ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 19

DOE Review Release 01/13/2010

Document Title:

Idaho National Laboratory and Argonne National 

Laboratory-West – Occupational Medical Dose

Document Number: ORAUT-TKBS-0007-3 

Revision: 02

Effective Date: 12/21/2009

Type of Document: TBD

Supersedes: Revision 01 and ORAUTTKBS-0026-3 Revision 01

Subject Expert(s): N/A

Site Expert(s): Norman D. Rohrig

Approval: Signature on File Approval Date: 12/07/2009

Jo Ann M. Jenkins, Document Owner

Concurrence: Signature on File Concurrence Date: 12/07/2009

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 12/07/2009

Edward F. Maher, Objective 3 Manager

Concurrence: Signature on File Concurrence Date: 12/07/2009

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 12/21/2009

Stuart L. Hinnefeld, Interim Director OCAS

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-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 2 of 19

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

01/15/2004 00 New Technical Basis Document for the Idaho National Engineering 

and Environmental Laboratory - Occupational Medical Dose. First 

approved issue. Initiated by Norman D. Rohrig.

05/28/2004 00 PC-1 Adds spleen to organ table on page 10. Eliminates date overlap in 

table on page 11. Initiated by Norman Rohrig.

Approval:

Norman D. Rohrig, Document Owner 

Signature on File 05/27/2004

Task 3 Manager, Judson Kenoyer, Task 3, Manager 

Signature on File 05/27/2004

Richard E. Toohey, Project Director 

Signature on File 05/27/2004

James W. Neton, OCAS Health Science Administrator

Signature on File 05/28/2004

01/31/2007 01 Approved Revision 01 as a result of biennial review. Revised 

language in the Purpose section as required by NIOSH. Attributions 

and Annotations section added. Changed treatment of eye and brain 

dose. As a result of internal formal review, add Table 3-3. 

Incorporates NIOSH formal review comments. This revision results 

in an increase in assigned dose and a PER is required. Constitutes 

a total rewrite of document. Initiated by Norman D. Rohrig.

12/21/2009 02 Revised to combine Argonne National Laboratory West Occupational 

Medical Dose technical basis document (ORAUT-TKBS-0026-3 Rev 

01) into the Idaho National Laboratory Occupational Medical Dose 

technical basis document. Separated X-ray doses into posterioranterior and lateral in Tables 3-7 and 3-8. Incorporates formal 

internal and NIOSH review comments. Constitutes a total rewrite of 

the document. Training required: As determined by the Objective 

Manager. Initiated by Jo Ann M. Jenkins. 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 3 of 19

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

4

3.1 Introduction ................................................................................................................................ 5

3.1.1 Purpose...........................................................................................................................6

3.1.2 Scope..............................................................................................................................6

3.2 Examination Frequencies .......................................................................................................... 6

3.3 Equipment and Techniques ....................................................................................................... 8

3.4 Organ Doses.............................................................................................................................. 9

3.5 Uncertainty............................................................................................................................... 11

3.6 Attributions and Annotations .................................................................................................... 12

References ...........................................................................................................................................13

Glossary................................................................................................................................................15

ATTACHMENT A, DOSES TO OTHER AREAS OF THE SKIN ..........................................................16

LIST OF TABLES

TABLE TITLE

3-1 Chest X-ray schedule from 1960 annual report ..........................................................................

PAGE

6

3-2 INL default X-ray schedule..........................................................................................................7

3-3 ANL-W default X-ray schedule....................................................................................................8

3-4 Skin entrance air kerma values...................................................................................................9

3-5 Dose conversion factors for ICRP Publication 34 organs ...........................................................9

3-6 General scheme for dose conversion factors (DCFs) for IREP organs not 

included in ICRP Pubilcation 34................................................................................................10

3-7 Organ doses (mrad) from PA chests at INL and ANL-W ..........................................................10

3-8 Organ doses (mrad) from LAT chests at the INL and ANL-W ..................................................11
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 4 of 19

ACRONYMS AND ABBREVIATIONS

AEC U.S. Atomic Energy Commission

AP anterior-posterior

ANL-W Argonne National Laboratory–West

CFR Code of Federal Regulations

cm centimeter

DOE U.S. Department of Energy

DOL U.S. Department of Labor

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

HVL half-value layer

Hz hertz

ICRP International Commission on Radiological Protection

in. inch

INL Idaho National Laboratory

IREP Interactive RadioEpidemiological Program

kg kilogram 

kVp peak kilovolts or applied kilovoltage

LAT lateral

lb pound

mA milliampere

mAs milliampere-seconds

mm millimeter

mrad millirad

ms millisecond

NCRP National Council for Radiation Protection and Measurements

NIOSH National Institute for Occupational Safety and Health

OCAS Office of Compensation Analysis and Support

ORAU Oak Ridge Associated Universities

PA posterior-anterior 

POC probability of causation

s second

SRDB Ref ID Site Research Database Reference Identification (number)

SRS Savannah River Site

TBD technical basis document 

U.S.C. United States Code

yr year

§ section or sections
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 5 of 19

3.1 INTRODUCTION

Technical basis documents and site profile documents are not official determinations made by the 

National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historic background information and guidance to assist in the preparation of 

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

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 [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

The statute also includes a definition of a DOE facility that excludes “buildings, structures, premises, 

grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 U.S.C. 

7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. While this 

definition excludes Naval Nuclear Propulsion Facilities from being covered under the Act, the section 

of EEOICPA that deals with the compensation decision for covered employees with cancer [i.e., 42 

U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally-derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external occupational radiation exposures are considered valid for inclusion in a dose reconstruction. 

No efforts are made to determine the eligibility of any fraction of total measured exposure for inclusion 

in dose reconstruction. NIOSH, however, does not consider the following exposures to be 

occupationally derived (NIOSH 2007): 

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation, 42 C.F.R. Pt. 82) define “performance of duty” for 

DOE employees with a covered cancer or restrict the “duty” to nuclear weapons work (NIOSH 2007). 

• Background radiation, including radiation from naturally occurring radon present in 

conventional structures

• Radiation from X-rays received in the diagnosis of injuries or illnesses or for therapeutic 

reasons

 

1 The U.S. Department of Labor (DOL) is ultimately responsible under the EEOICPA for determining the POC. 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 6 of 19

3.1.1

This section discusses the occupational medical dose workers received during employment at the 

Idaho National Laboratory (INL, formerly known as the Idaho National Engineering and Environmental 

Laboratory, the Idaho National Engineering Laboratory, and the National Reactor Testing Station) and 

Argonne National Laboratory–West (ANL-W), which have operated from February 1951 to the 

present. INL and ANL-W required preemployment and periodic physical examinations as part of their

occupational health and safety program. At first, the U.S. Atomic Energy Commission (AEC) provided 

these medical examinations for all contractors and AEC personnel. Later, the service became the 

responsibility of the site prime contractor. 

Purpose

3.1.2

The pre-employment, periodic and termination examinations typically included chest X-rays. The 

dose from these procedures depended not only on the characteristics of the X-ray machine and the 

procedures that were used but also on the frequency of examinations. This section discusses the 

various X-ray techniques and equipment that have been used over the years at INL and ANL-W. The 

primary source of information on medical X-rays is Idaho National Engineering and Environmental 

Laboratory (INEEL) History of the Occupational Medical Program (OMP) X-Ray Process (Collings and 

Creighton 2002), a report Bechtel BWXT Idaho prepared at INL at the request of NIOSH.

Scope

Section 3.2 discusses examination frequencies, and Section 3.3 describes equipment and techniques. 

Sections 3.4 and 3.5 discuss organ doses and uncertainty, respectively. Attributions and annotations, 

indicated by bracketed callouts and used to identify the source, justification, or clarification of the 

associated information, are presented in Section 3.6. 

3.2 EXAMINATION FREQUENCIES

Collings and Creighton (2002) reported that from 1954 to 1970, chest X-rays were performed on new 

hires and on radiation workers at ages 25, 30, 34, 37, and 40, every 2 years from ages 40 to 62, and 

then every year. They also reported that all employees went on this schedule in 1970. Table 3-1 

from the 1960 annual report (AEC 1961) lists a somewhat different schedule:

Table 3-1. Chest X-ray schedule from 1960 annual report

(AEC 1961).

Age

Radiation area employees

badged

Nonradiation employees

unbadged

18–24 4 yr At age 30

25–39 3 yr 5 yr

40–49 2 yr 3 yr

50–59 1 yr 2 yr

Over 60 1 yr 1 yr

This schedule is corroborated by a memorandum (Sommers 1961). The dose reconstructor should 

assume that the 1960 schedule applies to dose reconstruction for all workers in the 1954 to 1970 

period because it uses historical documentation. It also involved more examinations and is therefore 

favorable to claimants.

A review of the NIOSH-Office of Compensation Analysis and Support (OCAS) Claims Tracking 

System (NOCTS) showed that the database contains ANL-W worker X-ray records. From this it can 

be concluded that chest X-rays were given annually from 1959 to about 1975. It can be assumed that

they were given annually before that time. This contradicts the practice at INL even though these 

X-rays were given through the INL medical organization.
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 7 of 19

The Appendix to Chapter 0528 of the AEC Manual (AEC 1969) specified the following:

• A chest X-ray would be part of a medical examination.

• Workers under age 40 would receive an examination at a frequency that was influenced by 

several factors.

• Workers over age 40 would receive an examination at least every 2 years and approximately 

annually when indicated.

The schedule in the table is consistent with that requirement except for ages 40 to 49. The 1971 

annual report (AEC 1972) states the schedule for examinations was, “at time of hire, at ages 25, 30, 

34, 37, and 40, every two years until age 62 and then annually.” This is identical to that reported by 

Collings and Creighton (2002), and it is assumed to apply from 1970 to 1976.

Beginning in 1976, physicals occurred every 2 years for workers under age 45 and every year for 

those over age 45 (Collings and Creighton 2002). On February 1, 1978, chest X-rays were eliminated 

on periodic physicals except for high-risk individuals (as determined by the physician), in which case 

they were performed every 4 years (Collings and Creighton 2002). Records from the exposures are 

reported in each worker’s medical file. When available, the energy employee’s actual X-ray 

examination records should be used to assign occupational medical dose. Tables 3-2 and 3-3 list the 

X-ray schedule to use when the employee’s records are not available. 

Table 3-2 INL default X-ray schedule

Period Worker category/age Frequency Exposure type

Before 1954 No information; assume annual PA

1954–1969 New hires PA

Radiation workers

18–24 Every 4 yr

25–39 Triennial

40–49 Biennial

50 and over Annual

Nonradiation workers

30–39 Every 5 yr

40–49 Triennial

50–59 Biennial

60 and over Annual

1970-1976 New hires PA, LAT

25, 30, 34, 37, 40

40–62 Biennial

>62 Annual 

1977-1978 New hires PA, LAT

≤45 Biennial

>45 Annual

1979-Jan 1990 New hires PA

High risk Every 4 yr 

Feb 1990–present New hires PA, LAT

High risk Every 4 yr 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 8 of 19

Table 3-3 ANL-W default X-ray schedule 

Period Worker Category/Age Frequency Exposure Type

Before 1954 No information; assume annual PA

1954–1974 New hires PA

Annual

1975-1976 New hires PA, LAT

25, 30, 34, 37, 40

40–62 Biennial

>62 Annual 

1977-1978 New hires PA, LAT

≤45 Biennial

>45 Annual

1979-Jan 1990 New hires PA

High risk 4 years

Feb 1990- present New hires PA, LAT

High risk 4 years

3.3 EQUIPMENT AND TECHNIQUES

The standard distance from source to image was 72 in. (183 cm) for the posterior-anterior (PA; back 

to front) and lateral (LAT) chest exams.

The records indicate that none of the INL examinations used photofluorography (Rohrig 2003). The 

1971 annual report stated that a medical van took 22% of the 4,426 X-ray examinations and 

mentioned the Idaho Falls Navy dispensary as providing X-ray examinations (AEC 1972). Both of 

these facilities performed standard chest X-rays (Rohrig 2003) and did not do photofluorography. A 

key-word search of the INL records system using the words collimation, fluoroscopic, Health and 

Safety, Health and Safety Services, Medical X-ray, photofluorography, and X-ray resulted in nothing 

that indicated the use of photofluorographic techniques (Vivian and Rockhold 2003).

From 1954 to February 1990, X-ray examinations were performed with a single-phase General 

Electric Model DXD350 machine. The voltage was 90 kVp, the current was 300 mA, and the duration 

of the exposure was 1/15 s (67 ms). Added filtration of 2 mm Al was used, and a 10:1 grid was used 

to reduce scatter radiation (Collings and Creighton 2002). Tube window thickness is assumed to be 

about 0.5 mm Al equivalent. Based on Table A16 of International Commission on Radiological 

Protection (ICRP) Publication 34, Protection of the Patient in Diagnostic Radiology, the half-value 

layer (HVL) at 90 kVp and 2.5 mm Al total filtration is 2.58 mm Al (ICRP 1982). 

From February 1990 to the present, X-rays were performed with a high frequency Gendex Model 110-

0030G2. The voltage is 100 kVp, the current is 300 mA, and the duration is 32 ms. Added filtration of 

2 mm Al was used, and a 10:1 grid was used to reduce scatter radiation (Collings and Creighton 

2002). Tube window thickness is assumed to be about 0.5 mm. Based on Table A17 of ICRP 

Publication 34, the HVL at 100 kVp and 2.5 mm Al total filtration is 3.3 mm Al (ICRP 1982). 

Practices before 1954 are unclear. Offsite facilities might have been contracted to perform the 

examinations. The default value for entrance kerma of 200 mrad (ORAUT 2005a) is assumed for that 

period. 

From 1954 to 1970, the chest X-ray consisted of a single PA projection (Collings and Creighton 2002). 

From 1970 to 1978, the procedure consisted of both PA and LAT projections (Collings and Creighton 

2002). From 1978 to 1990, the LAT projection was dropped and only a PA projection was made 

(Collings and Creighton 2002). For the latest period from 1990 to the present, there have been both 

PA and LAT projections (Collings and Creighton 2002). For LAT projections, the exposure time was 

about 1.25-1.4 times that of the PA view [1]. An exposure time of 1.4 times that of the PA view was 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 9 of 19

used to calculate doses from LAT projections. In Collings and Creighton (2002), the terms PA and AP 

(anterior-posterior, front to back) appear somewhat interchangeably. Creighton attributed this 

presumed interchangeable usage to a typographical error. The August 21, 1975, U.S. Energy 

Research and Development Administration requirement for occupational medical programs (replaced 

in 1982) specified the minimum requirements for chest X-rays and specified a PA projection at least 

once every 5 years as well as when transferring to a job with cardiorespiratory system stress (ERDA 

1975).

Collimation and control of scatter for the INL facilities generally followed the state of the medical art as 

it improved. However, in the absence of particular information about collimation, this analysis 

assumed the dose conversion factors from Table 6-5 of ORAUT-OTIB-0006, Dose Reconstruction 

from Occupationally Related Diagnostic X-Ray Procedures ORAUT (2005a), for the pre-1970 period. 

3.4 ORGAN DOSES 

The entrance air kerma for 100 mAs can be determined from Table B3 of National Council on 

Radiation Protection and Measurements (NCRP) Report 102 (NCRP 1989) and the beam voltage, 

distance, and total filtration. The entrance air kerma for 100 mAs is then adjusted by the actual mAs 

used to determine the actual entrance air kerma at INL. Table 3-4 lists the skin entrance air kerma 

values in millirad.

Table 3-4. Skin entrance air kerma values (mrad). 

Air kerma PA LAT

Pre-1954 200 500

1954–January 1990a 52 74

February 1990–presenta 53 76

a. Table B-3 of NCRP Report 102 and site specific technique factors

Tables A2 to A9 of ICRP Publication 34 list Monte Carlo calculation results of the ratio of organ doses 

to air kerma for a 70-kg (154-lb) man or woman for the thyroid, ovaries, testes, lungs, female breast, 

uterus (embryo), active bone marrow, and total body under different exposure conditions (ICRP 

1982). These dose conversion factor results are shown in Table 3-5. 

Table 3-5. Dose conversion factors for ICRP Publication 34 organs.

Publication 34 

organs

Thyroid Testes

Lungs 

(female)

Lungs 

(male) Breast Ovary Uterus

Bone 

marrow 

(male)

Bone 

marrow 

Period Geometry (female)

Before 

1970a

PA 174 NA 451 419 49 NA NA 92 86

LAT 137 NA 220 193 255 NA NA 37 29

1970–

1990b

PA 32 <0.01 451 419 49 1 1.3 92 86

LAT 115 <0.1 220 193 255 0.6 0.6 37 29

1990–

presentb

PA 62 <0.01 610 565 91 3.2 3.0 146 141

LAT 151 <0.1 310 276 316 1.6 1.4 61 48

a. Based on ORAUT-OTIB-0006 (ORAUT 2005a) and/or measurements by Webster therein.

b. HVLs for 2.5 and 3.5 mm Al were used in place of the values for 2.58 and 3.3 mm of Al . 

For the pre-1970 period during which collimation is uncertain, organ dose values for PA chest from 

Table 6-5 of ORAUT-OTIB-0006 (ORAUT 2005a) were used. Under EEOICPA, cancers in several 

other organs are compensable, as listed in the Interactive RadioEpidemiological Program (IREP). 

The ratio of doses for two organs is affected by the relative atomic numbers of the tissue (bone dose 

is higher than dose in nearby muscle), the relative positions of the organ and the X-ray beam, and the 

depth in the body. Table 3-6 lists these other organs and the organs from Publication 34, which were 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 10 of 19

used to estimate the dose. For the eye and brain, modified dose conversion factors from ORAUTOTIB-0006 were used. 

Table 3-6. General scheme for Dose Conversion Factors (DCFs) for IREP 

organs not included in ICRP 34 (ORAUT 2005). 

Anatomical location ICRP 34 DCF

IREP organ without 

specific DCF

Thorax Lung Thymus

Esophagus

Bone surface 

Stomach/spleen

Liver/gall bladder

Abdomen Ovaries Urinary bladder

Colon

Uterus

HVLs of 2.5, 3.0, and 3.5 mm Al were used in place of the values of 2.58 and 3.3 mm Al. The skin 

entrance surface was assumed to be 30 cm from the film for the PA view and 40 cm from the film for 

the LAT view [2]. These distances account for body thickness and any other space between the 

person and the film. The entrance dose to the skin is the product of the entrance air kerma and a 

backscatter factor from Table B-8 of NCRP Report 102 (NCRP 1989). Dose to other areas of skin 

were determined in accordance with the general method described in OTIB-0006 (ORAUT 2005a). 

These values are shown in Attachment A. The organ dose from a PA projection is the product of the 

two table values, an inverse square correction, and the product of exposure current and time. Table 

3-7 lists these values. The second row in Table 3-7 lists the organs identified in ICRP Publication 34 

(ICRP 1982), and the fourth row lists the organs in IREP that are not in Publication 34. 

Collings and Creighton (2002) states that a LAT projection was taken in addition to the PA from 1975 

to 1978 and from 1990 to 2003. Table 3-8 provides the doses for the LAT exposure, which should be 

added to the associated value from Table 3-7 if both projections were used.

Table 3-7. Organ doses (mrad) from PA chests at INL and ANL-W. 

Period

ICRP Publication 34 organsa

Thyroid Testes

Lungs - 

female

Lungs

- male Breast Ovary 

Uterus 

embryo 

Bone 

marrow

- male

Bone 

marrow

- female

Other organs

Thymus Esophagus 

Stomach 

Bone Surface

Liver/spleen

Gall bladder

Bladder 

colon

Entrance 

Skin

Eye

brain

Before 

1954 35 5 90 84 10 25 25 18 17 270 6 

1954–

1969 9 5 24 22 3 25 25 5 4 70 2 

1970–Jan 

1990 2 0.001 23 22 3 0.1 0.1 5 4 70 2 

Feb 1990–

present 3 0.001 32 30 5 0.2 0.2 8 7 74 3 

a. ICRP (1982). 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 11 of 19

Table 3-8. Organ doses (mrad) from LAT chests at the INL and ANL-W. 

Period

ICRP Publication 34 organsa

Thyroid Testes

Lungs - 

Female

Lungs - 

Male Breast Ovary 

Uterus 

embryo 

Bone 

marrow - 

Male

Bone 

marrow 

- Female

Other organs

Thymus 

Esophagus 

Stomach 

Bone Surface

Liver/spleen

Gall bladder

Bladder 

colon

Entrance

Skin

Eye 

brain

Before 

1954

69 3 110 97 128 13 13 19 15 675 69

1954-1969 10 3 16 14 19 13 13 3 2 100 10

1970–Jan 

1990

9 0.01 16 14 19 0.04 0.04 3 2 100 9

Feb 1990–

present

11 0.01 24 21 24 0.1 0.1 5 4 106 11

a. ICRP (1982). 

3.5 UNCERTAINTY

Uncertainties in the occupational medical dose result from uncertainties in the current, voltage, and 

time for the exposures. The organ doses are also influenced by the size of the worker [3]. For IREP 

organs where an analogue organ is used from the ICRP Publication 34 organs (ICRP 1982), the IREP 

organs are deeper in the body so the dose to the IREP organ is lower than the dose to the analogue 

organ. No estimate is made of this one-sided uncertainty because it cannot lead to a larger dose [4].

The assigned uncertainties in OTIB-0006 (ORAUT 2005a) are generically valid for X-ray programs. 

The standard uncertainty due to voltage was 9%, that due to current was 5%, and that due to time 

was 25%. The uncertainty for voltage assumed a 5% voltage uncertainty; because the output has a 

V1.7 dependence, the resultant uncertainty is 9%. Output is directly proportional to current, which was 

assumed to have a 5% uncertainty [5]. The usually unfiltered voltage output from the voltage rectifier 

causes a pulsed character to the X-ray output at 120 Hz (twice the supply frequency). For short 

exposure times, this results in only a few pulses and thus a fairly large uncertainty due to time [6].

All Monte Carlo calculations have an uncertainty determined by the length of the run and the number 

of events scored for each calculation. For the organ dose calculations from ICRP Publication 34 

(ICRP 1982), this uncertainty was not stated. Based on judgment, it is assumed to be 5% at 1 sigma, 

which would require at least 400 counts in each scoring unit [7].

The error due to an individual’s body thickness has two causes: (1) an increase in superficial organ 

dose resulting from the fact that a larger person is physically closer to the radiation source, and (2) a 

potential decrease in dose to very deep organs resulting from additional shielding of these deep 

organs by overlying tissue. Information on worker thickness is rarely available, even in the medical 

literature. However, at SRS entrance skin dose measurements were made on nine workers of varying 

chest thicknesses (builds) (Cooley, 1967). While Cooley (1967) does not report the measured chest 

thicknesses for these nine workers, the entrance skin doses are reported and reflect the increases in 

exposure needed to radiograph thicker body parts, in this case, chests. The standard uncertainty of 

the range of measurements is 5.6, resulting in an uncertainty of 21% from this source. 

Substituting this value into the root mean square calculation for combined uncertainty described in 

ORAUT-OTIB-0006 (ORAUT 2005) instead of the 10% value used in that document, the resultant 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 12 of 19

standard uncertainty is 35% from these five sources. For further conservatism, it may be appropriate 

to assume that errors are all positive and that only +35% should be used as suggested in ORAUTOTIB-0006 (ORAUT 2005).

3.6 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 

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). 

Norman Rohrig served as the initial Document Owner for this document. Mr. Rohrig was previously 

employed at INL which shared boundaries with ANL-W and used the same Dosimetry systems 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. 

This revision has been overseen by a new Document Owner, who is fully responsible for the content 

of this document, including all findings and conclusions. In all cases where information or prior 

studies or writings from Mr. Rohrig are relied upon in this document by the Document Owner, those 

materials are fully attributed to the source.

[1] Rohrig, Norman. ORAU Team. Site Expert. July 2003.

Stated in phone conversation by Dr. Paul Creighton, INL Medical Director.

[2] Rohrig, Norman. ORAU Team. Site Expert.

Chest thickness for reference man is 23 cm. These values allow for some leeway, which 

result in values favorable to claimants. 

[3] Rohrig, Norman. ORAU Team. Site Expert.

Because radiation is attenuated by the body, the dose conversion factor is reduced for a larger 

person. Operators can increase the voltage slightly to compensate, which could increase the 

dose to an organ.

[4] Rohrig, Norman. ORAU Team. Site Expert.

If an organ is deeper in the body than a reference organ, there will be more attenuation to 

reach that organ.

[5] Rohrig, Norman. ORAU Team. Site Expert.

This is the same value as used for SRS and assumed in ORAUT-OTIB-0006 (ORAUT 2005a).

[6] Rohrig, Norman. ORAU Team. Site Expert.

For the early machine, the exposure time was 1/15 s or 8 pulses at 120 Hz from a full-wave 

rectifier power supply. A likely uncertainty is 1 pulse or 12.5%, which is less than the assigned 

uncertainty of 25%. Although the large uncertainty due to time does not apply to the high 

frequency Gendex machine, this uncertainty is included even though it only applies to the 

single phase machines. 

[7] Rohrig, Norman. ORAU Team. Site Expert.

ICRP did not state an uncertainty, but scientific expertise implies there is one. A 5% value 

would be consistent with stating the results to 2 significant digits. Determining a significantly 

smaller uncertainty would increase the effort significantly. This uncertainty does not drive the 

total uncertainty. 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 13 of 19

REFERENCES 

AEC (U.S. Atomic Energy Commission), 1961, Annual Report of the Health and Safety Division 1960, 

IDO-12019, Idaho Operations Office, Idaho Falls, Idaho, September. [SRDB Ref ID: 1230]

AEC (U.S. Atomic Energy Commission), 1969, "Chapter 0528, Occupational Health Program," AEC 

Manual, Washington, D.C., December 5. [SRDB Ref ID: 4644]

AEC (U.S. Atomic Energy Commission), 1972, 1971 Annual Report of the Health Services Laboratory, 

IDO-12076, Idaho Operations Office, Idaho Falls, Idaho. [SRDB Ref ID: 1431]

Collings, L. H., and P. Creighton, 2002, Idaho National Engineering and Environmental Laboratory 

(INEEL) History of the Occupational Medical Program (OMP) X-Ray Process, Bechtel BWXT 

Idaho, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho, April 8. 

[SRDB Ref ID: 1774, p. 9]

Cooley, R.C., 1967, “Personnel Radiation Exposures from Medical X-rays – Savannah River Plant – 

Part II,” memorandum to E. C. Morris, July 11. [SRDB Ref ID: 68124] 

Creighton, P. N., 2003, “Transmittal of Medical X-ray Information for the INEEL,” letter to L. Johnson 

(National Institute for Occupational Safety and Health), Idaho National Engineering and 

Environmental Laboratory, Idaho Falls, Idaho, June 24. [SRDB Ref ID: 4646]

ERDA (U.S. Energy Research and Development Administration), 1975, "Chapter 0528, ERDA 

Contractor Occupational Medical Program Handbook," ERDA Manual, Washington, D.C., 

August 21. [SRDB Ref ID: 4643]

ICRP (International Commission on Radiological Protection), 1982, Protection of the Patient in 

Diagnostic Radiology, Publication 34, Pergamon Press, Oxford, England.

NCRP (National Council on Radiation Protection and Measurements), 1989, Medical X-Ray, Electron 

Beam and Gamma-Ray Protection for Energies up to 50 MeV (Equipment Design, 

Performance and Use), Report 102, Bethesda, Maryland.

NIOSH (National Institute for Occupational Safety and Health), 2007, Radiation Exposures Covered 

for Dose Reconstructions Under Part B of the Energy Employees Occupational Illness 

Compensation Program Act, OCAS-IG-003, Rev. 0, Office of Compensation Analysis and 

Support, Cincinnati, Ohio, November. 

ORAUT (Oak Ridge Associated Universities Team), 2005a, Dose Reconstruction from Occupationally 

Related Diagnostic X-Ray Procedures, ORAUT-OTIB-0006, Rev. 03 PC-1, Oak Ridge, 

Tennessee, December 21.

ORAUT (Oak Ridge Associated Universities Team), 2005b, Savannah River Site, ORAUT-TKBS0003, Rev. 03, Oak Ridge, Tennessee, April 5.

Rohrig, N., 2003, notes on telephone conversation with J. Spickard of INEEL, Oak Ridge Associated 

Universities Team, Oak Ridge, Tennessee, November 12. [SRDB Ref ID: 13439]

Sommers, J. F., 1961, “Routine Blood Sampling Program at the MTR-ETR,” memorandum to All 

MTR/ETR Personnel, Som-165-61A-M, Phillips 66, National Reactor Testing Station, Idaho 

Falls, Idaho, December 15. [SRDB Ref ID: 4817]
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 14 of 19

Vivian, K. A., and Rockhold, L. E., 2003, "Transmittal of Medical Documents from the INEEL," letter to 

N. Rohrig (Intrepid Technology and Resources), CCN 46313, Bechtel BWXT Idaho, Idaho 

National Engineering and Environmental Laboratory, Idaho Falls, Idaho, November 18. 

[SRDB Ref ID: 7975]
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 15 of 19

GLOSSARY

U.S. Atomic Energy Commission (AEC) 

Federal agency created in 1946 to assume the responsibilities of the Manhattan Engineer 

District (nuclear weapons) and to manage the development, use, and control of nuclear energy 

for military and civilian applications. The U.S. Energy Research and Development 

Administration and the U.S. Nuclear Regulatory Commission assumed separate duties from 

the AEC in 1974. The U.S. Department of Energy succeeded the U.S. Energy Research and 

Development Administration in 1979.

anterior-posterior (AP) 

In relation to radiography, orientation of the body in which the X-rays pass from the front to the 

back of the body to the film. 

kerma 

Measure in units of absorbed dose (usually grays but sometimes rads) of the energy released 

by radiation from a substance. Kerma is the sum of the initial kinetic energies of all the 

charged ionizing particles liberated by uncharged particles per unit mass of a specified 

material. Free-in-air kerma refers to the amount of radiation at a location before adjustment 

for any external shielding from structures or terrain or backscatter from the body. The word 

derives from kinetic energy released per unit mass. 

lateral (LAT) 

In relation to radiography, orientation of the body in which the X-rays pass from one side of the 

body to the other.

posterior-anterior (PA) 

In relation to radiography, orientation of the body in which the X-rays pass from the back to the 

front of the body to the film. 

rad 

Traditional unit for expressing absorbed radiation dose, which is the amount of energy from 

any type of ionizing radiation deposited in any medium. A dose of 1 rad is equivalent to the 

absorption of 100 ergs per gram (0.01 joules per kilogram). The word derives from radiation 

absorbed dose. In the International System of Units (SI), the rad has been replaced by the 

gray (100 rads = 1 gray). 

radiograph 

Image produced on film by gamma rays or X-rays. Some of the rays (photons) can pass 

through parts of an item, while more opaque parts partially or completely absorb them and 

thus cast a shadow on the film. See radiology. 

X-ray 

(1) See X-ray radiation. (2) See radiograph. 

X-ray radiation 

Penetrating electromagnetic radiation (photons) of short wavelength (0.0005 to 10 

nanometers) and energy less than 250 kiloelectron-volts. X-rays usually come from excitation 

of the electron field around certain nuclei. Once formed, there is no difference between X-rays 

and gamma rays, but gamma photons originate inside the nucleus of an atom. 
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 16 of 19

Before 1954 

<1970 Chest

Area of skin

PA 

guidance

Dose 

(rem)

LAT (Left LAT) 

guidance Dose (rem)

R front shoulder EXSD 5.9E-03 ENSD 6.75E-01

R back shoulder ENSD 2.70E-01 ENSD 6.75E-01

L front shoulder EXSD 5.9E-03 EXSD 3.0E-03

L back shoulder ENSD 2.70E-01 EXSD 3.0E-03

R upper arm to elbow ENSD 2.70E-01 ENSD 6.75E-01

L upper arm to elbow ENSD 2.70E-01 EXSD 3.0E-03

L hand ENSD 2.70E-01 10% ENSD 6.75E-02

R hand ENSD 2.70E-01 10% ENSD 6.75E-02

L elbow, forearm, wrist ENSD 2.70E-01 10% ENSD 6.75E-02

R elbow, forearm, wrist ENSD 2.70E-01 10% ENSD 6.75E-02

R side of head (including ear) 10% ENSD 2.70E-02 Eye/Brain 6.85E-02

L side of head (including ear) 10% ENSD 2.70E-02 Eye/Brain 6.85E-02

Front left thigh RSD (0.52m) 8.E-05 RSD (0.52m) 1.E-04

Back left thigh RSD (0.52m) 8.E-05 RSD (0.52m) 1.E-04

Front right thigh RSD (0.52m) 8.E-05 RSD (0.52m) 1.E-04

Back right thigh RSD (0.52m) 8.E-05 RSD (0.52m) 1.E-04

L knee and below RSD (0.86m) 3.E-05 RSD (0.86m) 4.E-05

R knee and below RSD (0.86m) 3.E-05 RSD (0.86m) 4.E-05

L side of face Eye/brain 6.4E-03 Eye/brain 6.85E-02

R side of face Eye/brain 6.4E-03 Eye/brain 6.85E-02

L side of neck ENSD 2.70E-01 Eye/brain 6.85E-02

R side of neck ENSD 2.70E-01 Eye/brain 6.85E-02

Back of head 10% ENSD 2.70E-02 Eye/brain 6.85E-02

Front of neck Eye/brain 6.4E-03 Eye/brain 6.85E-02

Back of neck ENSD 2.70E-01 Eye/brain 6.85E-02

Front torso: Base of neck to end of 

sternum

EXSD 5.9E-03 Lung 1.10E-01

Front torso: End of sternum to lowest rib EXSD 5.9E-03 Lung 1.10E-01

Front torso: Lowest Rib to iliac crest EXSD 5.9E-03 Lung 1.10E-01

Front torso: Iliac crest to pubis 10% EXSD 5.9E-04 10% lung 1.10E-02

Back torso: Base of neck to mid-back ENSD 2.70E-01 Lung 1.10E-01

Back torso: Mid-back to lowest rib ENSD 2.70E-01 Lung 1.10E-01

Back torso: Lowest rib to iliac crest ENSD 2.70E-01 Lung 1.10E-01

Back torso: buttocks (Iliac crest and below) 10% ENSD 2.70E-02 10% lung 1.10E-02

Right torso: Base of neck to end of 

sternum

ENSD 2.70E-01 ENSD 6.75E-01

Right torso: End of sternum to lowest rib ENSD 2.70E-01 ENSD 6.75E-01

Right torso: Lowest Rib to iliac crest ENSD 2.70E-01 ENSD 6.75E-01

Right torso: Iliac crest to pubis (R hip) 10% ENSD 2.70E-02 10% ENSD 6.75E-02

Left torso: Base of neck to end of sternum ENSD 2.70E-01 EXSD 3.0E-03

Left torso: End of sternum to lowest rib ENSD 2.70E-01 EXSD 3.0E-03

Left torso: Lowest Rib to iliac crest ENSD 2.70E-01 EXSD 3.0E-03

Left torso: Iliac crest to pubis (L hip) 10% ENSD 2.70E-02 10% EXSD 3.E-04

ATTACHMENT A

DOSES TO OTHER AREAS OF THE SKIN

Page 1 of 4
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 17 of 19

1954–1969

<1970 Chest

Area of skin PA Guidance

Dose 

(rem)

LAT (Left LAT) 

Guidance Dose (rem)

R front shoulder EXSD 1.5E-03 ENSD 9.96E-02

R back shoulder ENSD 7.02E-02 ENSD 9.96E-02

L front shoulder EXSD 1.5E-03 EXSD 4.E-04

L back shoulder ENSD 7.02E-02 EXSD 4.E-04

R upper arm to elbow ENSD 7.02E-02 ENSD 9.96E-02

L upper arm to elbow ENSD 7.02E-02 EXSD 4.E-04

L hand ENSD 7.02E-02 10% ENSD 1.0E-02

R hand ENSD 7.02E-02 10% ENSD 1.0E-02

L elbow, forearm, wrist ENSD 7.02E-02 10% ENSD 1.0E-02

R elbow, forearm, wrist ENSD 7.02E-02 10% ENSD 1.0E-02

R side of head (including ear) 10% ENSD 7.0E-03 Eye/brain 1.01E-02

L side of head (including ear) 10% ENSD 7.0E-03 Eye/brain 1.01E-02

Front left thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Back left thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Front right thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Back right thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

L knee and below RSD (0.86m) 7.E-06 RSD (0.86m) 6.E-06

R knee and below RSD (0.86m) 7.E-06 RSD (0.86m) 6.E-06

L side of face Eye/brain 1.7E-03 Eye/brain 1.01E-02

R side of face Eye/brain 1.7E-03 Eye/brain 1.01E-02

L side of neck ENSD 7.02E-02 Eye/brain 1.01E-02

R side of neck ENSD 7.02E-02 Eye/brain 1.01E-02

Back of head 10% ENSD 7.0E-03 Eye/brain 1.01E-02

Front of neck Eye/brain 1.7E-03 Eye/brain 1.01E-02

Back of neck ENSD 7.02E-02 Eye/brain 1.01E-02

Front torso: base of neck to end of sternum EXSD 1.5E-03 Lung 1.62E-02

Front torso: end of sternum to lowest rib EXSD 1.5E-03 Lung 1.62E-02

Front torso: lowest rib to iliac crest EXSD 1.5E-03 Lung 1.62E-02

Front torso: iliac crest to pubis 10% EXSD 2.E-04 10% lung 1.6E-03

Back torso: base of neck to mid-back ENSD 7.02E-02 Lung 1.62E-02

Back torso: mid-back to lowest rib ENSD 7.02E-02 Lung 1.62E-02

Back torso: lowest rib to iliac crest ENSD 7.02E-02 Lung 1.62E-02

Back torso: buttocks (iliac crest and below) 10% ENSD 7.0E-03 10% lung 1.6E-03

Right torso: base of neck to end of sternum ENSD 7.02E-02 ENSD 9.96E-02

Right torso: end of sternum to lowest rib ENSD 7.02E-02 ENSD 9.96E-02

Right torso: lowest rib to iliac crest ENSD 7.02E-02 ENSD 9.96E-02

Right torso: iliac crest to pubis (r hip) 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Left torso: base of neck to end of sternum ENSD 7.02E-02 EXSD 4.E-04

Left torso: end of sternum to lowest rib ENSD 7.02E-02 EXSD 4.E-04

Left torso: lowest rib to iliac crest ENSD 7.02E-02 EXSD 4.E-04

Left torso: iliac crest to pubis (l hip) 10% ENSD 7.0E-03 10% EXSD 4.E-05

ATTACHMENT A

DOSES TO OTHER AREAS OF THE SKIN

Page 2 of 4
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 18 of 19

1970–1990

>1970 Chest

Area of skin PA Guidance

Dose 

(rem)

LAT (Left LAT) 

Guidance Dose (rem)

R front shoulder EXSD 1.5E-03 ENSD 9.96E-02

R back shoulder ENSD 7.02E-02 ENSD 9.96E-02

L front shoulder EXSD 1.5E-03 EXSD 4.E-04

L back shoulder ENSD 7.02E-02 EXSD 4.E-04

R upper arm to elbow 10% ENSD 7.0E-03 ENSD 9.96E-02

L upper arm to elbow 10% ENSD 7.0E-03 EXSD 4.E-04

L hand 10% ENSD 7.0E-03 10% ENSD 1.0E-02

R hand 10% ENSD 7.0E-03 10% ENSD 1.0E-02

L elbow, forearm, wrist 10% ENSD 7.0E-03 10% ENSD 1.0E-02

R elbow, forearm, wrist 10% ENSD 7.0E-03 10% ENSD 1.0E-02

R side of head (including ear) 10% ENSD 7.0E-03 10% ENSD 1.0E-02

L side of head (including ear) 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Front left thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Back left thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Front right thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

Back right thigh RSD (0.52m) 2.E-05 RSD (0.52m) 2.E-05

L knee and below RSD (0.86m) 7.E-06 RSD (0.86m) 6.E-06

R knee and below RSD (0.86m) 7.E-06 RSD (0.86m) 6.E-06

L side of face Eye/Brain 1.7E-03 10% ENSD 1.0E-02

R side of face Eye/Brain 1.7E-03 10% ENSD 1.0E-02

L side of neck 10% ENSD 7.0E-03 10% ENSD 1.0E-02

R side of neck 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Back of head 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Front of neck Thyroid 1.7E-03 10% ENSD 1.0E-02

Back of neck 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Front torso: base of neck to end of 

sternum EXSD 1.5E-03 Lung 1.62E-02

Front torso: end of sternum to lowest rib EXSD 1.5E-03 Lung 1.62E-02

Front torso: lowest rib to iliac crest 10% EXSD 2.E-04 10% lung 1.62E-02

Front torso: iliac crest to pubis 10% EXSD 2.E-04 10% lung 1.6E-03

Back torso: base of neck to mid-back ENSD 7.02E-02 Lung 1.62E-02

Back torso: mid-back to lowest rib ENSD 7.02E-02 Lung 1.62E-02

Back torso: lowest rib to iliac crest 10% ENSD 7.0E-03 10% lung 1.62E-02

Back torso: buttocks (iliac crest and below) 10% ENSD 7.0E-03 10% lung 1.6E-03

Right torso: base of neck to end of 

sternum ENSD 7.02E-02 ENSD 9.96E-02

Right torso: end of sternum to lowest rib ENSD 7.02E-02 ENSD 9.96E-02

Right torso: lowest rib to iliac crest 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Right torso: iliac crest to pubis (r hip) 10% ENSD 7.0E-03 10% ENSD 1.0E-02

Left torso: base of neck to end of sternum ENSD 7.02E-02 EXSD 4.E-04

Left torso: end of sternum to lowest rib ENSD 7.02E-02 EXSD 4.E-04

Left torso: lowest rib to iliac crest 10% ENSD 7.0E-03 10% EXSD 4.E-04

Left torso: iliac crest to pubis (l hip) 10% ENSD 7.0E-03 10% EXSD 4.E-05

ATTACHMENT A

DOSES TO OTHER AREAS OF THE SKIN

Page 3 of 4 

ATTACHMENT A

DOSES TO OTHER AREAS OF THE SKIN

Page 3 of 4
Document No. ORAUT-TKBS-0007-3 Revision No. 02 Effective Date: 12/21/2009 Page 19 of 19

1990–present

>1970 Chest

Area of skin PA Guidance

Dose 

(rem)

LAT (Left LAT) 

Guidance Dose (rem)

R front shoulder EXSD 2.2E-03 ENSD 1.06E-01

R back shoulder ENSD 7.42E-02 ENSD 1.06E-01

L front shoulder EXSD 2.2E-03 EXSD 7.E-04

L back shoulder ENSD 7.42E-02 EXSD 7.E-04

R upper arm to elbow 10% ENSD 7.4E-03 ENSD 1.06E-01

L upper arm to elbow 10% ENSD 7.4E-03 EXSD 7.E-04

L hand 10% ENSD 7.4E-03 10% ENSD 1.06E-02

R hand 10% ENSD 7.4E-03 10% ENSD 1.06E-02

L elbow, forearm, wrist 10% ENSD 7.4E-03 10% ENSD 1.06E-02

R elbow, forearm, wrist 10% ENSD 7.4E-03 10% ENSD 1.06E-02

R side of head (including ear) 10% ENSD 7.4E-03 10% ENSD 1.06E-02

L side of head (including ear) 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Front left thigh RSD (0.52m) 3.E-05 RSD (0.52m) 2.E-05

Back left thigh RSD (0.52m) 3.E-05 RSD (0.52m) 2.E-05

Front right thigh RSD (0.52m) 3.E-05 RSD (0.52m) 2.E-05

Back right thigh RSD (0.52m) 3.E-05 RSD (0.52m) 2.E-05

L knee and below RSD (0.86m) 1.E-05 RSD (0.86m) 7.E-06

R knee and below RSD (0.86m) 1.E-05 RSD (0.86m) 7.E-06

L side of face Eye/brain 3.3E-03 10% ENSD 1.06E-02

R side of face Eye/brain 3.3E-03 10% ENSD 1.06E-02

L side of neck 10% ENSD 7.4E-03 10% ENSD 1.06E-02

R side of neck 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Back of head 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Front of neck Thyroid 3.3E-03 10% ENSD 1.06E-02

Back of neck 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Front torso: base of neck to end of 

sternum EXSD 2.2E-03 Lung 2.36E-02

Front torso: end of sternum to lowest rib EXSD 2.2E-03 Lung 2.36E-02

Front torso: lowest rib to iliac crest 10% EXSD 2.E-04 10% lung 2.4E-03

Front torso: iliac crest to pubis 10% EXSD 2.E-04 10% lung 2.4E-03

Back torso: base of neck to mid-back ENSD 7.42E-02 Lung 2.36E-02

Back torso: mid-back to lowest rib ENSD 7.42E-02 Lung 2.36E-02

Back torso: lowest rib to iliac crest 10% ENSD 7.4E-03 10% lung 2.4E-03

Back torso: buttocks (iliac crest and below) 10% ENSD 7.4E-03 10% lung 2.4E-03

Right torso: base of neck to end of 

sternum ENSD 7.42E-02 ENSD 1.06E-01

Right torso: end of sternum to lowest rib ENSD 7.42E-02 ENSD 1.06E-01

Right torso: lowest rib to iliac crest 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Right torso: iliac crest to pubis (r hip) 10% ENSD 7.4E-03 10% ENSD 1.06E-02

Left torso: base of neck to end of sternum ENSD 7.42E-02 EXSD 7.E-04

Left torso: end of sternum to lowest rib ENSD 7.42E-02 EXSD 7.E-04

Left torso: lowest rib to iliac crest 10% ENSD 7.4E-03 10% EXSD 7.E-05

Left torso: iliac crest to pubis (l hip) 10% ENSD 7.4E-03 10% EXSD 7.E-05

ATTACHMENT A

DOSES TO OTHER AREAS OF THE SKIN

Page 4 of 4