ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 96

DOE Review Release 01/02/2014

Document Title:

Internal Coworker Dosimetry Data for the 

Savannah River Site

Document Number: ORAUT-OTIB-0081

Revision: 02

Effective Date: 12/16/2013

Type of Document: OTIB

Supersedes: Revision 01

Subject Expert(s): Matthew G. Arno and Nancy Chalmers

Approval: Signature on File Approval Date: 11/06/2013

Matthew G. Arno, Document Owner

Concurrence: Signature on File Concurrence Date: 11/06/2013

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 11/06/2013

Edward F. Maher, Objective 3 Manager

Concurrence: Vickie S. Short Signature on File for Concurrence Date: 11/06/2013

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 12/16/2013

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-0081 Revision No. 02 Effective Date: 12/16/2013 Page 2 of 96

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

02/08/2013 00 New technical information bulletin to provide internal coworker data 

for the Savannah River Site. Incorporates formal internal and NIOSH 

review comments. Training required: As determined by the 

Objective Manager. Initiated by Matthew Arno. 

04/01/2013 01 Revision initiated to correct the values provided in Tables 5-6, Type 

S uranium intake rates for 1968 through 2007, 5-10, changed end 

date from 2006 to 2007, A-3, plutonium bioassay data for 1955 

through 2007, and A-8, neptunium bioassay data for 1991 through 

2007. Incorporates formal internal review comments. No changes 

were made as a result of formal NIOSH review. No sections were 

deleted. Training required: As determined by the Objective 

Manager. Initiated by Matthew G. Arno. 

12/16/2013 02 Revision initiated to add dose reconstruction guidance for 

radionuclide assignment in response to an ABRWH request. Text 

added in Section 5.0 and a new Table 5-1 added. Intake rates for 

Cm and Cf added for the pre-1995 time period. Incorporates formal 

internal and NIOSH review comments. Training required: As 

determined by the Objective Manager. Initiated by Matthew G. Arno.
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 3 of 96

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................. 11

1.0 Introduction ............................................................................................................................ 13

2.0 Purpose ................................................................................................................................. 13

3.0 Data Overview ....................................................................................................................... 13

3.1 Bioassay Data Selection............................................................................................. 13

3.1.1 NOCTS Urinalysis Data .................................................................................. 14

3.1.2 NOCTS Whole-Body Count Data .................................................................... 14

3.1.3 Health Protection Radiation Exposure Database............................................. 15

3.1.4 Neptunium Logbook Data ............................................................................... 16

3.1.5 Americium Logbook Data................................................................................ 17

3.2 Analysis...................................................................................................................... 17

3.3 Tritium ........................................................................................................................ 18

3.4 Plutonium ................................................................................................................... 18

3.4.1 NOCTS-Based Analysis.................................................................................. 18

3.4.2 HPRED-Based Analysis.................................................................................. 18

3.5 Uranium...................................................................................................................... 18

3.5.1 NOCTS-Based Analysis.................................................................................. 18

3.5.2 HPRED-Based Analysis.................................................................................. 19

3.6 Americium, Curium, and Californium .......................................................................... 20

3.6.1 Logbook-Based Analysis................................................................................. 20

3.6.2 HPRED-Based Analysis.................................................................................. 20

3.7 Neptunium.................................................................................................................. 20

3.8 Fission and Activation Products.................................................................................. 21

3.8.1 Strontium ........................................................................................................ 21

3.8.2 Cesium-137 .................................................................................................... 21

3.8.3 Cobalt-60 ........................................................................................................ 21

3.9 Thorium ...................................................................................................................... 22

4.0 Intake Modeling...................................................................................................................... 22

4.1 Assumptions............................................................................................................... 22

4.2 Bioassay Fitting .......................................................................................................... 22

4.3 Tritium ........................................................................................................................ 22

4.4 Plutonium ................................................................................................................... 23

4.5 Uranium...................................................................................................................... 23

4.6 Americium, Curium, and Californium .......................................................................... 24

4.7 Neptunium.................................................................................................................. 25

4.8 Strontium.................................................................................................................... 25

4.9 Cesium-137................................................................................................................ 25

4.10 Cobalt-60.................................................................................................................... 25

4.11 Thorium ...................................................................................................................... 25

5.0 Assignment of Intakes and Doses .......................................................................................... 26

5.1 Tritium ........................................................................................................................ 29

5.2 Plutonium ................................................................................................................... 30

5.3 Uranium...................................................................................................................... 30

5.4 Americium/Curium/Californium ................................................................................... 31

5.5 Neptunium.................................................................................................................. 32

5.6 Fission/Activation Products......................................................................................... 32

5.6.1 Strontium ........................................................................................................ 32
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 4 of 96

5.6.2 Cesium-137 .................................................................................................... 32

5.6.3 Cobalt-60 ........................................................................................................ 33

5.7 Thorium ...................................................................................................................... 33

6.0 Attributions and Annotations .................................................................................................. 33

References ........................................................................................................................................ 35

ATTACHMENT A, BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS................. 38

ATTACHMENT B, COWORKER DATA FIGURES ............................................................................ 57
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 5 of 96

LIST OF TABLES

TABLE TITLE PAGE

3-1 SRS HPRED data import format ............................................................................................ 16

5-1 Radionuclides of concern potentially present at SRS facilities................................................ 26

5-2 Tritium annual doses and GSDs............................................................................................. 29

5-3 Type M plutonium gross alpha intake rates ............................................................................ 30

5-4 Type S plutonium gross alpha intake rates............................................................................. 30

5-5 Type F 234U intake rates ......................................................................................................... 30

5-6 Type M 234U intake rates ........................................................................................................ 30

5-7 Type S 234U intake rates........................................................................................................ 31

5-8 Type F 233U intake rates ......................................................................................................... 31

5-9 Type M 233U intake rates ........................................................................................................ 31

5-10 Type S 233U intake rates......................................................................................................... 31

5-11 Type M americium intake rates .............................................................................................. 31

5-12 Type M curium intake rates .................................................................................................... 31

5-13 Type M californium intake rates.............................................................................................. 31

5-14 Type M neptunium intake rates .............................................................................................. 32

5-15 Type F strontium intake rates................................................................................................. 32

5-16 Type F 137Cs intake rates ....................................................................................................... 33

5-17 Type M 60Co intake rates........................................................................................................ 33

5-18 Type S 60Co intake rates ........................................................................................................ 33

5-19 Type M 232Th intake rates....................................................................................................... 33

5-20 Type S 232Th intake rates ....................................................................................................... 33

A-1 NOCTS radionuclide type matrix............................................................................................ 38

A-2 HPRED radionuclide type matrix............................................................................................ 43

A-3 50th- and 84th-percentile urinary excretion rates of plutonium gross alpha, 1955 to 2007...... 43

A-4 50th- and 84th-percentile urinary excretion rates of uranium, 1953 to 2007 ........................... 44

A-5 50th- and 84th-percentile urinary excretion rates of americium, 1963 to 2007........................ 46

A-6 50th- and 84th-percentile urinary excretion rates of curium, 1963 to 2007 ............................. 47

A-7 50th- and 84th-percentile urinary excretion rates of californium, 1963 to 2007....................... 48

A-8 50th- and 84th-percentile urinary excretion rates of neptunium, 1961 to 1969 and 1991 

to 2007...................................................................................................................................49

A-9 50th- and 84th-percentile whole body burdens of neptunium, 1971 to 1989........................... 49

A-10 50th- and 84th-percentile urinary excretion rates of strontium, 1955 to 1965 and 1991 to 

2006.......................................................................................................................................50

A-11 50th- and 84th-percentile whole body burdens of cesium, 1961 to 1989 ................................ 51

A-12 50th- and 84th-percentile urinary excretion rates of 60Co, 1955 to 1970................................. 51

B-1 Summary of plutonium type M intake rates and dates ............................................................ 59

B-2 Summary of plutonium type S intake rates and dates............................................................. 61

B-3 Summary of uranium type F intake rates and dates ............................................................... 62

B-4 Summary of uranium type M intake rates and dates............................................................... 63

B-5 Summary of uranium type S intake rates and dates ............................................................... 69

B-6 Summary of americium type M intake rates and dates ........................................................... 73

B-7 Summary of curium type M intake rates and dates................................................................. 77

B-8 Summary of californium type M intake rates and dates .......................................................... 80

B-9 Summary of neptunium type M intake rates and dates........................................................... 87

B-10 Summary of strontium type F intake rates and dates.............................................................. 89

B-11 Summary of cesium type F intake rates and dates................................................................. 89

B-12 Summary of 60Co type M intake rates and dates .................................................................... 90

B-13 Summary of 60Co type S intake rates and dates..................................................................... 91

B-14 Summary of thorium type M intake rates and dates................................................................ 94
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 6 of 96

B-15 Summary of thorium type S intake rates................................................................................. 96

LIST OF FIGURES

FIGURE TITLE PAGE

B-1 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1955–1990, type M ........................... 57

B-2 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1991–2007, type M ........................... 57

B-3 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1955–1990, type M ........................... 57

B-4 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type M ........................... 58

B-5 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 58

B-6 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 58

B-7 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1955–1990, type S............................ 59

B-8 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake

rates compared with bioassay results, 50th percentile, 1991–2007, type S............................ 59

B-9 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1955–1990, type S............................ 60

B-10 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type S ............................ 60

B-11 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type S ................... 60

B-12 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type S ................... 61

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

compared with bioassay results, 50th percentile, type F ........................................................ 61

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

compared with bioassay results, 84th percentile, type F ........................................................ 62

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

compared with bioassay results, 50th percentile, type M ........................................................ 62

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

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

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

compared with bioassay results, 50th percentile, 1953, type S .............................................. 63

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

compared with bioassay results, 50th percentile, 1954, type S .............................................. 64

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

compared with bioassay results, 50th percentile, 1955–1956, type S..................................... 64

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

compared with bioassay results, 50th percentile, 1957–1967, type S..................................... 64

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

compared with bioassay results, 50th percentile, 1968–1980, type S..................................... 65

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

compared with bioassay results, 50th percentile, 1981–1990, type S..................................... 65

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

compared with bioassay results, 50th percentile, 1991–2000, type S..................................... 65
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 7 of 96

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

compared with bioassay results, 50th percentile, 2001–2007, type S..................................... 66

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

compared with bioassay results, 84th percentile, 1953, type S .............................................. 66

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

compared with bioassay results, 84th percentile, 1954, type S .............................................. 66

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

compared with bioassay results, 84th percentile, 1955–1956, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1957–1967, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1968–1980, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1981–1990, type S..................................... 68

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

compared with bioassay results, 84th percentile, 1991–2000, type S..................................... 68

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

compared with bioassay results, 84th percentile, 2001–2007, type S..................................... 68

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

compared with bioassay results, 50th percentile, all intake periods, type S............................ 69

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

compared with bioassay results, 84th percentile, all intake periods, type S............................ 69

B-35 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1963–1967, type M ........................... 70

B-36 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1968–1972, type M ........................... 70

B-37 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1973–1994, type M ........................... 70

B-38 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1995–2007, type M ........................... 71

B-39 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1963–1967, type M ........................... 71

B-40 Predicted americium bioassay results using IMBA-derived americium intake rates 

compared with bioassay results, 84th percentile, 1968–1972, type M .................................... 71

B-41 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1973–1994, type M ........................... 72

B-42 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1995–2007, type M ........................... 72

B-43 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 72

B-44 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 73

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

compared with bioassay results, 50th percentile, 1963–1967, type M .................................... 73

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

compared with bioassay results, 50th percentile, 1968–1972, type M .................................... 74

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

compared with bioassay results, 50th percentile, 1973–1994, type M .................................... 74

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

compared with bioassay results, 50th percentile, 1995–2007, type M .................................... 74

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

compared with bioassay results, 84th percentile, 1963–1967, type M .................................... 75
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 8 of 96

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

compared with bioassay results, 84th percentile, 1968–1972, type M .................................... 75

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

compared with bioassay results, 84th percentile, 1973–1994, type M .................................... 75

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

compared with bioassay results, 84th percentile, 1995–2007, type M .................................... 76

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

compared with bioassay results, 50th percentile, all intake periods, type M ........................... 76

B-54 Predicted curium bioassay results calculated using IMBA-derived curium intake rates 

compared with bioassay results, 84th percentile, all intake periods, type M ........................... 76

B-55 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1963–1967, type M ........................... 77

B-56 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1968–1972, type M ........................... 77

B-57 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1973–1994, type M ........................... 78

B-58 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1995–2007, type M ........................... 78

B-59 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1963–1967, type M ........................... 78

B-60 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1968–1972, type M ........................... 79

B-61 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1973–1994, type M ........................... 79

B-62 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1995–2007, type M ........................... 79

B-63 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 80

B-64 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 80

B-65 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–1964, type M ........................... 81

B-66 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1965–1967, type M ........................... 81

B-67 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1968–1969, type M ........................... 81

B-68 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1970–1974, type M ........................... 82

B-69 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1975–1979, type M ........................... 82

B-70 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1980–1990, type M ........................... 82

B-71 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1991–2007, type M ........................... 83

B-72 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961–1963, type M ........................... 83

B-73 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1964–1965, type M ........................... 83

B-74 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1966–1967, type M ........................... 84

B-75 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1968–1969, type M ........................... 84
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 9 of 96

B-76 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1970–1974, type M ........................... 84

B-77 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1975–1979, type M ........................... 85

B-78 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1980–1990, type M ........................... 85

B-79 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type M ........................... 85

B-80 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–2007 cumulative, type M, 

urinalysis data........................................................................................................................86

B-81 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–2007 cumulative, type M, 

WBC data ..............................................................................................................................86

B-82 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961–2007 cumulative, type M, 

urinalysis data........................................................................................................................86

B-83 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961-2007 cumulative, type M, 

urinalysis data, WBC data...................................................................................................... 87

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

rates compared with bioassay results, 50th percentile, 1955–1965, type F............................ 87

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

rates compared with bioassay results, 50th percentile, 1991–2006, type F............................ 88

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

rates compared with bioassay results, 84th percentile, 1955–1965, type F............................ 88

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

rates compared with bioassay results, 84th percentile, 1991–2006, type F............................ 88

B-88 Predicted cesium bioassay results calculated using IMBA-derived cesium intake rates 

compared with bioassay results, 50th percentile, type F ........................................................ 89

B-89 Predicted cesium bioassay results calculated using IMBA-derived cesium intake rates 

compared with bioassay results, 84th percentile, type F ........................................................ 89

B-90 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 50th percentile, type M ........................................................ 90

B-91 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 84th percentile, type M........................................................ 90

B-92 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 50th percentile, type S ........................................................ 91

B-93 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 84th percentile, type S ........................................................ 91

B-94 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1972, type M.............................................. 92

B-95 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1973 through 1989, type M ........................ 92

B-96 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1972, type M.............................................. 92

B-97 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1973 through 1989, type M ........................ 93

B-98 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

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

B-99 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates

compared with bioassay results, 84th percentile, all intakes periods, type M.......................... 93
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 10 of 96

B-100 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1972, type S .............................................. 94

B-101 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1973 through 1989, type S......................... 94

B-102 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1972, type S .............................................. 95

B-103 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1973 through 1989, type S......................... 95

B-104 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, all intakes periods, type S .......................... 95

B-105 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, all intake periods, type S............................ 96
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 11 of 96

ACRONYMS AND ABBREVIATIONS 

cm centimeter

cpm counts per minute

d day

DOE U.S. Department of Energy

dpm disintegrations per minute

DU depleted uranium

EU enriched uranium

g gram

GSD geometric standard deviation

HPRED Health Protection Radiation Exposure Database

hr hour

IA Insufficient Amount

ICRP International Commission on Radiological Protection Publication

ID identification

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

keV kiloelectron-volt, 1,000 electron-volts

L liter

LIP Lost in Process

MDA minimum detectable activity

MFP mixed fission product

MFPG mixed fission product - gamma

mL milliliter

nCi nanocurie

NIOSH National Institute for Occupational Safety and Health

NOCTS NIOSH-Office of Compensation Analysis and Support Claims Tracking System

NT natural uranium

OPOS one-person, one-sample

ORAU Oak Ridge Associated Universities

pCi picocurie

QA quality assurance

ROI region of interest

SRS Savannah River Site

TIB technical information bulletin

U.S.C. United States Code
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 12 of 96

WBC whole-body count

μg microgram

μm micrometer

§ section or sections
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 13 of 96

1.0 INTRODUCTION

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 

historical 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.

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)].

ORAUT-OTIB-0019, Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAUT 

2005a) describes the general process NIOSH uses to analyze bioassay data for the assignment of 

doses to individuals based on coworker results. ORAUT-PLAN-0014, 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 Savannah River Site (SRS) for 1991 through 2007. 

For the period before 1991, SRS does not have an electronic database of bioassay results. For years 

before 1991, the bioassay data in the NIOSH-Office of Compensation Analysis and Support Claims 

Tracking System (NOCTS) for SRS employees was used to develop a representative database of 

coworker bioassay data using the guidance of ORAUT-OTIB-0075, Use of Claimant Datasets for 

Coworker Modeling (ORAUT 2009).

A statistical analysis of the data was performed according to ORAUT-OTIB-0019 (ORAUT 2005a) and 

its implementing procedure, ORAUT-PROC-0095, Generating Summary Statistics for Coworker 

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

Analysis (IMBA) computer software to obtain intake rates for the assignment of dose distributions.

2.0 PURPOSE

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 SRS for whom no or insufficient monitoring records exist.

Attributions and annotations, indicated by bracketed callouts and used to identify the source, 

justification, or clarification of the associated information, are presented in Section 6.0. 

3.0 DATA OVERVIEW

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

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

3.1 BIOASSAY DATA SELECTION

Bioassay results were obtained directly from SRS in the form of an electronic database for 1991 

through 2007. For the period before 1991, SRS does not have an electronic database of bioassay 

results. For years before 1991, the bioassay data in NOCTS for SRS employees were used to 
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develop a representative database of coworker bioassay data (ORAUT 2009). In addition, neptunium 

and americium urinalysis bioassay data were obtained from SRS laboratory notebooks (DuPont 

1961–1969, 1963–1970, 1969, 1969–1973, 1970–1973, 1973–1978, 1973–1979, 1978–1983, 1979–

1980, 1980–1981a,b, 1981–1986, 1986–1989).

3.1.1 NOCTS Urinalysis Data

NOCTS data were used for this coworker study in the absence of a database of usable data from 

SRS for the period before 1991 as the best available compilation of data in a usable (i.e., electronic 

spreadsheet or database) form. The NOCTS database was queried on May 7, 2008, to generate a 

list of all claimants who worked at SRS before 1991. This list identified 1,421 individuals. Data for six 

additional individuals that became available during the data entry process were added for a total of 

1,427 individuals. The NOCTS identification (ID) numbers of the specific individuals are listed in 

ORAUT (2011). The in vitro bioassay data for these individuals were entered in spreadsheets (some 

already existed in this form after the completion of dose reconstructions for those individuals) and 

subjected to a 100% verification review by a second person. 

Records with results or units of “LIP” (Lost In Process) or “IA” (Insufficient Amount) were excluded 

from the evaluation because those records represent instances in which samples were collected but 

not analyzed. Records with units of per-unit-volume were adjusted to “per-1.5L” based on an 

assumed 1.5 L/d of urinary excretion. Volumes greater than 1 L were assumed to represent a full 

day’s voiding and were not adjusted. Volumes less than or equal to 1 L were normalized to 1.5 L.

3.1.2 NOCTS Whole-Body Count Data

NOCTS whole-body count (WBC) data were used for 137Cs and 237Np analyses. WBC data were used 

for 237Np only for the period during which urinalysis data were not available (i.e., 1970 to 1989). The 

NOCTS ID numbers of the specific individuals identified are listed in ORAUT (2011).

Cesium-137 Data

Cesium-137 results in nanocuries are commonly reported for WBCs in the NOCTS data. Some of the 

results are reported as a positive value, an uncensored value, a “<” value, or “<MDA” with a quantified 

count-specific minimum detectable activity (MDA) provided. Depending on the WBC reporting format, 

the MDA at the 95% confidence level is also available.

Neptunium-237 Data 

Unlike 137Cs, most WBC reports in NOCTS do not quantify the 237Np body burdens or report an MDA 

in units of activity. However, some of the reporting methods provide sufficient information to 

determine or estimate the 237Np body burden. Methods were developed to estimate 237Np for three of 

the different reporting forms used. These methods use the fact that a region of interest (ROI) used to 

report activity for radionuclides other than 237Np would also be reporting activity from 237Np or its 

decay product, 233Pa. Protactinium-233 is assumed to be in equilibrium with 237Np for the basis of 

calculating chronic intakes with a minimum duration of 1 year. 

The first form, “Whole Body Counter Data,” was in use from approximately 1960 through the mid1970s and was used with the 40-cm arc geometry (Taylor et al. 1995, p. 64). Other than 137Cs and 

40K, the amounts of radionuclides present are not quantified in units of activity. The results are 

presented as net counts per minute (“net cpm”). This form reports activities for 131I based on the 

number of counts in the ROI from 300 to 400 keV. Protactinium-233 has several gammas that fall 

totally or partially in that energy range – 300 keV (6.6%), 312 keV (38.6%), 340 keV (4.5%), 375 keV 

(0.6%), and 399 keV (1.27%) (Kocher 1981). The 300- and 399-keV peaks would fall half out and half

in of the ROI, so in effect those abundances are only half of the stated values. Therefore, the total 

gamma abundance in the 300- to 400-keV ROI for 233Pa is 47.6%. It is possible to use the reported 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 15 of 96

net cpm for 131I to estimate the 237Np body burden by assuming that 233Pa is in equilibrium with 237Np. 

The conversion factor from net counts in the 131I ROI to nanocuries of 237Np is 0.243 nCi/cpm. This 

conversion factor was determined by adjusting the 137Cs calibration factor of 0.136 nCi/cpm (Watts

1962–1967, p. 33) for the gamma abundances of 137Cs and 233Pa in their respective ROIs: 

(0.136)(0.85) ÷ 0.476. To refine the estimate, it is necessary to account for the Compton continuum 

contribution to the 131I ROI from the 40K body burden. The 40K contribution to the 131I ROI is 0.389 

count per 40K ROI net count (Watts 1962, p. 33). Therefore, the 237Np body burden can be calculated 

as: 

 0.243 ( ) 0.389 ( ) 237 131 40 nCi Np =× −×   I net cpm K net cpm   (3-1)

The second reporting form is untitled and was used in the mid- and late 1970s. It is distinguishable by 

having the date, time, and name on successive lines on the left margin at the top. This form reports 

counts in the 300-to-400-keV ROI but does not associate this ROI with a particular radionuclide. For 

each ROI, gross, background, net, “CALC,” and “DIFF” values are reported. The CALC and DIFF 

values correct the net counts to account for Compton scatter, with the CALC value being the Compton 

scatter contribution and the DIFF value being the net counts minus CALC. Therefore, when using 

these data, there is no need to apply a 40K Compton scatter as with the “Whole-Body Counter Data” 

form. When the 40-cm arc geometry was being used, assumed to be in the period before February 

1974, the 237Np body burden can be calculated as:

0.243 ( ) 237 nCi Np DIFF counts for 300 - to 400 - keV ROI = × (3-2)

After January 1974, when the stretcher geometry was in use, the conversion factor changes (Fleming 

1973–1979, p. 162) and the 237Np body burden can be calculated as:

0.0125 ( ) 237 nCi Np = × DIFF counts for 300 - to 400 - keV ROI (3-3)

The third reporting form is the “In-Vivo Count Results” form, which was in use from the late 1970s 

through the late 1980s. The ROI on this form applicable to determining 237Np is the 51Cr ROI covering 

the energy range from 290 to 349 keV. This form also reports DIFF values. In addition to the DIFF 

value, it reports the MDA in units of both nanocuries and counts. Having the MDA reported in both 

units permits the determination of a count-specific conversion factor from counts to nanocuries. The 

remaining step is the ratio of the conversion factor for 51Cr to that for 233Pa, which is 0.211 (based on 

the ratio of gamma abundances in the 51Cr ROI: 0.098 to 0.465). The 0.469 abundance is based on 

100% of the 312-keV gamma at 38.6% abundance, 95% of the 340-keV gamma at 4.5% abundance, 

and 55% of the 300-keV gamma at 6.6% abundance. Percentages are reduced from 100% to 

account for the fact that a portion of the gamma peak is outside of the region of interest. Therefore, 

the 237Np body burden can be calculated as:

0.211 ( ) ( ) ( ) 237 51 51 51 nCi Np =× × ÷ Cr DIFF counts Cr MDA nCi Cr MDA counts (3-4)

3.1.3 Health Protection Radiation Exposure Database

In vitro data for 1991 through 2007 were obtained from the SRS Health Protection Radiation Exposure 

Database (HPRED) in the form of a text file named “NIOSH_SRS.txt.” Review of the file revealed that 

it was in a fixed-width format. The text file was imported into a database according to the convention 

in Table 3-1. In a few instances, the field widths varied, which resulted in the first character of the 

“result” field at the end of the “isotope” field. The instances were manually corrected.
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Table 3-1. SRS HPRED data import format. 

No. Field title Start Field width Field type

1 OUO 1 18 Text

2 SSN 19 10 Long integer

3 Sort date 29 11 Text

4 Sort time 40 10 Text

5 Isotope 50 10 Text

6 Result 60 7 Double

7 Units 67 11 Text

8 Type 78 21 Text

9 Date received 99 11 Text

10 Time received 110 10 Text

11 Date added 120 11 Text

12 Time added 131 10 Text

13 Batch 141 10 Text

14 Sample # 151 7 Text

15 Activity 158 10 Text

16 Critical level 168 10 Text

17 Error 178 13 Text

From these data, the following records were excluded from further analysis:

• “Type” = “baseline”

• “Type” = “fecal” or any variation of the word fecal

• “Units” = “IA” but not “IA followup”

• “Type” = “QC”

Additional evaluation of the data resulted in modification as follows:

• If the “Sort date” field was blank or before January 1, 1990, the “Date received” was used 

instead.

• If the “Activity” field was blank, the “Result” field was used instead. Further, if the “Result” was 

positive (i.e., greater than zero), it was used as is; if the “Result” was negative, it was assumed 

to be a less-than value (i.e., “-1.5” was assumed to be “<1.5”) [1]. 

• Values with units of “per sample” were assumed to represent 24-hour samples.

• Records with units of per-unit-volume were adjusted to “per-1.5L” based on an assumed 

1.5 L/d for urinary excretion.

3.1.4 Neptunium Logbook Data

Neptunium urinalysis bioassay data were obtained from SRS laboratory notebooks (DuPont 1961–

1969, 1969) and from NOCTS records for years after 1969. The laboratory notebook data were 

transferred to a spreadsheet and subjected to a 100% verification review by a second person. 

Records with results or units of LIP or IA were excluded from the evaluation because those records 

represent instances in which samples were collected but not analyzed. It was assumed that all 

records are in units of dpm/1.5L. Many records were only partially legible, but contained enough 

information to infer the results; in particular, data indicated as “<0.0X” or “<0.XX” was assumed to be 

“<0.05”, a common reporting level. Similarly, results indicated as “<1” due to an illegible decimal 

place were changed to “<0.1,” the actual reporting level for the period.
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3.1.5 Americium Logbook Data

The americium data from the logbooks were transferred to a spreadsheet and subjected to a quality 

assurance (QA) verification in accordance with MIL-STD-105E, Sampling Procedures and Tables for 

Inspection by Attributes (DOD 1989). A total of 315 out of 17,449 records were randomly picked and 

reviewed for accuracy of the data transcription. The first round of verification identified generic issues, 

which were corrected; a second round of verification indicated an acceptable error rate. In the second 

round, 15 errors were identified, 7 of which were classified as critical errors (i.e., errors that would 

affect subsequent data analysis). Seven errors of a sample of 315 records equates to a 1% error rate 

in the full data set. Per MIL-STD-105E, for a lot between 10,001 and 35,000 items, fewer than 8 

errors results in lot acceptance based on the statistical variability of sampling. The errors that were 

identified during the QA process were corrected. In addition, other errors were discovered during 

subsequent statistical analyses of the data, usually as a result of identification of outliers in the 

dataset. The most common error was omission of the decimal due to legibility issues, resulting in 

higher than actual bioassay results. These corrections were made and documented before further 

analysis.

A single americium urine sample was commonly counted multiple times, usually twice but as many as

10 times was noted. The data in the logbooks consisted of one or more count rate results for each 

urine sample in units of dpm per disc, depending on how many times a sample was counted (this 

information was not used) and count-specific results in units of net dpm/1.5 L (this information was 

used). Further, a reported value for each sample, also in units of dpm/1.5 L, was usually provided. 

The result in dpm/1.5 L for each count of a sample was generally recorded as an uncensored value 

(i.e., the calculated result was recorded regardless of its value). In contrast, the “reported” values 

were generally censored (i.e., results less than some level, typically the detection or reporting limit 

were reported as a less-than result). Some dpm/1.5 L data that were less than zero were reported as 

zero.

Not all sample records included all this information, and in some instances the count-specific results 

were censored. If count-specific results were available, the valid results were averaged by the Oak 

Ridge Associated Universities (ORAU) Team to determine the sample result. This value was 

generally uncensored. If count-specific results were not available, the reported values were used, 

many of which were censored. Excluded samples included those marked as LIP, those marked 

“DTPA” to indicate chelation, or those that lacked sufficient identifying information (e.g., sample date 

or worker ID number).

Three sample results were excluded as false positives because the subsequent samples had no 

detected activity. In addition, all results for three individuals were excluded for an entire year due to 

an ingestion intake, a plutonium wound intake, and an incident that resulted in the highest assigned 

intake of 244Cm in the history of SRS. These incidents and intakes were characterized by an 

extremely high number of bioassay results, many of which were orders of magnitude higher than the 

bioassay data for other individuals and were considered unrepresentative of the potential exposure to 

an unmonitored worker.

3.2 ANALYSIS

Bioassay data were analyzed by year or multiyear span, depending 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 the data were log-transformed, the 50th and 84th 

percentiles were determined for each period through the use of the method described in ORAUTOTIB-0019 (ORAUT 2005a). 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. 
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In ORAUT-OTIB-0075 (ORAUT 2009), arguments are presented to support the practice of treating a 

claimant dataset as a simple random sample from the population of all monitored workers. One 

potential problem posed by using a claimant dataset is that workers who were involved in incidents 

usually submit more samples than workers who submit only routine (non-incident-related) samples. 

This is problematic because a small number of workers who were involved in incidents can dominate 

the claimant sample in a given year through the sheer number of submitted samples and because the 

samples in the dataset are no longer independent of each other. At SRS, the small population of 

workers subject to bioassay testing results in a similar problem. To compensate for the unequal 

number of samples submitted by workers, the “one-person, one-sample” (OPOS) technique was 

used, in which only one result was used for each person for each radionuclide for a given year. The 

OPOS statistic is calculated using the maximum possible mean methodology of ORAUT-RPRT-0053, 

Analysis of Stratified Coworker Datasets (ORAUT 2012).

3.3 TRITIUM

Claimant tritium urine bioassay data for 1954 to 1990 were obtained from the NOCTS dataset. This 

dataset contained 260,607 bioassay results for samples submitted by 1,520 workers between 1954 

and 1990. Tritium urine bioassay data for all workers from 1991 to 2007 were obtained from the 

HPRED dataset. This dataset contained 881,561 bioassay results for samples submitted by 21,320 

workers between 1991 and 2007. All bioassay results were reported in units of microcuries per liter.

3.4 PLUTONIUM

3.4.1 NOCTS-Based Analysis

NOCTS data were used for 1955 through 1990. Records with an isotope type identified in the “Pu” 

column of Table A-1 in Attachment A were tagged as plutonium data and used for this analysis. 

Records reporting gross plutonium results were assumed to be in units of dpm/1.5 L if no units were 

provided based on an examination of contemporaneous records. Isotope-specific results without units 

were assumed to be in units of dpm/1.0 L for the same reason. When isotopic data were reported, 

only the 239Pu measurements were used and were corrected to be plutonium gross alpha equivalent

assuming at 12% (fuel-grade) 10-year-aged plutonium mixture. Any records with mass units or in 

units of nanocuries or microcuries were assumed to be fecal samples and were excluded. Records 

within 60 days of chelation for an individual were also excluded.

3.4.2 HPRED-Based Analysis

HPRED was used for 1991 through 2007. HPRED records with an isotope type identified in the “Pu” 

column of Table A-2 in Attachment A were tagged as plutonium data and used for this analysis. Only 

the 239Pu measurements were used. The results were converted to plutonium gross alpha data 

assuming a 12% (fuel-grade) 10-year-aged plutonium mixture for intake modeling.

3.5 URANIUM

3.5.1 NOCTS-Based Analysis

In the NOCTS data, uranium urinalysis results are recorded in units of both mass (micrograms) and 

activity (disintegrations per minute). For the coworker study, the mass-based measurements were 

converted to equivalent activity assuming natural uranium (0.683 pCi/g) through 1967 and depleted 

uranium (DU; 0.372 pCi/g) thereafter and merged with the activity-based data before statistical 

analysis. Records with an isotope type identified in the “U (all)” column of Table A-1 in Attachment A 

were tagged as uranium data and used for this analysis. Assumptions used to provide missing units 

and volumes were based on an examination of contemporaneous records: 
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• Designation of missing units:

If the results field was “<5”, mass (μg) units were assumed

If the results field was “<1”, activity (dpm) units were assumed

If the results field was not “<5” or “<1”, 

– Activity (dpm) units were assumed if the Isotope = 

 EU (enriched uranium)

 Eu

 U234

 U235

 U238

– Otherwise mass (micrograms) units were assumed

• Assembly of mass data:

From the above selected records, records with mass units were selected, including:

– ug/L 

– μg/L

– ug/1.5L

– μg/1.5L

– ?g/L

– ?g/1.5L

– Those assigned mass units in the previous step 

From start of data through July 10, 1961, results were assumed to be “per liter” and converted 

to “per 1.5 liter” regardless of stated volume.

From July 11, 1961, through December 31, 1990, all results were assumed to be “per 1.5 liter” 

regardless of stated volume.

• Assembly of activity data:

Records with activity units were selected, including:

– dpm/ 1.5 L

– dpm/1.5L

– dpm/1.5l

– dpm/750ml

– dpm/L

– Records with missing units assigned activity units (A volume of 1.5 L was assumed for 

these records.)

3.5.2 HPRED-Based Analysis

HPRED was used for 1991 through 2007. HPRED records with an isotope type identified in the “U” 

column of Table A-2 in Attachment A were tagged as uranium data and used for this analysis. For 

mass-based uranium measurements, the specific activity of depleted uranium (0.372 pCi/g) was 

assumed based on ORAUT-TKBS-0003, Savannah River Site (ORAUT 2005b). If isotopic data were 

reported, the 234U, 235U, and 238U results for the same person (“SSN” field) and date (using “Sort date” 

or “Date received” per the above instructions) were summed to yield a gross uranium activity. If all 

three measurements were based on the “Result” field rather than the “Activity” field and were negative 

(i.e., <MDA measurements), the sum was treated as a <MDA measurement; otherwise, it was treated 

as a real measurement. Nonisotopic measurements [EU, (NT)/DU] were assumed to represent all 

uranium present.
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3.6 AMERICIUM, CURIUM, AND CALIFORNIUM

Bioassay techniques for americium, curium, and californium varied as a function of time at SRS. Of 

the techniques SRS used, the most significant feature is that differentiation between americium, 

curium, and californium was not possible until the use of alpha spectroscopy began in 1995. Before 

1995, regardless of the notation placed in an individual’s bioassay record, the analytical technique 

was the same. Therefore, americium, curium, and californium bioassay data are considered 

collectively before 1995 to determine excretion rates although separate intake rates are calculated. 

Beginning in 1995, each radionuclide was evaluated separately. 

3.6.1 Logbook-Based Analysis

Americium logbook data were used for 1966 through 1989. Records reporting gross americium/

curium/californium results were assumed to be in units of dpm/1.5 L if no units were provided, based 

on an examination of contemporaneous records. Records with units of “per unit mass” were assumed 

to be fecal samples and excluded.

Examination of the data revealed occasions during which individuals were involved in incidents that 

resulted in large intakes and excretions. These data were judged to be unrepresentative of coworkers 

and were removed. The incidents were:

• One individual was involved in an incident on March 9, 1970. This person’s bioassay data 

were excluded for the remainder of 1970.

• One individual was involved in an incident on March 16, 1972. This person’s bioassay data 

were excluded for the remainder of 1972.

• One individual had a plutonium wound intake on May 8, 1986, which affected the americium 

bioassay results. This person’s bioassay data were excluded for the remainder of 1986.

• Three individuals had false positive results, which were excluded.

3.6.2 HPRED-Based Analysis

HPRED data were used for 1991 through 2007. HPRED records with an isotope type identified in the 

“AmCmCf” column of Table A-2 in Attachment A were tagged as americium/curium/californium data 

and used for this analysis for 1991 through 1994. Beginning in 1995, each radionuclide was 

evaluated separately based on the isotope types identified in the “Am,” “Cm,” and “Cf” columns of 

Table A-2 and tagged as americium, curium, and californium, respectively. 

3.7 NEPTUNIUM

For neptunium, the NOCTS urinalysis data contained insufficient data for a coworker model for the 

period before the era for which HPRED data were available. However, bioassay laboratory logbook 

data were found that provided results for 1961 through 1969 (DuPont 1961–1969, 1969). These data 

were assumed to be a complete dataset for this period. 

NOCTS WBC data were used for 1970 through 1989.

For 1991 through 2007, HPRED data were used in the normal manner. HPRED records with an 

isotope type identified in the “Np” column of Table A-2 in Attachment A were tagged as neptunium 

data and used for this analysis for 1991 through 2007. 
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3.8 FISSION AND ACTIVATION PRODUCTS

Fission and activation products are evaluated in accordance with ORAUT-RPRT-0047, Assignment of

Fission and Activation Product Radionuclides for Non-Specific Bioassays at Savannah River Site – 

Comparison of Methods (ORAUT 2013a) or subsequent revisions, using either 90Sr or 137Cs as the 

indicator radionuclide. The indicator radionuclide to be used varies as a function of time based on the 

available data. For the period before 1991, urinalysis bioassay of beta-emitting radionuclides was 

available for 1955 through 1965 and of gamma-emitting radionuclides for 1966 through 1989, referred 

to as mixed fission product (MFP) and mixed fission product - gamma (MFPG) data respectively. 

WBC results for 137Cs were also available in this period. Starting in 1991, 90Sr-specific urinalysis 

results from the HPRED data were available and were used as the preferred indicator radionuclide.

3.8.1 Strontium

NOCTS data were used for 1955 through 1965. Records with an isotope type identified in the “MFP” 

column of Table A-1 in Attachment A were tagged as MFP data and used for this analysis. If no units 

or sample volume were provided, results were assumed to be in units of dpm/750 mL for 1955 

through 1959. For 1960 through 1965, the units were assumed to be dpm/500 mL if the result was 

“<30” or “<50” and dpm/1.5 L if the result was “<100,” “<60,” or positive. 

HPRED data were used for 1991 and after. HPRED records with an isotope type identified in the “Sr” 

column of Table A-2 in Attachment A were tagged as strontium data and used for this analysis for 

1991 through 2006.

3.8.2 Cesium-137

Cesium-137 was evaluated only for the period from 1961 through 1989 based on WBC data. For 

1990, a limited amount of 137Cs data was available due to a change in WBC methods, equipment, and 

reporting formats (use of the ABACOS system). The available data in a usable format for 1990 were 

inconsistent with the data for 1989 and potentially biased and were, therefore, not used. Uncensored 

data were used as is. Censored data or records for which an MDA but no result was provided were 

used as count-specific censoring levels. The MFPG data was evaluated but determined to be less 

sensitive than the WBC data and therefore was not used for this coworker study. Any contribution of 

fallout to 137Cs whole-body burdens and calculated intake rates was ignored. After 1990, 90Sr based 

on HPRED data was used to evaluate the intake of MFP. 

3.8.3 Cobalt-60

Cobalt-60 was evaluated for 1955 through 1970. During this period, some workers handled pure or 

relatively pure 60Co. The bioassay method used to monitor intakes from this work was MFP and 

MFPG analysis.

Cobalt-60 data were available in the form of MFP data for 1955 through 1965 and in the form of 

MFPG data from 1966 through 1970. Records with an isotope type identified in the “MFP” column of 

Table A-1 in Attachment A were tagged as MFP data and used for this analysis for 1955 through 

1965. If no units or sample volume were provided, results were assumed to be in units of 

dpm/750 mL for 1955 through 1959. For 1960 through 1965, the units were assumed to be 

dpm/500 mL if the result was “<30” or “<50” and dpm/1.5 L if the result was “<100,” “<60,” or positive.

Records with an isotope type identified in the “MFPG” column of Table A-1 in Attachment A were 

tagged as MFPG data and used for this analysis for 1966 through 1970. All records were assumed to 

be in units of nCi/1.5 L. In addition, records with an isotope type identified in the “MFP” column of 

Table A-1 for 1966 through 1970 were tagged as MFPG data if the recorded units were nCi/1.5 L, or if 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 22 of 96

there were no units given and the result was less than 30 and “FPIA Beta” was not recorded in the 

“Isotope” field. All the MFPG data were divided by 2 to account for the fact that 60Co has two strong 

gamma rays emitted per disintegration.

3.9 THORIUM

The separation technique SRS used for americium, curium, and californium before 1990 also 

captured thorium (NIOSH 2012; Butler and Hall 1970; Taylor et al 1995). Therefore, the americium, 

curium, and californium bioassay data discussed above in Section 3.6.1 was also used to model 

thorium intakes for 1972 through 1989.

4.0 INTAKE MODELING 

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

4.1 ASSUMPTIONS

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

uniform absolute error of 1 was applied to all results, thereby assigning the same weight to each 

result. The IMBA program requires results to be in units of activity per day; therefore, all urinalysis 

results were normalized as needed to 24-hour samples using 1,500 mL (the volume of urine assumed 

by SRS to be excreted in a 24-hour period).

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

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

chronic and 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

IMBA was used to fit the bioassay results to a series of inhalation intakes. Data from 1953 through 

2007 were fit as a series of chronic intakes. The intake assumptions were based on observed 

patterns 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 1953 through 2007 were divided independently into multiple chronic intake periods for 

each radionuclide.

4.3 TRITIUM

Tritium was evaluated differently than the other radionuclides in this coworker study. The OPOS 

methodology was not used. For tritium, the protocol 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:
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 23 of 96

• If there was a single urine sample in a calendar year and it was a nondetect, that result was 

excluded from the analysis because this was assumed to not be part of routine monitoring.

• Samples on the same date were ordered from lowest to highest. 

• All dose was assigned as if it occurred on the bioassay date. 

• 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 after a 

sample.

• Type 2 calculations were performed in all other situations.

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

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

] determined from a linear regression. 

Individuals that received less than 0.001 rem at three significant digits (i.e., less than 0.0005 rem), 

were excluded from the statistical analysis. The plotting positions were calculated with i/n – 1/(2n) 

convention specified in ORAUT-PROC-0095 (ORAUT 2006). Doses for 1954 to 1990 were calculated 

from the NOCTS dataset, which is considered a random sample of the complete dataset (ORAUT 

2009). Doses for 1991 to 2001 were calculated from the HPRED dataset, which is considered a 

complete dataset.

4.4 PLUTONIUM

Because the plutonium isotopes at SRS 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 SRS for relatively short periods, each chronic 

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

and S solubilities. This method resulted 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 or red in the figures in 

Attachment B; included results are shown in dark gray or blue. The results of the plutonium statistical 

analysis that was used to calculate the intakes are provided in Table A-3.

Plutonium Type M: The solid lines in Figures B-1 to B-4 in Attachment B show the individual fits to 

the 50th- and 84th-percentile excretion rates for type M materials. Figures B-5 and B-6 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 GSDs determined from the 

plutonium urinalysis. 

Plutonium Type S: The solid lines in Figures B-7 to B-10 in Attachment B show the individual fits to 

the 50th- and 84th-percentile excretion rates for type S materials. The same intake periods were 

applied for both percentiles because the values followed a similar pattern. Figures B-11 and B-12 

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 GSDs determined 

from the plutonium urinalysis. 

4.5 URANIUM

Because the uranium isotopes at SRS have very long radiological half-lives, and because the material 

is retained in the body for long periods for type S solubility, excretion results are not independent. For 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 24 of 96

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 SRS 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 resulted 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 or red in the figures in 

Attachment B; included results are shown in dark gray or blue. For type M and F solubility, this 

approach was not used. 

The 50th-percentile result for 1989 was excluded from the intake modeling due to the abnormally low 

result for that year in comparison with contemporaneous years. This action results in a slight increase 

in the calculated intake rate. The results of the uranium statistical analysis that were used to calculate 

the intakes are provided in Table A-4.

Uranium Type F: The solid lines in Figures B-13 and B-14 in Attachment B show the fit to the 50thand 84th-percentile excretion rates, respectively, for type F materials. Table B-3 lists the 50th- and 

84th-percentile intake rates along with the associated GSDs from the uranium urinalysis. 

Uranium Type M: The solid lines in Figures B-15 and B-16 in Attachment B show the fit to the 50thand 84th-percentile excretion rates, respectively, for type M materials. Table B-4 lists the 50th- and 

84th-percentile intake rates along with the associated GSDs from the uranium urinalysis. 

Uranium Type S: The solid lines in Figures B-17 to B-32 in Attachment B show the individual fits to 

the 50th- and 84th-percentile excretion rates for type S materials. The same intake periods were 

applied for both percentiles because the values followed a similar pattern. Figures B-33 and B-34 

show the 50th- and 84th-percentile predicted excretion rates, respectively, from all type S intakes. 

Table B-5 lists the 50th- and 84th-percentile intake rates along with the associated GSDs from the 

uranium urinalysis. 

4.6 AMERICIUM, CURIUM, AND CALIFORNIUM

As for plutonium, americium, curium, and californium intake periods were independently fit using only 

the bioassay results from the single intake period. This method resulted 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 or 

red in the figures in Attachment B; included results are shown in dark gray or blue. The results of the 

statistical analysis that was used to calculate the intakes are provided for americium in Table A-5, 

curium in Table A-6, and californium in Table A-7.

Americium Type M: The solid lines in Figures B-35 to B-42 in Attachment B show the individual fits 

to the 50th- and 84th-percentile excretion rates for type M materials. Figures B-43 and B-44 show the 

50th- and 84th-percentile predicted excretion rates, respectively, from all type M intakes. Table B-6 

lists the 50th- and 84th-percentile intake rates along with the associated GSDs from the americium 

urinalysis. 

Curium Type M: The solid lines in Figures B-45 to B-52 in Attachment B show the individual fits to 

the 50th- and 84th-percentile excretion rates for type M materials. Figures B-53 and B-54 show the fit 

to the 50th- and 84th-percentile excretion rates, respectively, for type M materials. Table B-7 lists the 

50th- and 84th-percentile intake rates along with the associated GSDs from the curium urinalysis. 

Californium Type M: The solid lines in Figures B-55 to B-62 in Attachment B show the individual fits 

to the 50th- and 84th-percentile excretion rates for type M materials. Figures B-63 and B-64 show the 

fit to the 50th- and 84th-percentile excretion rates, respectively, for type M materials. Table B-8 lists 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 25 of 96

the 50th- and 84th-percentile intake rates along with the associated GSDs from the californium

urinalysis. 

4.7 NEPTUNIUM

As for plutonium, neptunium intake periods were independently fit using only the bioassay results from 

the single intake period. This method resulted 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 or red in the 

figures in Attachment B; included results are shown in dark gray or blue. The results of the neptunium 

statistical analysis that was used to calculate the intakes are provided in Tables A-8 and A-9. The 

intake rate for 1989 was extrapolated to 1990 as a measure that is favorable to claimants. 

The solid lines in Figures B-65 to B-79 in Attachment B show the individual fits to the 50th- and 84thpercentile excretion rates for 1961 through 1989 and the combined fit for 1991 to 2007. The solid 

lines in Figures B-80 to B-83 show the 50th- and 84th-percentile predicted excretion rates, 

respectively, from all type M intakes. Table B-9 lists the 50th- and 84th-percentile intake rates along 

with the associated GSDs from the neptunium urinalysis for all years.

4.8 STRONTIUM

Strontium data, in the form of MFP data, were available for 1955 through 1965 and as 90Sr data for 

1991 through 2007. No strontium data were available for 1966 through 1990. These two periods 

were fit independently. The results of the strontium statistical analysis that was used to calculate the 

intakes are provided in Table A-10. The solid lines in Figures B-84 through B-87 in Attachment B 

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

strontium. Table B-10 lists the 50th- and 84th-percentile intake rates along with the associated GSDs 

from the strontium urinalysis. Because it was inconsistent with the contemporaneous results, 1996 

was excluded from the fit. This results in a higher intake being assigned for 1996, which is favorable 

to the claimant. 

4.9 CESIUM-137

The solid lines in Figures B-88 and B-89 in Attachment B show the fits to the 50th- and 84th-percentile 

whole-body burdens, respectively, for type F materials. Table B-11 lists the 50th- and 84th-percentile 

intake rates along with the associated GSDs from the 137Cs WBCs. The results of the cesium 

statistical analysis that was used to calculate the intakes are provided in Table A-11.

4.10 COBALT-60

The solid lines in Figures B-90 and B-91 in Attachment B show the fits to the 50th- and 84th-percentile 

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

intake rates along with the associated GSDs from the 60Co type M excretion rates. The solid lines in 

Figures B-92 and B-93 in Attachment B show the fits to the 50th- and 84th-percentile excretion rates, 

respectively, for type S materials. Table B-13 lists the 50th- and 84th-percentile intake rates along 

with the associated GSDs from the 60Co type S excretion rates. The results of the cobalt statistical 

analysis that was used to calculate the intakes are provided in Table A-12. 

4.11 THORIUM

Thorium intake periods were fit in the same manner as americium with the exception that both 

solubility types M and S were evaluated. Intake periods were independently fit using only the 

bioassay results from the single intake period. This method resulted in an overestimate of intakes for 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 26 of 96

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 or 

red in the figures in Attachment B; included results are shown in dark gray or blue. The results of the 

americium statistical analysis that was used to calculate the thorium intakes are provided in Table A5.

Thorium Type M: The solid lines in Figures B-94 to B-97 in Attachment B show the individual fits to 

the 50th- and 84th-percentile excretion rates for type M materials. Figures B-98 and B-99 show the 

50th- and 84th-percentile predicted excretion rates, respectively, from all type M intakes. Table B-14 

lists the 50th- and 84th-percentile intake rates along with the associated GSDs from the thorium 

urinalysis. 

Thorium Type S: The solid lines in Figures B-100 to B-103 in Attachment B show the fit to the 50thand 84th-percentile excretion rates for type S materials, respectively. Figures B-104 and B-105 show 

the 50th- and 84th-percentile predicted excretion rates, respectively, from all type S intakes. 

Table B-15 lists the 50th- and 84th-percentile intake rates along with the associated GSDs from the 

thorium urinalysis. 

5.0 ASSIGNMENT OF INTAKES AND DOSES

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

calculation of doses to individuals from bioassay data, a minimum 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 intake 

period. The GSDs for different intake periods were conservatively adjusted for consistency between 

intake periods for calculational efficiency. The 95th-percentile values were based on the adjusted 

GSD for the intake period. The original GSDs are provided in the Attachment B tables for each 

element. For input into the Interactive RadioEpidemiological Program (IREP), dose reconstructors 

should use the adjusted GSDs in the tables in Section 5.0 when assigning the 50th-percentile intakes. 

For cases in which there is justification that the individual might have had larger intakes than the 50thpercentile intake rates, dose reconstructors should use the 95th-percentile intake rates input into 

IREP as a constant.

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

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

used is provided. Coworker intakes should be assigned for radionuclides that could have been 

present at the worker’s location and for which the worker was not monitored. Table 5-1 lists the 

radionuclides potentially present at various SRS facilities or to which a worker who was assigned to a 

particular facility might have been exposed. Most radionuclides apply to the entire duration of the 

facility’s existence; a few radionuclides apply to limited periods as noted in the table (ORAUT 2013b). 

The dosimeter codes applicable to various time periods are included to assist with determining a 

worker’s work location. 

Table 5-1. Radionuclides of concern potentially present at SRS facilities. 

Building/facility Dosimeter 

Codes 1961-

1972

Dosimeter 

Codes 1973-

1990

Dosimeter 

Codes 

1991-2003 

Dosimeter 

Codes 

2004-

present

Radionuclides of concern

Reactors (R, P, 

L, K, C)

7A, 8A, 9A, 

10A, 11A, 

1C through 6C, 

1K, 1P, 1L, 1R

C01, C02, 

C03, K01, 

L01, P01 

LLL, NMM, 

SDDa Tritium, fission products

F-Area unknown 1A 1F through 5F, F, F01 235, CLB, Plutonium mixture, uranium, 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 27 of 96

Building/facility Dosimeter 

Codes 1961-

1972

Dosimeter 

Codes 1973-

1990

Dosimeter 

Codes 

1991-2003 

Dosimeter 

Codes 

2004-

present

Radionuclides of concern

facility 7F through 9F through F05, 

F07 through 

F09

FBL, FCA americium, neptunium, fission 

products

F-Area A-Line 1A See F canyon See F 

canyon

FCA Uranium

221-F B-Line 

(FB and JB 

lines)

1A 1F through 5F, 

7F through 9F

F, F01 

through F05, 

F07 through 

F09

FBL Plutonium mixture, americium

221-F Canyon 1A 1F through 5F, 

7F through 9F

F, F01 

through F05, 

F07 through 

F09

FBL, FCA, Plutonium mixture, uranium, 

fission products, thorium 

(through 1966), neptunium

F-Area Outside 

Facilities

1B 9F F09 FCA Plutonium mixture, uranium, 

fission products

PuFF and PEF 

(235-F)

1A 5F, 8F F05, F08 235 Plutonium mixture, 

americium, neptunium, 

thorium

235-F Vaults 1A 2F, 5F, 8F 2F, F05, F08 235 Plutonium mixture, uranium, 

neptunium, americium, 

curium, thorium

772-F and 772-

1F Laboratories

1A 1Ab A01 CLB Plutonium mixture, uranium, 

fission products, americium, 

tritium, neptunium

F/H Tank 

Farms, Effluent 

Treatment 

Facility (ETF), 

Cooling Water 

and Retention 

Basins

5F, 5H F05, H05 ETP, FTF Plutonium mixture, uranium, 

fission products, americium, 

neptunium

H-Area unknown 

facility

2A 1H through 6H H01 through 

H06

299, HBL, 

HCA

Tritium, plutonium mixture, 

uranium, americium, fission 

products, neptunium

HB Line Facility 2A 6H H06 HBL Plutonium mixture, fission 

products, americium,

neptunium, uraniumd 

H-Canyon and 

A-Line

2A 1H, 2H, 5H, 6H H, H01, H02, 

H05, H06

HCA Plutonium mixture, uranium, 

fission products, neptunium

221-H Area 

Outside 

Facilities

2A 9H H09 HCA Tritium, plutonium mixture, 

uranium, fission products,

neptunium

232-H, HANM, 

HAOM, Tritium 

complex

6F, 4H F06, H04, T TEF, TRI Tritium

300 M-Area, M 

area unknown 

facility

3A 3M M03 SDDa Uranium, thorium, plutonium 

mixture, neptunium, 

americium, curium (1964-65)

704-U, 704-B 1U, 6E, 7G U, U01, E06, 

G07

No active 

codes

Fission products
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 28 of 96

Building/facility Dosimeter 

Codes 1961-

1972

Dosimeter 

Codes 1973-

1990

Dosimeter 

Codes 

1991-2003 

Dosimeter 

Codes 

2004-

present

Radionuclides of concern

723-A, 773-A 5A, 6N 1A, 5A A01, A02, 

A05, 

SRTC Plutonium mixture, 

americium, curium, 

californium, thorium (October 

1972 and after), uranium, 

neptunium, fission products, 

tritium

735-A and 735-

11A

6F 5D A02, A03, 

A09, A16, 

B01

SRTC 

(apply 773-

A intakes)

Environmental radionuclides, 

neptunium (1962)

776-A 1A, 15A A01, A15 SRTC 

(apply 773-

A intakes)

Plutonium mixture, 

americium, curium, 

californium, thorium, uranium, 

neptunium (1961–1988), 

fission products, tritium

777-M 5B 5B A33 No active 

codes

Uranium, fission products, 

neptunium (through 1984)

CMX and TNX 5C 5C T01 No active 

codes

Uranium

Central shops & 

Maintenance, 

Pittsburgh 

Testing 

Laboratory

6C, 6H, 6I, 6M, 

6N, 6R, 12D, 

12E, 12I

5J, 5W, 

6B,6W, 7A, 7B, 

7G, 7I, 7J, 7K, 

7L, 7M, 7N,

7R, 7Q, 7W, 

8A through 8C, 

8H, through 

8M, 8P, 8S, 

8T, 1N

A12, A24, 

A25, A26, 

A27, A29, 

A34, J01, 

through J08, 

J12 through 

41

No active 

codes

Plutonium mixture, uranium, 

fission products, tritium, 

americium, curium, 

neptunium, thorium

D-Area 4A 1D, 4D D, D01, D04 SDD Tritium

E-Area Solid 

Waste Disposal 

Facility (SWDF)

12A 12B, 4F, 3G, 

8G

B12, G03, 

F04

SSS Tritium, plutonium mixture, 

fission products, neptunium

New Special 

Recovery

See H-Area 

unknown 

facility

See H-Area 

unknown 

facility

MPF Plutonium mixture, 

americium, uranium

Plutonium 

Storage Facility 

(PSF)

See H-Area 

unknown 

facility

See H-Area 

unknown 

facility

MPF Plutonium mixture, 

americium, uranium

Receiving Basin 

for Off-Site Fuel 

(RBOF) 

See H-Area 

unknown 

facility

See H-Area 

unknown 

facility

See H-Area 

unknown 

facility

RBO Plutonium mixture

Resin 

Regeneration 

Facility (RRF)

See H-Area 

unknown 

facility

See H-Area 

unknown 

facility

RBO Fission products

S-Area DWPF 1S, 2S, 1W, 

2W

S01, S02 SWM Plutonium mixture, fission 

products

Waste 

Certification 

Facility

3G G03 SSS Tritium, plutonium mixture, 

fission products

Z-Area 2Z Z02 ZZZ Tritium, fission products, 

plutonium mixture, all 

transuranic elements
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 29 of 96

Building/facility Dosimeter 

Codes 1961-

1972

Dosimeter 

Codes 1973-

1990

Dosimeter 

Codes 

1991-2003 

Dosimeter 

Codes 

2004-

present

Radionuclides of concern

Not identifiable 

or unknownc 

7Y, 8D, 8E, 

000, missing

R01, Y01, 

missing

Blank, any 

code not 

already 

listed

Plutonium mixture, uranium, 

fission products, tritium, 

americium, curium, 

californium, neptunium, 

thorium

Note: Any code with X should not be included. These indicate off plant assignment.

a. Code SDD is used both for the reactors and 300-M area. If no other information regarding work location is available, the

applicable radionuclides for both locations should be assigned.

b. Code 1A is used for both 772 and 773 prior to 1991. If no other information regarding work location is available, the 

applicable radionuclides for both locations should be assigned.

c. Unknown facility radionuclides should only be assigned if no information is available from any source regarding the 

worker’s work location. 

d. U-232/233 in Tables 5-8 through 5-10 should only be assigned for the HB Line for January 1, 1964 through September 

30, 1972.

Coworker intakes of fission and activation products were based on application of ORAUT-RPRT-0047

(ORAUT 2013a) using 90Sr or 137Cs as indicator radionuclides. The 90Sr data should be used for 

years for which it is available (1955 through 1965 and 1991 through 2006), and the 137Cs data should 

be used for the remainder of the years.

5.1 TRITIUM

Table 5-2 lists the tritium doses and GSDs to be used for each year of potential tritium exposure.

Table 5-2. Tritium annual doses (rem) and GSDs. 

Year

50th-percentile

dose GSD

95th-percentile

dose Year

50th-percentile

dose GSD

95th-percentile

dose

1954 0.008 3.00 0.047 1981 0.017 3.00 0.105

1955 0.010 3.00 0.064 1982 0.015 3.00 0.092

1956 0.014 3.00 0.085 1983 0.012 3.00 0.076

1957 0.019 3.00 0.115 1984 0.013 3.00 0.081

1958 0.024 3.00 0.146 1985 0.014 3.00 0.083

1959 0.025 3.41 0.187 1986 0.007 3.26 0.051

1960 0.036 3.45 0.275 1987 0.007 3.35 0.050

1961 0.034 3.52 0.273 1988 0.006 3.12 0.041

1962 0.036 3.17 0.238 1989 0.005 3.00 0.029

1963 0.034 3.00 0.205 1990 0.005 3.00 0.029

1964 0.046 3.33 0.333 1991 0.003 3.00 0.019

1965 0.041 3.51 0.326 1992 0.003 3.00 0.015

1966 0.031 3.38 0.227 1993 0.002 3.00 0.014

1967 0.032 3.00 0.197 1994 0.003 3.00 0.017

1968 0.033 3.24 0.229 1995 0.003 3.00 0.016

1969 0.035 3.02 0.215 1996 0.003 3.00 0.017

1970 0.028 3.23 0.195 1997 0.003 3.00 0.018

1971 0.034 3.00 0.205 1998 0.003 3.00 0.017

1972 0.032 3.38 0.234 1999 0.003 3.00 0.016

1973 0.028 3.40 0.209 2000 0.003 3.00 0.017

1974 0.031 3.30 0.221 2001 0.002 3.00 0.015

1975 0.033 3.13 0.215 2002 0.003 3.00 0.016

1976 0.031 3.17 0.207 2003 0.003 3.00 0.016
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 30 of 96

Year

50th-percentile

dose GSD

95th-percentile

dose Year

50th-percentile

dose GSD

95th-percentile

dose

1977 0.032 3.06 0.205 2004 0.002 3.00 0.015

1978 0.031 3.00 0.192 2005 0.002 3.00 0.012

1979 0.030 3.00 0.184 2006 0.001 3.00 0.008

1980 0.028 3.00 0.172 2007 0.002 3.00 0.010

5.2 PLUTONIUM

Tables 5-3 and 5-4 list the plutonium gross alpha intakes and associated GSDs to be used for each 

year of potential plutonium exposure.

Table 5-3. Type M plutonium gross alpha intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1955 12/31/1990 1.77 3.00 10.8

1/1/1991 12/31/2007 0.930 3.00 5.67

Table 5-4. Type S plutonium gross alpha intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1955 12/31/1990 20.69 3.00 126

1/1/1991 12/31/2007 13.6 3.00 82.9

5.3 URANIUM

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

uranium exposure. These intakes should be modeled as 100% 234U. In Building 773-A from January 

1, 1961 through September 30, 1972, and in Building 772-F and the HB-line from January 1, 1964 

through September 30, 1972, 233U production resulted in potential exposure to 233U containing 8 ppm 

232U. For workers in those areas and time periods, use the intakes in Tables 5-8 through 5-10 [2]. 

Table 5-5. Type F 234U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1953 12/31/1953 15.15 3.00 92.3

1/1/1954 12/31/1954 6.762 3.00 41.2

1/1/1955 12/31/1956 3.489 3.00 21.3

1/1/1957 12/31/1967 1.407 3.35 10.3

1/1/1968 12/31/1980 0.686 4.27 7.48

1/1/1981 12/31/1990 1.559 3.00 9.5

1/1/1991 12/31/2000 0.8747 3.00 5.33

1/12001 12/31/2007 0.1384 3.00 0.843

Table 5-6. Type M 234U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1953 12/31/1953 73.3 3.00 447

1/1/1954 12/31/1954 20.78 3.00 127

1/1/1955 12/31/1956 13.08 3.00 79.7

1/1/1957 12/31/1967 5.623 3.40 42.2

1/1/1968 12/31/1980 2.731 4.34 30.5

1/1/1981 12/31/1990 6.473 3.00 39.4

1/1/1991 12/31/2000 3.575 3.00 21.8

1/1/2001 12/31/2007 0.4823 3.00 2.94
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 31 of 96

Table 5-7. Type S 234U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1953 12/31/1953 2,293 3.00 13,972

1/1/1954 12/31/1954 1,050 3.00 6,398

1/1/1955 12/31/1956 407.8 3.00 2,485

1/1/1957 12/31/1967 89.4 3.25 623

1/1/1968 12/31/1980 41.24 4.24 443

1/1/1981 12/31/1990 107.1 3.00 653

1/1/1991 12/31/2000 58.73 3.00 358

1/1/2001 12/31/2007 10.89 3.00 66.4

Table 5-8. Type F 233U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

U-232 U-233 U-232 U-233

1/1/1961 12/31/1967 0.024 1.383 3.35 0.18 10.12

1/1/1968 9/30/1972 0.012 0.674 4.27 0.13 7.35

Table 5-9. Type M 233U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

U-232 U-233 U-232 U-233

1/1/1961 12/31/1967 0.096 5.527 3.40 0.72 41.48

1/1/1968 9/30/1972 0.046 2.685 4.34 0.52 29.98

Table 5-10. Type S 233U intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

U-232 U-233 U-232 U-233

1/1/1961 12/31/1967 1.52 87.88 3.25 10.6 612.4

1/1/1968 9/30/1972 0.70 40.54 4.24 7.5 435.5

5.4 AMERICIUM/CURIUM/CALIFORNIUM

Tables 5-11 to 5-13 list the americium, curium, and californium intakes and associated GSDs to be 

used for each year of potential americium, curium, and californium exposure. Before 1995, only one 

of americium, curium, or californium should be assigned because they are based on the same 

bioassay data. If no justification for using a specific radionuclide exists, then the most favorable to 

claimant one should be assigned. After 1994, the bioassay data for each radionuclide is a different 

dataset and one or more may be assigned as needed.

Table 5-11. Type M americium intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1963 12/31/1967 70.7 3.00 431

1/1/1968 12/31/1972 18.9 3.00 115

1/1/1973 12/31/1994 0.826 6.23 16.7

1/1/1995 12/31/2007 0.599 3.00 3.65

Table 5-12. Type M curium intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1963 12/31/1967 73.01 3.00 445

1/1/1968 12/31/1972 19.63 3.00 120

1/1/1973 12/31/1994 0.921 6.35 19.3

1/1/1995 12/31/2007 0.291 3.00 1.77

Table 5-13. Type M californium intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1963 12/31/1967 194.7 3.00 1186
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 32 of 96

1/1/1968 12/31/1972 53.88 3.00 328

1/1/1973 12/31/1994 3.01 6.62 67.5

1/1/1995 12/31/2007 1.55 3.00 9.45

5.5 NEPTUNIUM

Table 5-14 lists the neptunium intakes and associated GSDs to be used for each year of potential 

neptunium exposure.

Table 5-14. Type M neptunium intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1961 12/31/1963 0.528 3.02 3.24

1/1/1964 12/31/1964 0.528 12.37 33.0

1/1/1965 12/31/1965 4.84 3.00 29.5

1/1/1966 12/31/1967 4.84 3.08 30.9

1/1/1968 12/31/1969 1.79 3.21 12.2

1/1/1970 12/31/1974 93.5 3.00 570

1/1/1975 12/31/1979 38.7 4.25 418

1/1/1980 12/31/1990 2.90 5.46 47.2

1/1/1991 12/31/2007 0.336 3.00 2.05

5.6 FISSION/ACTIVATION PRODUCTS

Fission and activation products were evaluated in accordance with ORAUT-RPRT-0047 (ORAUT 

2013a), using either 90Sr or 137Cs as the indicator radionuclide. The chosen indicator radionuclide 

varied as a function of time based on the available data. Strontium should be used for 1955 through 

1965, 137Cs for 1966 through 1989, and strontium again for 1991 through 2007. Cobalt-60 intake 

rates are also provided for workers potentially exposed to purified 60Co (not as a part of a fission and 

activation product mixture).

5.6.1 Strontium

Table 5-15 lists the strontium intakes and associated GSDs to be used for each year of potential 

strontium exposure. For application of ORAUT-RPRT-0047 (ORAUT 2013a), the gross beta data 

(1955 through 1965) should be treated as chemically processed beta samples and the 90Sr data 

should be treated as strontium-specific data.

Table 5-15. Type F strontium intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

Gross beta data

1/1/1955 12/31/1962 58.93 3.00 359

1/1/1963 12/31/1964 168 3.00 1,024

1/1/1965 12/31/1965 349.9 3.00 2,132

Strontium-90 data

1/1/1991 12/31/1993 0.0393 3.00 0.239

1/1/1994 12/31/1998 1.98 3.00 12.07

1/1/1999 12/31/2001 0.177 8.79 6.31

1/1/2002 12/312006 0.517 4.72 6.64

5.6.2 Cesium-137

Table 5-16 lists the 137Cs intakes and associated GSDs to be used for each year of potential 137Cs 

exposure. The intake rate calculated for 1979 through 1989 has been extended to include 1990 as a 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 33 of 96

measure that is favorable to claimants because no data is available for 1990. Only the years for 

which 137Cs should be used as the indicator radionuclide are included in Table 5-15. 

Table 5-16. Type F 137Cs intake rates (pCi/d).

Start End 50th percentile GSD 95th percentile

1/1/1966 12/31/1967 224.1 3.00 1366

1/1/1968 12/31/1971 80.89 3.00 493

1/1/1972 12/31/1978 30.76 3.00 187

1/1/1979 12/31/1990 7.979 3.68 68.1

5.6.3 Cobalt-60

Tables 5-17 and 5-18 lists the 60Co intakes and associated GSDs to be used for each year of potential 

60Co exposure.

Table 5-17. Type M 60Co intake rates (pCi/d).

Start End 50th percentile GSD 95th percentile

1/1/1955 12/31/1962 169.4 3.00 1,032

1/1/1963 12/31/1964 499.7 3.00 3,045

1/1/1965 12/31/1965 1,050 3.00 6,398

1/1/1966 12/31/1966 4,743 3.00 28,901

1/1/1967 12/31/1968 13,290 3.00 80,982

1/1/1969 12/31/1970 3,189 3.00 19,432

Table 5-18. Type S 60Co intake rates (pCi/d). 

Start End 50th percentile GSD 95th percentile

1/1/1955 12/31/1962 667 3.00 4,064

1/1/1963 12/31/1964 2,004 3.00 12,211

1/1/1965 12/31/1965 4,221 3.00 25,721

1/1/1966 12/31/1966 18,150 3.00 110,596

1/1/1967 12/31/1968 53,580 3.00 326,488

1/1/1969 12/31/1970 11,680 3.00 71,172

5.7 THORIUM

Tables 5-19 and 5-20 list the 232Th intake rates and associated GSDs to be used for each year of 

potential thorium exposure. Include intakes of 228Th and 228Ra with activities equal to the 232Th intake 

rate. 

Table 5-19. Type M 232Th intake rates (dpm/d).

Start End 50th percentile GSD 95th percentile

1/1/1972 12/31/1972 15.31 3.34 111.4

1/1/1973 12/31/1989 1.149 8.49 38.8

Table 5-20. Type S 232Th intake rates (dpm/d). 

Start End 50th percentile GSD 95th percentile

1/1/1972 12/31/1972 725.5 3.34 5,281

1/1/1973 12/31/1989 15.90 8.41 527.9

6.0 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in this document, bracketed callouts have been inserted to indicate information, 

conclusions, and recommendations provided to assist in the process of worker dose reconstruction. 

These callouts are listed here in the Attributions and Annotations section, with information to identify 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 34 of 96

the source and justification for each associated item. Conventional References, which are provided in 

the next section of this document, link data, quotations, and other information to documents available 

for review on the Project’s Site Research Database (SRDB).

Tom LaBone served as the initial Subject Expert for this document. Mr. LaBone was previously 

employed at SRS and his work involved management, direction or implementation of radiation 

protection and/or health physics program policies, procedures or practices related to atomic weapons 

activities at the site. Preparation of this document has been overseen by a Document Owner who is 

fully responsible for the content, including all findings and conclusions. In all cases where such 

information or prior studies or writings are included or relied upon by Mr. LaBone, those materials are 

fully attributed to the source. Mr. LaBone’s Disclosure Statement is available at www.oraucoc.org. 

[1] Arno, Matthew G. Foxfire Scientific, Inc. Principal Health Physicist. January 2009. 

This is based on communications with Tom LaBone indicating “<” values were recorded as 

negative results in the HPRED database.

[2] Mahathy, James M. Oak Ridge Associated Universities. Health Physicist. October 2013. 233U was produced containing varying amounts of 232U, most of which were in the 5-7 ppm 

range (DuPont 1965a, 1965b, 1984a, 1984b). Use of 8 ppm is a conservative estimate of 232U 

content. 
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 35 of 96

REFERENCES

Butler, F. E., and R. M. Hall, 1970, “Determination of Actinides in Biological Samples with Bidentate 

Organophosphorus Extractant,” Analytical Chemistry, volume 42, number 9, pp. 1073–1076. 

[SRDB Ref ID: 119808]

DOD (U.S. Department of Defense), 1989, Sampling Procedures and Tables for Inspection by 

Attributes, MIL-STD-105E, Washington, D.C., May 10. [SRDB Ref ID: 24964]

DuPont (E. I. du Pont de Nemours and Company), 1961–1969, Special Product Log Records, 2-16-

1961 to 10-13-1969, Savannah River Laboratory, Aiken, South Carolina. [SRDB Ref ID: 

51953]

DuPont (E. I. du Pont de Nemours and Company), 1963–1970, Am., Cm Record Book, 5-29-1963 

thru 5-26-1970, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52008]

Dupont (E. I. du Pont de Nemours and Company), 1965a, Progress Report February 1965 Works 

Technical Department, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 68104]

Dupont (E. I. du Pont de Nemours and Company), 1965b, Progress Report May 1965 Works 

Technical Department, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 68105] 

DuPont (E. I. du Pont de Nemours and Company), 1969, Pu & Np Record Book, Savannah River 

Laboratory, Aiken, South Carolina, April 8. [SRDB Ref ID: 51973]

DuPont (E. I. du Pont de Nemours and Company), 1969–1973, Pu-AmCm Record Book, 5-14-1969 

thru 10-19-1973, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 53271]

DuPont (E. I. du Pont de Nemours and Company), 1970–1973, Am., Cm Record Book, 5-27-1970 

thru 2-9-1973, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52006]

DuPont (E. I. du Pont de Nemours and Company), 1973–1978, Am., Cm Record Book, 2-10-1973 

thru 4-30-1978, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52010]

DuPont (E. I. du Pont de Nemours and Company), 1973–1979, Pu-Am Record Book, 10-22-1973 thru 

2-1-1979, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 51970]

DuPont (E. I. du Pont de Nemours and Company), 1978–1983, Am., Cm Record Book, 5-1-1978 thru 

11-29-1983, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52019]

DuPont (E. I. du Pont de Nemours and Company), 1979–1980, Pu-Am Record Book, 2-2-1979 thru 7-

7-1980, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52018]

DuPont (E. I. du Pont de Nemours and Company), 1980–1981a, Am-Cm #5 Record Book, 8-12-1980 

thru 6-9-1981, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52012]

DuPont (E. I. du Pont de Nemours and Company), 1980–1981b, PU-Am #3 Record Book, 8-3-80 thru 

8-22-81, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 52015]

DuPont (E. I. du Pont de Nemours and Company), 1981–1986, Pu-Am Record Book, 10-23-1981 thru 

6-9-1986, Savannah River Plant, Aiken South Carolina. [SRDB Ref ID: 53283]
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 36 of 96

Dupont (E. I. du Pont de Nemours and Company), 1984a, History of the Savannah River Laboratory, 

Volume I – Production Reactor, Fuel, and Target Technology, Savannah River Plant, Aiken 

South Carolina. [SRDB Ref ID: 89232] 

Dupont (E. I. du Pont de Nemours and Company), 1984b, History of the Savannah River Laboratory, 

Volume II – Separations Technology, Savannah River Plant, Aiken South Carolina. [SRDB 

Ref ID: 89523]

DuPont (E. I. du Pont de Nemours and Company), 1986–1989, Pu-Am Record Book, 6-25-1986 thru 

8-9-1989, Savannah River Site, Aiken South Carolina. [SRDB Ref ID: 52022]

Fleming, R. R., 1973–1979, “R. R. Fleming Lab Notebook,” DPSTN-2011, E. I. Du Pont de Nemours 

and Company, Savannah River Laboratory, Aiken, South Carolina. [SRDB Ref ID: 61649]

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

Radionuclides by Workers, Publication 68, Pergamon Press, Oxford, England. [SRDB Ref ID: 

22731]

Kocher, D. C., 1981, Radioactive Decay Data Tables, A Handbook of Decay Data for Application to 

Radiation Dosimetry and Radiological Assessments, DOE/TIC-11026, U.S. Department of 

Energy, Office of Scientific and Technical Information, Washington, D.C. [SRDB Ref ID: 

32563]

NIOSH (National Institute for Occupational Safety and Health), 2012, SEC Petition Evaluation Report 

Petition SEC-00103, Addendum #3, Division of Compensation Analysis and Support, 

Cincinnati, Ohio, November 20.

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 

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

June 29.

ORAUT (Oak Ridge Associated Universities Team), 2005a, 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), 2005b, Savannah River Site, ORAUT-TKBS0003, Rev. 03, Oak Ridge, Tennessee, April 5.

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), 2009, Use of Claimant Datasets for Coworker 

Modeling, ORAUT-OTIB-0075, Rev. 00, Oak Ridge, Tennessee, May 25.

ORAUT (Oak Ridge Associated Universities Team), 2011, NOCTS ID Numbers Used in the SRS 

Internal Coworker Study, Oak Ridge, Tennessee, February 24. [SRDB Ref ID: 92815]

ORAUT (Oak Ridge Associated Universities Team), 2012, Analysis of Stratified Coworker Datasets, 

ORAUT-RPRT-0053, Rev. 01, Oak Ridge, Tennessee, July 16. 
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ORAUT (Oak Ridge Associated Universities Team), 2013a, Assignment of Fission and Activation 

Product Radionuclides for Non-Specific Bioassays at Savannah River Site – Comparison of 

Methods, ORAUT-RPRT-0047, Rev. 00, Oak Ridge, Tennessee, July 23. 

ORAUT (Oak Ridge Associated Universities Team), 2013b, Documented Communication with Former 

SRS Employees, Oak Ridge, Tennessee, April 29. [SRDB Ref ID: 126806] 

Taylor, G. A., K. W. Crase, T. R. La Bone, W. H. Wilkie, 1995. A History of Personnel Radiation 

Dosimetry at the Savannah River Site, WSRC-RP-95-234, Westinghouse Savannah River 

Company, Aiken, South Carolina, May. [SRDB Ref ID: 10931]

Watts, J. R., 1962–1967, “J. R. Watts Lab Notebook,” E. I. Du Pont de Nemours and Company, 

Savannah River Laboratory, Aiken, South Carolina. [SRDB Ref ID: 61711]
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 38 of 96

LIST OF TABLES

TABLE TITLE PAGE

A-1 NOCTS radionuclide type matrix............................................................................................ 38

A-2 HPRED radionuclide type matrix............................................................................................ 43

A-3 50th- and 84th-percentile urinary excretion rates of plutonium gross alpha, 1955 to 2007...... 43

A-4 50th- and 84th-percentile urinary excretion rates of uranium, 1953 to 2007 ........................... 44

A-5 50th- and 84th-percentile urinary excretion rates of americium, 1963 to 2007........................ 46

A-6 50th- and 84th-percentile urinary excretion rates of curium, 1963 to 2007 ............................. 47

A-7 50th- and 84th-percentile urinary excretion rates of californium, 1963 to 2007....................... 48

A-8 50th- and 84th-percentile urinary excretion rates of neptunium, 1961 to 1969 and 1991 

to 2007...................................................................................................................................49

A-9 50th- and 84th-percentile whole body burdens of neptunium, 1971 to 1989........................... 49

A-10 50th- and 84th-percentile urinary excretion rates of strontium, 1955 to 1965 and 1991 to 

2006.......................................................................................................................................50

A-11 50th- and 84th-percentile whole body burdens of cesium, 1961 to 1989 ................................ 51

A-12 50th- and 84th-percentile urinary excretion rates of 60Co, 1955 to 1970................................. 51

Table A-1. NOCTS radionuclide type matrix.

a

 

No. Nuclide U (all) Pu Sr Np MFP

1 FP X

2 Pu-238/239 X

3 Sr90 X

4 Pu X

5 Pu238

6 Pu239 X

7 U X

8 FPIA X

9 IA

10 IA beta X

11 IA gamma

12 Pu-239 X

13 Pu 238

14 Pu-238

15 EU X

16 Pu238/239 X

17 Am-Cm

18 Am

19 SP X

20 FP gamma

21 Pu 239 X

22 Eu X

23 AmCm

24 Sr-90 X

25 AmCmCf

26 UR X

27 Ur X

28 Sp X

29 Pu-238/Pu-239 X

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

Page 1 of 14
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 39 of 96

No. Nuclide U (all) Pu Sr Np MFP

30 Pu238-239 X

31 Am 

32 LMF X

33 FP X

34 F

35

36 Cf-252

37 Am-241

38 Cm-244

39 U-234 X

40 U-235 X

41 U-238 X

42 Np-237 X

43 239 X

44 238

45 Np X

46 Po

47 Pu-237

48 Pu238/Pu239 X

49 Th

50 P

51 TH

52 Cr

53 Fe

54 IP

55 NP X

56 Pu X

57 ENU X

58 Pu-241 X

59 EnU X

60 M

61 FPIA(PHA) X

62 Sr X

63 Pu X

64 AC

65 Cm244

66 E

67 Thorium

68 Pm147

69 Pu239 X

70 Pu238 

71 Uranium X

72 FP X

73 NT/ D U X

74 PU X

75 PP

76 Pu 238/239 X

77 FPIA X

78 Pu 238/Pu 239 X

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

Page 2 of 14
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 40 of 96

No. Nuclide U (all) Pu Sr Np MFP

79 Pu238/Pu-239 X

80 FP(IA) X

81 CM244

82 PU238

83 Sr 90 X

84 FP-I X

85 PU 239 X

86 PU 238

87 FP-IA X

88 PU X

89 AM

90 AM-CM

91 FP (IA) X

92 CM

93 Pu 239/239 X

94 PU238/239 X

95 Fp X

96 PU239 X

97 Pu/Am X

98 Am 241

99 AMCM

100 AM 

101 H3

102 D2O

103 RU X

104 Pu-Am-Cm X

105 U 234 X

106 U 235 X

107 U 238 X

108 IA-b X

109 IA-g

110 A

111 PU 238/239 X

112 AU X

113 FP (Np)

114 AM CM

115 FP/Pu X

116 PU238 

117 FU X

118 b g X

119 SR90 X

120 Pu241

121 Cf

122 Pu-239/240 X

123 UO3 X

124 PU239/AM X

125 FP & I131 X

126 FP-b X

127 FP-g

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

Page 3 of 14
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 41 of 96

No. Nuclide U (all) Pu Sr Np MFP

128 Pb

129 IA

130 Am241

131 NT/D U X

132 Unat X

133 Cm-Am

134 FPIA BETA X

135 AMCM 

136 Am Cm

137 PU vomitus

138 PU241

139 NT/DU X

140 U234 X

141 U235 X

142 U238 X

143 Hg

144 D20

145 I-131 X

146 PU-238/239 X

147 PU-238

148 PU-239 X

149 Lead

150 Cm242

151 AM-241

152 Pu FP X

153 UF X

154 Pu240 X

155 Pu242 X

156 Pu243 X

157 Pu244 X

158 Pu245 X

159 Pu246 X

160 Pu247 X

161 Pu248 X

162 Pu249 X

163 Pu251 X

164 Pu252 X

165 Pu250 X

166 Cf252

167 Merc

168 Np237 X

169 Iodine

170 IA X

171 g

172 Pu238 & 239 X

173 FL

174 SR X

175 beta-gamma X

176 alpha

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

Page 4 of 14
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 42 of 96

No. Nuclide U (all) Pu Sr Np MFP

177 IAFP X

178 Pu238, 239 X

179 NT/ D U X

180 PU238/PU239 X

181 CF252

182 AM241

183 NP237 X

184 Am/Cm

185 Mercury

186 Cm

187 Po-210

188 Alpha

189 I ACT X

190 ID

191 Ce144

192 Zr95/Nb95

193 Fluoride

194 FPIA(131I) X

195 R

196 HG

197 Am-CmCf

198 NP-237 X

199 GP

200 PB

201 Ru 106

202 Ce 144

203 Cm 244

204 Pu X

205 Cm/Cf

206 U X

207 Pu238

208 Pu239 X

209 PO210

210 Po 210

211 L.M.F. X

212 Beta

213 Pu (3.00 Am) X

214 DU X

215 Pu-238-239 X

216 FP/IA X

217 Nat-U X

218 PU238-239 X

219 Pa-231

220 Th-231

221 A 

222 Cm-Cf

223 Am-Cm 244

224 Cs 137

225 Pu/FP X

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

Page 5 of 14
Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 43 of 96

No. Nuclide U (all) Pu Sr Np MFP

226 NEU X

227 Pa 231

228 Th 231

a. Nuclide designations without an “X” were not used in the coworker study.

Table A-2. HPRED radionuclide type matrix. 

No. x U Pu Am/Cm/Cf Am Cm Cf Sr Np

1 H3

2 U-234 X

3 U-235 X

4 U-238 X

5 PU-238 X

6 PU-239 X

7 NP-237 X

8 AM-241 X X

9 CM-244 X X

10 CF-252 X X

11 SR90 X

12 NT/DU X

13 Pu238 X

14 Am241 X X

15 Pu239 X

16 EU X

17 AmCmCf X

18 Sr90 X

19 U234 X

20 U235 X

21 U238 X

22 Np237 X

23 Cm242 X X

24 Cm244 X X

25 Cf252 X X

Table A-3. 50th- and 84th-percentile urinary excretion rates of plutonium gross 

alpha, 1955 to 2007 (dpm/d). 

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1955 0.0273 0.068 203

7/1/1956 0.0106 0.050 314

7/1/1957 0.0263 0.056 312

7/1/1958 0.0371 0.061 286

7/1/1959 0.0307 0.085 337

7/1/1960 0.0188 0.080 350

7/1/1961 0.0074 0.028 367

7/1/1962 0.0430 0.073 398

7/1/1963 0.0049 0.028 338

7/1/1964 0.0134 0.054 327

7/1/1965 0.0295 0.060 414

7/1/1966 0.0291 0.064 376

7/1/1967 0.0240 0.068 355

7/1/1968 0.0147 0.053 384

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Document No. ORAUT-OTIB-0081 Revision No. 02 Effective Date: 12/16/2013 Page 44 of 96

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1969 0.0272 0.134 279

7/1/1970 0.0295 0.121 266

7/1/1971 0.0144 0.055 339

7/1/1972 0.0320 0.091 358

7/1/1973 0.0235 0.073 356

7/1/1974 0.0244 0.076 369

7/1/1975 0.0194 0.073 341

7/1/1976 0.0093 0.054 394

7/1/1977 0.0240 0.077 389

7/1/1978 0.0168 0.071 260

7/1/1979 0.0173 0.034 357

7/1/1980 0.0360 0.078 312

7/1/1981 0.0150 0.054 408

7/1/1982 0.0122 0.043 406

7/1/1983 0.0109 0.048 296

7/1/1984 0.0163 0.055 267

7/1/1985 0.0536 0.087 241

7/1/1986 0.0134 0.057 299

7/1/1987 0.0420 0.070 271

7/1/1988 0.0159 0.039 296

7/1/1989 0.0111 0.032 282

7/1/1990 0.0086 0.023 303

7/1/1991 2.39E-05 7.5E-04 8,694

7/1/1992 0.0006 0.0037 8,769

7/1/1993 0.0038 0.0121 6,604

7/1/1994 0.0076 0.0235 5,641

7/1/1995 0.0074 0.0237 5,257

7/1/1996 0.0087 0.0250 4,994

7/1/1997 0.0076 0.0263 4,919

7/1/1998 0.0088 0.0296 4,938

7/1/1999 0.0091 0.0258 4,322

7/1/2000 0.0086 0.0222 3,076

7/1/2001 0.0080 0.0205 2,734

7/1/2002 0.0093 0.0228 2,687

7/1/2003 0.0089 0.0229 2,545

7/1/2004 0.0075 0.0180 2,277

7/1/2005 0.0091 0.0223 2,477

7/1/2006 0.0083 0.0209 2,218

7/1/2007 0.0085 0.0213 2,077

Table A-4. 50th- and 84th-percentile urinary excretion rates of uranium, 1953 

to 2007 (dpm/d).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1953 4.076 7.573 31

7/1/1954 1.867 3.021 93

7/1/1955 0.9926 1.648 277

7/1/1956 0.9515 1.296 390

7/1/1957 0.392 1.370 207

7/1/1958 0.3738 1.388 151

7/1/1959 0.2422 0.807 201

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Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1960 0.2772 0.844 252

7/1/1961 0.1476 0.744 220

7/1/1962 0.3962 1.337 243

7/1/1963 0.7477 1.957 260

7/1/1964 0.7036 1.945 271

7/1/1965 0.4095 1.489 251

7/1/1966 0.4085 1.472 210

7/1/1967 0.3055 1.113 198

7/1/1968 0.1094 0.554 219

7/1/1969 0.1166 0.771 180

7/1/1970 0.09433 0.933 177

7/1/1971 0.1265 0.854 212

7/1/1972 0.1264 0.869 222

7/1/1973 0.1081 0.782 222

7/1/1974 0.1402 0.796 201

7/1/1975 0.2212 0.999 219

7/1/1976 0.3098 0.781 189

7/1/1977 0.1775 0.803 114

7/1/1978 0.4689 1.004 99

7/1/1979 0.3177 0.942 107

7/1/1980 0.2537 0.698 79

7/1/1981 0.07588 0.474 90

7/1/1982 0.3631 1.431 86

7/1/1983 0.7964 2.181 86

7/1/1984 0.2588 1.408 64

7/1/1985 0.4568 1.447 93

7/1/1986 0.08252 0.340 82

7/1/1987 0.6084 1.009 80

7/1/1988 0.2133 0.940 67

7/1/1989 0.02113 0.179 87

7/1/1990 1.048 1.202 36

7/1/1991 0.09117 0.344 2,349

7/1/1992 0.07548 0.274 2,842

7/1/1993 0.3592 0.698 2,952

7/1/1994 0.3419 0.873 2,511

7/1/1995 0.2393 0.569 2,401

7/1/1996 0.3281 0.748 2,193

7/1/1997 0.3409 0.724 2,045

7/1/1998 0.2581 0.573 2,267

7/1/1999 0.2207 0.589 2,116

7/1/2000 0.2388 0.665 1,597

7/1/2001 0.09381 0.422 1,410

7/1/2002 0.03714 0.086 1,411

7/1/2003 0.03625 0.088 1,300

7/1/2004 0.03338 0.080 1,291

7/1/2005 0.03486 0.080 1,473

7/1/2006 0.04674 0.092 1,093

7/1/2007 0.04698 0.091 914

ATTACHMENT A

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Table A-5. 50th- and 84th-percentile urinary excretion rates of americium, 1963

to 2007 (dpm/d).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1963 0.8360 1.296 43

7/1/1965 0.3360 0.769 126

7/1/1966 0.8282 2.027 155

7/1/1967 0.9520 1.476 227

7/1/1968 0.2527 0.627 364

7/1/1969 0.3065 0.890 379

7/1/1970 0.2320 0.517 567

7/1/1971 0.1693 0.419 663

7/1/1972 0.0721 0.241 650

7/1/1973 0.0082 0.064 644

7/1/1974 0.0093 0.096 456

7/1/1975 0.0102 0.075 467

7/1/1976 0.0130 0.081 450

7/1/1977 0.0037 0.042 383

7/1/1978 0.0258 0.257 228

7/1/1979 0.0249 0.270 322

7/1/1980 0.0096 0.070 230

7/1/1981 0.0028 0.016 267

7/1/1982 0.0021 0.008 307

7/1/1983 0.0054 0.045 303

7/1/1984 0.0063 0.069 275

7/1/1985 0.0119 0.120 259

7/1/1986 0.0035 0.040 273

7/1/1987 0.0175 0.088 305

7/1/1988 0.0185 0.141 288

7/1/1991 0.0180 0.0568 570

7/1/1992 0.0232 0.0608 373

7/1/1993 0.0156 0.0649 208

7/1/1994 0.0315 0.0951 180

7/1/1995 0.0124 0.0351 226

7/1/1996 0.0118 0.0362 271

7/1/1997 0.0113 0.0302 401

7/1/1998 0.0120 0.0286 681

7/1/1999 0.0121 0.0276 1,499

7/1/2000 0.0111 0.0237 2,130

7/1/2001 0.0094 0.0214 2,305

7/1/2002 0.0082 0.0210 2,473

7/1/2003 0.0072 0.0185 2,313

7/1/2004 0.0060 0.0159 1,985

7/1/2005 0.0058 0.0153 2,242

7/1/2006 0.0058 0.0164 2,103

7/1/2007 0.0062 0.0165 2,030

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Table A-6. 50th- and 84th-percentile urinary excretion rates of curium, 1963 to 

2007 (dpm/d). 

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1963 0.8360 1.296 43

7/1/1965 0.3360 0.769 126

7/1/1966 0.8282 2.027 155

7/1/1967 0.9520 1.476 227

7/1/1968 0.2527 0.627 364

7/1/1969 0.3065 0.890 379

7/1/1970 0.2320 0.517 567

7/1/1971 0.1693 0.419 663

7/1/1972 0.0721 0.241 650

7/1/1973 0.0082 0.064 644

7/1/1974 0.0093 0.096 456

7/1/1975 0.0102 0.075 467

7/1/1976 0.0130 0.081 450

7/1/1977 0.0037 0.042 383

7/1/1978 0.0258 0.257 228

7/1/1979 0.0249 0.270 322

7/1/1980 0.0096 0.070 230

7/1/1981 0.0028 0.016 267

7/1/1982 0.0021 0.008 307

7/1/1983 0.0054 0.045 303

7/1/1984 0.0063 0.069 275

7/1/1985 0.0119 0.120 259

7/1/1986 0.0035 0.040 273

7/1/1987 0.0175 0.088 305

7/1/1988 0.0185 0.141 288

7/1/1991 0.0180 0.0568 570

7/1/1992 0.0232 0.0608 373

7/1/1993 0.0156 0.0649 208

7/1/1994 0.0315 0.0951 180

7/1/1995 0.00204 0.00651 226

7/1/1996 0.00391 0.00826 271

7/1/1997 0.00710 0.01316 401

7/1/1998 0.00691 0.01350 681

7/1/1999 0.00266 0.00637 1,499

7/1/2000 0.00093 0.00291 2,130

7/1/2001 0.00164 0.00503 2,305

7/1/2002 0.00382 0.00893 2,473

7/1/2003 0.00355 0.00861 2,313

7/1/2004 0.00394 0.00951 1,984

7/1/2005 0.00458 0.01001 2,242

7/1/2006 0.00475 0.01053 2,103

7/1/2007 0.00390 0.00939 2,030

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Table A-7. 50th- and 84th-percentile urinary excretion rates of californium, 1963 

to 2007 (dpm/d).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1963 0.8360 1.296 43

7/1/1965 0.3360 0.769 126

7/1/1966 0.8282 2.027 155

7/1/1967 0.9520 1.476 227

7/1/1968 0.2527 0.627 364

7/1/1969 0.3065 0.890 379

7/1/1970 0.2320 0.517 567

7/1/1971 0.1693 0.419 663

7/1/1972 0.0721 0.241 650

7/1/1973 0.0082 0.064 644

7/1/1974 0.0093 0.096 456

7/1/1975 0.0102 0.075 467

7/1/1976 0.0130 0.081 450

7/1/1977 0.0037 0.042 383

7/1/1978 0.0258 0.257 228

7/1/1979 0.0249 0.270 322

7/1/1980 0.0096 0.070 230

7/1/1981 0.0028 0.016 267

7/1/1982 0.0021 0.008 307

7/1/1983 0.0054 0.045 303

7/1/1984 0.0063 0.069 275

7/1/1985 0.0119 0.120 259

7/1/1986 0.0035 0.040 273

7/1/1987 0.0175 0.088 305

7/1/1988 0.0185 0.141 288

7/1/1991 0.0180 0.0568 570

7/1/1992 0.0232 0.0608 373

7/1/1993 0.0156 0.0649 208

7/1/1994 0.0315 0.0951 180

7/1/1995 0.00469 0.0144 226

7/1/1996 0.00508 0.0146 271

7/1/1997 0.00684 0.0197 401

7/1/1998 0.00834 0.0215 681

7/1/1999 0.00648 0.0156 1,499

7/1/2000 0.00501 0.0123 2,130

7/1/2001 0.00346 0.0086 2,305

7/1/2002 0.00444 0.0112 2,473

7/1/2003 0.00662 0.0171 2,313

7/1/2004 0.00852 0.0206 1,984

7/1/2005 0.00848 0.0187 2,242

7/1/2006 0.00791 0.0180 2,103

7/1/2007 0.00844 0.0183 2,030

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Table A-8. 50th- and 84th-percentile urinary excretion rates of neptunium, 

1961 to 1969 and 1991 to 2007 (dpm/d).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1961 0.0216 0.0470 312

7/1/1962 0.0049 0.0291 933

7/1/1963 0.0057 0.0356 459

7/1/1964 0.0201 0.1078 48

7/1/1965 0.0835 0.1625 48

7/1/1966 0.1215 0.3365 32

7/1/1967 0.1205 0.3010 42

7/1/1968 0.0264 0.1401 68

7/1/1969 0.0470 0.1074 29

7/1/1991 0.0131 0.0422 89

7/1/1992 0.0049 0.0195 196

7/1/1993 0.0046 0.0283 266

7/1/1994 0.0150 0.0582 274

7/1/1995 0.0129 0.0385 249

7/1/1996 0.0126 0.0422 253

7/1/1997 0.0116 0.0333 447

7/1/1998 0.0107 0.0327 662

7/1/1999 0.0136 0.0379 825

7/1/2000 0.0128 0.0304 1,026

7/1/2001 0.0117 0.0257 981

7/1/2002 0.0123 0.0264 997

7/1/2003 0.0092 0.0199 971

7/1/2004 0.0086 0.0195 910

7/1/2005 0.0090 0.0199 1,081

7/1/2006 0.0110 0.0234 1,101

7/1/2007 0.0113 0.0248 1,111

Table A-9. 50th- and 84th-percentile whole body burdens of neptunium, 1971 

to 1989 (dpm).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1971 8,026 14,580 42

7/1/1973 4,909 11,512 47

7/1/1974 3,506 10,181 68

7/1/1975 1,155 5,307 85

7/1/1976 3,370 7,535 13

7/1/1977 1,036 5,729 54

7/1/1978 2,317 9,710 92

7/1/1979 1,351 7,717 67

7/1/1980 210 873 106

7/1/1981 150 1,013 122

7/1/1982 193 852 118

7/1/1983 244 1,024 106

7/1/1984 189 1,161 117

7/1/1985 66 693 75

7/1/1986 235 1,265 78

7/1/1987 477 2,299 96

7/1/1988 288 1,592 90

7/1/1989 186 1,162 86

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Table A-10. 50th- and 84th-percentile urinary excretion rates of strontium, 

1955 to 1965 and 1991 to 2006 (dpm/d).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1955 17.92 33.05 209

7/1/1956 11.37 40.88 285

7/1/1957 12.99 40.06 177

7/1/1958 15.82 44.47 136

7/1/1959 7.88 44.99 191

7/1/1960 25.44 45.26 276

7/1/1961 7.86 20.78 329

7/1/1962 11.38 41.71 391

7/1/1963 35.95 66.57 328

7/1/1964 41.48 66.46 319

7/1/1965 79.70 97.09 314

7/1/1991 0.00529 0.022 3,105

7/1/1992 0.01121 0.013 4,352

7/1/1993 0.005932 0.027 3,711

7/1/1994 0.4736 1.175 3,496

7/1/1995 0.6499 1.287 3,500

7/1/1996 0.02397 0.187 3,445

7/1/1997 0.4553 1.495 3,252

7/1/1998 0.2543 1.163 3,841

7/1/1999 0.08286 0.570 3,600

7/1/2000 0.04699 0.311 2,067

7/1/2001 0.06374 0.384 1,537

7/1/2002 0.1224 0.630 1,274

7/1/2003 0.127 0.611 1,118

7/1/2004 0.0987 0.481 1,001

7/1/2005 0.1327 0.594 1,267

7/1/2006 0.1734 0.703 1,174

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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Table A-11. 50th- and 84th-percentile whole body burdens of cesium, 1961 to 

1989 (pCi).

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1961 4,863 6,337 36

7/1/1962 5,508 8,699 52

7/1/1963 9,692 13,046 27

1/1/1966 15,400 20,361 19

1/1/1970 5,564 9,777 29

7/1/1972 3,457 4,785 32

7/1/1973 2,748 4,348 46

7/1/1974 2,344 4,014 70

7/1/1975 2,037 5,003 87

7/1/1976 1,914 4,126 60

7/1/1977 1,898 4,215 81

7/1/1978 1,749 4,476 94

7/1/1979 948 2,750 94

7/1/1980 600 1,909 109

7/1/1981 556 1,792 120

7/1/1982 468 1,560 119

7/1/1983 343 1,244 113

7/1/1984 397 1,343 115

7/1/1985 385 1,247 78

7/1/1986 1,082 4,014 117

7/1/1987 534 2,048 110

7/1/1988 618 2,701 110

7/1/1989 628 2,412 95

Table A-12. 50th- and 84th-percentile urinary excretion rates of 60Co, 1955 to 

1970. 

Effective bioassay date 50th percentile 84th percentile No. of employees

7/1/1955 17.92 33.05 209

7/1/1956 11.37 40.88 285

7/1/1957 12.99 40.06 177

7/1/1958 15.82 44.47 136

7/1/1959 7.88 44.99 191

7/1/1960 25.44 45.26 276

7/1/1961 7.86 20.78 329

7/1/1962 11.38 41.71 391

7/1/1963 35.95 66.57 328

7/1/1964 41.48 66.46 319

7/1/1965 79.70 97.09 314

7/1/1966 330 511 356

7/1/1967 1,131 1,753 436

7/1/1968 945 1,465 494

7/1/1969 355 551 429

7/1/1970 317 491 471

ATTACHMENT A

BIOASSAY DATA TYPES AND STATISTICAL ANALYSIS RESULTS

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LIST OF TABLES

TABLE TITLE PAGE

B-1 Summary of plutonium type M intake rates and dates ............................................................ 59

B-2 Summary of plutonium type S intake rates and dates............................................................. 61

B-3 Summary of uranium type F intake rates and dates ............................................................... 62

B-4 Summary of uranium type M intake rates and dates............................................................... 63

B-5 Summary of uranium type S intake rates and dates ............................................................... 69

B-6 Summary of americium type M intake rates and dates ........................................................... 73

B-7 Summary of curium type M intake rates and dates................................................................. 77

B-8 Summary of californium type M intake rates and dates .......................................................... 80

B-9 Summary of neptunium type M intake rates and dates........................................................... 87

B-10 Summary of strontium type F intake rates and dates.............................................................. 89

B-11 Summary of cesium type F intake rates and dates................................................................. 89

B-12 Summary of 60Co type M intake rates and dates .................................................................... 90

B-13 Summary of 60Co type S intake rates and dates..................................................................... 91

B-14 Summary of thorium type M intake rates and dates................................................................ 94

B-15 Summary of thorium type S intake rates................................................................................. 96

LIST OF FIGURES

FIGURE TITLE PAGE

B-1 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1955–1990, type M ........................... 57

B-2 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1991–2007, type M ........................... 57

B-3 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1955–1990, type M ........................... 57

B-4 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type M ........................... 58

B-5 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 58

B-6 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 58

B-7 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1955–1990, type S............................ 59

B-8 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, 1991–2007, type S............................ 59

B-9 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1955–1990, type S............................ 60

B-10 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type S............................ 60

B-11 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type S ................... 60

B-12 Predicted plutonium bioassay results calculated using IMBA-derived plutonium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type S ................... 61

ATTACHMENT B

COWORKER DATA FIGURES

Page 1 of 45
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B-13 Predicted uranium bioassay results calculated using IMBA-derived uranium intake rates 

compared with bioassay results, 50th percentile, type F ........................................................ 61

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

compared with bioassay results, 84th percentile, type F ........................................................ 62

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

compared with bioassay results, 50th percentile, type M ........................................................ 62

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

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

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

compared with bioassay results, 50th percentile, 1953, type S .............................................. 63

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

compared with bioassay results, 50th percentile, 1954, type S .............................................. 64

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

compared with bioassay results, 50th percentile, 1955–1956, type S..................................... 64

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

compared with bioassay results, 50th percentile, 1957–1967, type S..................................... 64

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

compared with bioassay results, 50th percentile, 1968–1980, type S..................................... 65

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

compared with bioassay results, 50th percentile, 1981–1990, type S..................................... 65

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

compared with bioassay results, 50th percentile, 1991–2000, type S..................................... 65

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

compared with bioassay results, 50th percentile, 2001–2007, type S..................................... 66

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

compared with bioassay results, 84th percentile, 1953, type S .............................................. 66

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

compared with bioassay results, 84th percentile, 1954, type S .............................................. 66

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

compared with bioassay results, 84th percentile, 1955–1956, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1957–1967, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1968–1980, type S..................................... 67

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

compared with bioassay results, 84th percentile, 1981–1990, type S..................................... 68

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

compared with bioassay results, 84th percentile, 1991–2000, type S..................................... 68

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

compared with bioassay results, 84th percentile, 2001–2007, type S..................................... 68

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

compared with bioassay results, 50th percentile, all intake periods, type S............................ 69

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

compared with bioassay results, 84th percentile, all intake periods, type S............................ 69

B-35 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1963–1967, type M ........................... 70

B-36 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1968–1972, type M ........................... 70

ATTACHMENT B

COWORKER DATA FIGURES

Page 2 of 45
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B-37 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1973–1994, type M ........................... 70

B-38 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, 1995–2007, type M ........................... 71

B-39 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1963–1967, type M ........................... 71

B-40 Predicted americium bioassay results using IMBA-derived americium intake rates 

compared with bioassay results, 84th percentile, 1968–1972, type M .................................... 71

B-41 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1973–1994, type M ........................... 72

B-42 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, 1995–2007, type M ........................... 72

B-43 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 72

B-44 Predicted americium bioassay results calculated using IMBA-derived americium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 73

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

compared with bioassay results, 50th percentile, 1963–1967, type M .................................... 73

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

compared with bioassay results, 50th percentile, 1968–1972, type M .................................... 74

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

compared with bioassay results, 50th percentile, 1973–1994, type M .................................... 74

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

compared with bioassay results, 50th percentile, 1995–2007, type M .................................... 74

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

compared with bioassay results, 84th percentile, 1963–1967, type M .................................... 75

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

compared with bioassay results, 84th percentile, 1968–1972, type M .................................... 75

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

compared with bioassay results, 84th percentile, 1973–1994, type M .................................... 75

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

compared with bioassay results, 84th percentile, 1995–2007, type M .................................... 76

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

compared with bioassay results, 50th percentile, all intake periods, type M ........................... 76

B-54 Predicted curium bioassay results calculated using IMBA-derived curium intake rates 

compared with bioassay results, 84th percentile, all intake periods, type M ........................... 76

B-55 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1963–1967, type M ........................... 77

B-56 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1968–1972, type M ........................... 77

B-57 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1973–1994, type M ........................... 78

B-58 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, 1995–2007, type M ........................... 78

B-59 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1963–1967, type M ........................... 78

B-60 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1968–1972, type M ........................... 79

ATTACHMENT B

COWORKER DATA FIGURES

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B-61 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1973–1994, type M ........................... 79

B-62 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, 1995–2007, type M ........................... 79

B-63 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 50th percentile, all intake periods, type M .................. 80

B-64 Predicted californium bioassay results calculated using IMBA-derived californium intake 

rates compared with bioassay results, 84th percentile, all intake periods, type M .................. 80

B-65 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–1964, type M ........................... 81

B-66 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1965–1967, type M ........................... 81

B-67 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1968–1969, type M ........................... 81

B-68 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1970–1974, type M ........................... 82

B-69 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1975–1979, type M ........................... 82

B-70 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1980–1990, type M ........................... 82

B-71 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1991–2007, type M ........................... 83

B-72 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961–1963, type M ........................... 83

B-73 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1964–1965, type M ........................... 83

B-74 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1966–1967, type M ........................... 84

B-75 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1968–1969, type M ........................... 84

B-76 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1970–1974, type M ........................... 84

B-77 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1975–1979, type M ........................... 85

B-78 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1980–1990, type M ........................... 85

B-79 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1991–2007, type M ........................... 85

B-80 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–2007 cumulative, type M, 

urinalysis data........................................................................................................................86

B-81 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 50th percentile, 1961–2007 cumulative, type M, 

WBC data ..............................................................................................................................86

B-82 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961–2007 cumulative, type M, 

urinalysis data........................................................................................................................86

ATTACHMENT B

COWORKER DATA FIGURES

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B-83 Predicted neptunium bioassay results calculated using IMBA-derived neptunium intake 

rates compared with bioassay results, 84th percentile, 1961-2007 cumulative, type M, 

urinalysis data, WBC data...................................................................................................... 87

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

rates compared with bioassay results, 50th percentile, 1955–1965, type F............................ 87

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

rates compared with bioassay results, 50th percentile, 1991–2006, type F............................ 88

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

rates compared with bioassay results, 84th percentile, 1955–1965, type F............................ 88

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

rates compared with bioassay results, 84th percentile, 1991–2006, type F............................ 88

B-88 Predicted cesium bioassay results calculated using IMBA-derived cesium intake rates 

compared with bioassay results, 50th percentile, type F ........................................................ 89

B-89 Predicted cesium bioassay results calculated using IMBA-derived cesium intake rates 

compared with bioassay results, 84th percentile, type F ........................................................ 89

B-90 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 50th percentile, type M........................................................ 90

B-91 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 84th percentile, type M........................................................ 90

B-92 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 50th percentile, type S ........................................................ 91

B-93 Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

compared with bioassay results, 84th percentile, type S ........................................................ 91

B-94 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1972, type M.............................................. 92

B-95 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1973 through 1989, type M ........................ 92

B-96 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1972, type M.............................................. 92

B-97 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1973 through 1989, type M ........................ 93

B-98 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

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

B-99 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates

compared with bioassay results, 84th percentile, all intakes periods, type M.......................... 93

B-100 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1972, type S .............................................. 94

B-101 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, 1973 through 1989, type S......................... 94

B-102 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1972, type S .............................................. 95

B-103 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, 1973 through 1989, type S......................... 95

B-104 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 50th percentile, all intakes periods, type S .......................... 95

B-105 Predicted thorium bioassay results calculated using IMBA-derived thorium intake rates 

compared with bioassay results, 84th percentile, all intake periods, type S............................ 96

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-1. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1955–1990, type M. 

Figure B-2. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1991–2007, type M. 

Figure B-3. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1955–1990, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-4. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1991–2007, type M. 

Figure B-5. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, all 

intake periods, type M. 

Figure B-6. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, all 

intake periods, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-1. Summary of plutonium type M intake rates (dpm/d) 

and dates. 

Years 50% 84% GSD Adj GSD 95%

1955–1990 1.77 5.103 2.88 3.00 10.8

1991–2007 0.930 2.542 2.73 3.00 5.67

Figure B-7. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1955–1990, type S. 

Figure B-8. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1991–2007, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-9. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1955–1990, type S. 

Figure B-10. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1991–2007, type S. 

Figure B-11. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 50th percentile, all 

intake periods, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-12. Predicted plutonium bioassay results calculated using IMBA-derived 

plutonium intake rates (line) compared with bioassay results (dots), 84th percentile, all 

intake periods, type S. 

Table B-2. Summary of plutonium type S intake rates (dpm/d) 

and dates. 

Years 50% 84% GSD

Adj 

GSD 95%

1955–1990 20.69 59.53 2.88 3.00 126

1991–2007 13.6 36.57 2.69 3.00 82.9

Figure B-13. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, type F. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-14. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, type F. 

Table B-3. Summary of uranium type F intake rates (dpm/d) and 

dates. 

Years 50% 84% GSD Adj GSD 95%

1953 15.15 28.15 1.86 3.00 92.3

1954 6.762 10.9 1.61 3.00 41.2

1955–1956 3.489 5.258 1.51 3.00 21.3

1957–1967 1.407 4.707 3.35 3.35 10.3

1968–1980 0.686 2.931 4.27 4.27 7.48

1981–1990 1.559 4.144 2.66 3.00 9.50

1991–2000 0.8747 2.113 2.42 3.00 5.33

2001–2007 0.1384 0.4005 2.89 3.00 0.843

Figure B-15. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-16. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, type M. 

Table B-4. Summary of uranium type M intake rates (dpm/d) and 

dates. 

Years 50% 84% GSD Adj GSD 95%

1953 73.3 136.2 1.86 3.00 447

1954 20.78 30.95 1.49 3.00 127

1955–1956 13.08 19.61 1.50 3.00 79.7

1957–1967 5.623 19.14 3.40 3.40 42.2

1968–1980 2.731 11.84 4.34 4.34 30.5

1981–1990 6.473 17.07 2.64 3.00 39.4

1991–2000 3.575 8.621 2.41 3.00 21.8

2001–2007 0.4823 1.386 2.87 3.00 2.94

Figure B-17. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1953, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-18. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1954, type S. 

Figure B-19. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1955–1956, 

type S. 

Figure B-20. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1957–1967, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-21. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1968–1980, type S. 

Figure B-22. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1981–1990, 

type S. 

Figure B-23. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1991–2000, 

type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-24. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 2001–2007, 

type S. 

Figure B-25. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1953, type S. 

Figure B-26. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 84th percentile, 1954, 

type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-27. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1955–1956, 

type S. 

Figure B-28. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1957–1967, 

type S. 

Figure B-29. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1968–1980, 

type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-30. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1981–1990, 

type S. 

Figure B-31. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1991–2000, 

type S. 

Figure B-32. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 2001–2007, 

type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-33. Predicted uranium bioassay results calculated using IMBA-derived uranium 

intake rates (line) compared with bioassay results (dots), 50th percentile, all intake 

periods, type S. 

Figure B-34. Predicted uranium bioassay results calculated using IMBA-derived 

uranium intake rates (line) compared with bioassay results (dots), 84th percentile, all 

intake periods, type S. 

Table B-5. Summary of uranium type S intake rates (dpm/d) and 

dates. 

Years 50% 84% GSD Adj GSD 95%

1953 2,293 4,261 1.86 3.00 13,972

1954 1,050 1,700 1.62 3.00 6,398

1955–1956 407.8 604.4 1.48 3.00 2,485

1957–1967 89.38 290.9 3.25 3.25 623

1968–1980 41.24 174.7 4.24 4.24 443

1981–1990 107.1 264.2 2.47 3.00 653

1991–2000 58.73 141.1 2.40 3.00 358

2001–2007 10.89 27.35 2.51 3.00 66.4

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-35. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1963–1967, type M. 

Figure B-36. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1968–1972, type M. 

Figure B-37. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1973–1994, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-38. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1995–2007, type M. 

Figure B-39. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1963–1967, type M. 

Figure B-40. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1968–1972, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-41. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1973–1994, type M. 

Figure B-42. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1995–2007, type M. 

Figure B-43. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 50th percentile, all 

intake periods, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-44. Predicted americium bioassay results calculated using IMBA-derived 

americium intake rates (line) compared with bioassay results (dots), 84th percentile, all 

intake periods, type M. 

Table B-6. Summary of americium type M intake rates 

(dpm/d) and dates. 

Years 50% 84% GSD Adj GSD 95%

1963–1967 70.7 134.8 1.91 3.00 431

1968–1972 18.9 49.53 2.62 3.00 115

1973–1994 0.826 5.142 6.23 6.23 16.7

1995–2007 0.599 1.523 2.54 3.00 3.65

Figure B-45. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1963–1967, 

type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-46. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1968–1972, 

type M. 

Figure B-47. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1973–1994, 

type M. 

Figure B-48. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1995–2007, 

type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-49. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1963–1967, 

type M. 

Figure B-50. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1968–1972, 

type M. 

Figure B-51. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1973–1994, 

type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-52. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1995–2007, 

type M. 

Figure B-53. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 50th percentile, all intake 

periods, type M. 

Figure B-54. Predicted curium bioassay results calculated using IMBA-derived curium 

intake rates (line) compared with bioassay results (dots), 84th percentile, all intake 

periods, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-7. Summary of curium type M intake rates (dpm/d) 

and dates. 

Years 50% 84% GSD Adj GSD 95%

1963–1967 73.01 139.2 1.91 3.00 444.9

1968–1972 19.63 51.4 2.62 3.00 119.6

1973–1994 0.921 5.852 6.35 6.35 19.3

1995–2007 0.291 0.6621 2.28 3.00 1.77

Figure B-55. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1963–1967, type M. 

Figure B-56. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1968–1972, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-57. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1973–1994, type M. 

Figure B-58. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 50th percentile, 

1995–2007, type M. 

Figure B-59. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1963–1967, type M. 

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Figure B-60. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1968–1972, type M. 

Figure B-61. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1973–1994, type M. 

Figure B-62. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 84th percentile, 

1995–2007, type M. 

ATTACHMENT B

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Figure B-63. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 50th percentile, all 

intake periods, type M. 

Figure B-64. Predicted californium bioassay results calculated using IMBA-derived 

californium intake rates (line) compared with bioassay results (dots), 84th percentile, all 

intake periods, type M. 

Table B-8. Summary of californium type M intake rates 

(dpm/d) and dates. 

Years 50% 84% GSD Adj GSD 95%

1963–1967 194.7 369.8 1.90 3.00 1,186

1968–1972 53.88 140.9 2.62 3.00 328.3

1973–1994 3.012 19.94 6.62 6.62 67.5

1995–2007 1.551 3.827 2.47 3.00 9.45

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Figure B-65. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1961–1964, type M. 

Figure B-66. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1965–1967, type M. 

Figure B-67. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1968–1969, type M. 

ATTACHMENT B

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Figure B-68. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1970–1974, type M. 

Figure B-69. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1975–1979, type M. 

Figure B-70. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1980–1990, type M. 

ATTACHMENT B

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Figure B-71. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1991–2007, type M. 

Figure B-72. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1961–1963, type M. 

Figure B-73. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1964–1965, type M. 

ATTACHMENT B

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Figure B-74. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1966–1967, type M. 

Figure B-75. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1968–1969, type M. 

Figure B-76. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1970–1974, type M. 

ATTACHMENT B

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Figure B-77. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1975–1979, type M. 

Figure B-78. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1980–1990, type M. 

Figure B-79. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1991–2007, type M. 

ATTACHMENT B

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Figure B-80. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1961–2007 

cumulative, type M, urinalysis data. 

Figure B-81. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1961–2007 

cumulative, type M, whole-body count data. 

Figure B-82. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1961–2007 

cumulative, type M, urinalysis data. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-83. Predicted neptunium bioassay results calculated using IMBA-derived neptunium 

intake rates (line) compared with bioassay results, 84th percentile, 1961–2007 cumulative, 

type M, urinalysis data, WBC data. 

Table B-9. Summary of neptunium type M intake rates

(dpm/d) and dates. 

Years 50% 84% GSD Adj GSD 95%

1961–1963 0.528 1.59 3.02 3.02 3.24

1964 0.528 6.53 12.37 12.37 33.0

1965 4.84 6.53 1.35 3.00 29.5

1966–1967 4.84 14.9 3.08 3.08 30.9

1968–1969 1.79 5.74 3.21 3.21 12.2

1970–1974 93.5 221 2.37 3.00 570

1975–1979 38.7 164 4.25 4.25 418

1980–1989 2.90 15.8 5.46 5.46 47.2

1991–2007 0.336 0.920 2.74 3.00 2.05

Figure B-84. Predicted strontium bioassay results calculated using IMBA-derived strontium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1955–1965, type F. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-85. Predicted strontium bioassay results calculated using IMBA-derived strontium 

intake rates (line) compared with bioassay results (dots), 50th percentile, 1991–2006, type F. 

Figure B-86. Predicted strontium bioassay results calculated using IMBA-derived strontium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1955–1965, type F. 

Figure B-87. Predicted strontium bioassay results calculated using IMBA-derived strontium 

intake rates (line) compared with bioassay results (dots), 84th percentile, 1991–2006, type F. 

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-10. Summary of strontium type F intake rates (dpm/d) and 

dates. 

Years 50% 84% GSD Adj GSD 95%

1955–1962 58.93 166.3 2.82 3.00 359

1963–1964 168 283.1 1.69 3.00 1,024

1965 350 417 1.19 3.00 2,132

1991–1993 0.0393 0.09039 2.30 3.00 0.239

1993–1998 1.98 5.556 2.80 3.00 12.07

1999–2001 0.177 1.552 8.79 8.79 6.31

2002–2006 0.517 2.441 4.72 4.72 6.64

Figure B-88. Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates (line) compared with bioassay results (dots), 50th percentile, type F. 

Figure B-89. Predicted cesium bioassay results calculated using IMBA-derived cesium intake 

rates (line) compared with bioassay results (dots), 84th percentile, type F. 

Table B-11. Summary of cesium type F intake rates (pCi/d) and 

dates. 

Years 50% 84% GSD Adj GSD 95%

1961–1962 89.27 131.5 1.47 3.00 544

1963 164.8 216.7 1.31 3.00 1,004

1964–1967 224.1 296.4 1.32 3.00 1,366

1968–1971 80.89 135.8 1.68 3.00 493

1972–1978 30.76 61.25 1.99 3.00 187

1979–1989 7.979 29.37 3.68 3.68 68.1

ATTACHMENT B

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Figure B-90. Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

(line) compared with bioassay results (dots), 50th percentile, type M. 

Figure B-91. Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

(line) compared with bioassay results (dots), 84th percentile, type M. 

Table B-12. Summary of 60Co type M intake rates (dpm/d) and

dates. 

Years 50% 84% GSD Adj GSD 95%

1955–1962 169.4 480.3 2.84 3.00 1,032

1963–1964 499.7 833 1.67 3.00 3,045

1965 1,050 1,236 1.18 3.00 6,398

1966 4,743 7,391 1.56 3.00 28,901

1967–1968 13,290 20,600 1.55 3.00 80,982

1969–1970 3,189 4,946 1.55 3.00 19,432

ATTACHMENT B

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Figure B-92. Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

(line) compared with bioassay results (dots), 50th percentile, type S. 

Figure B-93. Predicted 60Co bioassay results calculated using IMBA-derived 60Co intake rates 

(line) compared with bioassay results (dots), 84th percentile, type S. 

Table B-13. Summary of 60Co type S intake rates (dpm/d) and

dates.

Years 50% 84% GSD Adj GSD 95%

1955–1962 667 1,882 2.82 3.00 4,064

1963–1964 2,004 3,294 1.64 3.00 12,211

1965 4,221 4,963 1.18 3.00 25,721

1966 18,150 28,180 1.55 3.00 110,596

1967–1968 53,580 83,080 1.55 3.00 326,488

1969–1970 11,680 18,110 1.55 3.00 71,172

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Figure B-94. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, 1972, type M. 

Figure B-95. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, 1973 through 1989, type M. 

Figure B-96. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, 1972, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-97. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, 1973 through 1989, type M. 

Figure B-98. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, all intakes periods, type M. 

Figure B-99. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, all intakes periods, type M. 

ATTACHMENT B

COWORKER DATA FIGURES

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Table B-14. Summary of thorium type M intake rates 

(dpm/d) and dates. 

Years 50% 84% GSD Adj GSD 95%

1972 15.31 51.16 3.34 3.34 111.4

1973–1989 1.149 9.758 8.49 8.49 38.8

Figure B-100. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, 1972, type S. 

Figure B-101. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, 1973 through 1989, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-102. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, 1972, type S. 

Figure B-103. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, 1973 through 1989, type S. 

Figure B-104. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 50th percentile, all intakes periods, type S. 

ATTACHMENT B

COWORKER DATA FIGURES

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Figure B-105. Predicted thorium bioassay results calculated using IMBA-derived thorium intake 

rates (line) compared with bioassay results (dots), 84th percentile, all intakes periods, type S. 

Table B-15. Summary of thorium type S intake rates 

(dpm/d) and dates.

Years 50% 84% GSD Adj GSD 95%

1972 725.5 2,425 3.34 3.34 5,281.3

1973–1989 15.9 133.7 8.41 8.41 527.9

ATTACHMENT B

COWORKER DATA FIGURES

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