DRAFT 

REPORT TO THE ADVISORY BOARD 

ON RADIATION AND WORKER HEALTH

National Institute for Occupational Safety and Health 

SC&A’S DOSE RECONSTRUCTION 

OF CASE #[REDACTED] FROM THE 

FERNALD ENVIRONMENTAL MANAGEMENT PROJECT 

Contract No. 200-2009-28555 

SCA-TR-BDR2014-CN[REDACTED]

Prepared by 

Douglas Farver 

John Mauro 

Nicole Briggs 

S. Cohen & Associates 

1608 Spring Hill Road, Suite 400 

Vienna, Virginia 22182 

January 2014 

Disclaimer 

This document is made available in accordance with the unanimous desire of the Advisory Board on Radiation and 

Worker Health (ABRWH) to maintain all possible openness in its deliberations. However, the ABRWH and its 

contractor, SC&A, caution the reader that at the time of its release, this report is pre-decisional and has not been 

reviewed by the Board for factual accuracy or applicability within the requirements of 42 CFR 82. This implies that 

once reviewed by the ABRWH, the Board’s position may differ from the report’s conclusions. Thus, the reader 

should be cautioned that this report is for information only and that premature interpretations regarding its 

conclusions are unwarranted.
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S. Cohen & Associates:

Technical Support for the Advisory Board on

Radiation & Worker Health Review of

NIOSH Dose Reconstruction Program

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Effective Date: 

Draft – January 13, 2014

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BLIND DOSE RECONSTRUCTION 

OF CASE #[REDACTED] FROM THE

FERNALD ENVIRONMENTAL 

MANAGEMENT PROJECT

Page 2 of 75

Task Manager:

________________________ Date: __________

Douglas Farver, CHP

Supersedes:

N/A

Project Manager:

________________________ Date: __________

John Stiver, MS, CHP

Reviewers:

 Kathy Behling

 John Stiver

Record of Revisions

Revision 

Number Effective Date Description of Revision

0 (Draft) 01/13/2014 Initial issued.
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TABLE OF CONTENTS 

Executive Summary ........................................................................................................................ 5

Relevant Background Information ...................................................................................... 5

Presentation of Results ........................................................................................................ 6

Section I: DR–Method A ............................................................................................................... 8

I.1 Dose Reconstruction Overview .............................................................................. 8

I.1.1 SC&A Blind DR Approach ........................................................................ 8

I.2 External Doses ........................................................................................................ 9

I.2.1 Recorded Photon Doses ............................................................................ 10

I.2.2 Missed Photon Doses ................................................................................ 11

I.2.3 Recorded Electron (Shallow) Dose ........................................................... 12

I.3 Occupational Medical Dose .................................................................................. 13

I.4 Onsite Ambient Dose ............................................................................................ 13

I.5 Internal Dose ......................................................................................................... 13

I.5.1 Dose from Uranium .................................................................................. 15

I.5.2 Dose from Recycled Uranium Contaminants ........................................... 17

I.6 Environmental Dose.............................................................................................. 17

I.7 CATI Report and Radiological Incidents ............................................................. 17

I.8 Summary Conclusions .......................................................................................... 18

I.9 References ............................................................................................................. 18

Appendix I.A-1: IREP Input – SCC [Redacted] .............................................................. 20

Appendix I.A-2: IREP Input – BCC [Redacted] ............................................................. 24

Appendix I.A-3: IREP Input – BCC [Redacted] ............................................................. 28

Appendix I.A-4: IREP Input – SCC [Redacted] .............................................................. 32

Appendix I.A-5: IREP Input – SCC [Redacted] .............................................................. 36

Section II: DR–Method B ............................................................................................................ 40

II.1 Dose Reconstruction Overview ............................................................................ 40

II.1.1 Dose Reconstruction Approach ................................................................ 40

II.2 Relevant Case Information ....................................................................... 41

II.2.1 Interpretation of CATI and Other Background Information as 

Applicable to the DR ................................................................................ 42

II.2.2 Radiation Incidents ................................................................................... 43

II.2.3 Radiation Monitoring and Control Measures ........................................... 43

II.2.4 Primary Radionuclides of Concern ........................................................... 44

II.3 Reconstruction of External Dose .......................................................................... 45

II.3.1 Reliability of Skin Doses as Reconstructed Using External Beta 

Dosimetry Data ......................................................................................... 46

II.3.2 Reliability of Methods Used to Reconstruct Neutron Exposures ............. 51

II.3.3 Skin Exposures Associated with Deposition of Uranium Directly on 

Skin and Clothing ..................................................................................... 53

II.4 Internal Dose ......................................................................................................... 56

II.4.1 DR Assumptions ....................................................................................... 57

II.5 References ............................................................................................................. 61
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Appendix II.A-1: IREP Input – [Redacted] SCC on the [Redacted] ............................... 63

Appendix II.A-2: IREP Input – [Redacted] BCC on the [Redacted] ............................... 67

Appendix II.A-3: IREP Input – [Redacted] SCCs and BCC ........................................... 71

Attachment 1: Independent Verification of Dose Conversion Factor for Uranium 

Dust Settling on Skin ............................................................................................ 75

LIST OF TABLES 

Table ES-1. Primary Cancers ......................................................................................................... 5

Table ES-2. Derived Dose Estimates ............................................................................................. 6

Table I-1. Cancers and Diagnosis Date.......................................................................................... 8

Table I-2. Summary of SC&A-Derived External/Internal Dose Estimates for Method A ............ 9

Table I-3. External Dosimetry Records for FEMP Case #[Redacted] ........................................... 9

Table I-4. Effective Dose Conversion Factors and Energy Distributions for Plant [redact] ....... 10

Table I-5. Occupational Medical Doses ....................................................................................... 13

Table I-6. FEMP Uranium Bioassay Capabilities........................................................................ 13

Table I-7. Uranium Bioassay Results .......................................................................................... 14

Table I-8. Uranium Intakes .......................................................................................................... 16

Table I-9. Comparison of Alpha Dose Using IMBA and CADW ............................................... 16

Table I-10. Intakes from RU Contaminants ................................................................................. 17

Table II-1. Summary of SC&A-Derived Dose Estimates for Method B ..................................... 40

Table II-2. Specific Activities and Activity Fractions* ............................................................... 45

Table II-3. Example of External Dosimetry Data Recorded in Behalf of Case #[redacted] ....... 46

Table II-4. Tc-99 Content in Dust Samples ................................................................................. 50

Table II-5. Tc-99 Content in Waste Streams ............................................................................... 50

Table II-6. Statistical Parameters of Neutron-to-Photon Ratios .................................................. 52

Table II-7. External DR Parameters for Case #[redacted] ........................................................... 57

Table II-8. Skin Cancers and Total Assigned Doses ................................................................... 58

Table II-9. External Doses Calculated by SC&A (rem) .............................................................. 58

Table II-10. Calculated POC for Skin Cancers for Case #[redacted] .......................................... 61
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EXECUTIVE SUMMARY 

Under Contract No. 200-2009-28555, SC&A has been tasked by the Advisory Board on 

Radiation and Worker Health (Advisory Board) to perform eight blind dose reconstructions 

(DRs). This report presents the methodologies and results of our DR of one of the eight blind 

cases selected by the Advisory Board. 

To perform this blind DR, SC&A was provided with all of the Department of Energy (DOE) 

dosimetry records; the Department of Labor (DOL) correspondence, forms, and medical records; 

and the Computer-Assisted Telephone Interview (CATI) Report that were made available to the 

National Institute for Occupational Safety and Health (NIOSH) for constructing doses in behalf 

of Case #[redacted]. SC&A used two independent approaches to reconstruct occupational doses 

associated with this case. Both approaches used the available dosimetry records and current 

technical guidance documents published by NIOSH and the Oak Ridge Associated Universities 

Team (ORAUT). The first approach, which is referred to as DR–Method A, used the 

spreadsheets and other tools developed by NIOSH to calculate the doses, whereas the second 

approach, referred to as DR–Method B, manually calculated the doses [with the assistance of the 

internal dosimetry computer program Integrated Modules for Bioassay Analysis (IMBA)]. 

This Executive Summary provides an overview of the case and a comparison of the results of the 

two independent DR methods. Section I of this report provides a detailed discussion of the 

approach used to reconstruct external/internal occupational radiation doses using DR–Method A,

and Section II describes the reconstruction of doses using DR–Method B. 

RELEVANT BACKGROUND INFORMATION 

According to the DOL records, this case represents an energy employee (EE) who worked at the 

Feed Materials Production Center [FMPC, later known as the Fernald Environmental 

Management Project (FEMP)] from [redacted] to [redacted]. The EE was diagnosed with 

multiple squamous and basal cell skin cancers. The primary cancers, diagnosis dates, and 

ICD-9 codes are shown in Table ES-1. 

Table ES-1. Primary Cancers 

Diagnosis Date Description ICD-9 Code

[redacted] SCC [redacted] [redacted]

[redacted] BCC [redacted] [redacted]

[redacted] BCC [redacted] [redacted]

[redacted] SCC [redacted] [redacted]

[redacted] SCC [redacted] [redacted]

According to the DOE records and the CATI Report, the majority of the EE’s radiation exposure 

was received while working as a [redacted], [redacted], [redacted], [redacted], [redacted], 

[redacted], and [redacted], primarily in Plant [redacted], [redacted]. During the course of 

employment, the EE was monitored for external photon and electron radiation exposure and 

internal radiation exposure via in-vitro bioassays and chest counts. 
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PRESENTATION OF RESULTS 

The results of both independent DR methods are shown in Table ES-2. DR–Method A 

calculated external and internal doses using the EE’s dosimetry records. This method derived a 

total skin dose to the chest of 15.817 rem and doses ranging from 18.057 rem to 18.092 rem for 

the skin cancers of the [redacted], [redacted], [redacted], and [redacted]. The Method A skin 

doses varied depending on cancer location and date of diagnosis. 

DR–Method B derived a total skin dose to the chest of 16.510 rem and a dose of 18.818 rem to 

the skin of the [redacted], [redacted], [redacted], and [redacted]. DR–Method B explicitly 

evaluated external dose from photon, beta, and neutron dose, and occupational medical dose. 

Also, special consideration was given to the possible contribution of Tc-99 to the external dose, 

along with the skin dose that might have resulted from the direct deposition of uranium dust onto 

skin and clothing. Internal dose to the organs of concern included inhalation of uranium and 

consideration of the internal dose to the skin from recycled uranium. 

Table ES-2. Derived Dose Estimates 

DR–Method A DR–Method B

#1 SCC 

[redact]

(rem)

#2 BCC 

[redact]

(rem)

#3 BCC 

[redact]

(rem)

#4 SCC 

[redact]

(rem)

#5 SCC 

[redact]

(rem)

[redact]

(rem) 

(attenuated)

[redact], [redact], 

[redact], [redact]

(rem)

(unattenuated)

External Dose (Occupational)

 ▪ Recorded Photon Dose 

 <30 keV Photons 0.190 0.190 0.190 0.190 0.190 0.175 0.175

 30–250 keV Photons 0.481 0.481 0.481 0.481 0.481 0.545 0.545

 >250 keV Photons 0.764 0.764 0.764 0.764 0.764 0.877 0.877

 ▪ Missed Photon Dose 

 < 30 keV Photons 

– – – – – 0.024 0.024

 30–250 keV Photons 0.980 0.980 0.980 0.980 0.980 0.403 0.403

 >250 keV Photons – – – – – 0.479 0.479

 ▪ Missed Neutron Dose – – – – – 0.288 0.288

 ▪ Skin Deposition – – – – – 0.0845 0.0845

 ▪ Recorded Shallow Dose 

 Electrons >15 keV 13.304 15.559 15.559 15.559 15.559 13.265 15.519

 ▪ Occupational Medical Dose 0.065 0.049 0.041 0.081 0.081 0.131 0.131

Internal Dose 

 Uranium 0.030 0.031 0.034 0.034 0.034 0.238 0.293

 RU Contaminants 0.003 0.003 0.003 0.003 0.003 – –

Total 15.817 18.057 18.052 18.092 18.092 16.510 18.818

Even though two different DR approaches were used, the total skin doses calculated by DR–

Method A and DR–Method B for all skin cancers are nearly identical. Both DR methods 

assigned the majority of dose to exposure to electrons >15 keV (shallow dose), since the 
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recorded electron dose was by far the dominant contributor to skin dose, and both methods 

employed similar approaches to reconstruct these doses. However, as noted in Table ES-2, 

though the two approaches derived similar total doses, there are substantial differences in the 

approaches to reconstruct other portions of the external dose and internal dose. Only Method B 

considered neutron dose and dose due to potential skin contamination from deposition of 

radioactive particles. The disparity in occupational medical doses can be attributed to the fact 

that the two DR methods used differing guidance documents for assessing the x-ray dose. In 

addition, the significant difference in internal doses was due to varying approaches taken in 

fitting the bioassay data to an intake in IMBA. 

 

Both DR methods calculated a POC using NIOSH-Interactive RadioEpidemiological Program 

(IREP, v.5.7). Method A calculated a probability of causation (POC) value of 38.12%, and 

Method B derived a POC value of 39.33%, as described in Sections I and II below. 
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SECTION I: DR–METHOD A 

I.1 DOSE RECONSTRUCTION OVERVIEW 

This report presents the results of an independent blind dose reconstruction (DR) performed by 

SC&A for an energy employee (EE) who worked at the Feed Materials Production Center 

(FMPC) [later known as the Fernald Environmental Management Project (FEMP)] from October 

13, 1982, to March 31, 1997. The EE was diagnosed with five skin cancers (basal and 

squamous cell carcinoma) on the [redacted], [redacted], [redacted], [redacted], and 

[redacted], as shown in Table I-1. 

Table I-1. Cancers and Diagnosis Date 

# Description Primary/Secondary Diagnosis Date ICD-9 Code

1 SCC [redacted] Primary [redacted] [redacted]

2 BCC [redacted] Primary [redacted] [redacted]

3 BCC [redacted] Primary [redacted] [redacted]

4 SCC [redacted] Primary [redacted] [redacted]

5 SCC [redacted] Primary [redacted] [redacted]

According to the Computer-Assisted Telephone Interview (CATI) report, the EE was a 

[redacted], [redacted], [redacted], [redacted], [redacted], [redacted], and [redacted], and 

worked primarily in Plant [redacted], [redacted]. Uranium metal products were heat-treated 

and were extruded either onsite or sent offsite and returned to be machined into the final 

products. The EE was monitored for external photon and electron exposures from [redacted] 

through [redacted]. Internal exposure monitoring was also conducted by means of in-vitro 

bioassays and chest counts from [redacted] through [redacted].

I.1.1 SC&A BLIND DR APPROACH

SC&A reviewed all of the DOE records provided on behalf of this EE and all of the NIOSH 

procedures relevant to this case, which includes the Technical Basis Document (TBD) for the 

FEMP (issued as six separate TBDs numbered ORAUT-TKBS-0017-1 through ORAUT-TKBS0017-6) and Interpretation of Dosimetry Data for Assignment of Shallow Dose (ORAUT-OTIB0017). Using the guidance provided in these documents, along with the EE’s dosimetry records, 

SC&A manually calculated reasonable, claimant-favorable annual organ doses for each of the 

cancers, as shown in Table I-2. Appendices I.A-1 through I.A-5 provide a list of SC&A’s annual 

organ doses and also include IREP input parameters, such as energy range, distribution type, and 

uncertainty for each year. 
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Table I-2. Summary of SC&A-Derived External/Internal Dose Estimates for Method A 

#1 SCC 

[redact]

(rem)

#2 BCC 

[redact]

(rem)

#3 BCC 

[redact]

(rem)

#4 SCC 

[redact]

(rem)

#5 SCC 

[redact]

(rem)

External Dose (Occupational):*

 ▪ Recorded Photon Dose 

- <30 keV Photons: 0.190 0.190 0.190 0.190 0.190

- 30–250 keV Photons: 0.481 0.481 0.481 0.481 0.481

- >250 keV Photons: 0.764 0.764 0.764 0.764 0.764

 ▪ Missed Photon Dose - 30–250 keV Photons: 0.980 0.980 0.980 0.980 0.980

 ▪ Recorded Shallow Dose- Electrons >15 keV: 13.304 15.559 15.559 15.559 15.559

 ▪ Occupational Medical Dose: 0.065 0.049 0.041 0.081 0.081

Internal Dose:

- Uranium 0.030 0.031 0.034 0.034 0.034

- RU Contaminants 0.003 0.003 0.003 0.003 0.003

Total 15.817 18.057 18.052 18.092 18.092

* This table is limited to doses reconstructed based on external exposures “at a distance,” as measured by film 

badges, and does not include skin exposures that may have resulted from direct skin contamination. 

SC&A determined the probability of causation (POC) for this case using these annual doses as 

input into the IREP program. Since the EE was diagnosed with five independent cases of skin 

cancer, these doses were entered five times into the IREP program, one for each instance or 

cancer. The total doses shown in Table I-2 produced a POC of 38.12%. 

I.2 EXTERNAL DOSES 

The reconstruction of the skin dose to the EE began with a review of the EE’s film badge 

exposure records. A summary of the EE’s annual dosimetry records is shown in Table I-3. 

Dosimeter readings that were less than the LOD/2 were set to zero. 

Table I-3. External Dosimetry Records for FEMP Case #[Redacted]

Year Deep/DDE (rem) Shallow/Skin 

(rem)

[redact] 0.000 0.029

[redact] 0.159 2.881

[redact] 0.289 3.627

[redact] 0.141 2.039

[redact] 0.134 2.203

[redact] 0.402 4.512

[redact] 0.164 0.895

[redact] 0.021 0.355 

[redact] 0.000 0.000

[redact] 0.027 0.028

[redact] 0.000 0.000 

[redact] 0.037 0.301

[redact] 0.012 0.012 

[redact] 0.012 0.075 

[redact] 0.000 0.000 

[redact] 0.016 0.016
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In the sections that follow, a description is provided of how we reconstructed the dose to the skin 

considering recorded photon, beta doses, and missed doses. 

I.2.1 RECORDED PHOTON DOSES 

The DOE records show that this EE received positive recorded photon doses during each year 

from [redact] to [redact] except [redact] and [redact], [redact], and [redact]. SC&A used the 

guidance described in ORAUT-TKBS-0017-6 and ORAUT-OTIB-0017 in order to derive the 

organ dose from this exposure. The organ dose conversion factor (DCF) of 1.00 was applied in 

accordance with the External Dose Reconstruction Implementation Guideline (OCAS-IG-001). 

Based on guidance in ORAUT-TKBS-0017-6 and assuming the EE worked in Plant 6, an energy 

distribution of 13% <30 keV photons, 33% 30–250 keV photons, and 54% >250 keV photons 

was assumed. All electron doses are assumed to be associated with the >15 keV energy range. 

Table I-4 cites all DCFs used for calculating photon doses. 

Table I-4. Effective Dose Conversion Factors and Energy Distributions for Plant [redact]

Plant 6 – Exposure ([redact]–[redact])

Radiation Type Photons

Energy Range <30 keV 30–250 keV >250 keV

Energy Fraction 0.130 0.330 0.540

ICRP 60 CF NA NA NA

Organ DCF 1.000 1.000 1.000

Dosimeter CF 1.1 1.1 1

Eff. DCF*0.143 0.363 0.540

Plant 6 – Deep Dose Equivalent ([redact]–[redact])

Radiation Type Photons

Energy Range <30 keV 30–250 keV >250 keV

Energy Fraction 0.130 0.330 0.540

ICRP 60 CF NA NA NA

Organ DCF 1.000 1.000 1.000

Eff. DCF*0.130 0.330 0.540

*

 Effective DCF incorporates all correction factors cited above. 

Using the parameters provided in Table I-4 above, SC&A calculated the [redact] photon dose to 

the skin as follows:

[Redact]: Records show that for [redact], the EE received a deep dose (D) of 0.159 rem. 

The photon dose to the skin was assumed to be 13% <30 keV, 33% 30–250 keV and 54% 

>250 keV. An organ DCF of 1.0 for the skin was applied. A dosimeter correction factor

(CF) of 1.1 was applied for <30 keV photon and 30–250 keV photon doses until [redact].

 Skin Dose (<30 keV) = D × CF × DCF × 13% 

= 0.159 × 1.10 × 1.0 × 0.13 

 = 0.023 rem 

 Skin Dose (30–250 keV) = D × CF × DCF × 33% 

= 0.159 × 1.10 × 1.0 × 0.33 

 = 0.058 rem 
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 Skin Dose (>250 keV) = D × CF × DCF × 54% 

= 0.159 × 1 × 1.0 × 0.54 

 = 0.086 rem 

SC&A’s calculated <30 keV, 30–250 keV, and >250 keV skin doses are shown in entries #1, 

#13, and #25 of Appendices I.A-1 through I.A-5. 

The recorded photon doses were entered into IREP as a constant distribution with no uncertainty. 

I.2.2 MISSED PHOTON DOSES 

The EE was monitored on a monthly dosimeter exchange schedule from [redact]–[redact] and 

quarterly from [redact]–[redact]. Both OCAS-IG-001 and the FEMP TBD suggest assigning 

missed dose to monitored workers who received doses below the limit of detection (LOD).1 

After correcting for values that were below the LOD, SC&A counted a total of 89 zero photon 

readings during the EE’s employment. In order to calculate missed photon dose, the number of 

zero readings is multiplied by the appropriate LOD/2 value, along with the DCF. However, the 

site-specific guidance in ORAUT-OTIB-0017 cites the following for the assignment of missed 

dose to the skin.

1. If only the OW (shallow) reading was reported as zero, the missed dose 

assigned should be the appropriate OW LOD (divided by 2, treated as 

lognormal) and considered >15 keV electrons. 

2. If only the S (deep) reading was reported as zero, the missed dose assigned 

should be the appropriate S LOD (divided by 2, treated as lognormal) and 

considered 30–250 keV photons. 

3. If both the OW and S readings were reported as zero, the missed dose 

assigned should be the appropriate OW LOD (divided by 2, treated as 

lognormal) and considered 30–250 keV photons. 

SC&A followed the guidance presented in ORAUT-OTIB-0017, and found that there were no 

instances when the photon (or S) reading was positive and the beta (or OW) reading was zero. 

Therefore, there are no missed doses listed in the appendices for >15 keV electrons. The only 

missed doses are for 30–250 keV photons. 

For example, SC&A calculated the [redact] missed photon dose to the skin as follows:

[Redact]: Records show that for [redact], there were six dosimeter readings that were either 

zero or less than the LOD and marked as zero. The LOD for the time period is 0.030 rem, 

making the LOD/2 equal to 0.015 rem.

 

1

 On occasion, a worker’s records may indicate a dose for a given change-out period that is less than the 

LOD, but greater than the LOD/2. Under these circumstances, the reported value is assigned, as opposed to LOD/2, 

in order to be claimant favorable. However, the more typical case is that the reported value is “0,” which means less 

than the LOD. In these instances, the LOD/2 is assigned for a given change-out period. 
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 Skin Dose (30–250 keV) = (# zeros × LOD/2) × DCF 

= (6 × 0.015 rem) × 1.0 

 = 0.090 rem 

SC&A’s calculated 30–250 keV missed dose of 0.090 rem is shown in entry #49 of 

Appendices I.A-1 through I.A-5. 

The 30–250 keV photon missed doses were entered into IREP as a lognormal distribution with 

an uncertainty of 1.520. 

I.2.3 RECORDED ELECTRON (SHALLOW) DOSE 

The non-penetrating dose was assumed to be the reported beta dose in the site “Occupational 

Radiation Exposure Report” and was applied as >15 keV electrons. An additional correction for 

clothing attenuation was applied per guidance in the Technical Information Bulletin (TIB),

Interpretation of Dosimetry Data for Assignment of Shallow Dose (ORAUT-OTIB-0017). A 

reduction of the electron dose due to attenuation from clothing was applied to the SCC on the 

[redact] (#1 from Table I-1), because this cancer is located in an area normally covered with 

clothing. The calculated electron doses were multiplied by 0.855, which represents the midpoint 

of the uranium attenuation factors reported for two pairs of coveralls, including the paper liner 

(0.80) and one Dacron/cotton lab coat (0.91). Because the specific clothing worn by the EE 

could not be determined, the approach adopted is considered reasonable. The electron doses for 

the other four cancers were not reduced, because they were in locations where the skin would not 

normally be covered. 

For example, SC&A calculated the [redact] >15 keV dose to the skin of the [redact] as follows:

[Redact]: Records show that for [redact], the EE’s recorded deep dose (D) was 0.159 rem 

and the recorded shallow dose was 2.881 rem. The >15 keV electron dose is the difference 

between the shallow and deep doses multiplied by the organ DCF and, for this cancer, an 

attenuation factor of 0.855.

 Skin Dose (>15 keV electrons) = (shallow – deep) × DCF × 0.855 

= (2.881 rem – 0.159 rem) × 1.0 × 0.855 

 = 2.327 rem 

SC&A’s calculated >15 keV electron dose of 2.327 rem is shown in entry #38 of Appendix A-1. 

The non-attenuated value of 2.722 rem is shown in entry #38 of Appendices A-2 through A-5. 

The >15 keV electron doses were entered into IREP as a constant distribution with no 

uncertainty. 
Effective Date:

January 13, 2014

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I.3 OCCUPATIONAL MEDICAL DOSE 

The DOE records show that the EE received seven PA exams and one LAT ([redact]) x-ray 

exam during the employment period. Using the values presented in Table A-9 ORAUT-OTIB0006, SC&A assigned the total occupational medical doses shown in Table I-5.

Table I-5. Occupational Medical Doses 

# Location OTIB-0006 Dose (rem) Dose (rem) PA (<1985) PA (>1985) LAT (>1985)

1 SCC [redacted] 0.0024 0.0456 0.065

2 BCC [redacted] 0.0032 0.0039 0.0182 0.049

3 BCC [redacted] 0.0032 0.0039 0.0182 0.0029

4 SCC [redacted] 0.0135 0.0070 0.0182 0.081

5 SCC [redacted] 0.0135 0.0070 0.0182 0.081

In order to provide the most claimant-favorable results, the annual occupational medical dose 

values were entered into IREP as a normal distribution with 30% uncertainty and a photon 

energy range of 30–250 keV. 

I.4 ONSITE AMBIENT DOSE 

SC&A chose not to include external onsite ambient dose as part of this DR.

The EE was continuously monitored for ionizing radiation doses during employment at the 

FMPC. Therefore, all onsite ambient doses were assessed as part of the EE’s measured and 

missed doses. 

I.5 INTERNAL DOSE 

Internal dose monitoring records for radionuclides were reviewed. This included baseline 

thorium fecal bioassay, uranium urine, and chest count measurements. The DOE records show 

that the EE submitted 217 urine samples from [redacted] to [redacted] that were analyzed for 

uranium. Table I-6 shows the routine uranium in-vitro bioassay capabilities at the FMPC 

(ORAUT-TKBS-0017-5). A listing of the samples and results is shown in Table I-7. 

Table I-6. FEMP Uranium Bioassay Capabilities 

Type of Analysis Method Time Period MDL

Urine-uranium Fluorophotometry [redacted] to [redacted] 14 μg L-1

Chemchek KPA [redacted] to [redacted] 0.17 μg L-1(total U)
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Table I-7. Uranium Bioassay Results

Sample 

Date

Sample 

Number Result Result Units

Sample 

Date

Sample 

Number Result Result Units

Sample 

Date

Sample 

Number Result Result Units

[redact] 1.00 μg/L [redact] 597 3.00 μg/L [redact] 2794 9.00 μg/L

[redact] 9.00 μg/L [redact] 634 4.00 μg/L [redact] 3900 8.00 μg/L

[redact] 13.00 μg/L [redact] 706 3.00 μg/L [redact] 5505 7.00 μg/L

[redact] 0.00 μg/L [redact] 714 3.00 μg/L [redact] 6335 7.00 μg/L

[redact] 1.00 μg/L [redact] 769 3.00 μg/L [redact] 6711 7.00 μg/L

[redact] 6.00 μg/L [redact] 815 3.00 μg/L [redact] 6942 8.00 μg/L

[redact] 6.00 μg/L [redact] 906 3.00 μg/L [redact] 7438 8.00 μg/L

[redact] 5.00 μg/L [redact] 68 3.00 μg/L [redact] 8050 9.00 μg/L

[redact] 0.00 μg/L [redact] 183 3.00 μg/L [redact] 9285 8.00 μg/L

[redact] 0.00 μg/L [redact] 516 3.00 μg/L [redact] 481 9.00 μg/L

[redact] 3.00 μg/L [redact] 3.00 μg/L [redact] 1736 10.00 μg/L

[redact] 3.00 μg/L [redact] 617 3.00 μg/L [redact] 3121 10.00 μg/L

[redact] 2.00 μg/L [redact] 815 3.00 μg/L [redact] 5189 10.00 μg/L

[redact] 2.00 μg/L [redact] 861 3.00 μg/L [redact] 7227 9.00 μg/L

[redact] 18.00 μg/L [redact] 67 3.00 μg/L [redact] 8785 10.00 μg/L

[redact] 3.00 μg/L [redact] 141 3.00 μg/L [redact] 1230 11.00 μg/L

[redact] 3.00 μg/L [redact] 182 3.00 μg/L [redact] 1658 11.00 μg/L

[redact] 560 1.00 μg/L [redact] 154 5.00 μg/L [redact] 3031 11.00 μg/L

[redact] 219 3.00 μg/L [redact] 182 5.00 μg/L [redact] 4293 12.00 μg/L

[redact] 89 3.00 μg/L [redact] 191 5.00 μg/L [redact] 4600 12.00 μg/L

[redact] 809 3.00 μg/L [redact] 282 5.00 μg/L [redact] 6053 12.00 μg/L

[redact] 508 3.00 μg/L [redact] 296 5.00 μg/L [redact] 7343 12.00 μg/L

[redact] 174 3.00 μg/L [redact] 404 5.00 μg/L [redact] 9307 12.00 μg/L

[redact] 34 3.00 μg/L [redact] 427 5.00 μg/L [redact] 1647 14.00 μg/L

[redact] 77 3.00 μg/L [redact] 465 5.00 μg/L [redact] 1981 14.00 μg/L

[redact] 131 3.00 μg/L [redact] 515 5.00 μg/L [redact] 3525 14.00 μg/L

[redact] 186 3.00 μg/L [redact] 539 5.00 μg/L [redact] 5983 14.00 μg/L

[redact] 230 4.00 μg/L [redact] 655 5.00 μg/L [redact] 6661 14.00 μg/L

[redact] 430 3.00 μg/L [redact] 686 5.00 μg/L [redact] 8724 14.00 μg/L

[redact] 345 3.00 μg/L [redact] 769 5.00 μg/L [redact] 32 14.00 μg/L

[redact] 573 6.00 μg/L [redact] 831 5.00 μg/L [redact] 568 14.00 μg/L

[redact] 607 3.00 μg/L [redact] 860 5.00 μg/L [redact] 1332 14.00 μg/L

[redact] 417 5.00 μg/L [redact] 2 5.00 μg/L [redact] 2419 14.00 μg/L

[redact] 858 14.00 μg/L [redact] 67 5.00 μg/L [redact] 3554 14.00 μg/L

[redact] 988 7.00 μg/L [redact] 188 5.00 μg/L [redact] 5049 14.00 μg/L

[redact] 606 7.00 μg/L [redact] 252 5.00 μg/L [redact] 6098 14.00 μg/L

[redact] 266 3.00 μg/L [redact] 520 5.00 μg/L [redact] 7240 14.00 μg/L

[redact] 346 3.00 μg/L [redact] 576 5.00 μg/L [redact] 8618 14.00 μg/L

[redact] 742 3.00 μg/L [redact] 742 5.00 μg/L [redact] 14.00 μg/L

[redact] 851 3.00 μg/L [redact] 880 5.00 μg/L [redact] 9461 14.00 μg/L

[redact] 884 3.00 μg/L [redact] 175 5.00 μg/L [redact] 1168 14.00 μg/L

[redact] 976 5.00 μg/L [redact] 215 5.00 μg/L [redact] 1759 14.00 μg/L

[redact] 3 3.00 μg/L [redact] 265 5.00 μg/L [redact] 3178 14.00 μg/L

[redact] 53 3.00 μg/L [redact] 457 5.00 μg/L [redact] 6192 14.00 μg/L

[redact] 118 6.00 μg/L [redact] 665 5.00 μg/L [redact] 4144 14.00 μg/L

[redact] 175 3.00 μg/L [redact] 334 5.00 μg/L [redact] 4980 14.00 μg/L

[redact] 327 4.00 μg/L [redact] 13 5.00 μg/L [redact] 7257 0.80 μg/L

[redact] 355 3.00 μg/L [redact] 610 5.00 μg/L [redact] 8768 0.80 μg/L

[redact] 454 3.00 μg/L [redact] 681 5.00 μg/L [redact] 218 0.80 μg/L

[redact] 494 4.00 μg/L [redact] 899 5.00 μg/L [redact] 1865 0.8 μg/L

[redact] 639 3.00 μg/L [redact] 904 5.00 μg/L [redact] 3445 0.8 μg/L
Effective Date:

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Table I-7. Uranium Bioassay Results

Sample 

Date

Sample 

Number Result Result Units

Sample 

Date

Sample 

Number Result Result Units

Sample 

Date

Sample 

Number Result Result Units

[redact] 673 3.00 μg/L [redact] 51 5.00 μg/L [redact] 4165 0.8 μg/L

[redact] 753 3.00 μg/L [redact] 304 5.00 μg/L [redact] 582 0.8 μg/L

[redact] 792 4.00 μg/L [redact] 92 5.00 μg/L [redact] 2224 0.8 μg/L

[redact] 814 3.00 μg/L [redact] 560 5.00 μg/L [redact] 2256 0.8 μg/L

[redact] 951 3.00 μg/L [redact] 1906 5.00 μg/L [redact] 4386 0.8 μg/L

[redact] 90 3.00 μg/L [redact] 3324 5.00 μg/L [redact] 5961 0.8 μg/L

[redact] 112 3.00 μg/L [redact] 4581 5.00 μg/L [redact] 7977 0.8 μg/L

[redact] 210 3.00 μg/L [redact] 5873 5.00 μg/L [redact] 261 0.8 μg/L

[redact] 237 3.00 μg/L [redact] 7137 5.00 μg/L [redact] 1755 0.8 μg/L

[redact] 311 3.00 μg/L [redact] 8060 5.00 μg/L [redact] 2436 0.8 μg/L

[redact] 338 3.00 μg/L [redact] 8866 5.00 μg/L [redact] 4848 0.8 μg/L

[redact] 468 3.00 μg/L [redact] 9562 5.00 μg/L [redact] 6821 0.8 μg/L

[redact] 667 3.00 μg/L [redact] 1510 5.00 μg/L [redact] 9530 0.8 μg/L

[redact] 759 3.00 μg/L [redact] 1816 5.00 μg/L [redact] 767 0.8 μg/L

[redact] 950 3.00 μg/L [redact] 2019 5.00 μg/L [redact] 4563 0.8 μg/L

[redact] 988 3.00 μg/L [redact] 2088 5.00 μg/L [redact] 6132 0.8 μg/L

[redact] 102 3.00 μg/L [redact] 3210 5.00 μg/L [redact] 7836 0.8 μg/L

[redact] 114 3.00 μg/L [redact] 4677 5.00 μg/L [redact] 8934 0.8 μg/L

[redact] 221 3.00 μg/L [redact] 6297 5.00 μg/L

[redact] 252 3.00 μg/L [redact] 7952 8.00 μg/L

[redact] 359 3.00 μg/L [redact] 9324 8.00 μg/L

[redact] 390 3.00 μg/L [redact] 751 9.00 μg/L

[redact] 597 3.00 μg/L [redact] 1800 9.00 μg/L

I.5.1 DOSE FROM URANIUM 

All of the EE’s uranium bioassay results except one were below the minimum detection level 

(MDL) of the analyses. The urine sample submitted on [redact], had a result of 18 μgL-1 with an

MDL of 14 μgL-1. 

A computer code, the Integrated Modules for Bioassay Analysis (IMBA), was used to estimate 

intakes of radioactive material and the subsequent annual organ doses from the uranium bioassay 

data. The IMBA Expert ORAU-Edition was used for this DR. The ICRP 66 lung model with 

default aerosol characteristics was assumed, in conjunction with ICRP 68 metabolic models. 

To account for any potential undetected dose, internal dose was assigned based on a chronic 

intake assumed to have occurred throughout EE’s employment period. To account for the single 

elevated sample, an acute intake was assumed to have occurred on [redact], the midpoint 

between bioassay samples. The specific activity of uranium was assumed to be 2% enriched 

uranium (specific activity = 1.616 pCi/μg). In addition, the uranium intake was assessed as 

100% uranium-234, a claimant-favorable assumption. Both Types M and S uranium were 

considered and both resulted in similar overall doses. However, when consideration is given to 

the uranium intake quantities and recycled uranium (RU) contaminants, Type S uranium resulted 

in the most claimant-favorable doses. The calculated uranium intakes are shown in Table I-8. 
Effective Date:

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Table I-8. Uranium Intakes 

Type of Intake Date Quantity

Chronic [redacted] to [redacted] 128.54 pCi/day

Acute [redact] 228,000 pCi

Observation #1: For calculating internal doses using the above-cited chronic intake quantity, 

DR–Method A used both the IMBA software and Chronic Annual Dose Workbook (CADW). A 

comparison of resultant doses identified a discrepancy between these two calculational methods. 

As shown in Table I-9, CADW calculated a total alpha dose that is nearly 45% lower than the 

total dose calculated by IMBA. SC&A could not reconcile why there is difference between the 

IMBA calculation and the CADW calculation for uranium. 

Table I-9. Comparison of Alpha Dose Using IMBA and CADW 

Calendar 

Year

Alpha Dose Using 

IMBA (rem)

Alpha Dose Using 

CADW (rem)

[redacted] 1.17E-05 2.033E-05

[redacted] 1.32E-04 4.431E-05

[redacted] 2.02E-04 6.887E-05

[redacted] 8.83E-04 2.542E-04

[redacted] 6.74E-04 2.377E-04

[redacted] 7.50E-04 2.726E-04

[redacted] 8.30E-04 3.068E-04

[redacted] 9.04E-04 3.408E-04

[redacted] 9.79E-04 3.738E-04

[redacted] 1.05E-03 4.069E-04

[redacted] 1.13E-03 4.399E-04

[redacted] 1.20E-03 4.733E-04

[redacted] 1.28E-03 5.059E-04

[redacted] 1.35E-03 5.388E-04

[redacted] 1.43E-03 5.718E-04

[redacted] 1.42E-03 6.051E-04

[redacted] 1.40E-03 6.172E-04

[redacted] 1.40E-03 6.259E-04

[redacted] 1.41E-03 6.342E-04

[redacted] 1.41E-03 6.416E-04

[redacted] 1.41E-03 6.468E-04

[redacted] 1.41E-03 6.516E-04

[redacted] 1.41E-03 6.556E-04

[redacted] 1.40E-03 6.593E-04

[redacted] 1.40E-03 6.616E-04

[redacted] 1.40E-03 6.639E-04

[redacted] 1.40E-03 6.657E-04

[redacted] 1.39E-03 6.675E-04

[redacted] 1.39E-03 6.681E-04

[redacted] 1.38E-03 6.688E-04

[redacted] 4.34E-04 6.692E-04

Total 3.43E-02 1.526E-02
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I.5.2 DOSE FROM RECYCLED URANIUM CONTAMINANTS 

Production level quantities of recycled uranium (RU) were first introduced at the FEMP site in 

1961. Therefore, all uranium intakes after 1961 are assumed to have associated plutonium-239, 

neptunium-237, and technetium-99 intakes. According to ORAUT-TKBS-0017-5, the intakes of 

plutonium-239, neptunium-237, and technetium-99 will be 0.38%, 0.15%, and 9.4%, 

respectively, of the uranium intake, assuming 2% uranium enrichment. The RU intakes are 

shown in Table I-10. 

Table I-10. Intakes from RU Contaminants 

Type of 

Intake Date Pu-239 (S) Np-237 (M) Tc-99 (M)

Chronic [redacted] to [redacted] 5.001E-01 pCi/day 1.987E-01 pCi/day 1.227E+01 pCi/day

Acute [redact] 8.873E+02 pCi 3.526E+02 pCi 2.178E+04 pCi

The doses from the intakes of RU contaminants were all less than 0.003 rem and are included in 

the IREP table. SC&A notes that the issue of RU has been a topic of intense discussion in the 

Fernald Work Group (WG). After a series of white paper exchanges and WG discussions, 

NIOSH has agreed to change the default levels of plutonium-239, neptunium-237, and 

technetium-99 in RU over three periods of time that correspond to changing constituent 

concentration levels in incoming feed stocks. However, at the time that this DR was performed, 

the TBD has not been updated. Thus, in assigning dose to this EE from RU, SC&A used the 

intakes from ORAUT-TKBS-0017-5 in Table I-10. 

I.6 ENVIRONMENTAL DOSE 

The EE primarily worked in Plant [redacted] during employment at FEMP, and it was assumed 

that the EE might have been occupationally exposed to environmental levels of radioactive 

material while working there. According to Figure 4-2 of ORAUT-TKBS-0017-4, Plant 

[redacted] was located in Exposure Area [redact]. Tables A-1 and A-2 of the same document 

list the environmental radionuclide concentration and intake summaries for [redacted] to 

[redacted] and [redacted] to [redacted]. The CADW version 8.2.4 was used to calculate the 

EE’s environmental doses using intake values for Pu-239, Np-237, Tc-99, and Th-232 for 

[redact]. All of the environmental doses calculated for the time period from [redacted], through 

[redacted], were less than 0.001 rem and were not reported in the IREP table.

I.7 CATI REPORT AND RADIOLOGICAL INCIDENTS 

SC&A reviewed the EE’s DOE records and CATI Report to determine if the EE was involved in 

any radiological incidents that may not have been detected with external and internal radiological 

monitoring. There are several instances where the EE’s thermoluminescent dosimeter (TLD) 

was either lost or damaged; however, investigations were documented and either a zero or 

estimated dose assigned. There are three radiological incidents of note. In [redacted], the EE 

was in the vicinity of [redacted]. Bioassays were collected and the results were less than the 

detection limit. In [redacted], the EE was in the immediate area when [redacted] resulting in 

airborne particulates. Again, bioassays were collected and the results were less than the 
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detection limit. Finally, in [redacted], while in a controlled area, the EE noticed [redacted]. An 

investigation was conducted and the EE was assigned 0.015 rem for the quarter based on 

coworker information.

SC&A did not find any documentation of radiological incidents that occurred during a time the 

EE was not monitored for internal or external radiation exposure. 

I.8 SUMMARY CONCLUSIONS 

The EE worked at the Fernald facility from [redacted] through [redacted]. During most of the 

time, the EE was monitored for exposure to external and internal radiation. The EE was 

diagnosed with multiple skin cancers beginning in [redacted] through [redacted]. The DR

derived a total external and internal dose of approximately 18 rem to each bare skin (unattenuated) cancer location and 15.8 rem to the skin cancer on the [redact]. Approximately 

15.5 rem of the [redact] skin dose and 13.3 rem of the [redact] skin cancer doses were attributed 

to exposure to >15 keV electrons.

The total POC for the five multiple primary cancers was calculated using the IREP (version .5.7) 

and determined to be 40.92%.

I.9 REFERENCES 

ICRP (International Commission on Radiological Protection) 1991. 1990 Recommendations of 

the International Commission on Radiological Protection, Publication 60, Pergamon Press, 

Oxford, England. 

ICRP (International Commission on Radiological Protection) 1994. Human Respiratory Tract 

Model for Radiological Protection, ICRP Publication 66, Ann. ICRP 24 (1-3), 1994, Pergamon 

Press, Oxford, England. 

ICRP (International Commission on Radiological Protection) 1994. Dose Coefficients for 

Intakes of Radionuclides by Workers, ICRP Publication 68, Ann. ICRP 24 (4), Pergamon Press, 

Oxford, England. 

OCAS-IG-001. 2007. External Dose Reconstruction Implementation Guideline, Rev. 3, 

National Institute for Occupational Safety and Health, Office of Compensation Analysis and 

Support, Cincinnati, Ohio. November 21, 2007. 

ORAUT-OTIB-0006. 2005. Technical Information Bulletin: Dose Reconstruction from 

Occupationally Related Diagnostic X-Ray Procedures, Rev. 04, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. June 20, 2011. 

ORAUT-OTIB-0017. 2005. Technical Information Bulletin: Interpretation of Dosimetry Data 

for Assignment of Shallow Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. October 11, 2005. 
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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

ORAUT-TKBS-0017-4. 2006. Fernald Environmental Management Project – Occupational 

Environmental Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, Ohio. 

February 7, 2006. 

ORAUT-TKBS-0017-5. 2004. Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Occupational Internal Dose, Rev. 00, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. May 28, 2004. 

ORAUT-TKBS-0017-6. 2004. Technical Basis Document for the Fernald Environmental 

Management Project - Occupational External Dose, Rev. 00, Oak Ridge Associated Universities 

Team, Cincinnati, Ohio. April 20, 2004. 
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APPENDIX I.A-1: IREP INPUT – SCC [REDACTED]

EXPOSURE INFORMATION

Number of exposures 

148

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose Distribution 

Type Parameter 1 Parameter 2 Parameter 3

1 [redact] acute photons E<30keV Constant 0.023 0.000 0.000

2 [redact] acute photons E<30keV Constant 0.041 0.000 0.000

3 [redact] acute photons E<30keV Constant 0.018 0.000 0.000

4 [redact] acute photons E<30keV Constant 0.017 0.000 0.000

5 [redact] acute photons E<30keV Constant 0.052 0.000 0.000

6 [redact] acute photons E<30keV Constant 0.021 0.000 0.000

7 [redact] acute photons E<30keV Constant 0.003 0.000 0.000

8 [redact] acute photons E<30keV Constant 0.004 0.000 0.000

9 [redact] acute photons E<30keV Constant 0.005 0.000 0.000

10 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

11 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

12 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

13 [redact] acute photons E=30-250keV Constant 0.058 0.000 0.000

14 [redact] acute photons E=30-250keV Constant 0.105 0.000 0.000

15 [redact] acute photons E=30-250keV Constant 0.047 0.000 0.000

16 [redact] acute photons E=30-250keV Constant 0.044 0.000 0.000

17 [redact] acute photons E=30-250keV Constant 0.133 0.000 0.000

18 [redact] acute photons E=30-250keV Constant 0.054 0.000 0.000

19 [redact] acute photons E=30-250keV Constant 0.007 0.000 0.000

20 [redact] acute photons E=30-250keV Constant 0.009 0.000 0.000

21 [redact] acute photons E=30-250keV Constant 0.012 0.000 0.000

22 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

23 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

24 [redact] acute photons E=30-250keV Constant 0.005 0.000 0.000

25 [redact] acute photons E>250keV Constant 0.086 0.000 0.000

26 [redact] acute photons E>250keV Constant 0.156 0.000 0.000

27 [redact] acute photons E>250keV Constant 0.076 0.000 0.000

28 [redact] acute photons E>250keV Constant 0.072 0.000 0.000

29 [redact] acute photons E>250keV Constant 0.217 0.000 0.000

30 [redact] acute photons E>250keV Constant 0.089 0.000 0.000

31 [redact] acute photons E>250keV Constant 0.011 0.000 0.000

32 [redact] acute photons E>250keV Constant 0.015 0.000 0.000

33 [redact] acute photons E>250keV Constant 0.020 0.000 0.000

34 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

35 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

36 [redact] acute photons E>250keV Constant 0.009 0.000 0.000

37 [redact] acute electrons E>15keV Constant 0.029 0.000 0.000

38 [redact] acute electrons E>15keV Constant 2.722 0.000 0.000

39 [redact] acute electrons E>15keV Constant 3.338 0.000 0.000

40 [redact] acute electrons E>15keV Constant 1.898 0.000 0.000

41 [redact] acute electrons E>15keV Constant 2.069 0.000 0.000

42 [redact] acute electrons E>15keV Constant 4.110 0.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

21 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-1: IREP Input – SCC [Redacted] (continued)

43 [redact] acute electrons E>15keV Constant 0.731 0.000 0.000

44 [redact] acute electrons E>15keV Constant 0.334 0.000 0.000

45 [redact] acute electrons E>15keV Constant 0.001 0.000 0.000

46 [redact] acute electrons E>15keV Constant 0.264 0.000 0.000

47 [redact] acute electrons E>15keV Constant 0.063 0.000 0.000

48 [redact] acute photons E=30-250keV Lognormal 0.180 1.520 0.000

49 [redact] acute photons E=30-250keV Lognormal 0.090 1.520 0.000

50 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

51 [redact] acute photons E=30-250keV Lognormal 0.020 1.520 0.000

52 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

53 [redact] acute photons E=30-250keV Lognormal 0.100 1.520 0.000

54 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

55 [redact] acute photons E=30-250keV Lognormal 0.140 1.520 0.000

56 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

57 [redact] acute photons E=30-250keV Lognormal 0.010 1.520 0.000

58 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

59 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

60 [redact] acute photons E=30-250keV Lognormal 0.040 1.520 0.000

61 [redact] acute photons E=30-250keV Normal 0.003 0.001 0.000

62 [redact] acute photons E=30-250keV Normal 0.002 0.001 0.000

63 [redact] acute photons E=30-250keV Normal 0.005 0.001 0.000

64 [redact] acute photons E=30-250keV Normal 0.002 0.001 0.000

65 [redact] acute photons E=30-250keV Normal 0.005 0.001 0.000

66 [redact] acute photons E=30-250keV Normal 0.002 0.001 0.000

67 [redact] acute photons E=30-250keV Normal 0.046 0.014 0.000

68 [redact] chronic alpha Lognormal 0.000 3.000 0.000

69 [redact] chronic alpha Lognormal 0.000 3.000 0.000

70 [redact] chronic alpha Lognormal 0.000 3.000 0.000

71 [redact] chronic alpha Lognormal 0.001 3.000 0.000

72 [redact] chronic alpha Lognormal 0.001 3.000 0.000

73 [redact] chronic alpha Lognormal 0.001 3.000 0.000

74 [redact] chronic alpha Lognormal 0.001 3.000 0.000

75 [redact] chronic alpha Lognormal 0.001 3.000 0.000

76 [redact] chronic alpha Lognormal 0.001 3.000 0.000

77 [redact] chronic alpha Lognormal 0.001 3.000 0.000

78 [redact] chronic alpha Lognormal 0.001 3.000 0.000

79 [redact] chronic alpha Lognormal 0.001 3.000 0.000

80 [redact] chronic alpha Lognormal 0.001 3.000 0.000

81 [redact] chronic alpha Lognormal 0.001 3.000 0.000

82 [redact] chronic alpha Lognormal 0.001 3.000 0.000

83 [redact] chronic alpha Lognormal 0.001 3.000 0.000

84 [redact] chronic alpha Lognormal 0.001 3.000 0.000

85 [redact] chronic alpha Lognormal 0.001 3.000 0.000

86 [redact] chronic alpha Lognormal 0.001 3.000 0.000

87 [redact] chronic alpha Lognormal 0.001 3.000 0.000

88 [redact] chronic alpha Lognormal 0.001 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

22 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-1: IREP Input – SCC [Redacted] (continued)

89 [redact] chronic alpha Lognormal 0.001 3.000 0.000

90 [redact] chronic alpha Lognormal 0.001 3.000 0.000

91 [redact] chronic alpha Lognormal 0.001 3.000 0.000

92 [redact] chronic alpha Lognormal 0.001 3.000 0.000

93 [redact] chronic alpha Lognormal 0.001 3.000 0.000

94 [redact] chronic alpha Lognormal 0.001 3.000 0.000

95 [redact] chronic alpha Lognormal 0.000 3.000 0.000

96 [redact] chronic alpha Lognormal 0.000 3.000 0.000

97 [redact] chronic alpha Lognormal 0.000 3.000 0.000

98 [redact] chronic alpha Lognormal 0.000 3.000 0.000

99 [redact] chronic alpha Lognormal 0.000 3.000 0.000

100 [redact] chronic alpha Lognormal 0.000 3.000 0.000

101 [redact] chronic alpha Lognormal 0.000 3.000 0.000

102 [redact] chronic alpha Lognormal 0.000 3.000 0.000

103 [redact] chronic alpha Lognormal 0.000 3.000 0.000

104 [redact] chronic alpha Lognormal 0.000 3.000 0.000

105 [redact] chronic alpha Lognormal 0.000 3.000 0.000

106 [redact] chronic alpha Lognormal 0.000 3.000 0.000

107 [redact] chronic alpha Lognormal 0.000 3.000 0.000

108 [redact] chronic alpha Lognormal 0.000 3.000 0.000

109 [redact] chronic alpha Lognormal 0.000 3.000 0.000

110 [redact] chronic alpha Lognormal 0.000 3.000 0.000

111 [redact] chronic alpha Lognormal 0.000 3.000 0.000

112 [redact] chronic alpha Lognormal 0.000 3.000 0.000

113 [redact] chronic alpha Lognormal 0.000 3.000 0.000

114 [redact] chronic alpha Lognormal 0.000 3.000 0.000

115 [redact] chronic alpha Lognormal 0.000 3.000 0.000

116 [redact] chronic alpha Lognormal 0.000 3.000 0.000

117 [redact] chronic alpha Lognormal 0.000 3.000 0.000

118 [redact] chronic alpha Lognormal 0.000 3.000 0.000

119 [redact] chronic alpha Lognormal 0.000 3.000 0.000

120 [redact] chronic alpha Lognormal 0.000 3.000 0.000

121 [redact] chronic alpha Lognormal 0.000 3.000 0.000

122 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

123 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

124 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

125 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

126 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

127 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

128 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

129 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

130 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

131 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

132 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

133 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

134 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

23 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-1: IREP Input – SCC [Redacted] (continued)

135 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

136 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

137 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

138 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

139 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

140 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

141 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

142 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

143 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

144 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

145 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

146 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

147 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

148 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

24 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX I.A-2: IREP INPUT – BCC [REDACTED]

EXPOSURE INFORMATION

Number of exposures

151

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose Distribution 

Type Parameter 1 Parameter 2 Parameter 3

1 [redact] acute photons E<30keV Constant 0.023 0.000 0.000

2 [redact] acute photons E<30keV Constant 0.041 0.000 0.000

3 [redact] acute photons E<30keV Constant 0.018 0.000 0.000

4 [redact] acute photons E<30keV Constant 0.017 0.000 0.000

5 [redact] acute photons E<30keV Constant 0.052 0.000 0.000

6 [redact] acute photons E<30keV Constant 0.021 0.000 0.000

7 [redact] acute photons E<30keV Constant 0.003 0.000 0.000

8 [redact] acute photons E<30keV Constant 0.004 0.000 0.000

9 [redact] acute photons E<30keV Constant 0.005 0.000 0.000

10 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

11 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

12 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

13 [redact] acute photons E=30-250keV Constant 0.058 0.000 0.000

14 [redact] acute photons E=30-250keV Constant 0.105 0.000 0.000

15 [redact] acute photons E=30-250keV Constant 0.047 0.000 0.000

16 [redact] acute photons E=30-250keV Constant 0.044 0.000 0.000

17 [redact] acute photons E=30-250keV Constant 0.133 0.000 0.000

18 [redact] acute photons E=30-250keV Constant 0.054 0.000 0.000

19 [redact] acute photons E=30-250keV Constant 0.007 0.000 0.000

20 [redact] acute photons E=30-250keV Constant 0.009 0.000 0.000

21 [redact] acute photons E=30-250keV Constant 0.012 0.000 0.000

22 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

23 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

24 [redact] acute photons E=30-250keV Constant 0.005 0.000 0.000

25 [redact] acute photons E>250keV Constant 0.086 0.000 0.000

26 [redact] acute photons E>250keV Constant 0.156 0.000 0.000

27 [redact] acute photons E>250keV Constant 0.076 0.000 0.000

28 [redact] acute photons E>250keV Constant 0.072 0.000 0.000

29 [redact] acute photons E>250keV Constant 0.217 0.000 0.000

30 [redact] acute photons E>250keV Constant 0.089 0.000 0.000

31 [redact] acute photons E>250keV Constant 0.011 0.000 0.000

32 [redact] acute photons E>250keV Constant 0.015 0.000 0.000

33 [redact] acute photons E>250keV Constant 0.020 0.000 0.000

34 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

35 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

36 [redact] acute photons E>250keV Constant 0.009 0.000 0.000

37 [redact] acute electrons E>15keV Constant 0.029 0.000 0.000

38 [redact] acute electrons E>15keV Constant 2.722 0.000 0.000

39 [redact] acute electrons E>15keV Constant 3.338 0.000 0.000

40 [redact] acute electrons E>15keV Constant 1.898 0.000 0.000

41 [redact] acute electrons E>15keV Constant 2.069 0.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

25 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-2: IREP Input –BCC [Redacted] (continued)

42 [redact] acute electrons E>15keV Constant 4.110 0.000 0.000

43 [redact] acute electrons E>15keV Constant 0.731 0.000 0.000

44 [redact] acute electrons E>15keV Constant 0.334 0.000 0.000

45 [redact] acute electrons E>15keV Constant 0.001 0.000 0.000

46 [redact] acute electrons E>15keV Constant 0.264 0.000 0.000

47 [redact] acute electrons E>15keV Constant 0.063 0.000 0.000

48 [redact] acute photons E=30-250keV Lognormal 0.180 1.520 0.000

49 [redact] acute photons E=30-250keV Lognormal 0.090 1.520 0.000

50 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

51 [redact] acute photons E=30-250keV Lognormal 0.020 1.520 0.000

52 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

53 [redact] acute photons E=30-250keV Lognormal 0.100 1.520 0.000

54 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

55 [redact] acute photons E=30-250keV Lognormal 0.140 1.520 0.000

56 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

57 [redact] acute photons E=30-250keV Lognormal 0.010 1.520 0.000

58 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

59 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

60 [redact] acute photons E=30-250keV Lognormal 0.040 1.520 0.000

61 [redact] acute photons E=30-250keV Normal 0.003 0.001 0.000

62 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

63 [redact] acute photons E=30-250keV Normal 0.008 0.002 0.000

64 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

65 [redact] acute photons E=30-250keV Normal 0.008 0.002 0.000

66 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

67 [redact] acute photons E=30-250keV Normal 0.018 0.005 0.000

68 [redact] chronic alpha Lognormal 0.000 3.000 0.000

69 [redact] chronic alpha Lognormal 0.000 3.000 0.000

70 [redact] chronic alpha Lognormal 0.000 3.000 0.000

71 [redact] chronic alpha Lognormal 0.001 3.000 0.000

72 [redact] chronic alpha Lognormal 0.001 3.000 0.000

73 [redact] chronic alpha Lognormal 0.001 3.000 0.000

74 [redact] chronic alpha Lognormal 0.001 3.000 0.000

75 [redact] chronic alpha Lognormal 0.001 3.000 0.000

76 [redact] chronic alpha Lognormal 0.001 3.000 0.000

77 [redact] chronic alpha Lognormal 0.001 3.000 0.000

78 [redact] chronic alpha Lognormal 0.001 3.000 0.000

79 [redact] chronic alpha Lognormal 0.001 3.000 0.000

80 [redact] chronic alpha Lognormal 0.001 3.000 0.000

81 [redact] chronic alpha Lognormal 0.001 3.000 0.000

82 [redact] chronic alpha Lognormal 0.001 3.000 0.000

83 [redact] chronic alpha Lognormal 0.001 3.000 0.000

84 [redact] chronic alpha Lognormal 0.001 3.000 0.000

85 [redact] chronic alpha Lognormal 0.001 3.000 0.000

86 [redact] chronic alpha Lognormal 0.001 3.000 0.000

87 [redact] chronic alpha Lognormal 0.001 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

26 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-2: IREP Input –BCC [Redacted] (continued)

88 [redact] chronic alpha Lognormal 0.001 3.000 0.000

89 [redact] chronic alpha Lognormal 0.001 3.000 0.000

90 [redact] chronic alpha Lognormal 0.001 3.000 0.000

91 [redact] chronic alpha Lognormal 0.001 3.000 0.000

92 [redact] chronic alpha Lognormal 0.001 3.000 0.000

93 [redact] chronic alpha Lognormal 0.001 3.000 0.000

94 [redact] chronic alpha Lognormal 0.001 3.000 0.000

95 [redact] chronic alpha Lognormal 0.001 3.000 0.000

96 [redact] chronic alpha Lognormal 0.000 3.000 0.000

97 [redact] chronic alpha Lognormal 0.000 3.000 0.000

98 [redact] chronic alpha Lognormal 0.000 3.000 0.000

99 [redact] chronic alpha Lognormal 0.000 3.000 0.000

100 [redact] chronic alpha Lognormal 0.000 3.000 0.000

101 [redact] chronic alpha Lognormal 0.000 3.000 0.000

102 [redact] chronic alpha Lognormal 0.000 3.000 0.000

103 [redact] chronic alpha Lognormal 0.000 3.000 0.000

104 [redact] chronic alpha Lognormal 0.000 3.000 0.000

105 [redact] chronic alpha Lognormal 0.000 3.000 0.000

106 [redact] chronic alpha Lognormal 0.000 3.000 0.000

107 [redact] chronic alpha Lognormal 0.000 3.000 0.000

108 [redact] chronic alpha Lognormal 0.000 3.000 0.000

109 [redact] chronic alpha Lognormal 0.000 3.000 0.000

110 [redact] chronic alpha Lognormal 0.000 3.000 0.000

111 [redact] chronic alpha Lognormal 0.000 3.000 0.000

112 [redact] chronic alpha Lognormal 0.000 3.000 0.000

113 [redact] chronic alpha Lognormal 0.000 3.000 0.000

114 [redact] chronic alpha Lognormal 0.000 3.000 0.000

115 [redact] chronic alpha Lognormal 0.000 3.000 0.000

116 [redact] chronic alpha Lognormal 0.000 3.000 0.000

117 [redact] chronic alpha Lognormal 0.000 3.000 0.000

118 [redact] chronic alpha Lognormal 0.000 3.000 0.000

119 [redact] chronic alpha Lognormal 0.000 3.000 0.000

120 [redact] chronic alpha Lognormal 0.000 3.000 0.000

121 [redact] chronic alpha Lognormal 0.000 3.000 0.000

122 [redact] chronic alpha Lognormal 0.000 3.000 0.000

123 [redact] chronic alpha Lognormal 0.000 3.000 0.000

124 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

125 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

126 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

127 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

128 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

129 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

130 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

131 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

132 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

133 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

27 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-2: IREP Input –BCC [Redacted] (continued)

134 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

135 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

136 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

137 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

138 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

139 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

140 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

141 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

142 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

143 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

144 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

145 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

146 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

147 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

148 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

149 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

150 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

151 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

28 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX I.A-3: IREP INPUT – BCC [REDACTED]

EXPOSURE INFORMATION

Number of exposures

160

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose Distribution 

Type Parameter 1 Parameter 2 Parameter 3

1 [redact] acute photons E<30keV Constant 0.023 0.000 0.000

2 [redact] acute photons E<30keV Constant 0.041 0.000 0.000

3 [redact] acute photons E<30keV Constant 0.018 0.000 0.000

4 [redact] acute photons E<30keV Constant 0.017 0.000 0.000

5 [redact] acute photons E<30keV Constant 0.052 0.000 0.000

6 [redact] acute photons E<30keV Constant 0.021 0.000 0.000

7 [redact] acute photons E<30keV Constant 0.003 0.000 0.000

8 [redact] acute photons E<30keV Constant 0.004 0.000 0.000

9 [redact] acute photons E<30keV Constant 0.005 0.000 0.000

10 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

11 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

12 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

13 [redact] acute photons E=30-250keV Constant 0.058 0.000 0.000

14 [redact] acute photons E=30-250keV Constant 0.105 0.000 0.000

15 [redact] acute photons E=30-250keV Constant 0.047 0.000 0.000

16 [redact] acute photons E=30-250keV Constant 0.044 0.000 0.000

17 [redact] acute photons E=30-250keV Constant 0.133 0.000 0.000

18 [redact] acute photons E=30-250keV Constant 0.054 0.000 0.000

19 [redact] acute photons E=30-250keV Constant 0.007 0.000 0.000

20 [redact] acute photons E=30-250keV Constant 0.009 0.000 0.000

21 [redact] acute photons E=30-250keV Constant 0.012 0.000 0.000

22 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

23 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

24 [redact] acute photons E=30-250keV Constant 0.005 0.000 0.000

25 [redact] acute photons E>250keV Constant 0.086 0.000 0.000

26 [redact] acute photons E>250keV Constant 0.156 0.000 0.000

27 [redact] acute photons E>250keV Constant 0.076 0.000 0.000

28 [redact] acute photons E>250keV Constant 0.072 0.000 0.000

29 [redact] acute photons E>250keV Constant 0.217 0.000 0.000

30 [redact] acute photons E>250keV Constant 0.089 0.000 0.000

31 [redact] acute photons E>250keV Constant 0.011 0.000 0.000

32 [redact] acute photons E>250keV Constant 0.015 0.000 0.000

33 [redact] acute photons E>250keV Constant 0.020 0.000 0.000

34 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

35 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

36 [redact] acute photons E>250keV Constant 0.009 0.000 0.000

37 [redact] acute electrons E>15keV Constant 0.029 0.000 0.000

38 [redact] acute electrons E>15keV Constant 2.722 0.000 0.000

39 [redact] acute electrons E>15keV Constant 3.338 0.000 0.000

40 [redact] acute electrons E>15keV Constant 1.898 0.000 0.000

41 [redact] acute electrons E>15keV Constant 2.069 0.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

29 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-3: IREP Input – BCC [Redacted] (continued)

42 [redact] acute electrons E>15keV Constant 4.110 0.000 0.000

43 [redact] acute electrons E>15keV Constant 0.731 0.000 0.000

44 [redact] acute electrons E>15keV Constant 0.334 0.000 0.000

45 [redact] acute electrons E>15keV Constant 0.001 0.000 0.000

46 [redact] acute electrons E>15keV Constant 0.264 0.000 0.000

47 [redact] acute electrons E>15keV Constant 0.063 0.000 0.000

48 [redact] acute photons E=30-250keV Lognormal 0.180 1.520 0.000

49 [redact] acute photons E=30-250keV Lognormal 0.090 1.520 0.000

50 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

51 [redact] acute photons E=30-250keV Lognormal 0.020 1.520 0.000

52 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

53 [redact] acute photons E=30-250keV Lognormal 0.100 1.520 0.000

54 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

55 [redact] acute photons E=30-250keV Lognormal 0.140 1.520 0.000

56 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

57 [redact] acute photons E=30-250keV Lognormal 0.010 1.520 0.000

58 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

59 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

60 [redact] acute photons E=30-250keV Lognormal 0.040 1.520 0.000

61 [redact] acute photons E=30-250keV Normal 0.003 0.001 0.000

62 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

63 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

64 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

65 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

66 [redact] acute photons E=30-250keV Normal 0.004 0.001 0.000

67 [redact] acute photons E=30-250keV Normal 0.018 0.005 0.000

68 [redact] chronic alpha Lognormal 0.000 3.000 0.000

69 [redact] chronic alpha Lognormal 0.000 3.000 0.000

70 [redact] chronic alpha Lognormal 0.000 3.000 0.000

71 [redact] chronic alpha Lognormal 0.001 3.000 0.000

72 [redact] chronic alpha Lognormal 0.001 3.000 0.000

73 [redact] chronic alpha Lognormal 0.001 3.000 0.000

74 [redact] chronic alpha Lognormal 0.001 3.000 0.000

75 [redact] chronic alpha Lognormal 0.001 3.000 0.000

76 [redact] chronic alpha Lognormal 0.001 3.000 0.000

77 [redact] chronic alpha Lognormal 0.001 3.000 0.000

78 [redact] chronic alpha Lognormal 0.001 3.000 0.000

79 [redact] chronic alpha Lognormal 0.001 3.000 0.000

80 [redact] chronic alpha Lognormal 0.001 3.000 0.000

81 [redact] chronic alpha Lognormal 0.001 3.000 0.000

82 [redact] chronic alpha Lognormal 0.001 3.000 0.000

83 [redact] chronic alpha Lognormal 0.001 3.000 0.000

84 [redact] chronic alpha Lognormal 0.001 3.000 0.000

85 [redact] chronic alpha Lognormal 0.001 3.000 0.000

86 [redact] chronic alpha Lognormal 0.001 3.000 0.000

87 [redact] chronic alpha Lognormal 0.001 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

30 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-3: IREP Input – BCC [Redacted] (continued)

88 [redact] chronic alpha Lognormal 0.001 3.000 0.000

89 [redact] chronic alpha Lognormal 0.001 3.000 0.000

90 [redact] chronic alpha Lognormal 0.001 3.000 0.000

91 [redact] chronic alpha Lognormal 0.001 3.000 0.000

92 [redact] chronic alpha Lognormal 0.001 3.000 0.000

93 [redact] chronic alpha Lognormal 0.001 3.000 0.000

94 [redact] chronic alpha Lognormal 0.001 3.000 0.000

95 [redact] chronic alpha Lognormal 0.001 3.000 0.000

96 [redact] chronic alpha Lognormal 0.001 3.000 0.000

97 [redact] chronic alpha Lognormal 0.001 3.000 0.000

98 [redact] chronic alpha Lognormal 0.000 3.000 0.000

99 [redact] chronic alpha Lognormal 0.000 3.000 0.000

100 [redact] chronic alpha Lognormal 0.000 3.000 0.000

101 [redact] chronic alpha Lognormal 0.000 3.000 0.000

102 [redact] chronic alpha Lognormal 0.000 3.000 0.000

103 [redact] chronic alpha Lognormal 0.000 3.000 0.000

104 [redact] chronic alpha Lognormal 0.000 3.000 0.000

105 [redact] chronic alpha Lognormal 0.000 3.000 0.000

106 [redact] chronic alpha Lognormal 0.000 3.000 0.000

107 [redact] chronic alpha Lognormal 0.000 3.000 0.000

108 [redact] chronic alpha Lognormal 0.000 3.000 0.000

109 [redact] chronic alpha Lognormal 0.000 3.000 0.000

110 [redact] chronic alpha Lognormal 0.000 3.000 0.000

111 [redact] chronic alpha Lognormal 0.000 3.000 0.000

112 [redact] chronic alpha Lognormal 0.000 3.000 0.000

113 [redact] chronic alpha Lognormal 0.000 3.000 0.000

114 [redact] chronic alpha Lognormal 0.000 3.000 0.000

115 [redact] chronic alpha Lognormal 0.000 3.000 0.000

116 [redact] chronic alpha Lognormal 0.000 3.000 0.000

117 [redact] chronic alpha Lognormal 0.000 3.000 0.000

118 [redact] chronic alpha Lognormal 0.000 3.000 0.000

119 [redact] chronic alpha Lognormal 0.000 3.000 0.000

120 [redact] chronic alpha Lognormal 0.000 3.000 0.000

121 [redact] chronic alpha Lognormal 0.000 3.000 0.000

122 [redact] chronic alpha Lognormal 0.000 3.000 0.000

123 [redact] chronic alpha Lognormal 0.000 3.000 0.000

124 [redact] chronic alpha Lognormal 0.000 3.000 0.000

125 [redact] chronic alpha Lognormal 0.000 3.000 0.000

126 [redact] chronic alpha Lognormal 0.000 3.000 0.000

127 [redact] chronic alpha Lognormal 0.000 3.000 0.000

128 [redact] chronic alpha Lognormal 0.000 3.000 0.000

129 [redact] chronic alpha Lognormal 0.000 3.000 0.000

130 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

131 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

132 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

133 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

31 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-3: IREP Input – BCC [Redacted] (continued)

134 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

135 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

136 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

137 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

138 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

139 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

140 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

141 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

142 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

143 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

144 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

145 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

146 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

147 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

148 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

149 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

150 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

151 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

152 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

153 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

154 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

155 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

156 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

157 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

158 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

159 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

160 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

161 [redact] chronic electrons E<15keV Lognormal 2.000 2.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

32 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX I.A-4: IREP INPUT – SCC [REDACTED]

EXPOSURE INFORMATION

Number of exposures

160

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose Distribution 

Type Parameter 1 Parameter 2 Parameter 3

1 [redact] acute photons E<30keV Constant 0.023 0.000 0.000

2 [redact] acute photons E<30keV Constant 0.041 0.000 0.000

3 [redact] acute photons E<30keV Constant 0.018 0.000 0.000

4 [redact] acute photons E<30keV Constant 0.017 0.000 0.000

5 [redact] acute photons E<30keV Constant 0.052 0.000 0.000

6 [redact] acute photons E<30keV Constant 0.021 0.000 0.000

7 [redact] acute photons E<30keV Constant 0.003 0.000 0.000

8 [redact] acute photons E<30keV Constant 0.004 0.000 0.000

9 [redact] acute photons E<30keV Constant 0.005 0.000 0.000

10 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

11 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

12 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

13 [redact] acute photons E=30-250keV Constant 0.058 0.000 0.000

14 [redact] acute photons E=30-250keV Constant 0.105 0.000 0.000

15 [redact] acute photons E=30-250keV Constant 0.047 0.000 0.000

16 [redact] acute photons E=30-250keV Constant 0.044 0.000 0.000

17 [redact] acute photons E=30-250keV Constant 0.133 0.000 0.000

18 [redact] acute photons E=30-250keV Constant 0.054 0.000 0.000

19 [redact] acute photons E=30-250keV Constant 0.007 0.000 0.000

20 [redact] acute photons E=30-250keV Constant 0.009 0.000 0.000

21 [redact] acute photons E=30-250keV Constant 0.012 0.000 0.000

22 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

23 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

24 [redact] acute photons E=30-250keV Constant 0.005 0.000 0.000

25 [redact] acute photons E>250keV Constant 0.086 0.000 0.000

26 [redact] acute photons E>250keV Constant 0.156 0.000 0.000

27 [redact] acute photons E>250keV Constant 0.076 0.000 0.000

28 [redact] acute photons E>250keV Constant 0.072 0.000 0.000

29 [redact] acute photons E>250keV Constant 0.217 0.000 0.000

30 [redact] acute photons E>250keV Constant 0.089 0.000 0.000

31 [redact] acute photons E>250keV Constant 0.011 0.000 0.000

32 [redact] acute photons E>250keV Constant 0.015 0.000 0.000

33 [redact] acute photons E>250keV Constant 0.020 0.000 0.000

34 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

35 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

36 [redact] acute photons E>250keV Constant 0.009 0.000 0.000

37 [redact] acute electrons E>15keV Constant 0.029 0.000 0.000

38 [redact] acute electrons E>15keV Constant 2.722 0.000 0.000

39 [redact] acute electrons E>15keV Constant 3.338 0.000 0.000

40 [redact] acute electrons E>15keV Constant 1.898 0.000 0.000

41 [redact] acute electrons E>15keV Constant 2.069 0.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

33 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-4: IREP Input – SCC [Redacted] (continued)

42 [redact] acute electrons E>15keV Constant 4.110 0.000 0.000

43 [redact] acute electrons E>15keV Constant 0.731 0.000 0.000

44 [redact] acute electrons E>15keV Constant 0.334 0.000 0.000

45 [redact] acute electrons E>15keV Constant 0.001 0.000 0.000

46 [redact] acute electrons E>15keV Constant 0.264 0.000 0.000

47 [redact] acute electrons E>15keV Constant 0.063 0.000 0.000

48 [redact] acute photons E=30-250keV Lognormal 0.180 1.520 0.000

49 [redact] acute photons E=30-250keV Lognormal 0.090 1.520 0.000

50 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

51 [redact] acute photons E=30-250keV Lognormal 0.020 1.520 0.000

52 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

53 [redact] acute photons E=30-250keV Lognormal 0.100 1.520 0.000

54 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

55 [redact] acute photons E=30-250keV Lognormal 0.140 1.520 0.000

56 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

57 [redact] acute photons E=30-250keV Lognormal 0.010 1.520 0.000

58 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

59 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

60 [redact] acute photons E=30-250keV Lognormal 0.040 1.520 0.000

61 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

62 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

63 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

64 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

65 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

66 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

67 [redact] acute photons E=30-250keV Normal 0.018 0.005 0.000

68 [redact] chronic alpha Lognormal 0.000 3.000 0.000

69 [redact] chronic alpha Lognormal 0.000 3.000 0.000

70 [redact] chronic alpha Lognormal 0.000 3.000 0.000

71 [redact] chronic alpha Lognormal 0.001 3.000 0.000

72 [redact] chronic alpha Lognormal 0.001 3.000 0.000

73 [redact] chronic alpha Lognormal 0.001 3.000 0.000

74 [redact] chronic alpha Lognormal 0.001 3.000 0.000

75 [redact] chronic alpha Lognormal 0.001 3.000 0.000

76 [redact] chronic alpha Lognormal 0.001 3.000 0.000

77 [redact] chronic alpha Lognormal 0.001 3.000 0.000

78 [redact] chronic alpha Lognormal 0.001 3.000 0.000

79 [redact] chronic alpha Lognormal 0.001 3.000 0.000

80 [redact] chronic alpha Lognormal 0.001 3.000 0.000

81 [redact] chronic alpha Lognormal 0.001 3.000 0.000

82 [redact] chronic alpha Lognormal 0.001 3.000 0.000

83 [redact] chronic alpha Lognormal 0.001 3.000 0.000

84 [redact] chronic alpha Lognormal 0.001 3.000 0.000

85 [redact] chronic alpha Lognormal 0.001 3.000 0.000

86 [redact] chronic alpha Lognormal 0.001 3.000 0.000

87 [redact] chronic alpha Lognormal 0.001 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

34 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-4: IREP Input – SCC [Redacted] (continued)

88 [redact] chronic alpha Lognormal 0.001 3.000 0.000

89 [redact] chronic alpha Lognormal 0.001 3.000 0.000

90 [redact] chronic alpha Lognormal 0.001 3.000 0.000

91 [redact] chronic alpha Lognormal 0.001 3.000 0.000

92 [redact] chronic alpha Lognormal 0.001 3.000 0.000

93 [redact] chronic alpha Lognormal 0.001 3.000 0.000

94 [redact] chronic alpha Lognormal 0.001 3.000 0.000

95 [redact] chronic alpha Lognormal 0.001 3.000 0.000

96 [redact] chronic alpha Lognormal 0.001 3.000 0.000

97 [redact] chronic alpha Lognormal 0.001 3.000 0.000

98 [redact] chronic alpha Lognormal 0.000 3.000 0.000

99 [redact] chronic alpha Lognormal 0.000 3.000 0.000

100 [redact] chronic alpha Lognormal 0.000 3.000 0.000

101 [redact] chronic alpha Lognormal 0.000 3.000 0.000

102 [redact] chronic alpha Lognormal 0.000 3.000 0.000

103 [redact] chronic alpha Lognormal 0.000 3.000 0.000

104 [redact] chronic alpha Lognormal 0.000 3.000 0.000

105 [redact] chronic alpha Lognormal 0.000 3.000 0.000

106 [redact] chronic alpha Lognormal 0.000 3.000 0.000

107 [redact] chronic alpha Lognormal 0.000 3.000 0.000

108 [redact] chronic alpha Lognormal 0.000 3.000 0.000

109 [redact] chronic alpha Lognormal 0.000 3.000 0.000

110 [redact] chronic alpha Lognormal 0.000 3.000 0.000

111 [redact] chronic alpha Lognormal 0.000 3.000 0.000

112 [redact] chronic alpha Lognormal 0.000 3.000 0.000

113 [redact] chronic alpha Lognormal 0.000 3.000 0.000

114 [redact] chronic alpha Lognormal 0.000 3.000 0.000

115 [redact] chronic alpha Lognormal 0.000 3.000 0.000

116 [redact] chronic alpha Lognormal 0.000 3.000 0.000

117 [redact] chronic alpha Lognormal 0.000 3.000 0.000

118 [redact] chronic alpha Lognormal 0.000 3.000 0.000

119 [redact] chronic alpha Lognormal 0.000 3.000 0.000

120 [redact] chronic alpha Lognormal 0.000 3.000 0.000

121 [redact] chronic alpha Lognormal 0.000 3.000 0.000

122 [redact] chronic alpha Lognormal 0.000 3.000 0.000

123 [redact] chronic alpha Lognormal 0.000 3.000 0.000

124 [redact] chronic alpha Lognormal 0.000 3.000 0.000

125 [redact] chronic alpha Lognormal 0.000 3.000 0.000

126 [redact] chronic alpha Lognormal 0.000 3.000 0.000

127 [redact] chronic alpha Lognormal 0.000 3.000 0.000

128 [redact] chronic alpha Lognormal 0.000 3.000 0.000

129 [redact] chronic alpha Lognormal 0.000 3.000 0.000

130 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

131 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

132 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

133 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

35 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix I.A-4: IREP Input – SCC [Redacted] (continued)

134 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

135 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

136 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

137 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

138 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

139 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

140 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

141 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

142 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

143 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

144 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

145 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

146 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

147 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

148 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

149 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

150 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

151 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

152 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

153 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

154 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

155 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

156 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

157 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

158 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

159 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

160 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

36 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX I.A-5: IREP INPUT – SCC [REDACTED]

EXPOSURE INFORMATION

Number of exposures

160

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose Distribution 

Type Parameter 1 Parameter 2 Parameter 3

1 [redact] acute photons E<30keV Constant 0.023 0.000 0.000

2 [redact] acute photons E<30keV Constant 0.041 0.000 0.000

3 [redact] acute photons E<30keV Constant 0.018 0.000 0.000

4 [redact] acute photons E<30keV Constant 0.017 0.000 0.000

5 [redact] acute photons E<30keV Constant 0.052 0.000 0.000

6 [redact] acute photons E<30keV Constant 0.021 0.000 0.000

7 [redact] acute photons E<30keV Constant 0.003 0.000 0.000

8 [redact] acute photons E<30keV Constant 0.004 0.000 0.000

9 [redact] acute photons E<30keV Constant 0.005 0.000 0.000

10 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

11 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

12 [redact] acute photons E<30keV Constant 0.002 0.000 0.000

13 [redact] acute photons E=30-250keV Constant 0.058 0.000 0.000

14 [redact] acute photons E=30-250keV Constant 0.105 0.000 0.000

15 [redact] acute photons E=30-250keV Constant 0.047 0.000 0.000

16 [redact] acute photons E=30-250keV Constant 0.044 0.000 0.000

17 [redact] acute photons E=30-250keV Constant 0.133 0.000 0.000

18 [redact] acute photons E=30-250keV Constant 0.054 0.000 0.000

19 [redact] acute photons E=30-250keV Constant 0.007 0.000 0.000

20 [redact] acute photons E=30-250keV Constant 0.009 0.000 0.000

21 [redact] acute photons E=30-250keV Constant 0.012 0.000 0.000

22 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

23 [redact] acute photons E=30-250keV Constant 0.004 0.000 0.000

24 [redact] acute photons E=30-250keV Constant 0.005 0.000 0.000

25 [redact] acute photons E>250keV Constant 0.086 0.000 0.000

26 [redact] acute photons E>250keV Constant 0.156 0.000 0.000

27 [redact] acute photons E>250keV Constant 0.076 0.000 0.000

28 [redact] acute photons E>250keV Constant 0.072 0.000 0.000

29 [redact] acute photons E>250keV Constant 0.217 0.000 0.000

30 [redact] acute photons E>250keV Constant 0.089 0.000 0.000

31 [redact] acute photons E>250keV Constant 0.011 0.000 0.000

32 [redact] acute photons E>250keV Constant 0.015 0.000 0.000

33 [redact] acute photons E>250keV Constant 0.020 0.000 0.000

34 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

35 [redact] acute photons E>250keV Constant 0.006 0.000 0.000

36 [redact] acute photons E>250keV Constant 0.009 0.000 0.000

37 [redact] acute electrons E>15keV Constant 0.029 0.000 0.000

38 [redact] acute electrons E>15keV Constant 2.722 0.000 0.000

39 [redact] acute electrons E>15keV Constant 3.338 0.000 0.000

40 [redact] acute electrons E>15keV Constant 1.898 0.000 0.000

41 [redact] acute electrons E>15keV Constant 2.069 0.000 0.000
Effective Date:

January 13, 2014

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Appendix I.A-5: IREP Input – SCC [Redacted] (continued)

42 [redact] acute electrons E>15keV Constant 4.110 0.000 0.000

43 [redact] acute electrons E>15keV Constant 0.731 0.000 0.000

44 [redact] acute electrons E>15keV Constant 0.334 0.000 0.000

45 [redact] acute electrons E>15keV Constant 0.001 0.000 0.000

46 [redact] acute electrons E>15keV Constant 0.264 0.000 0.000

47 [redact] acute electrons E>15keV Constant 0.063 0.000 0.000

48 [redact] acute photons E=30-250keV Lognormal 0.180 1.520 0.000

49 [redact] acute photons E=30-250keV Lognormal 0.090 1.520 0.000

50 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

51 [redact] acute photons E=30-250keV Lognormal 0.020 1.520 0.000

52 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

53 [redact] acute photons E=30-250keV Lognormal 0.100 1.520 0.000

54 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

55 [redact] acute photons E=30-250keV Lognormal 0.140 1.520 0.000

56 [redact] acute photons E=30-250keV Lognormal 0.120 1.520 0.000

57 [redact] acute photons E=30-250keV Lognormal 0.010 1.520 0.000

58 [redact] acute photons E=30-250keV Lognormal 0.030 1.520 0.000

59 [redact] acute photons E=30-250keV Lognormal 0.050 1.520 0.000

60 [redact] acute photons E=30-250keV Lognormal 0.040 1.520 0.000

61 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

62 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

63 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

64 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

65 [redact] acute photons E=30-250keV Normal 0.014 0.004 0.000

66 [redact] acute photons E=30-250keV Normal 0.007 0.002 0.000

67 [redact] acute photons E=30-250keV Normal 0.018 0.005 0.000

68 [redact] chronic alpha Lognormal 0.000 3.000 0.000

69 [redact] chronic alpha Lognormal 0.000 3.000 0.000

70 [redact] chronic alpha Lognormal 0.000 3.000 0.000

71 [redact] chronic alpha Lognormal 0.001 3.000 0.000

72 [redact] chronic alpha Lognormal 0.001 3.000 0.000

73 [redact] chronic alpha Lognormal 0.001 3.000 0.000

74 [redact] chronic alpha Lognormal 0.001 3.000 0.000

75 [redact] chronic alpha Lognormal 0.001 3.000 0.000

76 [redact] chronic alpha Lognormal 0.001 3.000 0.000

77 [redact] chronic alpha Lognormal 0.001 3.000 0.000

78 [redact] chronic alpha Lognormal 0.001 3.000 0.000

79 [redact] chronic alpha Lognormal 0.001 3.000 0.000

80 [redact] chronic alpha Lognormal 0.001 3.000 0.000

81 [redact] chronic alpha Lognormal 0.001 3.000 0.000

82 [redact] chronic alpha Lognormal 0.001 3.000 0.000

83 [redact] chronic alpha Lognormal 0.001 3.000 0.000

84 [redact] chronic alpha Lognormal 0.001 3.000 0.000

85 [redact] chronic alpha Lognormal 0.001 3.000 0.000

86 [redact] chronic alpha Lognormal 0.001 3.000 0.000

87 [redact] chronic alpha Lognormal 0.001 3.000 0.000
Effective Date:

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Appendix I.A-5: IREP Input – SCC [Redacted] (continued)

88 [redact] chronic alpha Lognormal 0.001 3.000 0.000

89 [redact] chronic alpha Lognormal 0.001 3.000 0.000

90 [redact] chronic alpha Lognormal 0.001 3.000 0.000

91 [redact] chronic alpha Lognormal 0.001 3.000 0.000

92 [redact] chronic alpha Lognormal 0.001 3.000 0.000

93 [redact] chronic alpha Lognormal 0.001 3.000 0.000

94 [redact] chronic alpha Lognormal 0.001 3.000 0.000

95 [redact] chronic alpha Lognormal 0.001 3.000 0.000

96 [redact] chronic alpha Lognormal 0.001 3.000 0.000

97 [redact] chronic alpha Lognormal 0.001 3.000 0.000

98 [redact] chronic alpha Lognormal 0.000 3.000 0.000

99 [redact] chronic alpha Lognormal 0.000 3.000 0.000

100 [redact] chronic alpha Lognormal 0.000 3.000 0.000

101 [redact] chronic alpha Lognormal 0.000 3.000 0.000

102 [redact] chronic alpha Lognormal 0.000 3.000 0.000

103 [redact] chronic alpha Lognormal 0.000 3.000 0.000

104 [redact] chronic alpha Lognormal 0.000 3.000 0.000

105 [redact] chronic alpha Lognormal 0.000 3.000 0.000

106 [redact] chronic alpha Lognormal 0.000 3.000 0.000

107 [redact] chronic alpha Lognormal 0.000 3.000 0.000

108 [redact] chronic alpha Lognormal 0.000 3.000 0.000

109 [redact] chronic alpha Lognormal 0.000 3.000 0.000

110 [redact] chronic alpha Lognormal 0.000 3.000 0.000

111 [redact] chronic alpha Lognormal 0.000 3.000 0.000

112 [redact] chronic alpha Lognormal 0.000 3.000 0.000

113 [redact] chronic alpha Lognormal 0.000 3.000 0.000

114 [redact] chronic alpha Lognormal 0.000 3.000 0.000

115 [redact] chronic alpha Lognormal 0.000 3.000 0.000

116 [redact] chronic alpha Lognormal 0.000 3.000 0.000

117 [redact] chronic alpha Lognormal 0.000 3.000 0.000

118 [redact] chronic alpha Lognormal 0.000 3.000 0.000

119 [redact] chronic alpha Lognormal 0.000 3.000 0.000

120 [redact] chronic alpha Lognormal 0.000 3.000 0.000

121 [redact] chronic alpha Lognormal 0.000 3.000 0.000

122 [redact] chronic alpha Lognormal 0.000 3.000 0.000

123 [redact] chronic alpha Lognormal 0.000 3.000 0.000

124 [redact] chronic alpha Lognormal 0.000 3.000 0.000

125 [redact] chronic alpha Lognormal 0.000 3.000 0.000

126 [redact] chronic alpha Lognormal 0.000 3.000 0.000

127 [redact] chronic alpha Lognormal 0.000 3.000 0.000

128 [redact] chronic alpha Lognormal 0.000 3.000 0.000

129 [redact] chronic alpha Lognormal 0.000 3.000 0.000

130 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

131 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

132 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

133 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

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Appendix I.A-5: IREP Input – SCC [Redacted] (continued)

134 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

135 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

136 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

137 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

138 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

139 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

140 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

141 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

142 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

143 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

144 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

145 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

146 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

147 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

148 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

149 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

150 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

151 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

152 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

153 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

154 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

155 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

156 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

157 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

158 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

159 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000

160 [redact] chronic electrons E>15keV Lognormal 0.000 3.000 0.000
Effective Date:

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SECTION II: DR–METHOD B 

II.1 DOSE RECONSTRUCTION OVERVIEW 

Section II of this report presents a blind DR for a claimant that worked at Fernald and contracted 

five skin cancers. This worker was monitored under an external and internal radiation 

monitoring program, which included recorded photon and beta exposure and uranium bioassay 

data. 

Our investigation evaluated recorded and missed doses to penetrating and non-penetrating 

radiation based on film badge and TLD data, potential neutron exposures, exposures associated 

with the direct deposition of uranium dust on bare skin and clothing, and internal dose from 

uranium inhalation. The following table summarizes our estimate of the worker’s skin dose. 

Based on these results, we derived a POC of 39.33%.

Table II-1. Summary of SC&A-Derived Dose Estimates for Method B 

Dose for [redact] BCC

(Unattenuated) (rem)

Dose for [redact]

BCC & SCCs (rem)

Dose [redact] SCC

(Attenuated) (rem)

Recorded photon dose 1.6 1.6 1.6

Recorded shallow dose 15.5 15.5 13.3

Missed photon dose 0.9 0.9 0.9

Occupational x-ray 0.13 0.13 0.13

Missed neutron dose 0.288 0.288 0.288

Skin deposition 0.201 0.201 0.201

Internal dose 0.254 0.293 0.238

Total 18.9 18.9 16.6

II.1.1 DOSE RECONSTRUCTION APPROACH 

The approach used by SC&A to perform this blind DR began with developing an understanding 

of the work history of this EE vis-à-vis the types of activities that were ongoing in different 

buildings and time periods at Fernald. This was accomplished by reviewing the totality of the 

EE’s records, and also reviewing the site profile and other documents in the Site Research 

Database (SRDB) that would help us understand the types of activities and exposures this EE

might have experienced each year of employment at Fernald. Once we were able to develop an 

understanding of this EE’s occupational/radiological exposure history, we compiled all the 

information available that would help us reconstruct the EE’s exposure for each year of 

employment at Fernald. This information included the EE’s personnel dosimetry and bioassay 

records (including urine samples and chest counts) and air sampling, as well as other data that 

might help to characterize the internal and external radiation exposures this EE might have 

experienced. We reconstructed the doses as needed for the IREP input sheets, which were used 

to derive a POC for this worker.
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II.2 RELEVANT CASE INFORMATION 

According to the DOL records, this case represents a [redacted] EE born in [redacted] who

worked at Fernald from [redacted] to [redacted] as a [redacted], [redacted], [redacted], 

[redacted], and [redacted]. Beginning in [redacted] through [redacted], the EE was diagnosed 

with several non-melanoma skin cancers on the [redacted], [redacted], [redacted], and 

[redacted].

The DR for the case relied heavily on the detailed information provided by the EE in the CATI 

Report. For this reason, we provide excerpts of the interview. The following are verbatim

statements cited in the CATI Report for Case #[redacted].

Job Locations and Responsibilities 

Locations 

[redacted]: Laboratory

[redacted]: Plant [redacted]

[redacted]: Plant [redacted]

[redacted]: Plant [redacted]

[redacted]: Numerous Plants: [EE] said they went anywhere the work was; this 

involved moving throughout the facility.

[redacted]: [EE] said they went anywhere the work was; [the EE] said they were 

in about 80% of the buildings on-site.

[redacted]: [redacted]

[redacted]: Plant [redacted], Plant [redacted] and miscellaneous jobs 

throughout the site

Duties 

[Redacted in full.]

The CATI Report also provides the following information regarding the EE: 

 The EE was exposed to lead, radon, thorium, natural and enriched uranium, and 

plutonium 

 The EE always wore coveralls, safety glasses, a head cover, and goggles at all times, and 

showered before going to lunch and at quitting time 

 The EE wore gloves and shoe covers for certain jobs 

 The EE wore a film badge on the EE’s chest or collar and always on the outside of the 

EE’s clothing 

 In the early years they did not frisk, but did so in later years 

 The EE worked under a radiation work permit when working as a [redacted]

 The EE was required to received x-ray examinations as a requirement for employment 

(an initial and annual x-rays) 
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 The EE was involved in incidents 

 The EE names several coworkers 

In the interview, the EE also described the following incidents: 

Incident One: [Redacted in full.]

Incident Two: [Redacted in full.]

II.2.1 INTERPRETATION OF CATI AND OTHER BACKGROUND INFORMATION 

AS APPLICABLE TO THE DR

The worker was employed at FMPC, also known as Fernald, from [redacted], to [redacted]. 

During that period, management of the Fernald operating contract changed several times. 

[Redacted in full.]. Dates of employment for the worker with each contractor were as follows 

(DOE Response_[Redacted]_D103.pdf, p. 21):

[Redacted in full.]

During the EE’s employment at Fernald, the EE’s work breakdown and work locations were as 

follows (CATI Summary Draft_[Redacted]_P12241_v1.pdf, p. 10): 

 [Redacted], Laboratory 

 [Redacted], Plant [Redacted]

 [Redacted], Plant [Redacted]

 [Redacted], Plant [Redacted]

 [Redacted], Numerous Plants

 [Redacted], About 80% of on-site buildings

 [Redacted], [Redacted], [Redacted]

 [Redacted], Plant [Redacted] and Plant [Redacted]

In all of the jobs, except that of [redacted], the worker was exposed to radioactive materials for 

40+ hours per week. As a [redacted], exposure to radiation was about 10 hours per week.

The worker received x-rays at the time of employment and at each annual physical. The EE had 

at least one additional x-ray relating to a [redacted] (DOE Response_[redacted]_D103.pdf, p. 

92). 

A considerable portion of the EE’s employment ([redacted]–[redacted] and [redacted]–

[redacted]) was spent in Plant [redacted]. Operations in Plant [redacted] included (ORAUTTKBS-0017-2):

[Redacted in full.]
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In Plant [redacted], the EE’s exposure was to depleted and/or enriched uranium. The EE was 

also exposed to thorium while working with the [redacted] in [redacted]–[redacted]. 

Elsewhere, the EE cites exposure to lead, radon, radium, thorium, plutonium, natural uranium, 

enriched uranium and uranium dust (CATI Summary Draft _[redacted]_v2.pdf, [redact]). The 

EE states in the CATI Report that the EE was exposed to “plutonium (green salt)” in Plant 

[redacted]. This appears to be in error. Plant [redacted] did indeed produce green salt 

(uranium tetrafluoride or UF4), but did not handle plutonium except as a contaminant introduced 

with RU.

II.2.2 RADIATION INCIDENTS 

As discussed in Section II.2 above, the CATI describes two incidents where non-routine 

radiation exposures could have occurred. Incident 1 occurred in Plant [redacted] when the 

worker was [redacted]. The EE was wearing coveralls, a hard hat, gloves and a face shield. 

According to the incident report, Incident 2 occurred in Plant [redacted] while the worker was 

[redacted]. [redacted]. During the [redacted]. After the EE felt better, the EE donned a 

chemical respirator instead of a particulate respirator and completed the test. In the CATI, the 

EE said that the test was not completed, and the EE only used a particulate respirator. On 

[redacted], a special request was made for a whole-body scan of the worker, who at the time 

was doing decontamination in Building [redacted]. The scan did not detect any significant 

exposure.

On [redacted], the EE was involved in an incident not mentioned in the CATI. At that time, the

EE was [redacted]. Consequently, the next day the EE’s urine was tested, and the EE received a 

whole-body count, which showed negligible contamination from Pb-212, Ac-228, U-235 and 

U-238 (DOE Response_[redacted]_D103.pdf, p. 77).

 

II.2.3 RADIATION MONITORING AND CONTROL MEASURES 

Based on the CATI, the EE’s radiation monitoring and radiological control measures included 

the following: 

 Wore a head cover, coveralls and safety glasses at all times 

 Wore cotton gloves in the work area and sometimes shoe covers 

 Took a shower when leaving the work area for lunch and at the end of the day as well as 

anytime the EE left the contaminated side of the work area for the clean side 

 Wore radiation monitoring badge at all times either on the EE’s chest pocket or just 

below the collar of the EE’s coveralls 

 Used a whole-body frisker, after [redacted], to assess contamination when passing from 

the contaminated side to the clean side of the work area 

 Radiation surveys were performed while the EE was employed as an [redacted] if a work 

permit was required to enter a particular area
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 Urinalysis monitoring performed routinely for uranium intake from [redacted] through 

[redacted]

 Additional urine samples were taken if an incident occurred 

 Limited fecal samples were analyzed for thorium in [redacted]

 Received about seven in-vivo lung scans between [redacted] and [redacted] with all 

results reported as less than the limit of detection (DOE Response_[redacted]_

D103.pdf, p. 40).

II.2.4 PRIMARY RADIONUCLIDES OF CONCERN 

On a generic basis, workers at FMPC were exposed to uranium and progeny (including enriched, 

depleted, natural and recycled), thorium and progeny, thoron and progeny, and radon and 

progeny. Specific activities and activity fractions are summarized in Table II-2 (from ORAUTTKBS-0017-2, Table 2-49). It should be noted that as part of discussions in the Fernald WG, 

NIOSH has agreed to change the default levels of plutonium-239, neptunium-237, and 

technetium-99 in RU over three periods of time that correspond to changing constituent 

concentration levels in incoming feed stocks. However, at the time that this DR was performed, 

the TBD has not been updated. Thus, in assigning dose to this EE from RU, SC&A used the 

values cited in Table II-2 below. 
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Table II-2. Specific Activities and Activity Fractions* 

Uranium 

Enrichment

U+Cont.

(Bq/mg)

U Pu - 80ppb Np – 300 ppb Tc- 5000 ppb

Bq/mg f act. Bq/mg f act. Bq/mg f act. Bq/mg f act.

Depleted 4.53E+01 1.38E+01 0.305 1.83E-01 0.004 7.77E03 1.72E-04 3.13E+00 0.69

Natural 5.76E+01 2.61E+01 0.453 1.83E-01 0.003 7.77E03 1.35E-04 3.13E+00 0.54

2% Enrich 9.14E+01 6.03E+01 0.66 1.83E-01 0.002 7.77E03 8.50E-05 3.13E+00 0.34

Specific Activities for Enriched Uranium:

Uranium Enrichment Isotopes Mass % f activities

Depleted U-234

U-235

U-238

0.05

0.25

99.75

0.083

0.014

0.903

Natural U-234

U-235

U-238

0.0057

0.7204

99.273

0.504

0.023

0.473

2% Enrich U-234

U-235

U-238

0.02

2.0

97.98

0.770

0.026

0.204

Specific Activities for Thorium:

Thorium-232 would be the default isotope. The degree of equilibrium is impossible to estimate, due to the variation 

in times since chemical separation of the feed stock. The specific activity value for 232Th and daughters is 

1.11E-07 Ci/gm or 4.11 Bq/mg.

Working Level (WL) Conversion Factor for Rn daughters:

1 WL = 100 pCi/L for 100% Rn daughter equilibrium

1 WLM (100% equilibrium) = 1.70E+04 pCi

WLM = 0.118 (feq )(Rn concentration in pCi/L), equilibrium factor feq = 0.4(for indoor), 0.7(for outdoor) and 

2,000 hrs exposure time.

*Recycled uranium (RU) is uranium which was recovered from spent fuel processing plants at Hanford, Savannah 

River, ICPP, and West Valley. Between 1958 and 1988, 17,966 MT of RU was shipped to FMPC. Information 

above can be used to estimate the exposures to lead, plutonium, and technetium, as well as the uranium isotopes. 

II.3 RECONSTRUCTION OF EXTERNAL DOSE 

Since the worker was diagnosed with several non-melanoma skin cancers on the [redacted], 

[redacted], [redacted], and [redacted], it is deemed likely that the reconstruction of external 

gamma and beta doses were likely the major sources of skin exposure. However, the DR also 

considered assigning doses to skin from neutron exposures and from direct deposition of fine 

particles of uranium and uranium flakes on the exposed and covered portions of this worker’s 

body. In assessing skin dose from potential direct deposition of uranium particles/flakes, 

consideration was given to the fact that the EE worked at Fernald from [redacted] to [redacted], 

when contamination control measures were in place, such as wearing protective clothing and

showering at least daily after completing a work day or a particular task. As will be noted 

throughout this blind DR, it was necessary to perform an in-depth review of many of the issues 

associated with external exposures of skin, which can be quite complex. We believe that we 
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have uncovered a number of site profile issues that, though they do not affect this blind DR, 

should be considered by the Fernald DR WG as part of the site profile issues resolution process. 

II.3.1 RELIABILITY OF SKIN DOSES AS RECONSTRUCTED USING EXTERNAL 

BETA DOSIMETRY DATA 

The administrative record for this worker indicates that the EE was monitored for external 

exposures under a monthly external dosimetry program for most of the EE’s employment at 

Fernald, and the program monitored deep dose equivalent and non-penetrating exposures. 

Table II-3 presents an example of the types of external dosimetry data that were provided by 

DOE for this worker. The administrative record also includes annual roll-up doses and doses in 

handwritten form. In addition, there appears to be a limited amount of data on external 

exposures to hands and forearms. 

Table II-3. Example of External Dosimetry Data Recorded in Behalf of Case #[redacted]

Given that the EE was monitored for deep and shallow doses and the cancers of concern are skin 

cancers, we attempted to determine whether the data are complete, adequate, and accurate with 

respect to reconstructing doses to skin for the broad range of jobs that this worker performed. 

These job assignments included working with uranium metal, uranium salts, enriched and RU, 

and thorium. In addition, the EE was also involved in incidents where the EE’s skin could have 

been contaminated with uranium. 
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Section 6.0 of the site profile (ORAUT-TKBS-0017-6) is helpful in understanding the 

complexity of the external exposures that the EE might have experienced. Noteworthy are 

exposure to Tc-99 (0.292 MeV beta), and the strong beta emitters associated with the progeny of 

U-238 (e.g., Pa-234m with its 2.29 MeV beta). Also, Section 6.3.1 of the site profile, Site 

Historic Administrative Practices, provides an understanding of the types of external dosimetry 

practices employed at the facility from [redacted] through [redacted].

 

As indicated in Table 6-3 of ORAUT-TKBS-0017-6, workers were badged with the Oak Ridge 

National Laboratory (ORNL) beta/gamma dosimeters from [redacted] to [redacted]. According 

to the ORNL site profile (ORAUT-TKBS-0012-6), a number of different types of film badges 

and TLDs were issued at ORNL beginning in 1975. It appears that a type of hybrid Class 2 or 

Class 3 dosimeter was likely employed for this Fernald worker from [redacted] to [redacted]. 

According to the ORNL site profile, Class 2 dosimeters were issued for whole-body and skin 

dose, and for indicating neutron exposure, but not to quantifiably measure neutron exposure. 

The Class 2 dosimeter contained a TLD-100 chip under an aluminum filter, and two thin TLD700 chips, one under an open window (OW) and the other under plastic. The Type 3 (and red 

dot issued [redacted]–[redacted]) dosimeter was a four-element design with a TLD-600 and a 

TLD-700 under a cadmium filter, a TLD-600 and a TLD-700 under an aluminum filter, and two 

thin (0.015-inch) TLD-700 chips under the OW and plastic filters. A vapor-sealed NTA film 

monitored fast neutrons. The Type 3 and red dot dosimeters were issued to radiation workers for 

whom neutron monitoring was appropriate. It does not appear that the EE was issued red dot 

dosimeters. 

Table 6-3 of the FEMP site profile indicates that from 1959 to 1985, the “ORNL dosimeter” was 

used with a Cu, Cd, plastic, lead and filter, and also an OW portion, and Table 6-4 indicates that 

calibration of the dosimeters used radium and uranium until 1985 with results expressed in units 

of air exposure (i.e., Roentgens). The combination of different types of filters allows the readout 

to account for the over-response of film or TLDs2

to low-energy photons, to reliably measure 

beta and low-energy non-penetrating photons to determine skin exposures, and to determine if 

neutron exposures were occurring. These features appear to be adequate to obtain a reliable 

estimate of skin exposures if (1) the dosimeter was worn outside of clothing (which, according to 

the CATI, they were), (2) consideration was given to any special packaging, and (3) calibration 

of the dosimeters employed photon and electron energy spectra that were comparable to the 

spectra experienced by the workers. 

From 1985 to the present, Fernald used commercial Panasonic TLDs with multiple filters, and 

according to Table 6-4 of the site profile, these dosimeters were calibrated using a phantom to 

derive dose in units of rem, as required for radiation protection reporting requirements. In all 

cases, natural background was subtracted from the reported exposures. Sections 6.3.2.2 and 

6.3.3.2 of the ORAUT-TKBS-0017-6 explain that Cs-137 was used for gamma calibration, and it 

appears that a uranium slab was used for beta calibration. Also, algorithms were developed and 

tested to convert the readout under each element of the TLD to deep dose equivalent and skin 

 

2

 There appears to be some ambiguity regarding whether film or TLD multi-element dosimetry was 

employed into the 1980s, as discussed in Section 6.3.2.1. However, the discussion that follows is applicable to each 

type of dosimeter. 
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dose. The section also describes problems encountered in beta calibration. Issues related to 

calibration of beta/photon dosimeters are discussed in Section 6.3.3 of the site profile, which 

emphasizes the importance of using appropriate calibration sources when calibrating dosimeters 

for beta exposures. 

In light of the many complexities and uncertainties regarding the types of dosimeters that might 

have been used at Fernald, Table 6-4 of the site profile recommends that, from 1954 to 1985, 

when film was used, the skin dose should be estimated using the OW plus deep dose results. For 

1985 to the present, when TLDs were used, the skin dose should be determined by summing the 

non-penetrating (Npen) plus deep dose readouts. In addition, Section 6.5 of the site profile 

addresses the need for conversion factors (CFs) to the dosimeter results; i.e., add 10% dose to the 

<250 MeV fractions given in Table 6-8. However, these recommended adjustment factors are 

limited to film (i.e., pre-1985) and only to the deep dose results, and no CFs are recommended 

for non-penetrating dose. 

Section 6.6.1 of the site profile addresses missed dose, and recommends that 1⁄2 the MDL for 

missed beta/photon dose be used. For 1959–1984, the recommended MDL is 30 mrem/change 

out (which was monthly at that time), and from 1984 to the present, the recommended MDL is 

20 mrem/change out (which was quarterly during that time period). 

II.3.1.1 Issues Related to Tc-99 

Based on our review, the external dosimetry program for photon and beta exposures appears 

comprehensive and reliable. However, one issue arose during our investigations that required 

further investigation; namely, exposures to Tc-99. 

Section 6.3.2 of ORAUT-TKBS-0017-6 acknowledges that many of the facilities and activities at 

Fernald involved the generation of considerable dust, and that dosimeters were placed in plastic 

bags for protection against dust contamination. Such plastic bags would shield the sensitive 

elements (whether film or TLD) resulting in an underestimate of the beta exposure. The site 

profile further explains that the dosimeters were calibrated with plastic bags in place, and, as 

such, should provide reliable estimates of both penetrating and non-penetrating exposures, 

because calibration takes into consideration the presence of the plastic bags. However, it must 

be acknowledged that even a small change in the energy distribution of beta emitters in the 

working environment, as compared to that used for calibration purposes, could affect the 

accuracy of the calibration factors, especially in the presence of additional shielding, such as the 

use of plastic bags to protect the dosimeters from dust. Variability in the energy distribution of 

beta emitters at Fernald could be of concern because of the presence of Tc-99 at the facility. 

Since the dosimeters were calibrated with uranium, the question that needs to be addressed is to 

what degree the presence of Tc-99 could substantively affect calibration factors based on 

uranium and the recorded beta doses. 

The maximum beta energy for Tc-99 is 0.29 MeV, while the maximum energy of the principal 

beta emitters associated with U-238 are its short-lived progeny; i.e., Pa-234m (max beta = 

2.26 MeV) and Th-238 (max beta = 0.199 MeV). The implications are that a dosimeter 

calibrated for beta exposure using U-238 (with baggie) will be virtually useless for monitoring 
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beta exposures to Tc-99, because most of the Tc-99 betas would be shielded by the baggie. 

However, since the amount of Tc-99 present in RU is minute,3the issue of the presence of the 

baggie affecting the calibration factor is of marginal significance. On this basis, we conclude 

that the film badge and/or TLD results for non-penetrating exposure can be used to reconstruct 

skin exposures at Fernald, as long as the Tc-99 was not separated from the RU and had a specific 

activity in RU that was on the order of 1,346 ppb.

4

 Table 5-9 in the site profile (ORAUT-TKBS00175-5, 5/28/204) indicates that the RU subgroup with the highest level of Tc-99 was subgroup 

6B with a relative concentration of 8,934 ppb (“bootstrap” mean).5Though higher than the 

overall average of 1,346 ppb, such a relative concentration of Tc-99 in RU would still not 

contribute significantly to the external beta dose as compared to U-238 and its short-lived 

progeny, primarily Pa-234m. 

Though we found that none of the RU groups could represent an important source of beta 

exposure from Tc-99 as compared to that from U-238 and its short-lived progeny, we 

investigated whether there might be some processes that enriched various waste streams in Tc-99 

relative to U-238. As stated in SC&A 2011, hydrofluorination (which occurred in Plant 4) could 

increase the airborne technetium concentration: 

[Hydrofluorination] reacted uranium dioxide powder with HF to produce a UF4

powder. The process is not believed to have permitted separation of constituents 

because, regardless of chemical reaction, the powders were mechanically or 

pneumatically moved through the solid-gas reaction processes from start to 

finish. The exception to this presumption is the situational data that suggest that 

the Tc-99 constituent tended to volatilize in high temperature processes, such as 

hydrofluorination, and would tend to collect on dust collector residues and 

media (DOE 2000, page D.1-72 and D.1-73, emphasis added). 

However, the Plant 4 dust collector samples reported in Fernald 1987 (Tables 58 through 65; see 

Table II-4) show that none of these samples has a Tc-99 specific activity greater than the 

8,934 ppb in RU subgroup 6B. Hence, this source of waste material enriched in Tc-99 is not an 

important contributor to external beta dose as compared to that of U-238 and its progeny. 

 

3

 Section 5.2.2 (Table 5-10) of ORAUT-TKBS-00175-5 states that typical RU contained 1,346 ppb of 

Tc-99. Since the half-life of Tc-99 is 2.1E5 years and that of U-238 is 4.4E9 years, the contribution of Tc-99 

external beta exposures relative to that of Pa-234m is small; i.e. on a per unit mass basis for RU, the beta flux from 

Pa-234m is about 15 times greater than that from Tc-99 in RU, and the energy of the Pa-234m beta distribution is 

about 10 times greater than that of the Tc-99 beta distribution based on Emax. 

4

 During the ongoing Fernald WG discussions, the agreed upon default 95th percentile levels of RU post1970 are 20,000 ppb. However, at the time this DR was performed, the TBD had not been changed to reflect the 

increased value. 

5

The values reported in Table 5-9 of the site profile are referred to (by DOE) as “bootstrap means” of the 

19 subgroup data distributions. The bootstrap mean is similar to a standard arithmetic mean (AM), but the technique 

is designed to minimize the influence of “outliers” in a dataset.
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Table II-4. Tc-99 Content in Dust Samples 

Sample Tc-99 μCi/kg-U Tc-99/U-238 Tc-99 ppb

G4-2 82 24.6% 4,791

G4-4 52 15.6% 3,038

G4-5 97 29.1% 5,668

G4-7 110 33.0% 6,427

G4-12 2.1 0.6% 123

G4-13 93 27.9% 5,434

G4-14 0.046 0.0% 2.7

G4-15 53 15.9% 3,097

Given the importance of external beta exposure to this particular worker’s DR, we investigated 

this issue further and found that purifying the uranium will result in some products and waste 

streams that have a lower concentration (relative to uranium) of impurities (including 

technetium) than the feed material, and some that have a higher concentration of impurities. 

Thus, depending on the type of material being handled (either feed material, product, or waste), a 

worker could be exposed to technetium concentrations that were consistent with, lower than, or 

higher than the concentration in RU. 

Uranium purification occurred in Plant 2/3, according to ORAUT-TKBS-0017-2, Section 2.2.3, 

and DOE 2000, Figure D-1 and Attachment D.1, Section 2.0. The raffinate from Plant 2/3 

(depleted of uranium, but enhanced in technetium) was transferred to Waste Pits 3 or 5. 

Table II-5 shows the increase in the Tc-99 to U-238 ratio in Waste Pits 3 and 5 materials 

compared to enriched RU. As shown, there is about twice as much Tc-99 in Waste Pit 9 and 8 

times higher concentrations in Waste Pit 5 as compared to enriched uranium. 

Table II-5. Tc-99 Content in Waste Streams 

FEMP Area TBD 

Source U-238 Tc-99 Units Tc-99/ U-238 Const. Closed Waste Type

Waste Pit 1 Table 2-26 1,950.6 3.6 (pCi/g) 0.2% 1952 1959 Dry

Waste Pit 6 Table 2-40 16,975. 127. (pCi/g) 0.7% 1979 1985 Solids

Waste Pit 4 Table 2-34 4,644. 80.45 (pCi/g) 1.7% 1960 1985 Solids

Waste Pit 2 Table 2-28 4,725.4 128.9 (pCi/g) 2.7% 1957 1964 Dry

Clearwell Table 2-42 621.5 98.85 (pCi/g) 15.9% 1959 1970 Runoff

Burn Pit Table 2-43 175.33 29.21 (pCi/g) 16.7% 1957 1984 Combust.

Depleted Uranium Table 2-49 12.46 3.13 (Bq/mg) 25.1% N.A. N.A. N.A.

Natural Uranium Table 2-49 12.35 3.13 (Bq/mg) 25.3% N.A. N.A. N.A.

2% Enrich Uranium Table 2-49 12.3 3.13 (Bq/mg) 25.4% N.A. N.A. N.A.

Waste Pit 3 Table 2-31 442. 233.4 (pCi/g) 52.8% 1958 1969 Slurries

Waste Pit 5 Table 2-37 641.17 1,274.5 (pCi/g) 198.8% 1968 1987 Slurries

The waste stream with the highest concentration of Tc-99 relative to U-238 is that in Waste Pit 5, 

where the activity ratio of Tc-99 to U-238 is a factor of 2, which would appear to be important. 

However, from Federal Guidance Report (FGR) 13 (EPA 1999), the mortality (and morbidity) 

risk factor to the skin from submersion in Tc-99 (2.01E-19, 2.01E-19 Bq-1) is only about 5% of 

the submersion risk factor for Pa-234m (4.03E-18, 4.03E-18 Bq-1). Thus, for enriched uranium 
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(with a Tc-99 to U-238 ratio of 25.4%), the Tc-99 contribution to the skin risk is about 1.25% of 

the Pa-234m risk. For Plant 4 (with a maximum Tc-99 to U-238 ratio of 33.0%), the Tc-99 

contribution to the skin risk is about 1.67% of the Pa-234m risk. For Waste Pit 5 (with a Tc-99 

to U-238 ratio of 198.8%), the Tc-99 contribution to the skin risk is about 10% of the Pa-234m 

risk. We conclude that external exposure of skin to Tc-99 relative to that of U-238 is not very 

significant (i.e., about 10%), even under worst-case conditions. Based on this EE’s work history, 

most of the EE’s time was spent in Plant [redacted], Plant [redacted], and the [redacted]. The 

EE does not appear to have spent significant time in areas with a higher technetium-to-uranium 

ratio (i.e., Plant [redacted] or Plant [redacted], or around Waste Pits [redacted]), although the 

EE may have been in these areas while the EE was working as a [redacted] (in Numerous 

Plants) or as an [redacted] (in about 80% of the buildings onsite) or in the [redacted]

(throughout the site). Thus, it is expected that Tc-99 would contribute less than 10% (and maybe 

only about 1.25%) to the EE’s skin cancer risk. 

II.3.2 RELIABILITY OF METHODS USED TO RECONSTRUCT NEUTRON 

EXPOSURES 

As indicated in Table II-3 above, no values are reported for neutron exposures for this worker. 

The reason might be because measurements were made but no exposures were detected, or 

measurements were not made. It is difficult to judge whether we are dealing with a missed dose 

or a situation where no attempt was made to measure neutron exposures. As best we can 

determine from reading the site profile, it appears that some attempt was made to at least detect 

the presence of neutron exposures. A discussion of this matter is provided in Section 6.3.5 of the 

site profile (ORAUT-TKBS-0017-6), where it states the following: 

The documentation for FEMP did not include any reference to neutron dosimetry 

with the exception of high-range, gamma-sensitive 1290 film. This film was 

packaged with the sensitive 508 film and exchanged on an annual basis. There 

was some concern expressed in AEC audit letters (Johnson and Heacker 1963) 

that mention “the badge also contains components to evaluate personnel 

exposure from criticality accidents” (an event that never occurred at Fernald). 

There was no established need for neutron dosimetry at FEMP even though there 

were large quantities of UF4 and UF6. Enrichments were low enough (typically 

<2% 235U) that alpha neutron reactions were limited. The limitations of NTA film 

were well documented including an MDL of approximately 40 mrem for fast 

neutrons. Based on studies and calculations it was concluded that fast neutron 

exposures at FEMP would be less than the MDL (Robinson 2001*). The purpose 

of the following section is to discuss and develop a neutron to photon ratio for 

estimating neutron doses at Fernald. A possible source of low level neutron 

exposure at Fernald is the alpha,n reaction from the uranium alpha particle 

interactions with fluorine atoms. This reaction primarily occurs with the 

production and storage of UF4 (green salt). The areas at Fernald which 

produced and/or stored green salt include the Pilot Plant, Plant 4, Warehouse 4B 

and any other warehouse at Fernald for which the material stored is unknown. 

The neutron to photon ratio described below should only be applied to workers 
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who were exposed to Uranium – Fluorine materials (i.e. UF4, UF6) at Fernald. 

* A reference for Robinson 2001 could not be found in ORAUT-TKBS-0017-6.

Beginning in Section 6.3.5.1, the site profile presents an approach to reconstructing neutron 

exposures using neutron-to-photon ratios. As explained in the site profile, neutron dose rates 

from UF4 canisters containing different levels of enrichment were measured using bubble 

dosimeters, and, in a separate set of measurements of different canisters, photon dose rates were 

determined. Bubble dosimeters consist of a small clear plastic cylindrical vial containing a clear 

polymer in which are dispersed tiny droplets of superheated liquid. When a neutron strikes a 

droplet, the droplet immediately vaporizes, forming a visible gas bubble trapped in the gel. The 

number of droplets provides a direct measurement of the tissue-equivalent neutron dose. It is 

useful because of its sensitivity and its nearly linear response over a wide range of neutron 

energies (see Reilly 1989).

Adjustments were made to the dataset to account for differences in geometry between the two 

sets of measurements for depleted and enriched uranium, and distributions of neutron-to-photon 

ratios were derived from the dataset, one for depleted uranium and one for enriched uranium. 

The results of the analysis are provided in Table II-6 as follows (from Table 6-10 of the site 

profile): 

Table II-6. Statistical Parameters of Neutron-to-Photon Ratios 

Enrichment Geometric 

Mean GSD Upper 95th%

Depleted Uranium 0.07 1.74 0.17

Low Enriched Uranium 0.10 1.71 0.23

 Source: ORAUT-TKBS-0017-6, Table 6-10

In addition to these neutron-to-photon ratios, Table 6-9 of the site profile presents the measured 

neutron dose rates adjacent to canisters containing UF4 enriched at 1.25% to 2%. Neutron 

exposure rates of 0.1069 mrem/hr were obtained using bubble dosimeters. 

The site profile explains that, though most uranium handled at Fernald was not enriched, it is 

difficult to determine what level of enriched uranium might have been handled by a given 

worker over a given time period, and recommends employing the low-enriched uranium ratio for 

employees who worked in the Pilot Plant, Plant 4, any warehouse or other area known to store 

UF4, or any of the onsite warehouses for which the stored material is not known. The site profile 

further recommends that the neutron energy distribution should be assumed to range from 0.1 to 

2.0 MeV. 

Given some of the limitations associated with the neutron-to-photon ratios, it might be prudent to 

evaluate doses to neutrons using both the neutron-to-photon ratio approach and also the direct 

measurements of the neutron dose rates in mrem/hr for slightly enriched uranium, and make 

assumptions regarding exposure duration for this worker. 

 
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Neutron-to-Photon Ratio Approach 

As discussed above, the recorded photon doses for this worker were primarily below the MDL, 

and from [redacted]–[redacted], the recommended MDL is 30 mrem/change out (which was 

monthly during that time). From [redacted] to the present, the recommended MDL is 20 mrem/ 

change out (which was quarterly during that time period). Using a neutron-to-photon ratio of 0.1 

and a photon dose rate of 15 mrem/month, the annual neutron dose to the skin for this worker 

using the neutron-to-photon ratio approach is 15 mrem/month × 0.1 × 12 months = 18 mrem/yr. 

Missed neutron doses are included in entries #84–#99 in Appendices II.A-1, II.A-2, II.A-3. 

Direct Neuron Measurements 

As described above, the measured neutron dose rate adjacent to canisters containing UF4

enriched at 1.25% to 2% was 0.1069 mrem/hr, as estimated using bubble dosimeters. Assuming 

a worker spent full time adjacent to such a source, the annual neutron exposure would be about 

200 mrem/yr. We consider this neutron dose to be an unrealistic upper bound value because it is 

unreasonable to assume that a worker spent all their time adjacent to such a neutron source. 

Hence, we believe that 18 mrem/yr calculated by the neutron-to-photon ratio approach, as 

described above, represents a reasonable, if not conservative, estimate of neutron exposure rate 

for this worker. 

II.3.3 SKIN EXPOSURES ASSOCIATED WITH DEPOSITION OF URANIUM 

DIRECTLY ON SKIN AND CLOTHING 

A skin exposure scenario that is of concern at Fernald is the direct deposition of airborne 

uranium dust on bare skin and clothing. This exposure scenario is not addressed in the Fernald 

site profile, but was raised as a generic issue at the May 21, 2013, meeting of the Dose 

Reconstruction Subcommittee. At that meeting, NIOSH introduced a strategy for reconstructing 

skin doses from this scenario for the Bridgeport Brass facility, as follows: 

An assessment was made to determine the skin dose from routine skin 

contamination associated with uranium operations. Based on the Technical Basis 

Document: An Exposure Matrix for Bridgeport Brass: Havens Laboratory and 

Adrian Plant (ORAUT-TKBS-0030 Rev. 01), the geometric mean of the Table 3-5 

individual daily weighted-average air concentration is 250 dpm/m3 with a 

geometric standard deviation of 2.2. This results in a 95th percentile air 

concentration of 915 dpm/m3. Assuming a terminal settling velocity of 

0.00075 m/s and 8 hours of operations, a constant air concentration of 

915 dpm/m3 would result in a surface contamination level of 1.98 dpm/cm2. One 

could assume that the skin of the head, neck, and hands were re-contaminated at 

the same level of general surfaces every workday (250 workdays) of the year. The 

skin on the head, neck, and hands represent about 14% of the total body skin 

area. A maximizing skin dose rate of 40 mrem per 10,000 dpm/cm2

per hour can 

be applied to determine the skin dose to the affected area (Technical Basis for 

Beta Skin Dose Calculations at the Y12 Plant, SRDB 19821) [Thomas and Bogard 

1994]. This would result in a dose to the affected skin of about 16 mrem. Per 
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guidance in Interpretation of Dosimetry Data For Assignment of Shallow Dose 

(ORAUT-OTIB-0017 Rev. 01), the 16 mrem to the affected skin could be 

converted to the dose to the skin based on the described approach for nonuniform exposures, resulting in a geometric mean annual skin dose of about 2 

mrem with a geometric standard deviation of 8. As a note, this is a bounding 

estimate using a maximizing skin dose rate and contamination levels. A more 

realistic skin dose rate and the use of the geometric mean air concentration would 

result in an exposure of less than 1 mrem. 

We agree with the basic strategy described by NIOSH, except that substantial skin exposure to 

beta emitters associated with uranium can also contribute significant exposure through clothing. 

NIOSH’s assumption that only bare skin (representing 14% of total skin in the above example) is 

subject to contamination/radiation exposure from the deposition of airborne activity is 

unrealistic. This is particularly true for work environments involving heavy physical activity, 

worker perspiration, and damp clothing. Thus, any deposition of airborne contaminants (as well 

as contact with existing contaminated surfaces in the workplace) by clothing worn by a worker 

must reasonably be assumed to become contaminated, and that, at a minimum, the level of 

contamination is comparable to that of bare skin. In Section 6.3.4.2 of Feed Materials 

Production Center site profile (ORAUT-TKBS-0017-6), NIOSH provides the following guidance 

for determining the skin dose under clothing from exposure to uranium: 

Results of tests of FEMP dosimeters used during the 1960s (Heatherton 1960) 

included the conclusion that the half-value thickness of absorption of UX-2 

(

234Pa) beta energy was approximately 110 mg/cm2

. It was determined that “the 

combined dose rate from the surface of uranium metal in equilibrium with its two 

daughters, UX-1 (234Th) and UX-2 (234Pa), is about 240 mrad/hr.” It was also 

determined that approximately 95% of the surface dose rate, or approximately 

228 mrad/hr, originated from the UX-2 in the metal . . . It was also determined 

that coveralls worn by workers (about 30 mg/cm2

) reduced uranium beta 

exposure to the skin by approximately 20%. Figure 6-6, at the end of this TBD, 

summarizes these data. [Emphasis added.] 

Figure II-1. Beta Dose vs. Skin Depth 

(Source: ORAUT-TKBS-0017-6, Figure 6-6) 
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On this basis and given that the worker spent extended periods of time in Plant [redacted], 

where [redacted], it is reasonable to assume that the EE experienced some degree of skin 

exposure due to the direct deposition of uranium oxide dust on skin and clothing. As such, we 

consider it appropriate to assign a skin dose from this exposure scenario using appropriate 

airborne uranium dust loadings as our starting point.

SC&A explored two strategies for estimating the typical airborne dust loading this worker might 

have experienced while working in Plant [redacted]. The first was to review the information in 

Section 5.3.2 of the site profile (ORAUT-TKBS-0017-5) titled, “Air Monitoring Program.” The 

other is to back-calculate the airborne dust loadings that this worker might have experienced 

based on the EE’s bioassay data. 

Inspection of the bioassay data for this worker, as provided by the DOE, reveals that urine 

samples were collected quarterly throughout employment at Fernald, and more often when 

elevated levels of uranium were observed. All the data are reported in units of microgram/L and 

range from below the MDL (which appears to be as high as 14 micrograms/L) to a high of 

18 microgram/L. The vast majority of the results were below the MDL. We elected to perform a 

plausible but perhaps overestimate of the airborne dust loading by assuming an average urine 

concentration of 7 μg/L (i.e., 1⁄2 the MDL) and used this value to estimate the chronic intake rate 

of Type S uranium that would result in this concentration of uranium in urine. Assuming the 

uranium is 2% enriched, we converted the mass concentration to activity concentration using a 

unit conversion factor of 1.616 pCi/microgram of uranium, yielding an average uranium 

concentration in urine of 11.3 pCi/L and an excretion rate of 15.82 pCi/day. 

Using this chronic uranium excretion rate, IMBA was run to derive the uranium intake rate that 

would yield this excretion rate assuming Type S uranium and that the excretion rate followed a 

normal distribution with a 30% standard deviation. The result of this calculation is a uranium 

inhalation rate of 3,173 pCi/day, which assumes the intake was 2% enriched uranium. The 

average airborne concentration of uranium that is associated with this intake rate is about 330 

pCi/m3. 

The annual skin dose associated with the direct deposition of airborne uranium onto skin and 

clothing is estimated as follows: 

Daily Skin Contamination = (330 pCi/m3)(0.00075 m/s)(3,600 sec/hr)(8 hr/day) = 

7,095 pCi/m2

after 8 hours of exposure 

Unit Conversion = (7,095 pCi/m2)(1 GA/27 pCi) (1dis/sec-Bq))(60 sec/min) = 

16,765 dpm/m2= 1.57 dpm/cm 

 

Skin Dose Rate = (1.57 dpm/cm2)(40 mrem/hr cm2/10,000 dpm)

6

 = 6.28E-3 mrem/hr 

Yearly Skin Dose = (6.28E-3 mrem/h)(8 h/d)(250 d/yr) = 12.57 mrem/yr 

 

6

 SC&A independently checked this DCF and confirmed that it is reasonable. See Attachment 1. 
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This annual exposure rate is directly proportional to the assumed average uranium concentration 

in urine. It is also important to acknowledge that this model assumes all the uranium deposited 

on skin and clothing during the course of a work day is completely removed at the end of the day 

after showering, and any uranium on clothing is removed during daily laundering. Both these 

assumptions would tend to reduce the annual exposure. Hence, we believe this annual dose is a 

plausible estimate of the exposures, and could be 10 times higher. The skin deposition dose of 

12.57 mrem is assigned for each year of employment, as cited in entries #100–#115 of 

Appendices II.A-1, II.A-2, and II.A-3. 

It is also possible that the worker experienced exposures to large flakes of uranium falling 

directly onto the EE’s skin and clothing. This topic was discussed at length during the July 18, 

2013, meeting of the Procedures Review Subcommittee. There appears to be general agreement 

that a skin exposure scenario involving the deposition of fine dust particles onto skin is plausible, 

but not large flakes; at least they would not be present for extended periods of time if they 

occurred. Hence, we ruled out this scenario. However, if such a scenario were to occur, the 

exposure rate to the skin directly under the flake would approach 240 mrem/hr. 

II.4 INTERNAL DOSE 

Based on a review of the EE’s bioassay data, it appears that the EE was on a quarterly uranium 

bioassay program from [redacted] to [redacted]. The urinalyses results ranged from 0 to 

18 μg/L, with most of the results being close to or below the MDL of 14 μg/L. Therefore, it was 

assumed that the EE’s chronic uranium intake rate during employment resulted in a urine 

concentration of 7 μg/L or an excretion rate of 9.8 μg/day. Assuming that all the uranium was 

2% enriched (i.e., 1.616 pCi/μg), the EE’s chronic uranium excretion rate can be assumed to be 

15.82 pCi/day. Based on this excretion rate, which was entered into IMBA as an annual value 

with a data type of ‘real,’ the chronic uranium intake rate would be 267 pCi/day Type M or 

3,173 pCi/day Type S uranium. 

SC&A’s DR–Method B acknowledges that, by assuming a chronic annual intake at the level of 

1⁄2 MDA for [redacted] years, one should see a buildup of uranium in the body. Therefore, we 

generated a plot showing the uranium concentration in urine (μg/L) as a function of time for a 

worker that chronically inhaled 3,173 pCi/day of 2% enriched Type S uranium from [redacted] 

to [redacted], as shown in Figure II-2 below. 
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Figure II-2. Concentration in Urine (μg/L) for Chronic Inhalation of 3,173 pCi/day of 2% 

enriched Type S Uranium 

For an additional comparison, Method B ran IMBA assuming 15.82 pCi/day with a data type of 

‘real’ on the last day of the EE’s employment and back calculated an intake of 2,656 pCi/d. 

Although this approach resulted in a lower intake value, this comparison indicated that our initial 

assumptions were reasonable. Therefore, Method B calculated internal doses assuming the 

claimant-favorable inhalation intake of 3,173 pCi/d of Type S uranium. This resulted in a total 

internal dose of approximately 300 mrem from the time of employment to the date of diagnosis. 

The annual internal doses to the skin are cited in entries #116–#142 of Appendix II.A-1, entries 

#116–#143 of Appendix II.A-2, and entries #116–#146 of Appendix II.A-3.

DR–Method B also investigated the potential exposures to skin from inadvertent ingestion and 

the intake of RU and found the exposures to be negligible. 

II.4.1 DR ASSUMPTIONS 

Table II-7 below presents the external DR parameters used in our assessment for each year and 

work location. 

Table II-7. External DR Parameters for Case #[redacted]

Facility wide, D&D ([redacted], [redacted]–[redacted])

Photons Electrons

30–250 keV >250 keV >15 keV

Energy fraction 40% 60% 100%

DCF 1 1 1

Attenuation factor

(for SCC on chest only) NA NA 0.855
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Table II-7. External DR Parameters for Case #[redacted]

Plant 6 ([redacted]–[redacted])

Photons Electrons

<30 keV 30–250 

keV

>250 

keV >15 keV

Energy fraction 13% 33% 54%

DCF 1 1 1 1

Attenuation factor

(for SCC on chest only) NA NA NA 0.855

Table II-8 presents details on each skin cancer documented in the DOL files and the associated 

dose assigned by SC&A in the DR. Table II-9 presents a breakdown of each type of assigned 

dose for each skin cancer location. Appendices II.A-1 and II.A-2 list the IREP input values used 

to calculate the POC for this DR. Note the majority of the assigned dose is attributed to recorded 

shallow dose. 

Table II-8. Skin Cancers and Total Assigned Doses 

Cancer Type Location Diagnosis 

Date ICD Code

Calculated dose to the skin 

(rem)

Unattenuated Attenuated

Squamous cell carcinoma [redacted] [redacted] [redacted] NA 16.6

Basal cell carcinoma [redacted] [redacted] [redacted] 18.9 NA

Basal cell carcinoma [redacted] [redacted] [redacted] 18.9 NA

Squamous cell carcinoma [redacted] [redacted] [redacted] 18.9 NA

Squamous cell carcinoma [redacted] [redacted] [redacted] 18.9 NA

Table II-9. External Doses Calculated by SC&A (rem) 

Appendix II.A-2 and II.A-3 Skin Dose

Bare Skin (rem)

Appendix II.A-1 Skin Dose

Attenuated due to Clothing (rem)

Recorded photon dose 1.6 1.6

Recorded shallow dose 15.5 13.3

Missed photon dose 0.9 0.9

X-ray 0.13 0.13

Missed neutron dose 0.288 0.288

Skin deposition 0.201 0.201

Total 18.64 16.40

II.4.1.1 Recorded Photon Doses 

The values in the deep dose equivalent (DDE) column are the deep dose values recorded by the 

personnel dosimeter. The recorded photon doses are divided into the energy fractions 

appropriate for each plant location described in Table 6-8 of ORAUT-TKBS-0017-6. In cases 

involving skin cancers, the claimant-favorable assumption is a DCF of 1.0 for all recorded and 

missed external doses, as per the procedures in ORAUT-OTIB-0017. An example of SC&A’s 

calculation of recorded photon dose for [redacted] is provided below. 

In [redacted], the EE received a recorded DDE dose of 0.173 rem. Since the EE was working in 

Plant [redacted] at the time, the recorded photon dose is divided into photon energy fractions of 
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<30 keV, 30–250 keV, and >250 keV. As was previously mentioned, a DCF of 1.0 is used for 

cancers involving the skin. 

Calculated skin dose (<30 keV) = 0.173*1*0.13 = 0.022 rem 

Calculated skin dose (30–250 keV) = 0.173*1*0.33 = 0.057 rem 

Calculated skin dose (>250 keV) = 0.173*1*0.54 = 0.093 rem 

Using the procedures in OCAS-IG-001, these doses are assumed to have a normal distribution 

with a 30% standard deviation. The recorded photon doses are listed in entries #1 through #36 of 

Appendices II.A-1 and II.A-2 and a total 1.6 rem for each of the cancer sites. 

II.4.1.2 Recorded Shallow Dose 

The values in the shallow dose equivalent (SDE) column are all of the doses recorded by the 

OW, which includes both penetrating and non-penetrating (gamma plus beta) doses. The 

shallow beta dose is separated out by subtracting the DDE from the SDE values. All of the 

recorded shallow doses are assumed to be >15 keV electrons, as per the procedures in Table 6-8 

of ORAUT-TKBS-0017-6, and a DCF is 1.0 is used. An example of SC&A’s calculation of 

recorded photon dose for [redacted] is provided below. 

In [redacted], the EE received a recorded non-penetrating dose of 2.7 rem. Since the DCF is 1.0 

and there are no other multipliers for the cancers located on the [redacted] and [redacted], the 

assigned dose for that year is 2.7 rem. For the cancer located on the [redacted], the beta dose is 

assumed to be attenuated by clothing and coveralls. The clothing attenuation procedures for 

shallow dose are described on page 7 of ORAUT-OTIB-0017:

For likely non-compensable cases, an acceptable claimant-favorable approach is 

to assume 100% transmission (i.e., ignore attenuation). For likely compensable 

cases, an acceptable minimizing approach is to assume a transmission of 0.6 

(unless there is evidence a face shield was used and the skin cancer was on the 

face, in which case 0.41 would be appropriate). For cases in which a best 

estimate is applied and the specific type of protective clothing is unknown, a 

factor of 0.855 for uranium is appropriate (equal to the average of the 0.80 and 

0.91 factors listed above). 

SC&A chose the best-estimate attenuation factor of 0.855 and applied it to the recorded shallow 

dose. For [redacted], the assigned shallow dose to the skin of the [redacted] is 2.32 rem. Using 

the procedures in OCAS-IG-001, the shallow doses are assumed to have a normal distribution 

with a 30% standard deviation. The recorded photon doses are listed in entries #37 through #47 

of Appendices II.A-1 and II.A-2 and a total 15.5 rem to the skin on the [redacted] and 

[redacted] and 13.3 rem to the skin on the [redacted]. The recorded shallow dose represents the 

majority of the total assigned dose. 
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II.4.1.3 Missed Photon Dose 

SC&A assigned missed dose to the skin by multiplying the number of zero readings per year by 

one-half the limit of detection (LOD). SC&A reviewed the external dosimetry data in detail and 

assessed each monthly recorded value. Each reading that is below the LOD/2 is considered a 

zero reading. The procedures on page 21 of ORAUT-OTIB-0017 are used to assess the missed 

dose. These procedures are specific for Savannah River and Hanford, but they seemed 

appropriate and claimant favorable for Fernald as well. 

For any badge cycle with a zero result in either the OW or S reading, or both, 

assign a single missed dose as explained in Items 7-9 below. 

If only the OW reading was reported as zero, the missed dose assigned should be 

the appropriate OW LOD for that era (divided by 2, treated as lognormal) and 

considered electrons (corrected for attenuation, if applicable) or low-energy 

photons (multiplied by 0.6 in the film badge era, if applicable) consistent with the 

approach taken in Step 2. 

If only the S reading was reported as zero, the missed dose assigned should be the 

appropriate S LOD for that era (divided by 2, treated as lognormal) and 

considered 30-250 keV photons. 

If both the OW and S readings were reported as zero, the missed dose assigned 

should be the appropriate OW LOD for that era (divided by 2, treated as 

lognormal) and considered 30-250 keV photons. 

After reviewing the monthly exchange data, SC&A found that all of the zero and below the 

LOD/2 readings were penetrating deep dose values. Therefore, all of the missed dose is assigned 

as photons. An example of SC&A’s calculation of recorded photon dose for [redacted] is 

provided below. 

In [redacted], the EE received 6 zero readings and the LOD/2 is 15 mrem. Since the EE was 

working in Plant [redacted] at the time, the recorded photon dose is divided into photon energy 

fractions of <30 keV, 30–250 keV, and >250 keV. As was previously mentioned, the DCF of 

1.0 is used for cancers involving the skin.

Calculated missed skin dose (<30 keV) = 6 zeroes*0.015*1*0.13 = 0.012 rem 

Calculated missed skin dose (30–250 keV) = 6 zeroes*0.015*1*0.33 = 0.030 rem 

Calculated missed skin dose (>250 keV) = 6 zeroes*0.015*1*0.54 = 0.049 rem 

Using the procedures in OCAS-IG-001, these doses are assumed to have a lognormal distribution 

with a geometric standard deviation of 1.52. The missed photon doses are listed in entries #48 

through #77 of Appendices II.A-1 and II.A-2, and a total 0.904 rem for each of the cancer sites. 
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II.4.1.4 Occupational Medical Dose 

SC&A assigned occupational medical dose for each documented x-ray examination in the DOE 

records. The EE had conventional chest x-rays performed in [redacted], [redacted], [redacted], 

[redacted], [redacted] and [redacted]. The x-ray doses to the skin were assigned using the 

values in Tables 3-14 through 3-16 of ORAUT-TKBS-0017-3. Using the procedures in 

ORAUT-TKBS-0017-3, these doses are assumed to be 30–250 keV photons and have a normal 

distribution with a 30% standard deviation. The occupational medical doses are listed in entries 

#78 through #83 of Appendices II.A-1 and II.A-2 and a total 0.131 rem for each of the cancer 

sites. 

II.4.1.5 Calculation of POC 

The IREP input values of Appendix II.A-1 and Appendix II.A-2 were imported into the IREP 

program available on the DCAS website. Since there are multiple primary cancer sites for this 

case, the multiple case site portion of the IREP program was used in order to determine the total 

POC for this DR. The POC is determined to be 39.33%, which would not make this claim 

eligible for compensation. Table II-10 presents the calculated POC for each skin cancer site. 

Table II-10. Calculated POC for Skin Cancers for Case #[redacted]

Skin Cancer POC

SCC [redacted] 4.58%

BCC [redacted] 16.51%

BCC [redacted] 15.73%

SCC [redacted] 4.94%

SCC [redacted] 4.94%

Total 39.33%

II.5 REFERENCES

DOE (U.S. Department of Energy), 2000. Recycled Uranium Project Report, Final Report, Ohio 

Field Office, Fernald Environmental Management Project, Fernald Ohio. 

EPA 1999. U.S. Environmental Protection Agency, “Cancer Risk Coefficients for 

Environmental Exposure to Radionuclides,” 402-R-99-001, September 1999. 

Fernald 1987. History of FMPC Radionuclide Discharges, FMPC-2082, M.W. Boback, T.A., 

Dugan, D.A., Fleming, R.B., Grant, and R.W. Keys, May 1987. 

Heatherton, R.C., 1960. Estimation of Depth Dose from UX2 Beta Rays. 

Johnson, W.A. and H.V. Heacker, 1963. Health Protection Review of National Lead Co. of Ohio 

Letter Report, Atomic Energy Commission, Bethesda, Maryland. 
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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

OCAS-IG-001. 2007. External Dose Reconstruction Implementation Guideline, Rev. 3, 

National Institute for Occupational Safety and Health, Office of Compensation Analysis and 

Support, Cincinnati, Ohio. November 21, 2007. 

ORAUT-TKBS-0012-6. 2007. Oak Ridge National Laboratory – Occupational External Dose, 

Rev. 1, Oak Ridge Associated Universities Team, Cincinnati, Ohio. September 10, 2007. 

ORAUT-OTIB-0017. 2005. Technical Information Bulletin: Interpretation of Dosimetry Data 

for Assignment of Shallow Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. October 11, 2005. 

ORAUT-TKBS-0017-2, 2004. Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Site Description, Rev. 00, Oak Ridge Associated Universities 

Team, Cincinnati, Ohio. May 20, 2004. 

ORAUT-TKBS-0017-3, 2004. Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Occupational Medical Dose, Rev. 00, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. February 11, 2004. 

ORAUT-TKBS-0017-5. 2004. Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Occupational Internal Dose, Rev. 00, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. May 28, 2004. 

ORAUT-TKBS-0017-6, 2004. Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Occupational External Dose, Rev. 00, Oak Ridge Associated 

Universities Team, Cincinnati, Ohio. April 20, 2004. 

ORAUT-TKBS-0030. 2013. An Exposure Matrix for Bridgeport Brass: Havens Laboratory and 

Adrian Plant, Rev. 01. Oak Ridge Associated Universities Team, Cincinnati, Ohio. January 24, 

2013.

Reilly, E.J., 1989. “A Trident Scholar Project Report No. 159, Evaluation of Bubble Dosimeter 

Response to Neutron Radiation,” United States Naval Academy, USNA-TSPR; No. 150. 

SC&A 2011. “SC&A Review of Issues Related to Reconstruction of Doses for Workers 

Exposed to Recycled Uranium at Fernald – A Second White Paper, Sanford Cohen and 

Associates, Inc., April 2011. 

Thomas, J.M., and R.S. Bogard, 1994. Technical Basis for Beta Skin Dose Calculations at the Y12 Plant, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. March 1994. (SRDB 19821)
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APPENDIX II.A-1: IREP INPUT – [REDACTED] SCC ON THE 

[REDACTED]

Exposure 

year

Radiation Type Exposure 

rate Distribution Parameter 1 Parameter 2

1 [redact] <30 keV photons acute normal 0.022 0.007

2 [redact] <30 keV photons acute normal 0.038 0.011

3 [redact] <30 keV photons acute normal 0.021 0.006

4 [redact] <30 keV photons acute normal 0.018 0.005

5 [redact] <30 keV photons acute normal 0.052 0.016

6 [redact] <30 keV photons acute normal 0.024 0.007

7 [redact] 30–250 keV photons acute normal 0.002 0.001

8 [redact] 30–250 keV photons acute normal 0.057 0.017

9 [redact] 30–250 keV photons acute normal 0.095 0.029

10 [redact] 30–250 keV photons acute normal 0.054 0.016

11 [redact] 30–250 keV photons acute normal 0.047 0.014

12 [redact] 30–250 keV photons acute normal 0.133 0.040

13 [redact] 30–250 keV photons acute normal 0.060 0.018

14 [redact] 30–250 keV photons acute normal 0.020 0.006

15 [redact] 30–250 keV photons acute normal 0.011 0.003

16 [redact] 30–250 keV photons acute normal 0.016 0.005

17 [redact] 30–250 keV photons acute normal 0.015 0.004

18 [redact] 30–250 keV photons acute normal 0.014 0.004

19 [redact] 30–250 keV photons acute normal 0.011 0.003

20 [redact] 30–250 keV photons acute normal 0.004 0.001

21 [redact] 30–250 keV photons acute normal 0.006 0.002

22 [redact] >250 keV photons acute normal 0.003 0.001

23 [redact] >250 keV photons acute normal 0.093 0.028

24 [redact] >250 keV photons acute normal 0.156 0.047

25 [redact] >250 keV photons acute normal 0.088 0.026

26 [redact] >250 keV photons acute normal 0.076 0.023

27 [redact] >250 keV photons acute normal 0.217 0.065

28 [redact] >250 keV photons acute normal 0.098 0.029

29 [redact] >250 keV photons acute normal 0.030 0.009

30 [redact] >250 keV photons acute normal 0.016 0.005

31 [redact] >250 keV photons acute normal 0.023 0.007

32 [redact] >250 keV photons acute normal 0.022 0.007

33 [redact] >250 keV photons acute normal 0.022 0.006

34 [redact] >250 keV photons acute normal 0.016 0.005

35 [redact] >250 keV photons acute normal 0.007 0.002

36 [redact] >250 keV photons acute normal 0.010 0.003

37 [redact] <15 keV electrons acute normal 0.04 0.012

38 [redact] <15 keV electrons acute normal 2.32 0.696

39 [redact] <15 keV electrons acute normal 2.85 0.856

40 [redact] <15 keV electrons acute normal 1.60 0.481

41 [redact] >15 keV electrons acute normal 1.76 0.529

42 [redact] >15 keV electrons acute normal 3.51 1.054

43 [redact] >15 keV electrons acute normal 0.62 0.185

44 [redact] >15 keV electrons acute normal 0.28 0.084
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Appendix II.A-1: IREP Input – [Redacted] SCC on the [Redacted] (continued)

45 [redact] >15 keV electrons acute normal 0.009 0.003

46 [redact] >15 keV electrons acute normal 0.230 0.069

47 [redact] >15 keV electrons acute normal 0.046 0.014

48 [redact] <30 keV photons acute lognormal 0.012 1.52

49 [redact] <30 keV photons acute lognormal 0.004 1.52

50 [redact] <30 keV photons acute lognormal 0.003 1.52

51 [redact] <30 keV photons acute lognormal 0.005 1.52

52 [redact] 30–250 keV photons acute lognormal 0.018 1.52

53 [redact] 30–250 keV photons acute lognormal 0.030 1.52

54 [redact] 30–250 keV photons acute lognormal 0.099 1.52

55 [redact] 30–250 keV photons acute lognormal 0.007 1.52

56 [redact] 30–250 keV photons acute lognormal 0.013 1.52

57 [redact] 30–250 keV photons acute lognormal 0.040 1.52

58 [redact] 30–250 keV photons acute lognormal 0.044 1.52

59 [redact] 30–250 keV photons acute lognormal 0.048 1.52

60 [redact] 30–250 keV photons acute lognormal 0.008 1.52

61 [redact] 30–250 keV photons acute lognormal 0.008 1.52

62 [redact] 30–250 keV photons acute lognormal 0.008 1.52

63 [redact] 30–250 keV photons acute lognormal 0.016 1.52

64 [redact] 30–250 keV photons acute lognormal 0.064 1.52

65 [redact] >250 keV photons acute lognormal 0.027 1.52

66 [redact] >250 keV photons acute lognormal 0.049 1.52

67 [redact] >250 keV photons acute lognormal 0.016 1.52

68 [redact] >250 keV photons acute lognormal 0.011 1.52

69 [redact] >250 keV photons acute lognormal 0.022 1.52

70 [redact] >250 keV photons acute lognormal 0.060 1.52

71 [redact] >250 keV photons acute lognormal 0.066 1.52

72 [redact] >250 keV photons acute lognormal 0.072 1.52

73 [redact] >250 keV photons acute lognormal 0.012 1.52

74 [redact] >250 keV photons acute lognormal 0.012 1.52

75 [redact] >250 keV photons acute lognormal 0.012 1.52

76 [redact] >250 keV photons acute lognormal 0.024 1.52

77 [redact] >250 keV photons acute lognormal 0.096 1.52

78 [redact] 30–250 keV photons acute normal 0.024 0.0071

79 [redact] 30–250 keV photons acute normal 0.024 0.0071

80 [redact] 30–250 keV photons acute normal 0.024 0.0071

81 [redact] 30–250 keV photons acute normal 0.017 0.0051

82 [redact] 30–250 keV photons acute normal 0.021 0.0064

83 [redact] 30–250 keV photons acute normal 0.021 0.0064

84 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

85 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

86 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

87 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

88 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

89 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

65 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-1: IREP Input – [Redacted] SCC on the [Redacted] (continued)

90 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

91 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

92 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

93 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

94 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

95 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

96 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

97 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

98 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

99 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

100 [redact] >15 keV electrons acute normal 0.013 0.0038

101 [redact] >15 keV electrons acute normal 0.013 0.0038

102 [redact] >15 keV electrons acute normal 0.013 0.0038

103 [redact] >15 keV electrons acute normal 0.013 0.0038

104 [redact] >15 keV electrons acute normal 0.013 0.0038

105 [redact] >15 keV electrons acute normal 0.013 0.0038

106 [redact] >15 keV electrons acute normal 0.013 0.0038

107 [redact] >15 keV electrons acute normal 0.013 0.0038

108 [redact] >15 keV electrons acute normal 0.013 0.0038

109 [redact] >15 keV electrons acute normal 0.013 0.0038

110 [redact] >15 keV electrons acute normal 0.013 0.0038

111 [redact] >15 keV electrons acute normal 0.013 0.0038

112 [redact] >15 keV electrons acute normal 0.013 0.0038

113 [redact] >15 keV electrons acute normal 0.013 0.0038

114 [redact] >15 keV electrons acute normal 0.013 0.0038

115 [redact] >15 keV electrons acute normal 0.013 0.0038

116 [redact] alpha chronic normal 5.69E-05 0.0000

117 [redact] alpha chronic normal 7.95E-04 0.0002

118 [redact] alpha chronic normal 1.51E-03 0.0005

119 [redact] alpha chronic normal 2.26E-03 0.0007

120 [redact] alpha chronic normal 3.05E-03 0.0009

121 [redact] alpha chronic normal 3.87E-03 0.0012

122 [redact] alpha chronic normal 4.73E-03 0.0014

123 [redact] alpha chronic normal 5.58E-03 0.0017

124 [redact] alpha chronic normal 6.46E-03 0.0019

125 [redact] alpha chronic normal 7.36E-03 0.0022

126 [redact] alpha chronic normal 8.29E-03 0.0025

127 [redact] alpha chronic normal 9.19E-03 0.0028

128 [redact] alpha chronic normal 1.01E-02 0.0030

129 [redact] alpha chronic normal 1.11E-02 0.0033

130 [redact] alpha chronic normal 1.20E-02 0.0036

131 [redact] alpha chronic normal 1.26E-02 0.0038

132 [redact] alpha chronic normal 1.27E-02 0.0038

133 [redact] alpha chronic normal 1.30E-02 0.0039

134 [redact] alpha chronic normal 1.32E-02 0.0040
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

66 of 75

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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-1: IREP Input – [Redacted] SCC on the [Redacted] (continued)

135 [redact] alpha chronic normal 1.33E-02 0.0040

136 [redact] alpha chronic normal 1.34E-02 0.0040

137 [redact] alpha chronic normal 1.35E-02 0.0041

138 [redact] alpha chronic normal 1.37E-02 0.0041

139 [redact] alpha chronic normal 1.37E-02 0.0041

140 [redact] alpha chronic normal 1.38E-02 0.0041

141 [redact] alpha chronic normal 1.39E-02 0.0042

142 [redact] alpha chronic normal 5.44E-03 0.0016
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

67 of 75

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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX II.A-2: IREP INPUT – [REDACTED] BCC ON THE 

[REDACTED]

Exposure 

year

Radiation Type

Exposure 

rate Distribution Parameter 1 Parameter 2

1 [redact] <30 keV photons acute normal 0.0225 0.007

2 [redact] <30 keV photons acute normal 0.0376 0.011

3 [redact] <30 keV photons acute normal 0.0212 0.006

4 [redact] <30 keV photons acute normal 0.0183 0.005

5 [redact] <30 keV photons acute normal 0.0523 0.016

6 [redact] <30 keV photons acute normal 0.0235 0.007

7 [redact] 30–250 keV photons acute normal 0.0020 0.001

8 [redact] 30–250 keV photons acute normal 0.0571 0.017

9 [redact] 30–250 keV photons acute normal 0.0954 0.029

10 [redact] 30–250 keV photons acute normal 0.0538 0.016

11 [redact] 30–250 keV photons acute normal 0.0465 0.014

12 [redact] 30–250 keV photons acute normal 0.1327 0.040

13 [redact] 30–250 keV photons acute normal 0.0597 0.018

14 [redact] 30–250 keV photons acute normal 0.0200 0.006

15 [redact] 30–250 keV photons acute normal 0.0108 0.003

16 [redact] 30–250 keV photons acute normal 0.0156 0.005

17 [redact] 30–250 keV photons acute normal 0.0148 0.004

18 [redact] 30–250 keV photons acute normal 0.0144 0.004

19 [redact] 30–250 keV photons acute normal 0.0108 0.003

20 [redact] 30–250 keV photons acute normal 0.0044 0.001

21 [redact] 30–250 keV photons acute normal 0.0064 0.002

22 [redact] >250 keV photons acute normal 0.0030 0.001

23 [redact] >250 keV photons acute normal 0.0934 0.028

24 [redact] >250 keV photons acute normal 0.1561 0.047

25 [redact] >250 keV photons acute normal 0.0880 0.026

26 [redact] >250 keV photons acute normal 0.0761 0.023

27 [redact] >250 keV photons acute normal 0.2171 0.065

28 [redact] >250 keV photons acute normal 0.0977 0.029

29 [redact] >250 keV photons acute normal 0.0300 0.009

30 [redact] >250 keV photons acute normal 0.0162 0.005

31 [redact] >250 keV photons acute normal 0.0234 0.007

32 [redact] >250 keV photons acute normal 0.0222 0.007

33 [redact] >250 keV photons acute normal 0.0216 0.006

34 [redact] >250 keV photons acute normal 0.0162 0.005

35 [redact] >250 keV photons acute normal 0.0066 0.002

36 [redact] >250 keV photons acute normal 0.0096 0.003

37 [redact] <15 keV electrons acute normal 0.0470 0.014

38 [redact] <15 keV electrons acute normal 2.7130 0.814

39 [redact] <15 keV electrons acute normal 3.3380 1.001

40 [redact] <15 keV electrons acute normal 1.8760 0.563

41 [redact] <15 keV electrons acute normal 2.0620 0.619

42 [redact] <15 keV electrons acute normal 4.1100 1.233

43 [redact] <15 keV electrons acute normal 0.7220 0.217

44 [redact] <15 keV electrons acute normal 0.3270 0.098

45 [redact] <15 keV electrons acute normal 0.0010 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

68 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-2: IREP Input – [Redacted] BCC on the [Redacted] (continued)

46 [redact] <15 keV electrons acute normal 0.2690 0.081

47 [redact] <15 keV electrons acute normal 0.0540 0.016

48 [redact] <30 keV photons acute lognormal 0.0117 1.52

49 [redact] <30 keV photons acute lognormal 0.0039 1.52

50 [redact] <30 keV photons acute lognormal 0.0026 1.52

51 [redact] <30 keV photons acute lognormal 0.0052 1.52

52 [redact] 30–250 keV photons acute lognormal 0.0180 1.52

53 [redact] 30–250 keV photons acute lognormal 0.0297 1.52

54 [redact] 30–250 keV photons acute lognormal 0.0990 1.52

55 [redact] 30–250 keV photons acute lognormal 0.0066 1.52

56 [redact] 30–250 keV photons acute lognormal 0.0132 1.52

57 [redact] 30–250 keV photons acute lognormal 0.0400 1.52

58 [redact] 30–250 keV photons acute lognormal 0.0440 1.52

59 [redact] 30–250 keV photons acute lognormal 0.0480 1.52

60 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

61 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

62 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

63 [redact] 30–250 keV photons acute lognormal 0.0160 1.52

64 [redact] 30–250 keV photons acute lognormal 0.0640 1.52

65 [redact] >250 keV photons acute lognormal 0.0270 1.52

66 [redact] >250 keV photons acute lognormal 0.0486 1.52

67 [redact] >250 keV photons acute lognormal 0.0162 1.52

68 [redact] >250 keV photons acute lognormal 0.0108 1.52

69 [redact] >250 keV photons acute lognormal 0.0216 1.52

70 [redact] >250 keV photons acute lognormal 0.0600 1.52

71 [redact] >250 keV photons acute lognormal 0.0660 1.52

72 [redact] >250 keV photons acute lognormal 0.0720 1.52

73 [redact] >250 keV photons acute lognormal 0.0120 1.52

74 [redact] >250 keV photons acute lognormal 0.0120 1.52

75 [redact] >250 keV photons acute lognormal 0.0120 1.52

76 [redact] >250 keV photons acute lognormal 0.0240 1.52

77 [redact] >250 keV photons acute lognormal 0.0960 1.52

78 [redact] 30–250 keV photons acute normal 0.0237 0.00711

79 [redact] 30–250 keV photons acute normal 0.0237 0.00711

80 [redact] 30–250 keV photons acute normal 0.0237 0.00711

81 [redact] 30–250 keV photons acute normal 0.0171 0.00513

82 [redact] 30–250 keV photons acute normal 0.0214 0.00642

83 [redact] 30–250 keV photons acute normal 0.0214 0.00642

84 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

85 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

86 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

87 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

88 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

89 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

90 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

91 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

92 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

69 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-2: IREP Input – [Redacted] BCC on the [Redacted] (continued)

93 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

94 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

95 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

96 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

97 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

98 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

99 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

100 [redact] >15 keV electrons acute normal 0.013 0.0038

101 [redact] >15 keV electrons acute normal 0.013 0.0038

102 [redact] >15 keV electrons acute normal 0.013 0.0038

103 [redact] >15 keV electrons acute normal 0.013 0.0038

104 [redact] >15 keV electrons acute normal 0.013 0.0038

105 [redact] >15 keV electrons acute normal 0.013 0.0038

106 [redact] >15 keV electrons acute normal 0.013 0.0038

107 [redact] >15 keV electrons acute normal 0.013 0.0038

108 [redact] >15 keV electrons acute normal 0.013 0.0038

109 [redact] >15 keV electrons acute normal 0.013 0.0038

110 [redact] >15 keV electrons acute normal 0.013 0.0038

111 [redact] >15 keV electrons acute normal 0.013 0.0038

112 [redact] >15 keV electrons acute normal 0.013 0.0038

113 [redact] >15 keV electrons acute normal 0.013 0.0038

114 [redact] >15 keV electrons acute normal 0.013 0.0038

115 [redact] >15 keV electrons acute normal 0.013 0.0038

116 [redact] alpha chronic normal 5.69E-05 0.0000

117 [redact] alpha chronic normal 7.95E-04 0.0002

118 [redact] alpha chronic normal 1.51E-03 0.0005

119 [redact] alpha chronic normal 2.26E-03 0.0007

120 [redact] alpha chronic normal 3.05E-03 0.0009

121 [redact] alpha chronic normal 3.87E-03 0.0012

122 [redact] alpha chronic normal 4.73E-03 0.0014

123 [redact] alpha chronic normal 5.58E-03 0.0017

124 [redact] alpha chronic normal 6.46E-03 0.0019

125 [redact] alpha chronic normal 7.36E-03 0.0022

126 [redact] alpha chronic normal 8.29E-03 0.0025

127 [redact] alpha chronic normal 9.19E-03 0.0028

128 [redact] alpha chronic normal 1.01E-02 0.0030

129 [redact] alpha chronic normal 1.11E-02 0.0033

130 [redact] alpha chronic normal 1.20E-02 0.0036

131 [redact] alpha chronic normal 1.26E-02 0.0038

132 [redact] alpha chronic normal 1.27E-02 0.0038

133 [redact] alpha chronic normal 1.30E-02 0.0039

134 [redact] alpha chronic normal 1.32E-02 0.0040

135 [redact] alpha chronic normal 1.33E-02 0.0040

136 [redact] alpha chronic normal 1.34E-02 0.0040

137 [redact] alpha chronic normal 1.35E-02 0.0041

138 [redact] alpha chronic normal 1.37E-02 0.0041

139 [redact] alpha chronic normal 1.37E-02 0.0041
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

70 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-2: IREP Input – [Redacted] BCC on the [Redacted] (continued)

140 [redact] alpha chronic normal 1.38E-02 0.0041

141 [redact] alpha chronic normal 1.39E-02 0.0042

142 [redact] alpha chronic normal 1.39E-02 0.0042

143 [redact] alpha chronic normal 7.41E-03 0.0022
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

71 of 75

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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

APPENDIX II.A-3: IREP INPUT – [REDACTED] SCCS AND BCC

Exposure 

year

Radiation Type Exposure 

rate Distribution Parameter 1 Parameter 2

1 [redact] <30 keV photons acute normal 0.0225 0.007

2 [redact] <30 keV photons acute normal 0.0376 0.011

3 [redact] <30 keV photons acute normal 0.0212 0.006

4 [redact] <30 keV photons acute normal 0.0183 0.005

5 [redact] <30 keV photons acute normal 0.0523 0.016

6 [redact] <30 keV photons acute normal 0.0235 0.007

7 [redact] 30–250 keV photons acute normal 0.0020 0.001

8 [redact] 30–250 keV photons acute normal 0.0571 0.017

9 [redact] 30–250 keV photons acute normal 0.0954 0.029

10 [redact] 30–250 keV photons acute normal 0.0538 0.016

11 [redact] 30–250 keV photons acute normal 0.0465 0.014

12 [redact] 30–250 keV photons acute normal 0.1327 0.040

13 [redact] 30–250 keV photons acute normal 0.0597 0.018

14 [redact] 30–250 keV photons acute normal 0.0200 0.006

15 [redact] 30–250 keV photons acute normal 0.0108 0.003

16 [redact] 30–250 keV photons acute normal 0.0156 0.005

17 [redact] 30–250 keV photons acute normal 0.0148 0.004

18 [redact] 30–250 keV photons acute normal 0.0144 0.004

19 [redact] 30–250 keV photons acute normal 0.0108 0.003

20 [redact] 30–250 keV photons acute normal 0.0044 0.001

21 [redact] 30–250 keV photons acute normal 0.0064 0.002

22 [redact] >250 keV photons acute normal 0.0030 0.001

23 [redact] >250 keV photons acute normal 0.0934 0.028

24 [redact] >250 keV photons acute normal 0.1561 0.047

25 [redact] >250 keV photons acute normal 0.0880 0.026

26 [redact] >250 keV photons acute normal 0.0761 0.023

27 [redact] >250 keV photons acute normal 0.2171 0.065

28 [redact] >250 keV photons acute normal 0.0977 0.029

29 [redact] >250 keV photons acute normal 0.0300 0.009

30 [redact] >250 keV photons acute normal 0.0162 0.005

31 [redact] >250 keV photons acute normal 0.0234 0.007

32 [redact] >250 keV photons acute normal 0.0222 0.007

33 [redact] >250 keV photons acute normal 0.0216 0.006

34 [redact] >250 keV photons acute normal 0.0162 0.005

35 [redact] >250 keV photons acute normal 0.0066 0.002

36 [redact] >250 keV photons acute normal 0.0096 0.003

37 [redact] <15 keV electrons acute normal 0.0470 0.014

38 [redact] <15 keV electrons acute normal 2.7130 0.814

39 [redact] <15 keV electrons acute normal 3.3380 1.001

40 [redact] <15 keV electrons acute normal 1.8760 0.563

41 [redact] <15 keV electrons acute normal 2.0620 0.619

42 [redact] <15 keV electrons acute normal 4.1100 1.233

43 [redact] <15 keV electrons acute normal 0.7220 0.217

44 [redact] <15 keV electrons acute normal 0.3270 0.098
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

72 of 75

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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-3: IREP Input – [Redacted] SCCs and BCC (continued)

45 [redact] <15 keV electrons acute normal 0.0010 0.000

46 [redact] <15 keV electrons acute normal 0.2690 0.081

47 [redact] <15 keV electrons acute normal 0.0540 0.016

48 [redact] <30 keV photons acute lognormal 0.0117 1.52

49 [redact] <30 keV photons acute lognormal 0.0039 1.52

50 [redact] <30 keV photons acute lognormal 0.0026 1.52

51 [redact] <30 keV photons acute lognormal 0.0052 1.52

52 [redact] 30–250 keV photons acute lognormal 0.0180 1.52

53 [redact] 30–250 keV photons acute lognormal 0.0297 1.52

54 [redact] 30–250 keV photons acute lognormal 0.0990 1.52

55 [redact] 30–250 keV photons acute lognormal 0.0066 1.52

56 [redact] 30–250 keV photons acute lognormal 0.0132 1.52

57 [redact] 30–250 keV photons acute lognormal 0.0400 1.52

58 [redact] 30–250 keV photons acute lognormal 0.0440 1.52

59 [redact] 30–250 keV photons acute lognormal 0.0480 1.52

60 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

61 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

62 [redact] 30–250 keV photons acute lognormal 0.0080 1.52

63 [redact] 30–250 keV photons acute lognormal 0.0160 1.52

64 [redact] 30–250 keV photons acute lognormal 0.0640 1.52

65 [redact] >250 keV photons acute lognormal 0.0270 1.52

66 [redact] >250 keV photons acute lognormal 0.0486 1.52

67 [redact] >250 keV photons acute lognormal 0.0162 1.52

68 [redact] >250 keV photons acute lognormal 0.0108 1.52

69 [redact] >250 keV photons acute lognormal 0.0216 1.52

70 [redact] >250 keV photons acute lognormal 0.0600 1.52

71 [redact] >250 keV photons acute lognormal 0.0660 1.52

72 [redact] >250 keV photons acute lognormal 0.0720 1.52

73 [redact] >250 keV photons acute lognormal 0.0120 1.52

74 [redact] >250 keV photons acute lognormal 0.0120 1.52

75 [redact] >250 keV photons acute lognormal 0.0120 1.52

76 [redact] >250 keV photons acute lognormal 0.0240 1.52

77 [redact] >250 keV photons acute lognormal 0.0960 1.52

78 [redact] 30–250 keV photons acute normal 0.0237 0.00711

79 [redact] 30–250 keV photons acute normal 0.0237 0.00711

80 [redact] 30–250 keV photons acute normal 0.0237 0.00711

81 [redact] 30–250 keV photons acute normal 0.0171 0.00513

82 [redact] 30–250 keV photons acute normal 0.0214 0.00642

83 [redact] 30–250 keV photons acute normal 0.0214 0.00642

84 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

85 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

86 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

87 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

88 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

89 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

73 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-3: IREP Input – [Redacted] SCCs and BCC (continued)

90 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

91 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

92 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

93 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

94 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

95 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

96 [redact] 0.1– 2 MeV neutrons chronic normal 0.018 0.0054

97 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

98 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

99 [redact] 0.1–2 MeV neutrons chronic normal 0.018 0.0054

100 [redact] >15 keV electrons acute normal 0.013 0.0038

101 [redact] >15 keV electrons acute normal 0.013 0.0038

102 [redact] >15 keV electrons acute normal 0.013 0.0038

103 [redact] >15 keV electrons acute normal 0.013 0.0038

104 [redact] >15 keV electrons acute normal 0.013 0.0038

105 [redact] >15 keV electrons acute normal 0.013 0.0038

106 [redact] >15 keV electrons acute normal 0.013 0.0038

107 [redact] >15 keV electrons acute normal 0.013 0.0038

108 [redact] >15 keV electrons acute normal 0.013 0.0038

109 [redact] >15 keV electrons acute normal 0.013 0.0038

110 [redact] >15 keV electrons acute normal 0.013 0.0038

111 [redact] >15 keV electrons acute normal 0.013 0.0038

112 [redact] >15 keV electrons acute normal 0.013 0.0038

113 [redact] >15 keV electrons acute normal 0.013 0.0038

114 [redact] >15 keV electrons acute normal 0.013 0.0038

115 [redact] >15 keV electrons acute normal 0.013 0.0038

116 [redact] alpha chronic normal 5.69E-05 0.0000

117 [redact] alpha chronic normal 7.95E-04 0.0002

118 [redact] alpha chronic normal 1.51E-03 0.0005

119 [redact] alpha chronic normal 2.26E-03 0.0007

120 [redact] alpha chronic normal 3.05E-03 0.0009

121 [redact] alpha chronic normal 3.87E-03 0.0012

122 [redact] alpha chronic normal 4.73E-03 0.0014

123 [redact] alpha chronic normal 5.58E-03 0.0017

124 [redact] alpha chronic normal 6.46E-03 0.0019

125 [redact] alpha chronic normal 7.36E-03 0.0022

126 [redact] alpha chronic normal 8.29E-03 0.0025

127 [redact] alpha chronic normal 9.19E-03 0.0028

128 [redact] alpha chronic normal 1.01E-02 0.0030

129 [redact] alpha chronic normal 1.11E-02 0.0033

130 [redact] alpha chronic normal 1.20E-02 0.0036

131 [redact] alpha chronic normal 1.26E-02 0.0038

132 [redact] alpha chronic normal 1.27E-02 0.0038

133 [redact] alpha chronic normal 1.30E-02 0.0039

134 [redact] alpha chronic normal 1.32E-02 0.0040
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

74 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Appendix II.A-3: IREP Input – [Redacted] SCCs and BCC (continued)

135 [redact] alpha chronic normal 1.33E-02 0.0040

136 [redact] alpha chronic normal 1.34E-02 0.0040

137 [redact] alpha chronic normal 1.35E-02 0.0041

138 [redact] alpha chronic normal 1.37E-02 0.0041

139 [redact] alpha chronic normal 1.37E-02 0.0041

140 [redact] alpha chronic normal 1.38E-02 0.0041

141 [redact] alpha chronic normal 1.39E-02 0.0042

142 [redact] alpha chronic normal 1.39E-02 0.0042

143 [redact] alpha chronic normal 1.39E-02 0.0042

144 [redact] alpha chronic normal 1.40E-02 0.0042

145 [redact] alpha chronic normal 1.40E-02 0.0042

146 [redact] alpha chronic normal 4.41E-03 0.0013
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

75 of 75

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

ATTACHMENT 1: INDEPENDENT VERIFICATION OF DOSE 

CONVERSION FACTOR FOR URANIUM DUST SETTLING ON SKIN 

Prepared by Michael Mallett 

8/11/2013 

VARSKIN V.4 calculates the calibration factor as 0.21 mrad/hr per Bq/cm2. The ORNL value is 

0.24 mrem/hr per Bq/cm2. In other words, the 40 mrem/hr dose conversion factor ORNL 

reported is now calculated as 35 mrem/hr—slightly different beta spectra in the data tables. The 

current result includes the photon contribution, which was not a capability of VARSKIN 1.