19

Note: the 2001 intake is additive to the 1990-2008 intake.
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Figure B-106. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1950 to 1955, 

50th percentile, type S.

Figure B-107. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1956 to 1957, 

50th-percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-108. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1958 to 1965, 

50th percentile, type S.

Figure B-109. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1966 to 1973, 

50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-110. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1974 to 1982, 

50th percentile, type S.

Figure B-111. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1983 to 1989, 

50th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-112. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1990 to 2008, 

50th percentile, type S.

Figure B-113. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1950 to 1955, 

84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-114. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1956 and 1957, 

84th percentile, type S.

Figure B-115. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1958 to 1965, 

84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-116. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1966 to 1973, 

84th percentile, type S.

Figure B-117. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1974 to 1982, 

84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-118. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1983 to 1989, 

84th percentile, type S.

Figure B-119. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 1990 to 2008, 

84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-120. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), all intake 

periods, 50th percentile, type S.

Figure B-121. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), all intake 

periods, 84th percentile, type S.

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-11. Summary of uranium type S intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1950 12/31/1955 1520 4760 3.13

1/1/1956 12/31/1957 655.5 2125 3.24

1/1/1958 12/31/1965 141 664.5 4.71

1/1/1966 12/31/1973 59.25 390.4 6.59

1/1/1974 12/31/1982 19.66 182.3 9.27

1/1/1983 12/31/1989 104.5 463.5 4.44

1/1/1990 12/31/2008 10.97 50.12 4.57

1/1/2001 12/31/2001 80.980 109.5 1.35

Note: The 2001 intake is additive to the 1990-2008 intake.

Figure B-122. Predicted cesium bioassay results calculated using IMBA-derived 

cesium intake rates (line) compared with bioassay results (dots) from all intakes, 

50th percentile, type F.

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-123. Predicted cesium bioassay results calculated using IMBA-derived 

cesium intake rates (line) compared with bioassay results (dots) from all intakes, 

84th percentile, type F.

Table B-12. Summary of type F 137Cs intake rates (pCi/d) and dates.

Start End 50th percentile 84th percentile GSD

1/1/1970 12/31/1974 185.5 540.9 2.92

1/1/1975 12/31/1979 130.7 428.9 3.28

1/1/1980 12/31/1984 69.47 136.2 1.96

1/1/1985 12/31/1988 47.36 99.75 2.11

1/1/1990 12/31/1993 30.16 62.85 2.08