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 ROCKY FLATS PLANT

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 

NOTICE: This information is protected by Privacy Act 5 USC §552a; disclosure to any third party without 

the written consent of the individual to whom the information pertains is strictly prohibited.
Effective Date:

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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-CN0[REDACTED]

Effective Date: 

Draft – January 13, 2014

Revision No. 0 (Draft)

SC&A’S DOSE RECONSTRUCTION OF 

CASE #[REDACTED] FROM THE ROCKY 

FLATS PLANT 

Page 2 of 41

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 ........................................................................................................ 5

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

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

I.2 External Dose .......................................................................................................... 9

I.2.1 Recorded Photon Dose ................................................................................ 9

I.2.2 Missed Photon Dose ................................................................................. 10

I.2.3 Recorded Neutron Dose ............................................................................ 10

I.2.4 Missed Neutron Dose ................................................................................ 11

I.2.5 Occupational Medical Dose ...................................................................... 12

I.2.6 Onsite Ambient Dose ................................................................................ 12

I.3 Internal Dose ......................................................................................................... 12

I.3.1 Dose from Plutonium/Americium............................................................. 13

I.3.2 Dose from Tritium .................................................................................... 15

I.3.2 Environmental Dose.................................................................................. 15

I.4 Dose from Radiological Incidents ........................................................................ 15

I.5 Summary Conclusions .......................................................................................... 15

I.6 References ............................................................................................................. 16

Appendix I-A: IREP Input – Lung............................................................................................... 17

Section II: DR–Method B ............................................................................................................ 20

II.1 Dose Reconstruction Overview .............................................................................. 20

II.1.1 Introduction ............................................................................................. 20

II.1.2 Relevant Background Information .......................................................... 21

II.1.3 Radiation Incidents .................................................................................. 21

II.2 External Dose ........................................................................................................ 22

II.2.1 Completeness and Reliability of External Dosimetry Records................. 22

II.2.2 Reliability of Methods Used to Reconstruct Neutron Exposures ............. 23

II.2.3 Reconstruction of External Doses ............................................................. 25

II.3 Internal Dose ......................................................................................................... 30

II.3.1 Missed Plutonium Dose using the In-Vitro Urinalysis Bioassay Data ..... 30

II.3.2 Missed Americium Dose using the In-Vitro Urinalysis Bioassay 

Data ........................................................................................................... 31

II.3.3 Missed Plutonium Dose using Lung Count Results ................................. 31

II.3.4 Missed Americium Dose using Lung Count Results ................................ 33

II.3.5 Depleted Uranium Dose ............................................................................ 34

II.5 Summary Conclusions .......................................................................................... 35

II.6 References ............................................................................................................. 35

Appendix II-A: IREP Input – Lung ............................................................................................. 37
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LIST OF TABLES 

Table ES-1. Derived Dose Estimates ............................................................................................. 6

Table I-1. Summary of Method A-Derived External/Internal Dose Estimates ............................. 8

Table I-2. Effective Dose Conversion Factors and Energy Distributions ..................................... 9

Table I-3. In-Vitro Bioassay Results ........................................................................................... 13

Table I-4. Pu/Am Chronic Intakes – [redacted]–[redacted]......................................................... 14

Table I-5. OTIB-0049 Adjusted Doses ........................................................................................ 14

Table II-1. Assigned Dose for Case #[redacted] .......................................................................... 20

Table II-2. Default Neutron Energy Distribution for RFP ........................................................... 24

Table II-3. Assigned External Doses for Case #[redacted] .......................................................... 25

Table II-4. External DR Parameters for Case #[redacted] ........................................................... 25

Table II-5. Lung Dose Conversion Factors (30–250 keV) .......................................................... 26

Table II-6. Photon Dosimeter Uncertainty Factors for RFP ........................................................ 26

Table II-7. Unmonitored Doses ................................................................................................... 29

Table II-8. Plutonium/Americium Bioassay Results for Case #[redacted] .................................. 30

Table II-9. Plutonium Intakes and Doses Calculated from Bioassay Results.............................. 31

Table II-10. Americium and Plutonium Lung Count MDA ........................................................ 32

Table II-11. Type S Plutonium Intakes and Doses from Lung Counts ........................................ 32

Table II-12. Tritium Bioassay Results for Case #[redacted] ....................................................... 34
Effective Date:

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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 concerning one case 

selected by the Advisory Board, which represents a worker from the Rocky Flats Plant (RFP). 

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 

NIOSH for constructing doses in behalf of this case. SC&A used two independent approaches to 

reconstruct occupational external and internal doses in behalf of this case. Both approaches used 

the available dosimetry records and current guidance from the National Institute for 

Occupational Safety and Health (NIOSH). 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. 

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 

RFP from [redacted], through [redacted], and again from [redacted], through [redacted]. The 

EE was diagnosed with lung cancer (ICD Code 162.9) in [redacted]. Although this is a covered 

cancer under the Special Exposure Cohort (SEC), the current RFP SEC would not cover the time 

period this EE worked at the RFP. 

According to the DOE records, the majority of the EE’s radiation exposure was received while 

working as a [redacted], primarily in the plutonium buildings [redacted], [redacted], 

[redacted], [redacted], and [redacted]. During the course of employment, the EE was 

monitored for external photon and neutron radiation exposure and internal radiation exposure by 

urinalyses and lung counts.

PRESENTATION OF RESULTS 

The results of both independent DR methods are shown in Table ES-1. DR–Method A derived a 

total lung dose of 41.914 rem, with a probability of causation (POC) of 56.71%; while DR–

Method B derived a total lung dose of 71.944 rem, with a POC of 55.75%. Although the 

Method B total dose was almost double the Method A total dose, the POCs were nearly identical. 

This can be explained by the fact that Method A entered the doses into the NIOSH-Interactive 

RadioEpidemiological Program (IREP) as a lognormal distribution with a geometric standard 

deviation (GSD) of 3 and Method B entered the annual doses into IREP as a normal distribution 

with a 30% uncertainty. 
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Table ES-1. Derived Dose Estimates 

DR–Method A DR–Method B

External Dose (Occupational):

 ▪ Recorded Dose

 - Photons <30 keV 0.019 0.018

 - Photons 30–250 keV 1.440 1.551

 - Neutrons 1.127 1.107

 ▪ Missed Dose

 - Photons 0.048 0.038

 - Neutrons 0.312 0.324

 ▪ Unmonitored Dose

 - Photons NA 0.677

 - Neutrons NA 0.521

 ▪ Occupational Medical Dose

 - Photons 30–250 keV 0.294 0.294

Internal Dose:

 - Plutonium/Americium (Alpha) 38.676 57.114

 - DU (Alpha) NA 10.300

Total 41.914 71.944

There were a number of similarities between the two methods for determining both the external 

doses and the internal doses, with variance in methodology that led to some different dose 

assignments. These can be summarized as follows: 

External Doses 

Photon Dose 

DR–Method A derived a total photon dose of 1.507 rem compared to 2.284 rem derived by DR–

Method B. The difference was mainly from DR–Method A using a minimizing approach, which 

only assigned dose from actual recorded dose and recorded missed dose (zeros); whereas, DR–

Method B used a best-estimate approach, which added missed or unmonitored doses when gaps 

occurred in the dosimetry records. A minor difference in photon dose assignment occurred 

because DR–Method A assigned 100% 30 keV and 100% 30–250 keV photon doses, and DR–

Method B assigned 25% <30 keV and 75% photon doses. Assigning 100% 30 keV and 100% 

30–250 keV photon doses is claimant favorable, but assigning 25% <30 keV and 75% photon 

doses is more realistic for the lung. 

Neutron Dose 

DR–Method A derived a total neutron dose of 1.439 rem compared to 1.888 rem derived by 

DR–Method B. Again, the difference was mainly from DR–Method A using a minimizing 

approach, which only assigned dose from actual recorded dose and recorded missed dose (zeros); 

whereas DR–Method B used a best-estimate approach, which added missed or unmonitored 

doses when gaps occurred in the dosimetry records. Both methods used the appropriate energy 

distributions and ICRP conversion factors. 
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Environmental External Dose 

As per Occupational On-Site Ambient Dose Reconstruction for DOE Sites (ORAUT-PROC0060), neither method assigned environmental external dose, because the EE was monitored or 

assigned missed dose during the employment period. 

Occupational Medical Dose 

DR–Method A and DR–Method B both derived a total medical x-ray dose of 0.294 rem. 

Internal Doses 

For internal dose assignments, the largest differences in assigned dose between DR–Method A 

and DR–Method B were that the results of DR–Method B included potential depleted uranium 

(DU) intake/dose, whereas DR–Method A did not assess a dose from DU. Additionally, DR–

Method A combined the data from the two bioassay methods (lung counts and urinalyses) when 

determining the projected intakes, whereas DR–Method B analyzed the bioassay data separately.

DU Dose 

DR–Method B assigned potential internal intake from DU, which was very claimant favorable 

because the EE worked in the plutonium facility. DR–Method A did not consider that the EE 

was sufficiently exposed to DU to warrant dose assignment, because the bioassay was performed 

as a precautionary measure as the result of an incident and no uranium was detected by the 

bioassay. This difference results in an additional 10.300 rem being assigned by DR–Method B. 

Plutonium/Americium 

DR–Method A used the lung counts and the urinalyses results in combination to perform a bestfit analysis of the bioassay data, whereas DR–Method B analyzed the lung counts and urinalyses 

results separately and compared the results, and selected the lung count as being more 

representative of the intakes. Both DR methods considered the potential different solubility 

types and used the type resulting in the highest dose. DR–Method A derived a total lung dose of 

38.676 rem and DR–Method B derived a total lung dose of 57.114 rem. 
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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 Rocky Flats Plant (RFP) from 

[redacted], to [redacted], and [redacted], to [redacted]. The EE was diagnosed with 

squamous cell lung cancer (ICD-9 Code 162.9) on [redacted].

According to Department of Labor (DOL) and Department of Energy (DOE) records, the EE 

worked as a [redacted] primarily in buildings [redacted], [redacted], [redacted], [redacted] and 

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

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

bioassays and chest counts from [redacted] through [redacted]. The DOL records also indicated 

that the EE was a [redacted]. 

SC&A reviewed all of the DOL and DOE records provided on behalf of this employee and all of 

the NIOSH procedures relevant to this case and the site profile for the RFP, which was issued as 

six separate technical basis documents (TBDs) numbered ORAUT-TKBS-0011-1 through 

ORAUT-TKBS-0011-6. Using the guidance provided in these documents, along with the 

employee’s dosimetry records, SC&A manually calculated reasonable, claimant-favorable 

annual organ doses shown in Table I-1. Appendix I-A provides a list of SC&A’s annual organ 

doses and also includes the NIOSH-Interactive RadioEpidemiological Program (IREP) input 

parameters, such as energy range, distribution type, and uncertainty for each year. 

Table I-1. Summary of Method A-Derived External/Internal Dose Estimates 

Appendix I-A

Exposure Entry No.

Lung Dose 

(rem)

External Dose (Occupational):

 ▪ Recorded Dose

 - Photons < 30 keV 35–40 0.019

 - Photons 30–250 keV 1–6 1.440

 - Neutrons <10 keV 7–13 0.101

 - Neutrons 10–100 keV 14–20 0.021

 - Neutrons 0.1–2 MeV 21–27 0.691

 - Neutrons 2–20 MeV 28–34 0.313

▪ Missed Dose

 - Photons 30–250 keV 41–45 0.048

 - Neutrons <10 keV 46–51 0.028

 - Neutrons 10–100 keV 52–57 0.006

 - Neutrons 0.1–2 MeV 58–63 0.191

 - Neutrons 2–20 MeV 64–69 0.087

 ▪ Occupational Medical Dose

 - Photons 30–250 keV 70–76 0.293

Internal Dose:

 - Plutonium/Americium (Alpha) 77–109 38.676

Total 41.914

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

input into the IREP program. The IREP program was also run using the [redacted] option, since 

this was a lung cancer. The total doses shown in Table I-1 produced a POC of 56.71%.

I.2 EXTERNAL DOSE 

The reconstruction of the EE’s external doses began with a review of the DOE records. In the 

sections that follow, a description is provided of how SC&A reconstructed the dose to the lung 

considering the recorded and missed doses. 

I.2.1 Recorded Photon Dose 

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

employment except for [redacted], when the limit of detection (LOD) was 0.020 R. SC&A used 

the guidance described in ORAUT-TKBS-0011-6 in order to derive the organ dose from this 

exposure. The organ dose conversion factors (DCFs) shown in Table I-2 were applied in 

accordance with Table 4.1a and Appendix A of the External Dose Reconstruction 

Implementation Guideline, (OCAS-IG-001). 

Table I-2. Effective Dose Conversion Factors and Energy Distributions 

Plutonium Facility (Buildings [redacted]) – Exposure ([redacted]–[redacted])

Photons Neutrons

<30 keV 30–250 keV <10 keV 10–100 keV 100 keV–2 MeV 2–20 MeV

Energy Range 100% 100% — — — —

ICRP 60 CF — — 0.0755 0.0309 1.31 0.345

Organ DCF 0.030 0.986 1.523 0.751 0.579 1.004

DCFEffective 0.030 0.986 0.115 0.023 0.758 0.346

Plutonium Facility (Buildings [redacted]) – Deep Dose Equivalent ([redacted]–[redacted])

Photons Neutrons

<30 keV 30–250 keV <10 keV 10–100 keV 100 keV–2 MeV 2–20 MeV

Energy Range 100% 100% — — — —

ICRP 60 CF — — 0.0755 0.0309 1.31 0.345

Organ DCF 0.050 0.695 1.332 0.737 0.557 0.950

DCFEffective 0.050 0.695 0.101 0.023 0.730 0.328

SC&A calculated the [redacted] photon dose to the lung using assumptions provided in Table I2 as follows:

 [Redacted]: Records show that for [redacted], the EE received (above the LOD/2 value) a 

deep dose (D) of 0.447 R and shallow dose (S) of 0.517 R. The photon dose to the lung was 

assumed to be 100% <30 keV and 100% 30–250 keV. Lung DCFs of 0.030 for <30 keV 

photons and 0.986 for 30–250 keV shown in Table I-2 were applied.

 Lung Dose (<30 keV) = (S - D) × DCF × 100% 

= (0.517-0.447) × 0.030 × 1.0 

 = 0.002 rem 
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 Lung Dose (30–250 keV) = D × DCF × 100% 

= 0.447 × 0.986 × 1.0 

 = 0.441 rem 

SC&A’s calculated <30 keV and 30–250 keV lung doses are shown in entries #35 and #1, 

respectively, of Appendix I-A. 

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

Although uncertainty would normally be factored in, the resulting POC was greater than 50%; 

therefore, uncertainty factors were not needed. SC&A found that the current DR tool available 

on the server would not factor in uncertainty for this case. 

I.2.2 Missed Photon Dose 

The EE was monitored on a monthly dosimeter exchange schedule from the end of [redacted]

through the middle of [redacted]. Both OCAS-IG-001 and ORAUT-TKBS-0011-6 suggest 

assigning missed dose to monitored workers who received doses below the LOD.1 After 

correcting for values that were below the LOD, SC&A counted a total of 5 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, along with the DCF.

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

 [Redacted]: Records show that for [redacted], there was one dosimeter reading that was 

either zero or less than the LOD/2 and marked as zero. The LOD for the time period is 0.020 

R, making the LOD/2 equal to 0.010 R.

 Lung Dose (30–250 keV) = (# zeros × LOD/2) × DCF 

 = (1 × 0.010 R) × 0.986 

 = 0.010 rem 

SC&A’s calculated 30–250 keV missed dose of 0.010 rem is shown in entry #42 of 

Appendix I-A. 

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 Neutron Dose 

The DOE records show that this EE was monitored for neutrons and received positive recorded 

neutron doses during each year of employment from [redacted]–[redacted]. SC&A calculated 

the neutron doses to the lung using the International Commission on Radiological Protection 

(ICRP) correction factors (CFs) and organ DCFs shown in Table I-2. 

 

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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For example, SC&A calculated the [redacted] neutron doses as follows:

 [Redacted]: Records show that for [redacted], the EE’s recorded neutron dose (N), above 

the LOD/2 value, was 0.247 rem. The calculated neutron dose is simply the recorded dose 

multiplied by the effective DCF (or organ DCF × ICRP 60 CF).

 <10 keV neutrons = N × DCFeff 

= 0.247 rem × 0.115 

 = 0.028 rem 

 10–100 keV neutrons = N × DCFeff 

= 0.247 rem × 0.023 

 = 0.006 rem 

 

0.1–2 MeV neutrons = N × DCFeff

= 0.247 rem × 0.758 

 = 0.187 rem

 2.0–20 MeV neutrons = N × DCFeff 

= 0.247 rem × 0.346 

 = 0.086 rem 

SC&A’s calculated neutron doses for [redacted] are shown as IREP entries #8, #15, #22, and 

#29 of Appendix I-A. The total neutron dose was 1.127 rem. The neutron doses were entered 

into IREP as a constant distribution with no uncertainty.

I.2.4 Missed Neutron Dose 

Missed neutron doses were calculated based on a dosimeter reading that was either zero or less 

than the LOD/2 and was therefore marked as zero. Like the photon missed doses, a monthly 

dosimeter exchange frequency was assumed. A total of 20 dosimeter results were less than the 

LOD/2 and marked as zero. The number of zero readings for a year is multiplied by the 

appropriate LOD/2 and the DCFeff from Table I-2.

SC&A calculated the [redacted] missed neutron doses to the lung as follows:

 [Redacted]: Records show that for [redacted], there were five dosimeter readings that were

either less than the LOD/2 or marked as zero. The LOD for the time period is 0.020 rem, 

making the LOD/2 equal to 0.010 rem.

<10 keV neutrons = (# zeros × LOD/2) × DCFeff 

= (5 × 0.010 rem) × 0.115 

 = 0.006 rem 

10–100 keV neutrons = (# zeros × LOD/2) × DCFeff 

= (5 × 0.010 rem) × 0.023 

 = 0.001 rem 
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0.1–2 MeV neutrons = (# zeros × LOD/2) × DCFeff 

= (5 × 0.010 rem) × 0.758 

 = 0.038 rem 

2.0–20 MeV neutrons = (# zeros × LOD/2) × DCFeff 

= (5 × 0.010 rem) × 0.346 

 = 0.017 rem 

SC&A’s calculated neutron doses are shown as IREP entries #46, #52, #58, and #64 of 

Appendix I-A. The total missed neutron dose is 0.312 rem. The missed neutron doses were 

entered into IREP as a lognormal distribution with an uncertainty of 1.520. 

I.2.5 Occupational Medical Dose 

In addition to the estimated dose received from site operations, the doses received from 

diagnostic x-ray procedures that were required as a condition of employment were also included 

in the overall dose. The x-ray dose was based on information in the RFP TBD for Occupational 

Medical Dose, ORAUT-TKBS-0011-3. The DOE records show that the EE received three x-ray 

exams; two chest exams and one left foot exam. Table 3-1 of ORAUT-TBKS-0011-3 indicates 

an annual x-ray examination frequency for workers from [redacted]–[redacted]. Therefore, an 

annual PA chest x-ray was assumed for each year for the EE’s employment from [redacted]–

redacted]. The annual x-ray dose to the lung is shown in Table 3-6 of ORAUT-TKBS-0011-3 

as 0.042 rem per year. The total occupational medical dose of 0.294 rem is shown in IREP 

entries #70–#76 of Appendix I-A. 

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.2.6 Onsite Ambient Dose 

The EE was monitored for ionizing radiation doses during all of the EE’s employment at the 

RFP, and the dosimetry results account for any doses from stack releases or other radiation 

sources that may have been unmonitored at the site in that era. Therefore, no onsite ambient 

doses were assigned, in accordance with guidance in the procedure, Occupational On-Site 

Ambient Dose Reconstruction for DOE Sites (ORAUT-PROC-0060). 

I.3 INTERNAL DOSE 

Internal dose monitoring records for radionuclides were reviewed. The in-vitro bioassay results 

are shown in Table I-3. 
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Table I-3. In-Vitro Bioassay Results

Date Type Nuclide Result Units MDA

[redacted] Urine Am 0.01 dpm/24hr 0.31

[redacted] Urine Am 0.01 dpm/24hr 0.31

[redacted] Urine Am 0.00 dpm/24hr 0.31

[redacted] Urine Pu 0.00 dpm/24hr 0.24

[redacted] Urine Pu 0.03 dpm/24hr 0.24

[redacted] Urine Pu 0.01 dpm/24hr 0.24

[redacted] Urine Pu 0.04 dpm/24hr 0.24

[redacted] Urine Pu 0.08 dpm/24hr 0.24

[redacted] Urine H-3 795.0 pCi/L Unknown

[redacted] Urine H-3 890.0 pCi/L Unknown

[redacted] Urine H-3 833.0 pCi/L Unknown

According to the RFP TBD ORAUT-TKBS-0011-5, the actual minimum detectable amount 

(MDA) for the tritium analyses has not been quantified for the methods in the [redacted] and 

[redacted]; however, it is likely in the range of several hundred to several thousand picocuries 

per liter. The current MDA for tritium is 600 pCi/L. 

The EE was also monitored for plutonium and americium via chest counts. The EE had eight 

chest counts from [redacted]–[redacted] with all results less than the MDA.

I.3.1 Dose from Plutonium/Americium 

All of the EE’s bioassay results were below the MDA of the analyses for plutonium and 

americium. The plutonium urine and chest count results and the americium urine and chest 

count results were used to calculate the total plutonium intake. 

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 urine and chest 

count 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 the EE’s first employment period, [redacted], to 

[redacted]. The EE did not have any urinalyses performed during the [redacted] second period of 

employment during [redacted]. The level of the intake was based on one-half the MDA of the 

analysis. Using IMBA and a maximum likelihood fitting method, the total plutonium intake rate 

was determined to be 106.9 dpm/day of Type S plutonium, based on both the urine and chest 

count data. Following the same method, the americium urine and chest count data were used to 

determine the Type S americium intake rate of 5.0 dpm/day. The RFP Pu-Am Intake Calculation 

tool was used to determine the isotopic mixture for weapons-grade plutonium with Pu-241 

weight percent of 0.36%. Table I-4 shows the individual plutonium and americium intake rates 

based on the plutonium urine and chest count data. SC&A noted that the Am-241 intake rate 
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derived using the urine data was consistent with the intake rate derived using the chest count 

data. 

Table I-4. Pu/Am Chronic Intakes – [redacted]–[redacted]

Nuclide Type Intake Rate (dpm/day)

Pu-238 S 2.5

Pu-239/240 S 104.5

Pu-241 S 592.5

Am-241 S 5.04

The chronic annual dose workbook (CADW) was used to calculate the annual doses from each 

of the above chronic intakes. The methods described in ORAUT-OTIB-0049 were used to 

account for the increased organ doses due to the intake of plutonium that is strongly retained in 

the lung. This type of plutonium is also known as Type SS plutonium. The methods described 

in Section 4.0 of ORAUT-OTIB-0049 and Attachment D were used to modify the plutonium and 

americium doses from CADW based on a 5-year chronic intake. Table I-5 shows the isotopic 

doses from CADW, the dose adjustment and chest count adjustment factors from Attachment D, 

yearly fraction to account for partial year exposure in [redacted] and [redacted] (since CADW 

only calculates whole year doses), and the total adjusted dose. The total dose from intakes of 

plutonium and americium was 38.676 rem. 

Table I-5. OTIB-0049 Adjusted Doses

[**]

Isotopic Dose (rem) Total 

Dose 

(rem)

Dose 

Adj. 

Factor

OTIB-49

Adj.

Dose

*Chest

Count 

Adj. 

Factor

Annual

Adj.

Dose

Frac. 

of 

Year

Total 

Adj. 

Dose 

(rem)

Pu-239 Pu-238 Pu-241 Am-241

1.408E+00 3.891E-02 1.918E-03 7.821E-02 1.527 1.6 2.443 2.6 0.9398 0.175 0.165

1.844E+00 5.045E-02 5.079E-03 1.015E-01 2.001 1.9 3.803 2.6 1.4625 1.000 1.463

2.055E+00 5.586E-02 9.050E-03 1.124E-01 2.232 2.1 4.688 2.6 1.8031 1.000 1.803

2.210E+00 5.978E-02 1.329E-02 1.204E-01 2.403 2.4 5.767 2.6 2.2182 1.000 2.218

2.325E+00 6.269E-02 1.741E-02 1.265E-01 2.532 2.6 6.582 2.6 2.5316 1.000 2.532

2.417E+00 6.499E-02 2.125E-02 1.312E-01 2.634 3.5 9.219 2.6 3.5458 0.532 1.885

1.075E+00 2.771E-02 2.284E-02 5.639E-02 1.181 4.5 5.317 2.6 2.0448 0.625 1.277

6.966E-01 1.761E-02 2.290E-02 3.617E-02 0.773 5.7 4.408 2.6 1.6954 1.000 1.695

5.286E-01 1.324E-02 2.190E-02 2.740E-02 0.591 6.9 4.079 2.6 1.5688 1.000 1.569

4.117E-01 1.023E-02 2.040E-02 2.130E-02 0.464 8.2 3.802 2.6 1.4622 1.000 1.462

3.289E-01 8.109E-03 1.883E-02 1.698E-02 0.373 9.6 3.579 2.6 1.3764 1.000 1.376

2.697E-01 6.598E-03 1.740E-02 1.391E-02 0.308 11 3.384 2.6 1.3016 1.000 1.302

2.266E-01 5.494E-03 1.617E-02 1.166E-02 0.260 12 3.119 2.6 1.1995 1.000 1.200

1.942E-01 4.672E-03 1.511E-02 9.985E-03 0.224 13 2.912 2.6 1.1200 1.000 1.120

1.693E-01 4.039E-03 1.420E-02 8.692E-03 0.196 15 2.944 2.6 1.1323 1.000 1.132

1.499E-01 3.546E-03 1.342E-02 7.685E-03 0.175 16 2.792 2.6 1.0739 1.000 1.074

1.342E-01 3.151E-03 1.274E-02 6.871E-03 0.157 17 2.668 2.6 1.0263 1.000 1.026

1.212E-01 2.822E-03 1.212E-02 6.199E-03 0.142 18 2.562 2.6 0.9855 1.000 0.986

1.102E-01 2.546E-03 1.154E-02 5.625E-03 0.130 20 2.598 2.6 0.9991 1.000 0.999

1.007E-01 2.309E-03 1.101E-02 5.136E-03 0.119 21 2.503 2.6 0.9625 1.000 0.963

9.248E-02 2.104E-03 1.050E-02 4.710E-03 0.110 23 2.525 2.6 0.9712 1.000 0.971

8.513E-02 1.921E-03 1.001E-02 4.329E-03 0.101 24 2.434 2.6 0.9360 1.000 0.936

7.851E-02 1.758E-03 9.535E-03 3.988E-03 0.094 26 2.439 2.6 0.9379 1.000 0.938

7.257E-02 1.613E-03 9.076E-03 3.681E-03 0.087 27 2.347 2.6 0.9028 1.000 0.903

6.719E-02 1.481E-03 8.635E-03 3.405E-03 0.081 29 2.341 2.6 0.9002 1.000 0.900

6.226E-02 1.361E-03 8.203E-03 3.150E-03 0.075 31 2.324 2.6 0.8939 1.000 0.894

5.770E-02 1.251E-03 7.782E-03 2.917E-03 0.070 33 2.298 2.6 0.8840 1.000 0.884
Effective Date:

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Table I-5. OTIB-0049 Adjusted Doses

[**]

Isotopic Dose (rem) Total 

Dose 

(rem)

Dose 

Adj. 

Factor

OTIB-49

Adj.

Dose

*Chest

Count 

Adj. 

Factor

Annual

Adj.

Dose

Frac. 

of 

Year

Total 

Adj. 

Dose 

(rem)

Pu-239 Pu-238 Pu-241 Am-241

5.355E-02 1.151E-03 7.378E-03 2.705E-03 0.065 35 2.267 2.6 0.8720 1.000 0.872

4.974E-02 1.061E-03 6.991E-03 2.508E-03 0.060 37 2.231 2.6 0.8581 1.000 0.858

4.622E-02 9.774E-04 6.617E-03 2.327E-03 0.056 39 2.189 2.6 0.8421 1.000 0.842

4.294E-02 9.006E-04 6.255E-03 2.161E-03 0.052 41 2.142 2.6 0.8240 1.000 0.824

3.994E-02 8.312E-04 5.912E-03 2.007E-03 0.049 43 2.094 2.6 0.8052 1.000 0.805

3.718E-02 7.674E-04 5.586E-03 1.866E-03 0.045 46 2.088 2.6 0.8032 1.000 0.803

38.676

* The dose is divided by the Chest Count Adjustment Factor. 

[**] [The dates in this column have been redacted.]

I.3.2 Dose from Tritium 

The EE submitted three bioassay samples that were analyzed for tritium. Using those results, a 

chronic tritium intake was calculated for the time period of [redacted]– [redacted]. The tritium 

intake rate was calculated to be 1,150 pCi/day, and the total dose was <0.001 rem. Therefore, 

the doses from the tritium intakes were not included in the IREP table.

I.3.2 Environmental Dose 

Since the EE’s bioassay data were used to assess internal dose for the EE’s major employment 

period, no additional environmental dose was calculated. 

I.4 DOSE FROM RADIOLOGICAL INCIDENTS 

SC&A reviewed the EE’s DOE records to determine if the EE was involved in any radiological 

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

The EE submitted urine, fecal, and nasal samples in response to a possible [redacted] incident 

due to [redacted] on [redacted]. A urine sample, fecal sample, and chest count were taken on the 

same date as the nasal smear and analyzed for plutonium. The results of the analyses did not 

indicate any uptake of plutonium or uranium. No additional dose was assigned from radiological 

incidents. 

I.5 SUMMARY CONCLUSIONS 

The EE worked at the RFP facility from [redacted] through [redacted] and from [redacted]

through [redacted]. During that time, the EE was monitored for exposure to external and

internal radiation. The EE was diagnosed with lung cancer in [redacted]. The DR derived a 

total external and internal dose of 41.914 rem to the lung. The total POC for the primary lung

cancer was calculated using the NIOSH-IREP (v.5.7) and determined to be 73.54%.
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

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

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I.6 REFERENCES 

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

International Commission on Radiological Protection, ICRP 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), 1994, 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-0049. 2010. Technical Information Bulletin: Estimating Doses for Plutonium 

Strongly Retained in the Lung, Rev. 01 PC-2, Oak Ridge Associated Universities, Cincinnati, 

Ohio. November 29, 2010. 

ORAUT-PROC-0060. 2006. Occupational On-Site Ambient Dose Reconstruction for DOE 

Sites, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, Ohio. June 28, 2006. 

ORAUT-TKBS-0011-3. 2007. Technical Basis Document for the Rocky Flats Plant –

Occupational Medical Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. April 23, 2007.

ORAUT-TKBS-0011-5. 2007. Technical Basis Document for the Rocky Flats Plant –

Occupational Internal Dose, Rev. 02, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. August 17, 2007. 

ORAUT-TKBS-0011-6. 2010. Technical Basis Document for the Rocky Flats Plant –

Occupational External Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. October 20, 2010. 
Effective Date:

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APPENDIX I-A: IREP INPUT – LUNG 

EXPOSURE 

INFORMATION

Number of 

exposures

109

Exposure #

Exposure 

Year

Exposure 

Rate Radiation Type

Dose 

Distribution 

Type

Parameter 

1

Parameter 

2

Parameter 

3

1 [redacted] Acute photons E=30–250keV Constant 0.441 0.000 0.000

2 [redacted] Acute photons E=30–250keV Constant 0.233 0.000 0.000

3 [redacted] Acute photons E=30–250keV Constant 0.351 0.000 0.000

4 [redacted] Acute photons E=30–250keV Constant 0.326 0.000 0.000

5 [redacted] Acute photons E=30–250keV Constant 0.059 0.000 0.000

6 [redacted] Acute photons E=30–250keV Constant 0.031 0.000 0.000

7 [redacted] Chronic neutrons E<10keV Constant 0.002 0.000 0.000

8 [redacted] Chronic neutrons E<10keV Constant 0.028 0.000 0.000

9 [redacted] Chronic neutrons E<10keV Constant 0.007 0.000 0.000

10 [redacted] Chronic neutrons E<10keV Constant 0.026 0.000 0.000

11 [redacted] Chronic neutrons E<10keV Constant 0.017 0.000 0.000

12 [redacted] Chronic neutrons E<10keV Constant 0.013 0.000 0.000

13 [redacted] Chronic neutrons E<10keV Constant 0.008 0.000 0.000

14 [redacted] Chronic neutrons E=10–100keV Constant 0.000 0.000 0.000

15 [redacted] Chronic neutrons E=10–100keV Constant 0.006 0.000 0.000

16 [redacted] Chronic neutrons E=10–100keV Constant 0.001 0.000 0.000

17 [redacted] Chronic neutrons E=10–100keV Constant 0.005 0.000 0.000

18 [redacted] Chronic neutrons E=10–100keV Constant 0.004 0.000 0.000

19 [redacted] Chronic neutrons E=10–100keV Constant 0.003 0.000 0.000

20 [redacted] Chronic neutrons E=10–100keV Constant 0.002 0.000 0.000

21 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.012 0.000 0.000

22 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.187 0.000 0.000

23 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.048 0.000 0.000

24 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.171 0.000 0.000

25 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.120 0.000 0.000

26 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.092 0.000 0.000

27 [redacted] Chronic neutrons E=100keV–2MeV Constant 0.061 0.000 0.000

28 [redacted] Chronic neutrons E=2–20MeV Constant 0.006 0.000 0.000

29 [redacted] Chronic neutrons E=2–20MeV Constant 0.086 0.000 0.000

30 [redacted] Chronic neutrons E=2–20MeV Constant 0.022 0.000 0.000

31 [redacted] Chronic neutrons E=2–20MeV Constant 0.078 0.000 0.000

32 [redacted] Chronic neutrons E=2–20MeV Constant 0.054 0.000 0.000

33 [redacted] Chronic neutrons E=2–20MeV Constant 0.041 0.000 0.000

34 [redacted] Chronic neutrons E=2–20MeV Constant 0.027 0.000 0.000

35 [redacted] Acute photons E<30keV Constant 0.002 0.000 0.000

36 [redacted] Acute photons E<30keV Constant 0.002 0.000 0.000

37 [redacted] Acute photons E<30keV Constant 0.005 0.000 0.000

38 [redacted] Acute photons E<30keV Constant 0.003 0.000 0.000

39 [redacted] Acute photons E<30keV Constant 0.005 0.000 0.000

40 [redacted] Acute photons E<30keV Constant 0.002 0.000 0.000

41 [redacted] Acute photons E=30–250keV Lognormal 0.010 1.520 0.000

42 [redacted] Acute photons E=30–250keV Lognormal 0.010 1.520 0.000

43 [redacted] Acute photons E=30–250keV Lognormal 0.010 1.520 0.000
Effective Date:

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Revision No.

0 (Draft)

Document No. 

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Appendix I-A: IREP Input – Lung (continued) 

44 [redacted] acute photons E=30–250keV Lognormal 0.010 1.520 0.000

45 [redacted] acute photons E=30–250keV Lognormal 0.007 1.520 0.000

46 [redacted] chronic neutrons E<10keV Lognormal 0.006 1.520 0.000

47 [redacted] chronic neutrons E<10keV Lognormal 0.008 1.520 0.000

48 [redacted] chronic neutrons E<10keV Lognormal 0.005 1.520 0.000

49 [redacted] chronic neutrons E<10keV Lognormal 0.005 1.520 0.000

50 [redacted] chronic neutrons E<10keV Lognormal 0.003 1.520 0.000

51 [redacted] chronic neutrons E<10keV Lognormal 0.002 1.520 0.000

52 [redacted] chronic neutrons E=10–100keV Lognormal 0.001 1.520 0.000

53 [redacted] chronic neutrons E=10–100keV Lognormal 0.002 1.520 0.000

54 [redacted] chronic neutrons E=10–100keV Lognormal 0.001 1.520 0.000

55 [redacted] chronic neutrons E=10–100keV Lognormal 0.001 1.520 0.000

56 [redacted] chronic neutrons E=10–100keV Lognormal 0.001 1.520 0.000

57 [redacted] chronic neutrons E=10–100keV Lognormal 0.000 1.520 0.000

58 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.038 1.520 0.000

59 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.053 1.520 0.000

60 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.030 1.520 0.000

61 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.035 1.520 0.000

62 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.023 1.520 0.000

63 [redacted] chronic neutrons E=100keV–2MeV Lognormal 0.012 1.520 0.000

64 [redacted] chronic neutrons E=2–20MeV Lognormal 0.017 1.520 0.000

65 [redacted] chronic neutrons E=2–20MeV Lognormal 0.024 1.520 0.000

66 [redacted] chronic neutrons E=2–20MeV Lognormal 0.014 1.520 0.000

67 [redacted] chronic neutrons E=2–20MeV Lognormal 0.016 1.520 0.000

68 [redacted] chronic neutrons E=2–20MeV Lognormal 0.010 1.520 0.000

69 [redacted] chronic neutrons E=2–20MeV Lognormal 0.005 1.520 0.000

70 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

71 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

72 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

73 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

74 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

75 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

76 [redacted] acute photons E=30–250keV Normal 0.042 0.013 0.000

77 [redacted] chronic alpha Lognormal 0.165 3.000 0.000

78 [redacted] chronic alpha Lognormal 1.463 3.000 0.000

79 [redacted] chronic alpha Lognormal 1.803 3.000 0.000

80 [redacted] chronic alpha Lognormal 2.218 3.000 0.000

81 [redacted] chronic alpha Lognormal 2.532 3.000 0.000

82 [redacted] chronic alpha Lognormal 1.885 3.000 0.000

83 [redacted] chronic alpha Lognormal 1.277 3.000 0.000

84 [redacted] chronic alpha Lognormal 1.695 3.000 0.000

85 [redacted] chronic alpha Lognormal 1.569 3.000 0.000

86 [redacted] chronic alpha Lognormal 1.462 3.000 0.000

87 [redacted] chronic alpha Lognormal 1.376 3.000 0.000

88 [redacted] chronic alpha Lognormal 1.302 3.000 0.000

89 [redacted] chronic alpha Lognormal 1.200 3.000 0.000

90 [redacted] chronic alpha Lognormal 1.120 3.000 0.000

91 [redacted] chronic alpha Lognormal 1.132 3.000 0.000

92 [redacted] chronic alpha Lognormal 1.074 3.000 0.000

93 [redacted] chronic alpha Lognormal 1.026 3.000 0.000
Effective Date:

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Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

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Appendix I-A: IREP Input – Lung (continued) 

94 [redacted] chronic alpha Lognormal 0.986 3.000 0.000

95 [redacted] chronic alpha Lognormal 0.999 3.000 0.000

96 [redacted] chronic alpha Lognormal 0.963 3.000 0.000

97 [redacted] chronic alpha Lognormal 0.971 3.000 0.000

98 [redacted] chronic alpha Lognormal 0.936 3.000 0.000

99 [redacted] chronic alpha Lognormal 0.938 3.000 0.000

100 [redacted] chronic alpha Lognormal 0.903 3.000 0.000

101 [redacted] chronic alpha Lognormal 0.900 3.000 0.000

102 [redacted] chronic alpha Lognormal 0.894 3.000 0.000

103 [redacted] chronic alpha Lognormal 0.884 3.000 0.000

104 [redacted] chronic alpha Lognormal 0.872 3.000 0.000

105 [redacted] chronic alpha Lognormal 0.858 3.000 0.000

106 [redacted] chronic alpha Lognormal 0.842 3.000 0.000

107 [redacted] chronic alpha Lognormal 0.824 3.000 0.000

108 [redacted] chronic alpha Lognormal 0.805 3.000 0.000

109 [redacted] chronic alpha Lognormal 0.803 3.000 0.000
Effective Date:

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Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

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SECTION II: DR–METHOD B 

II.1 DOSE RECONSTRUCTION OVERVIEW

This report presents a blind dose reconstruction (DR) for a claimant that worked at the Rocky 

Flats Plant (RFP) and was later diagnosed with lung cancer. This worker was monitored under 

an external and internal monitoring program. 

Our investigation evaluated recorded and unmonitored external photon dose, potential external 

neutron exposures, occupational medical dose, and missed internal dose from exposures to 

plutonium, americium, and depleted uranium (DU). The following table summarizes our 

estimate of the worker’s lung dose from the annual doses presented in Appendix II-A, which is 

used as input to the NIOSH-Interactive RadioEpidemiological Program (IREP) to derive the 

probability of causation (POC). 

Table II-1. Assigned Dose for Case #[redacted]

Radiation Type Appendix II-A Exposure No. Lung Dose

(rem)

Recorded photon 1–12 1.569

Missed photon 13–17 0.038

Unmonitored photon 18–27 0.677

Recorded neutron 28–51 1.107

Unmonitored neutron 52–71 0.521

Missed neutron 72–97 0.324

Occupational medical 98–104 0.294

Missed plutonium 105–136 55.650

Missed americium 137–169 1.464

Missed depleted uranium 170–202 10.300

Total 71.944

We calculated a dose of 71.944 rem to the lung and derived a POC of 55.75%.

II.1.1 Introduction 

The approach used by SC&A to perform this blind DR began with developing an understanding 

of the work history of this worker, vis-à-vis the types of activities that were ongoing in different 

buildings and time periods at RFP. This was accomplished by reviewing the totality of the 

worker’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 worker 

might have experienced each year of employment at RFP. Once we were able to develop a rich 

understanding of this worker’s occupational/radiological exposure history, we compiled all the 

information available that would help us reconstruct the worker’s exposure for each year of 

employment at RFP. This information included the EE’s personnel dosimetry and bioassay 

records (including urine samples and chest counts) and air sampling and other data that might 

help to characterize the internal and external radiation exposures this worker might have 

experienced. An attempt was then made to develop the input sheets to IREP that we believe 
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places a plausible but realistic upper bound on the annual exposures that the worker might have 

experienced to the organ of concern up to the time of cancer diagnosis. The IREP input was then 

used to derive the POC for this worker. 

II.1.2 Relevant Background Information 

According to the DOL records, this case involves an EE who worked at the RFP as a [redacted]

from [redacted], to [redacted], and then again from [redacted], through [redacted]. On 

[redacted], the EE was diagnosed with lung cancer (squamous cell, ICD Code 162.9). The 

worker describes the EE as a [redacted].

According to the DOL forms filed by this worker, the EE was a [redacted]. The EE states the 

following regarding the EE’s job responsibilities:

[This section redacted in full.]

The DOL forms indicate the following: 

 The EE occasionally wore self-contained breathing apparatus (SCBA) when [redacted]

 The EE always carried a face mask with filter cartridges and wore it when necessary 

 The EE often wore a disposable mask 

 The EE wore a full protective suit, radiation monitoring badge, and pocket dosimeter 

every day 

 The EE worked with cesium, californium, cobalt machine, plutonium, polonium, tritium, 

uranium, and x-ray machines 

 The EE was never involved in a major accident 

 The EE had numerous urine samples collected 

The administrative record for this worker indicates that DOE provided internal and external 

dosimetry records, diagnostic x-ray records, and incident investigation reports for this worker, 

which included cuts and bruises. The DOE records also provided a tabulation of the type of 

work activities that this worker might have been involved in as a [redacted] and worked in 

Building [redacted]. Many of these activities are relevant to exposures to non-radioactive toxic 

and hazardous chemicals, but also include exposure to plutonium, weapons component packing, 

and radiography. 

II.1.3 Radiation Incidents

The worker’s DOE records indicate that the EE may have been involved in an incident on 

[redacted]. The EE experienced a [redacted]. This incident is well documented in the DOE 

records. Immediately following the incident, the EE was given a nasal smear and had a 

urinalysis bioassay, a fecal bioassay, and a lung count. ORAUT-TKBS-0011-5 discusses how 

individuals were monitored at RFP following an incident. 
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Nasal smear (later called swab) and fecal sample data were occasionally 

obtained throughout RFP operations as supplemental data for workers with 

actual or suspected significant inhalation intakes. Through the 1980s, they were 

used subjectively to verify that an intake did occur and to estimate the possible 

magnitude of the intake. The data have also been used to determine or confirm 

the ppm 241Am in the inhaled plutonium mixture. 

The EE was given follow-up body counts on [redacted]; [redacted]; and [redacted]. The lung 

counts tested for exposure to plutonium/americium as well as uranium/thorium. An incident 

report dated [redacted], stated the following:

This letter is to inform you of the results of the bioassay studies carried out by 

Radiation Dosimetry following the incident [redacted].

The urine sample received following the incident indicated no significant increase 

in your plutonium systemic burden. 

The nasal sample contained 45.7 dpm of plutonium and 0.481 dpm of americium. 

These values are of little significance and do not indicate that a significant 

amount of plutonium was [redacted].

Our primary method to assess the deposition of plutonium in your lungs is the 

body counter. Your initial body count and the recounts on [redacted], 

[redacted], and [redacted] were background, indicating no detectable activity in 

your lungs. 

Our conclusion is that no increase in your systemic or lung burden occurred as a 

result of this incident. 

All of the test results following the incident were below the limit of detection (LOD). The 

internal dose assessment using these results is discussed below in the internal dose section. 

II.2 EXTERNAL DOSE 

II.2.1 Completeness and Reliability of External Dosimetry Records 

The administrative record for this worker indicates that the EE was monitored for external 

exposures under what appears to be a monthly external dosimetry program for the EE’s entire 

employment at RFP. Exhibit II-1 presents the external dosimetry data provided by DOE for this 

worker. 
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Exhibit II-1. External Dosimetry Records for Case #[redac

II.2.2 Reliability of Methods Used to Reconstruct Neutron Exposures 

The RFP TBD for external dosimetry (ORAUT-TKBS-0011-6) describes the neutron monitoring 

program. Prior to 1971, NTA film was used to monitor for neutron exposure, but that method 

was problematic. Section 6.7.3.3 of the TBD describes the Neutron Dose Reconstruction Project 

(NDRP) that was started at RFP to determine neutron exposures to workers prior to 1971. 

For this case, it is not necessary for us to address the NDRP data, since the EE began work at 

RFP in [redacted]. Therefore, we refer to Section 6.7.3.1 of the TBD, which describes the 

neutron dosimetry used at RFP beginning in 1971. 

In 1971, RFP started using an albedo neutron TLD. Documentation of the 

research performed to develop this dosimeter (Falk 1971) indicates a practical 

lower neutron dose limit of 10 to 20 mrem in the presence of a photon dose as 
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high as 100 mrem. The upper limit of this estimate was selected as the LOD for 

this dosimeter. 

In 1983, the Panasonic UD-809 dosimeter was introduced at RFP to measure 

neutrons. Data are not available on the LOD for this dosimeter system. Because 

the hardware is the same as that used in 1990, it was assumed to be similar to 

performance of the system at that time. The assumed LOD is 32 mrem. 

In 1990, an algorithm update was incorporated in the Panasonic dosimetry 

system (Stanford 1990). The documentation cites a minimum detectable neutron 

dose of 15 to 32 mrem for a moderated 252Cf source. 

SC&A’s method for calculating neutron dose is described in detail below. 

The RFP TBD provides an extensive discussion of the recommended International Commission 

on Radiological Protection (ICRP) weighting factors for assignment of neutron dose. Table 6-17 

of ORAUT-TKBS-0011-6 is reproduced here as Table II-2. 

The doses and fractions discussed above are based on quality factors published in 

NCRP (1971). NIOSH (2007) [OCAS-IG-001] indicates the use of radiation 

weighting factors from ICRP Publication 60 (ICRP 1991). To perform this 

correction, the neutron energy deposition values in rad for each energy were 

multiplied by the ICRP radiation weighting factor to determine the corrected dose 

equivalent. These values were totaled for each neutron energy interval used in 

this dose reconstruction and compared with the value determined previously 

using quality factors from NCRP (1971). Column 3 of Table 6-17 lists the 

multipliers that were determined for each neutron energy interval. The fraction 

of the dose using NCRP (1971) quality factors and the dose multiplier using ICRP 

(1991) radiation weighting factors were combined to determine a dose multiplier 

(column 4 of Table 6-17). The neutron dose reported in the worker's dose record 

should be multiplied by these factors to determine the ICRP (1991) neutron dose 

for each neutron energy interval. 

Table II-2. Default Neutron Energy Distribution for RFP 

Neutron energy intervals Fraction of dose (NCRP 38) Dose multiplier (ICRP 60) Dose multiplier (a)

<10 keV 0.035 2.13 0.0755

10–100 keV 0.017 1.86 0.0309

0.1–2 MeV 0.687 1.91 1.31

2–20 MeV 0.261 1.32 0.345

>20 MeV 0 none None

(a) Multiply the reported dose by these factors to determine the ICRP 60 neutron dose for each neutron energy 

interval. 

Source: ORAUT-TKBS-0011-6, Table 6-17
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II.2.3 Reconstruction of External Doses 

SC&A thoroughly reviewed the dosimetry records for Case #[redacted] and found that this EE 

was monitored for external photon and neutron exposures through most of the EE’s employment. 

These records, along with the RFP external dose TBD (ORAUT-TKBS-0011-6) and the External 

Dose Reconstruction Implementation Guideline (OCAS-IG-001), were used to reconstruct the 

external doses for this case. The DR includes an assessment of recorded and missed photon 

dose, recorded and missed neutron dose, unmonitored photon and neutron dose, and occupational 

medical dose. Table II-3 is a summary of the assigned doses and Appendix II-A presents the 

IREP input values used to determine the POC. The assigned external doses totaled 4.529 rem to 

the lung for this case.

Table II-3. Assigned External Doses for Case #[redacted]

Radiation Type Appendix II-A Exposure No. Lung Dose (rem)

Recorded photon 1–12 1.569

Missed photon 13–17 0.038

Unmonitored photon 18–27 0.677

Recorded neutron 28–51 1.107

Unmonitored neutron 52–71 0.521

Missed neutron 72–97 0.324

Occupational medical 98–04 0.293

Total 4.529

Table II-4 lists the external dose parameters used to calculate doses. The default photon energy 

distributions at RFP are listed in Table 6-10 of ORAUT-TKBS-0011-6, and the default neutron 

energy distributions and ICRP CFs are listed in Table 6-17. These parameters are discussed in 

detail below. 

Table II-4. External DR Parameters for Case #[redacted]

Photons Neutrons

<30 keV 30–250 keV <10 keV 10–100 keV 0.1–2 MeV 2–20 MeV

Energy fraction 25% 75% 3.5% 1.7% 68.7 % 26.1%

Organ DCFs 1979–1982

(R to Organ dose)

0.03 1.13 1.523 0.751 0.579 1.004

Organ DCFs 1983–1985

(Hp10 to Organ dose)

0.05 0.8 1.332 0.737 0.557 0.95

ICRP correction factor NA NA 2.13 1.86 1.91 1.32

II.2.3.1 Recorded Photon Dose 

The EE was monitored on a monthly and quarterly basis for external exposure to photons with 

thermoluminescent dosimeters (TLDs). If the EE had positive readings above the LOD for each 

exchange period, it is not necessary to assign missed photon dose. The recorded photon doses 

were calculated using the energy fractions and DCFs listed in Table II-4, along with dosimeter 
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uncertainty factors discussed below. The assignment of claimant-favorable DCFs is 

complicated. Table 6-11 of ORAUT-TKBS-0011-6 indicates that for the time [redacted] 

through [redacted], the Exposure (R) to organ DCF should be used based on the types of 

dosimeters used at the time. For the period [redacted] to [redacted], the Hp(10) to organ DCFs 

should be used based on the use of specific TLDs at RFP. For low-energy photons (<30 keV 

photons), NIOSH recommends using the plutonium-specific DCFs listed in Table 4.1a of OCASIG-001 for plutonium exposures at RFP. For the lung, those DCFs are 0.030 for the exposure 

(R) to organ dose and 0.050 for the Hp(10) to organ dose. 

For the 30–250 keV photon DCFs, the procedures in OCAS-IG-001 recommend that the 

rotational or isometric DCFs be used for the lung, as opposed to the anterior-posterior (AP)

DCFs. Page 39 of OCAS-IG-001 states the following: 

The AP DCF values in Appendix A are not the most claimant favorable for bone 

(surface), bone (red marrow), esophagus, and lung when the dosimeter is worn on 

the chest. For these organs, if the dosimeter is worn on the chest, multiply the 

Appendix A values of ROT [rotational] and ISO [idometric] by the factors in Table 

4.1a instead of using the AP value. In these cases, the ROT or ISO geometries 

are more claimant favorable than the AP value in Appendix A. However, the 

correction factors need not be applied if it is determined that the most 

representative geometry is 100% AP or other compensating claimant[-]favorable 

determinations have been made in dose reconstruction. 

In order to calculate the recorded photon doses, the measured values were multiplied by the 

rotational DCFs from Appendix A of OCAS-IG-001, along with the CFs for those DCFs in 

Table 4.1a of OCAS-IG-001. It should be noted that there are two tables labeled Table 4.1a on 

pages 38 and 39 of OCAS-IG-001. The first one pertains to plutonium-specific DCFs and the 

second table lists CFs for ROT and ISO DCFs. Table II-5 lists the lung DCFs derived from 

those values. SC&A used the ROT DCFs of 1.13 and 0.800 in this case, because this would be 

the EE’s most likely geometry relative to the radiation sources.

Table II-5. Lung Dose Conversion Factors (30–250 keV) 

AP ROT (Exp) ROT (Hp 10) ISO (Exp) ISO (Hp 10)

Lung DCF (OCAS-IG-001) 0.695 0.779 0.552 0.625 0.441

Correction factor NA 1.45 1.45 1.58 1.58

Adjusted lung DCF 0.695 1.13 0.800 0.988 0.697

In addition, the TBD provides dosimeter uncertainty factors. Table II-6 below summarizes those 

uncertainty factors from pages 42 and 43 of ORAUT-TKBS-0011-6. 

Table II-6. Photon Dosimeter Uncertainty Factors for RFP 

Dates Photon Dosimeter Uncertainty Factor

1969–1982 (Readings under 100 mrem) 2

1969–1982 (Readings over 100 mrem) 1.26

1983–1998 1.23
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These factors were used to calculate the photon doses for this DR. An example of SC&A’s 

calculations is given below for the year [redacted].

For [redacted], the EE had recorded readings (above LOD/2) for shallow dose of 0.790 rem, 

deep dose of 0.447 rem, and neutron dose of 0.247 rem.

Calculated photon dose to the lung = 0.447 rem * energy fraction * DCF * UF

Calculated <30 keV photon dose to the lung = 0.447 * 0.25 * 0.030 * 1.26 = 0.004 rem 

Calculated 30–250 keV photon dose to the lung = 0.447 *0.75* 1.13 * 1.26 = 0.477 rem 

SC&A calculated 1.569 rem to the lung for the years [redacted] through [redacted], as cited in 

entries #1–#12 of Appendix II-A. These values are entered with a constant distribution with no 

uncertainty because of the use of the uncertainty factor in deriving the dose.

II.2.3.2 Missed Photon Dose 

The EE had photon readings that were below the LOD/2 value. For each of those instances, 

SC&A assigned missed photon dose. The missed photon doses are calculated by multiplying the 

number of zero readings by the LOD/2 value for the dosimeter, the energy fraction, and organ 

DCFs. 

An example of SC&A missed dose calculation is provided below for [redacted].

For [redacted], there is 1 zero reading for photons:

Missed photon dose = # of zeroes * LOD/2 * energy fraction * DCF 

Calculated <30 keV missed photon dose = 1 zero * 0.010 rem * 0.25* 0.030 = 0.0001 rem 

Calculated 30–250 keV missed photon dose = 1 zero *0.010 rem * 0.75* 1.13 = 0.008 rem 

SC&A calculated 0.038 rem to the lung for the years [redacted] through [redacted], as cited in 

entries #13–#17 of Appendix II-A. These values are entered as the geometric mean of a 

lognormal distribution with a geometric standard deviation (GSD) of 1.52. The total <30 keV 

missed dose was <0.001 rem, and as such, was not entered into the IREP Input tables.

II.2.3.3 Recorded/Assigned Neutron Dose 

DR–Method B determined that the EE had neutron readings from [redacted] through 

[redacted]. It is not clear from the procedures if the neutron doses measured by the TLDs in the 

1980s and 1990s at RFP are considered accurate measurements. At other DOE facilities, the 

TLD neutron readings are used to assign neutron doses in DRs. However, Table 6-22 of the RFP 

TBD (ORAUT-TKBS-0011-6) lists neutron-to-photon dose ratios. SC&A’s Method B decided 

to calculate the neutron doses using two methods and compare the results. First, the recorded 

TLD neutron readings were used to determine the neutron doses. The recorded neutron values 

are multiplied by the neutron energy fractions, which include the associated ICRP CFs, and the 

neutron DCFs for the lung. These parameters are listed here in Table II-4. Additional details 
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regarding the ICRP weighting factors are discussed below. An example of SC&A’s recorded 

neutron dose calculation is given below for [redacted].

In [redacted], the EE had a recorded neutron reading of 0.247 rem, which was >LOD/2.

Calculated neutron dose = 0.247 rem * ICRP CF * DCF 

<10 keV neutron dose = 0.247 rem * 0.0755 * 1.523 = 0.028 rem 

10–100 keV neutron dose = 0.247 rem * 0.0309 * 0.751 = 0.006 rem 

0.1–2 MeV neutron dose = 0.247 rem * 1.31 * 0.579 = 0.187 rem 

2–20 MeV neutron dose = 0.247 rem * 0.345 * 1.004 = 0.086 rem 

Using the recorded neutron values, SC&A calculated a total dose of 1.107 rem to the lung. 

Our second method of determining the neutron doses involved the neutron-to-photo dose ratios. 

These ratios were applied to the recorded photon doses, along with the energy fractions (which 

include the ICRP CFs) and organ DCFs. An example of SC&A’s derived neutron dose 

calculations is given below for [redacted].

In [redacted], the EE had a recorded photo dose of 0.447 rem:

Assigned neutron dose = 0.447 rem * ratio * ICRP CF * DCF 

<10 keV neutron dose = 0.447 rem * 0.43 * 0.0755 * 1.332 = 0.019 rem 

10–100 keV neutron dose = 0.447 rem * 0.43 * 0.0309 * 0.737 = 0.004 rem 

0.1–2 MeV neutron dose = 0.447 rem * 0.43 * 1.31 * 0.557 = 0.140 rem 

2–20 MeV neutron dose = 0.447 rem * 0.43 * 0.345 * 0.95 = 0.063 rem 

Using the neutron-to-photon dose ratios and the recorded photon values, SC&A calculated a total 

dose of 0.840 rem to the lung. The neutron doses calculated using the recorded values are 

slightly higher than those calculated using the neutron-to-photon dose ratio; therefore, the 

recorded neutron doses were included in the calculation of the POC. These values are entered as 

the mean of a normal distribution with a standard deviation of 30%. 

II.2.3.4 Missed Neutron Dose 

The EE did have some zero neutron readings during employment; therefore, SC&A decided it 

would be appropriate for a best-estimate DR to assign missed neutron dose. The missed neutron 

doses are calculated by multiplying the number of zero readings by the LOD/2 value for the 

dosimeter, along with the energy fractions, ICRP CFs, and organ DCFs. 

An example of SC&A missed dose calculation is provided below for [redacted].

For [redacted], there are 5 zero readings for neutrons:

Missed neutron dose = # of zeroes * LOD/2 * ICRP CF * DCF 

<10 keV neutron dose = 5 zeroes * 0.010 rem * 0.0755 * 1.523 = 0.006 rem 

10–100 keV neutron dose = 5 zeroes * 0.010 rem* 0.0309 * 0.751 = 0.001 rem 

0.1–2 MeV neutron dose = 5 zeroes * 0.010 rem* 1.31 * 0.579 = 0.038 rem 

2–20 MeV neutron dose = 5 zeroes * 0.010 rem* 0.345 * 1.004 = 0.017 rem 
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SC&A calculated a total dose of 0.324 rem to the lung for missed neutron dose, as cited in 

entries #72–#97 of Appendix II-A. These values are entered as a lognormal distribution with a 

GSD of 1.52. 

II.2.3.5 Unmonitored Dose 

SC&A assigned unmonitored doses for the years the EE was employed onsite at RFP, but did not 

have monitoring records. For some of these years, the EE was only employed for a few months 

of the year; therefore, the doses were prorated based on the number of working months. SC&A 

assigned unmonitored doses using the values from the plutonium coworker model in Table C-4 

of ORAUT-TKBS-0011-6. There were some months in the years [redacted], [redacted], 

[redacted], [redacted], and [redacted] where no dosimetry readings were recorded. Given this 

EE’s job duties and the amount of recorded dose the EE received, SC&A decided it would be 

claimant favorable to assign the 95th percentile values of the coworker model for the month the 

EE was not monitored. Table II-7 shows the calculations for unmonitored photon and neutron 

doses. The photon and neutron doses were then divided into the appropriate energy fractions 

listed in Table II-4 above. The assigned unmonitored photon dose totaled 0.677 rem, and the 

assigned unmonitored neutron dose totaled 0.521 rem. These values are entered as the mean of a 

normal distribution with a standard deviation of 30%. 

Table II-7. Unmonitored Doses 

Year # Months not 

monitored

Unmonitored CW Dose 

(rem)

Unmonitored Doses Prorated for Time 

(rem)

Photon Neutron Photon Neutron

[redacted] 1.1 0.638 0.268 0.058 0.025

[redacted] 2 0.600 0.252 0.100 0.042

[redacted] 4 0.854 0.359 0.285 0.120

[redacted] 2 0.848 0.356 0.141 0.059

[redacted] 6 0.917 0.385 0.459 0.193

Total: 15.1 1.043 0.438

The example calculation for the year [redacted] is given below:

Unmonitored photon dose = 0.917 rem * energy fraction * DCF * Time fraction 

<30 keV photon dose to the lung = 0.917 * 0.25 * 0.050 * (6/12) = 0.006 rem 

30–250 keV photon dose to the lung = 0.917 *0.75* 0.80 * (6/12) = 0.275 rem 

Unmonitored neutron dose = 0.385 rem * ICRP CF * DCF * Time fraction 

<10 keV neutron dose = 0.385 rem * 0.0755 * 1.332 * (6/12) = 0.019 rem 

10–100 keV neutron dose = 0.385 rem * 0.0309 * 0.737 * (6/12) = 0.004 rem 

0.1–2 MeV neutron dose = 0.385 rem * 1.31 * 0.557 * (6/12) = 0.140 rem 

2–20 MeV neutron dose = 0.385 rem * 0.345 * 0.95 * (6/12) = 0.063 rem 

SC&A calculated 0.677 rem to the lung from unmonitored photon dose, as cited in entries #18–

#27 of Appendix II-A. SC&A calculated 0.521 rem to the lung from unmonitored neutron dose, 

as cited in entries #52–#71 of Appendix II-A. These values are entered as the mean of a normal 

distribution with a standard deviation of 30%. 
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II.2.3.6 Occupational Medical Dose 

The EE had two documented x-ray exams in [redacted] and [redacted], both of which were 

conventional chest x-rays. The procedures in Attachment A of ORAUT-PROC-0061 

recommend that occupational medical dose be assigned for every year of employment at RFP. 

The procedures state that the x-ray doses should be assigned with the “Frequency per TBD Table 

3-1, or actual records if records indicate more procedures than Table 3-1.” SC&A assigned 

occupational medical dose from these exams using the values in Table 3-6 of ORAUT-TKBS0011-3. The doses are assigned as acute 30–250 keV photons as the mean of a normal 

distribution with 30% standard deviation. The occupational medical doses totaled 0.294 rem as 

cited in entries #98–#104 of Appendix II-A.

II.3 INTERNAL DOSE 

The EE was monitored for plutonium and americium via urinalysis bioassays during 

employment. As was previously mentioned, the EE was involved in an [redacted] incident on 

[redacted]. Immediately following the incident, the EE was given a nasal smear and had a 

urinalysis bioassay, a fecal bioassay, and a lung count. The EE was given follow-up body counts 

on [redacted]; [redacted]; and [redacted]. In addition, the EE was given lung counts, which 

were assessed for exposure to plutonium/americium as well as uranium/thorium. All of the 

bioassays and lung count results were below the minimum detectable activity (MDA) and 

considered normal. The internal doses from [redacted] plutonium are particularly important in 

this case, since the EE was diagnosed with lung cancer. Internal dose from inhalation of 

plutonium represents the majority of the assigned dose for this case. SC&A’s Method B

performed internal dose assessments using results from each of these internal monitoring 

methods. A comparison of these results was made, and the doses that were considered the most 

scientifically sound and claimant favorable were used to determine the POC for this case, as 

described in Sections II.3.1 through II.3.5 below. 

II.3.1 Missed Plutonium Dose using the In-Vitro Urinalysis Bioassay Data 

The EE had several urinalysis bioassays for plutonium during employment, all of which were 

below the MDA. Those results are reproduced here as Table II-8. 

Table II-8. Plutonium/Americium Bioassay Results for Case #[redacted]

Date of bioassay Type Radionuclide Result (dpm/24hr)

[redacted] urinalysis P 0 <MDA

[redacted] urinalysis P 0 <MDA

[redacted] urinalysis A

P

0.01

0.03

<MDA

<MDA

[redacted] urinalysis P 0.01 <MDA

[redacted] urinalysis A

P

0.01

0

<MDA

<MDA

[redacted] urinalysis P 0.04 <MDA

[redacted] urinalysis A 0 <MDA

Table 5-5 of ORAUT-TKBS-0011-5 lists the MDA as 0.24 dpm/24 hour. The urinalysis 

bioassays measured the combination of Pu-239+240, but the IMBA program separates these 
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isotopes. We used the isotopic fractions of alpha activity in weapons-grade plutonium listed in 

Table 5-1 of ORAUT-TKBS-0011-5 and applied them to the 1⁄2 MDA value. These values were 

used as input into the IMBA program in order to derive the intakes and doses from chronically 

inhaled plutonium. We used the last plutonium bioassay result from [redacted], and assumed 

Type S absorption, since this would be claimant favorable in cases involving the lung. IMBA 

was used to calculate the chronic intakes from the first to the last day of employment. Those 

calculated intakes are listed below in Table II-9. Those intakes were then used to calculate the 

doses to the lung for each year until the date of diagnosis. According to the procedures in 

ORAUT-OTIB-0049, Estimating Doses for Plutonium Strongly Retained in the Lung, this 

employee had the potential for exposure to highly insoluble Super S plutonium. The doses from 

bioassay results are multiplied by 4 to estimate the dose from Super S plutonium. The dose to 

the lung from missed plutonium totaled 298 rem. However, this dose was not entered into the 

IREP Input table because the lung count data (which represents a more direct bioassay method) 

was used as described in a later section. 

Table II-9. Plutonium Intakes and Doses Calculated from Bioassay Results 

Isotope Absorption Type Fraction of Weapons

Grade Pu (WGP)

Excreted bioassay rate

(dpm/24 hr) Intake (dpm/d) Dose (rem)

Pu-238 Type S 0.023 0.0028 10.72 2.24

Pu-239 Type SS 0.8 0.098 369 280

Pu-240 Type S 0.18 0.022 82.88 15.8

II.3.2 Missed Americium Dose using the In-Vitro Urinalysis Bioassay Data 

The EE had several urinalysis bioassays for americium during the RFP employment period, all of 

which were below the MDA of 0.31 dpm/24hour (ORAUT-TKBS-0011-5, Table 5-6). The 1⁄2 

MDA value was used as input in the IMBA program in order to derive the doses from 

chronically inhaled americium. Method B used the last americium bioassay result from 

[redacted], and assumed Type S absorption, since this would be claimant favorable in cases 

involving the lung. IMBA was used to calculate the chronic intakes from the first day of 

employment to the last date of employment. The calculated intake is 12.87 dpm/d, which results 

in 2.730 rem to the lung. However, this dose was not entered into the IREP Input table, because 

the lung count data (which represents a more direct bioassay method) was used as described in a 

later section. 

II.3.3 Missed Plutonium Dose using Lung Count Results

SC&A also calculated missed plutonium dose using the lung count results. All of the results 

were below the MDA. SC&A’s Method B chose to assign missed dose using the lung count 

taken on [redacted]. It is usually claimant favorable to calculate missed intake using the MDA 

value from the last test result and then assuming a chronic intake throughout employment. In 

this case, the last lung count was performed in [redacted] and represents a screening lung count 

performed with a Phoswich detector with a high americium MDA. Since the EE did receive lung 

counts following the inhalation incident using detectors that were much more sensitive, we 

decided to use the results from the second to last lung count on [redacted].
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The lung counts measure exposure to Am-24; therefore, conversion is needed in order to 

determine the associated intake of plutonium. The EE’s lung count was considered a “full-time” 

test at 2,000 seconds and a “standard system” test, since it included both the right and left sides. 

Table B-11 of ORAUT-TKBS-0011-5 lists the MDA values for Am-241 given the type of 

detector and the conditions in which the test was performed. The concentration of americium in 

units of parts per million (ppm) is used to determine the associated MDA of plutonium for the 

lung counts. Section B.1 of ORAUT-TKBS-0011-5 discusses the detection of americium as a 

surrogate for plutonium in lung counts. 

Plutonium was not detected directly because of the low abundance of gamma 

photons and because of the severe attenuation of the more abundant, low-energy 

L X-rays. Instead, the 59.5-keV gamma photon from 241Am was used as a 

surrogate. The isotope 241Am was present to some extent in all WG [weaponsgrade] plutonium at RFP. The activity of plutonium was then calculated from the 

detected 241Am by measuring, calculating, or assuming the fraction of the 241Am in 

the plutonium mixture on the date of the lung count. At RFP, the fraction of the 

241Am in the plutonium mixture has historically been characterized in terms of 

parts per million by weight. Direct in vivo measurement of plutonium in the 

lungs, although investigated, was never implemented at RFP. The RFP lung 

counter detected 241Am. The assessment of the MDA, therefore, is focused on the 

MDA for 241Am. The MDA for plutonium can then be derived from the 241Am 

MDA based on the value of the ppm 241Am for the plutonium mixture. 

The lung count records in this EE’s files indicate that the EE was potentially exposed to 

plutonium with a concentration of americium at 740 ppm. Using the conversion method in 

Attachment B of ORAUT-TKBS-0011-5, Table B-9, the americium MDAs should be multiplied 

by 20.7 in order to get the MDA for plutonium. Table II-10 below presents the MDA values for 

Pu/Am used in our analysis. 

Table II-10. Americium and Plutonium Lung Count MDA 

Test Date Detector Type Am-241 MDA (nCi) Pu MDA (nCi)

07/13/1984 PGT-1 0.21 4.347

The plutonium MDA represents Pu-239+240. The 1⁄2 MDA value for plutonium is 2,174 pCi. 

Method B used the isotopic fractions of alpha activity in weapons-grade plutonium listed in 

Table 5-1 of ORAUT-TKBS-0011-5 and applied them to the 1⁄2 MDA value. These values were 

used as input into the IMBA program in order to derive the intakes and doses. 

Table II-11. Type S Plutonium Intakes and Doses from Lung Counts

Isotope Absorption Type Fraction of 

WGP

Lung Count Measurement of 

1⁄2 MDA (pCi)

Intake 

(pCi/d)

Dose 

(rem)

Pu-238 Type S 0.023 51 1.528 0.709

Pu-239 Type S 0.8 1774 52.44 22.1

Pu-240 Type S 0.18 399 11.77 4.98

It is possible that this EE was exposed to highly insoluble Super S plutonium. We followed the 

guidance in ORAUT-OTIB-0049, which is the technical information bulletin (TIB) that pertains 

to exposure to highly insoluble plutonium. In order to account for exposure to Super S highly 
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insoluble plutonium, the annual doses from lung counts are multiplied by adjustment factors. 

These factors are dependent upon the number of years that the individual was exposed. The 

exposure is determined by the number of absolute years, not by calendar years. For this case, 

year 1 would be from the first day of employment, [redacted], to [redacted]. Therefore, this EE 

was chronically exposed for [redacted] years. The procedures recommend that the exposure 

period be rounded down. Page 10 of ORAUT-OTIB-0049 states the following: 

Because the dose adjustment factors decrease as the chronic exposure period 

increases, for chronic intakes for partial years, dose reconstructors should 

truncate the partial year and use the dose adjustment factor table for the full 

year; for instance, if the intake period is 4.5 years, use the dose adjustment 

factors for a 4-year chronic intake. 

The procedures in ORAUT-OTIB-0049 recommend that the doses from each of the plutonium 

isotopes be adjusted for Super S absorption. Page 17 of this TIB describes the following: 

Adjustment factors apply only to doses resulting from intakes of plutonium for 

which the activity isotopic ratio of 239+240Pu to 238Pu is greater than 1. This 

restriction is based on the observed behavior of relatively pure 238Pu, which tends 

to be more soluble than 239Pu. When this condition is met, SS behavior applies to 

all isotopes in the plutonium mixture. 

The annual Type S lung doses for each isotope are multiplied by the adjustment factors from 

Table D-1, page 46 of ORAUT-OTIB-0049, from the chronic 6 years column. In order to 

correct the doses for the year in which the test was performed, the results are then divided by the 

adjustment factor from that year. In this case, it is the factor of 2.6 from year 5. This additional 

adjustment is performed so that the Type SS dose for the year the lung count was taken is equal 

to the Type S dose. Page 11 of ORAUT-OTIB-0049 describes this procedure: 

To calculate Type SS lung doses from chest count measurements, the dose to the 

lung is first calculated assuming that Type S material was inhaled. This dose is 

then adjusted upward with the factors given in Appendix D. However, the 

application of the adjustment factor will result in an implied Type SS lung content 

that is inconsistent with the original chest count. To make the observed and 

predicted chest counts agree, the Type SS lung dose must be adjusted downward 

by applying the adjustment factor for the year of the chest count used to determine 

the intake. 

The Type SS lung dose from the chest count data totaled 55.650 rem. 

II.3.4 Missed Americium Dose using Lung Count Results 

SC&A also calculated missed americium dose using the lung count results. All of the results 

were below the MDA. As with the plutonium dose, we chose to assign missed dose using the 

lung count taken on July 13, 1984. The lung count MDA for americium is 0.21 nCi (ORAUTTKBS-0011-5, Table 5-11). A chronic intake of 3.11 pCi/d was calculated by the IMBA 
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program using the 1⁄2 MDA value. Using this intake, the total lung dose from exposure to 

americium from the beginning of employment to the date of diagnosis is 1.464 rem. 

II.3.5 Depleted Uranium Dose 

Given this EE’s work duties, it is possible that the EE was exposed to DU while at RFP. In 

addition, the EE was monitored for uranium/thorium exposure with lung counts following the 

radiological incident in [redacted]. All of the results were below the MDA. SC&A’s Method B

decided to assign missed dose from exposure to DU. It was determined that this EE would not 

have had exposure to thorium. Our review of the site profile revealed that the time periods and 

locations where the EE worked were such that thorium exposures were not plausible, but 

exposures to DU were plausible. 

II.3.5.1 Lung Count MDAs 

SC&A calculated the missed dose from exposure to DU using the MDA of the lung counts. 

Section 5.3.2.2.2 of ORAUT-TKBS-0011-5 states the following regarding the uranium MDA for 

lung counts: 

U-238 worker-specific MDA can be obtained by multiplying the Am-241 workerspecific MDA by 9.4. That result is divided by 0.89 to obtain the worker-specific 

MDA for DU. 

The Am-241 MDA of 0.21 nCi was used in our assessment based on the count performed on July 

13, 1984. One-half this MDA value is multiplied by the alpha activity fractions for DU listed on 

Table 5-4 of ORAUT-TKBS-0011-5. The DU daily intake rates derived using these MDA 

values in the IMBA program were as follows: 3.25 pCi/d of U-234, 0.44 pCi/d of U-235, and 

29.26 pCi/d of U-238. Using these intakes in the IMBA program and assuming a chronic intake 

from the beginning to the end of employment produced a total missed dose to the lung from DU

of 10.300 rem. 

II.3.5.2 Missed Tritium Dose 

This EE was monitored for tritium in [redacted] and [redacted]. Table II-12 lists the urinalysis 

results.

Table II-12. Tritium Bioassay Results for Case #[redacted]

Date of Bioassay Type Radionuclide Result (pCi/L)

[redacted] urinalysis tritium 795

[redacted] urinalysis tritium 890

[redacted] urinalysis tritium 833

Section 5.3.1.6 of ORAUT-TKBS-0011-5 describes the MDAs for tritium: 

Although the actual MDA has not been quantified for the methods in the 1970s 

and 1980s, it likely is in the range of several hundred to several thousand 
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picocuries per liter. The current MDA for tritium is 600 pCi/L (RFETS 1998c, p. 

7-3). 

We determined that it was not necessary to assign doses due to exposure to tritium, because the 

concentrations of tritium in urine, as described above in Table 12, are associated with whole 

body doses well below 1 mrem/yr. 

II.5 SUMMARY CONCLUSIONS 

SC&A performed dose assessments using all of the monitoring data available in the DOE records 

for this EE. In the records, the EE is described as [redacted], and this information was included 

in the POC calculation. For the internal dose, SC&A decided to use the lung count results for 

plutonium, americium, and DU in the IREP calculation for determining the POC. In comparison 

to the lung count results, which directly measured the radionuclide exposure for this EE, the 

urinalysis bioassay results may be a gross overestimate of the EE’s actual exposure. SC&A’s 

DR–Method B concluded that the doses derived from the lung count data represent a realistic 

and scientifically sound dose assessment, while still being favorable to the claimant. The IREP 

input values of Appendix II-A were imported into the IREP program available on the DCAS 

website. The POC was determined to be 55.75%, which would make this claim eligible for 

compensation. 

II.6 REFERENCES 

Falk, R. B., 1971. A Personnel Neutron Dosimeter Using Lithium Fluoride Thermoluminescent 

Dosimeters, RFP-1581, Dow Chemical Company, Rocky Flats Division, Golden, Colorado. 

January 20, 1971. [SRDB Ref ID: 1272] 

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

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

Oxford, England. 

NCRP (National Council on Radiation Protection and Measurements), 1971, Protection Against 

Neutron Radiation, NCRP Report 38, Bethesda, Maryland, January 4. 

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-0049. 2010. Technical Information Bulletin: Estimating Doses for Plutonium 

Strongly Retained in the Lung, Rev. 01 PC-2, Oak Ridge Associated Universities, Cincinnati, 

Ohio. November 29, 2010. 

ORAUT-PROC-0061. 2006. Occupational X-ray Dose Reconstruction for DOE Sites, Rev. 01, 

Oak Ridge Associated Universities Team, Cincinnati, Ohio. July 21, 2006. 
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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-0011-3. 2007. Technical Basis Document for the Rocky Flats Plant –

Occupational Medical Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. April 23, 2007. 

ORAUT-TKBS-0011-5. 2007. Technical Basis Document for the Rocky Flats Plant –

Occupational Internal Dose, Rev. 02, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. August 17, 2007. 

ORAUT-TKBS-0011-6. 2010. Technical Basis Document for the Rocky Flats Plant –

Occupational External Dose, Rev. 01, Oak Ridge Associated Universities Team, Cincinnati, 

Ohio. October 20, 2010. 

RFETS (Rocky Flats Environmental Technology Site) 1998c. “Other Isotopes,” Internal 

Dosimetry Technical Basis Documentation, Section 1, Version 3, U.S. Department of Energy, 

Golden, Colorado. 

Stanford, N., 1990. Whole Body TLD Dose Algorithm for Panasonic 802/809 TLD Pair, Rocky 

Flats Plant External Dosimetry Program. September 30, 1990. [SRDB Ref ID: 4641] 
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APPENDIX II-A: IREP INPUT – LUNG 

EXPOSURE 

INFORMATION

Number of 

exposures

202

Exposure # Exposure 

Year Exposure Rate Radiation Type Dose Distribution Type Parameter 1 Parameter 2 Parameter 3

1 [redacted] acute photons E<30keV Constant 0.004 0 0.000

2 [redacted] acute photons E<30keV Constant 0.002 0 0.000

3 [redacted] acute photons E<30keV Constant 0.003 0 0.000

4 [redacted] acute photons E<30keV Constant 0.007 0 0.000

5 [redacted] acute photons E<30keV Constant 0.001 0 0.000

6 [redacted] acute photons E<30keV Constant 0.001 0 0.000

7 [redacted] acute photons E=30–250keV Constant 0.477 0 0.000

8 [redacted] acute photons E=30–250keV Constant 0.252 0 0.000

9 [redacted] acute photons E=30–250keV Constant 0.38 0 0.000

10 [redacted] acute photons E=30–250keV Constant 0.347 0 0.000

11 [redacted] acute photons E=30–250keV Constant 0.063 0 0.000

12 [redacted] acute photons E=30–250keV constant 0.032 0 0.000

13 [redacted] acute photons E=30–250keV lognormal 0.008 1.52 0.000

14 [redacted] acute photons E=30–250keV lognormal 0.008 1.52 0.000

15 [redacted] acute photons E=30–250keV lognormal 0.008 1.52 0.000

16 [redacted] acute photons E=30–250keV lognormal 0.008 1.52 0.000

17 [redacted] acute photons E=30–250keV lognormal 0.006 1.52 0.000

18 [redacted] acute photons E<30keV normal 0.0004 0.004 0.000

19 [redacted] acute photons E<30keV normal 0.0008 0.008 0.000

20 [redacted] acute photons E<30keV normal 0.0036 0.021 0.000

21 [redacted] acute photons E<30keV normal 0.0018 0.011 0.000

22 [redacted] acute photons E<30keV normal 0.0057 0.023 0.000

23 [redacted] acute photons E=30–250keV normal 0.050 0.012 0.000

24 [redacted] acute photons E=30–250keV normal 0.085 0.023 0.000

25 [redacted] acute photons E=30–250keV normal 0.171 0.064 0.000

26 [redacted] acute photons E=30–250keV normal 0.085 0.032 0.000

27 [redacted] acute photons E=30–250keV normal 0.275 0.069 0.000

28 [redacted] chronic neutrons E<10keV normal 0.028 0.009 0.000

29 [redacted] chronic neutrons E<10keV normal 0.007 0.002 0.000

30 [redacted] chronic neutrons E<10keV normal 0.026 0.008 0.000

31 [redacted] chronic neutrons E<10keV normal 0.017 0.005 0.000

32 [redacted] chronic neutrons E<10keV normal 0.013 0.004 0.000

33 [redacted] chronic neutrons E<10keV normal 0.008 0.003 0.000

34 [redacted] chronic neutrons E=10-100keV normal 0.006 0.002 0.000

35 [redacted] chronic neutrons E=10-100keV normal 0.001 0 0.000

36 [redacted] chronic neutrons E=10-100keV normal 0.005 0.002 0.000

37 [redacted] chronic neutrons E=10-100keV normal 0.004 0.001 0.000

38 [redacted] chronic neutrons E=10-100keV normal 0.003 0.001 0.000

39 [redacted] chronic neutrons E=10-100keV normal 0.002 0.001 0.000

40 [redacted] chronic neutrons E=100keV-2MeV normal 0.187 0.056 0.000

41 [redacted] chronic neutrons E=100keV-2MeV normal 0.048 0.014 0.000
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Appendix II-A: IREP Input – Lung (continued) 

42 [redacted] chronic neutrons E=100keV-2MeV normal 0.171 0.051 0.000

43 [redacted] chronic neutrons E=100keV-2MeV normal 0.12 0.036 0.000

44 [redacted] chronic neutrons E=100keV-2MeV normal 0.092 0.028 0.000

45 [redacted] chronic neutrons E=100keV-2MeV normal 0.061 0.018 0.000

46 [redacted] chronic neutrons E=2-20MeV normal 0.086 0.026 0.000

47 [redacted] chronic neutrons E=2-20MeV normal 0.022 0.007 0.000

48 [redacted] chronic neutrons E=2-20MeV normal 0.078 0.023 0.000

49 [redacted] chronic neutrons E=2-20MeV normal 0.054 0.016 0.000

50 [redacted] chronic neutrons E=2-20MeV normal 0.041 0.012 0.000

51 [redacted] chronic neutrons E=2-20MeV normal 0.027 0.008 0.000

52 [redacted] chronic neutrons E<10keV normal 0.003 0.001 0.000

53 [redacted] chronic neutrons E<10keV normal 0.005 0.001 0.000

54 [redacted] chronic neutrons E<10keV normal 0.012 0.004 0.000

55 [redacted] chronic neutrons E<10keV normal 0.006 0.002 0.000

56 [redacted] chronic neutrons E<10keV normal 0.019 0.006 0.000

57 [redacted] chronic neutrons E=10-100keV normal 0.001 0 0.000

58 [redacted] chronic neutrons E=10-100keV normal 0.001 0 0.000

59 [redacted] chronic neutrons E=10-100keV normal 0.003 0.001 0.000

60 [redacted] chronic neutrons E=10-100keV normal 0.001 0 0.000

61 [redacted] chronic neutrons E=10-100keV normal 0.004 0.001 0.000

62 [redacted] chronic neutrons E=100keV-2MeV normal 0.017 0.005 0.000

63 [redacted] chronic neutrons E=100keV-2MeV normal 0.032 0.01 0.000

64 [redacted] chronic neutrons E=100keV-2MeV normal 0.087 0.026 0.000

65 [redacted] chronic neutrons E=100keV-2MeV normal 0.043 0.014 0.000

66 [redacted] chronic neutrons E=100keV-2MeV normal 0.140 0.042 0.000

67 [redacted] chronic neutrons E=2-20MeV normal 0.008 0.002 0.000

68 [redacted] chronic neutrons E=2-20MeV normal 0.015 0.004 0.000

69 [redacted] chronic neutrons E=2-20MeV normal 0.041 0.012 0.000

70 [redacted] chronic neutrons E=2-20MeV normal 0.021 0.006 0.000

71 [redacted] chronic neutrons E=2-20MeV normal 0.063 0.019 0.000

72 [redacted] chronic neutrons E<10keV lognormal 0.001 1.52 0.000

73 [redacted] chronic neutrons E<10keV lognormal 0.006 1.52 0.000

74 [redacted] chronic neutrons E<10keV lognormal 0.008 1.52 0.000

75 [redacted] chronic neutrons E<10keV lognormal 0.005 1.52 0.000

76 [redacted] chronic neutrons E<10keV lognormal 0.005 1.52 0.000

77 [redacted] chronic neutrons E<10keV lognormal 0.003 1.52 0.000

78 [redacted] chronic neutrons E<10keV lognormal 0.002 1.52 0.000

79 [redacted] chronic neutrons E=10-100keV lognormal 0.001 1.52 0.000

80 [redacted] chronic neutrons E=10-100keV lognormal 0.002 1.52 0.000

81 [redacted] chronic neutrons E=10-100keV lognormal 0.001 1.52 0.000

82 [redacted] chronic neutrons E=10-100keV lognormal 0.001 1.52 0.000

83 [redacted] chronic neutrons E=10-100keV lognormal 0.001 1.52 0.000

84 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.008 1.52 0.000

85 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.038 1.52 0.000

86 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.053 1.52 0.000

87 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.03 1.52 0.000

88 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.035 1.52 0.000

89 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.023 1.52 0.000

90 [redacted] chronic neutrons E=100keV-2MeV lognormal 0.012 1.52 0.000
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Appendix II-A: IREP Input – Lung (continued) 

91 [redacted] chronic neutrons E=2-20MeV lognormal 0.003 1.52 0.000

92 [redacted] chronic neutrons E=2-20MeV lognormal 0.017 1.52 0.000

93 [redacted] chronic neutrons E=2-20MeV lognormal 0.024 1.52 0.000

94 [redacted] chronic neutrons E=2-20MeV lognormal 0.014 1.52 0.000

95 [redacted] chronic neutrons E=2-20MeV lognormal 0.016 1.52 0.000

96 [redacted] chronic neutrons E=2-20MeV lognormal 0.01 1.52 0.000

97 [redacted] chronic neutrons E=2-20MeV lognormal 0.005 1.52 0.000

98 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

99 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

100 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

101 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

102 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

103 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

104 [redacted] acute photons E=30–250keV normal 0.042 0.013 0.000

105 [redacted] chronic alpha normal 1.20E+00 0.36 0.000

106 [redacted] chronic alpha normal 1.86E+00 0.558 0.000

107 [redacted] chronic alpha normal 2.30E+00 0.689 0.000

108 [redacted] chronic alpha normal 2.82E+00 0.847 0.000

109 [redacted] chronic alpha normal 3.21E+00 0.963 0.000

110 [redacted] chronic alpha normal 3.72E+00 1.116 0.000

111 [redacted] chronic alpha normal 4.73E+00 1.418 0.000

112 [redacted] chronic alpha normal 2.49E+00 0.746 0.000

113 [redacted] chronic alpha normal 2.25E+00 0.675 0.000

114 [redacted] chronic alpha normal 2.09E+00 0.628 0.000

115 [redacted] chronic alpha normal 1.94E+00 0.581 0.000

116 [redacted] chronic alpha normal 1.80E+00 0.539 0.000

117 [redacted] chronic alpha normal 1.64E+00 0.491 0.000

118 [redacted] chronic alpha normal 1.64E+00 0.491 0.000

119 [redacted] chronic alpha normal 1.52E+00 0.456 0.000

120 [redacted] chronic alpha normal 1.43E+00 0.43 0.000

121 [redacted] chronic alpha normal 1.36E+00 0.407 0.000

122 [redacted] chronic alpha normal 1.37E+00 0.412 0.000

123 [redacted] chronic alpha normal 1.31E+00 0.393 0.000

124 [redacted] chronic alpha normal 1.26E+00 0.379 0.000

125 [redacted] chronic alpha normal 1.27E+00 0.381 0.000

126 [redacted] chronic alpha normal 1.22E+00 0.366 0.000

127 [redacted] chronic alpha normal 1.22E+00 0.365 0.000

128 [redacted] chronic alpha normal 1.17E+00 0.352 0.000

129 [redacted] chronic alpha normal 1.17E+00 0.35 0.000

130 [redacted] chronic alpha normal 1.16E+00 0.347 0.000

131 [redacted] chronic alpha normal 1.14E+00 0.343 0.000

132 [redacted] chronic alpha normal 1.09E+00 0.328 0.000

133 [redacted] chronic alpha normal 1.08E+00 0.323 0.000

134 [redacted] chronic alpha normal 1.09E+00 0.326 0.000

135 [redacted] chronic alpha Normal 1.06E+00 0.318 0.000

136 [redacted] chronic alpha Normal 1.04E+00 0.311 0.000

137 [redacted] chronic alpha Normal 0.01 0.003 0.000

138 [redacted] chronic alpha Normal 0.12 0.036 0.000

139 [redacted] chronic alpha Normal 0.142 0.043 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

40 of 41

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: IREP Input – Lung (continued) 

140 [redacted] chronic alpha Normal 0.156 0.047 0.000

141 [redacted] chronic alpha Normal 0.167 0.05 0.000

142 [redacted] chronic alpha Normal 0.175 0.052 0.000

143 [redacted] chronic alpha Normal 0.18 0.054 0.000

144 [redacted] chronic alpha Normal 0.156 0.047 0.000

145 [redacted] chronic alpha Normal 0.064 0.019 0.000

146 [redacted] chronic alpha Normal 0.047 0.014 0.000

147 [redacted] chronic alpha Normal 0.036 0.011 0.000

148 [redacted] chronic alpha Normal 0.029 0.009 0.000

149 [redacted] chronic alpha Normal 0.023 0.007 0.000

150 [redacted] chronic alpha Normal 0.019 0.006 0.000

151 [redacted] chronic alpha Normal 0.016 0.005 0.000

152 [redacted] chronic alpha Normal 0.014 0.004 0.000

153 [redacted] chronic alpha Normal 0.012 0.004 0.000

154 [redacted] chronic alpha Normal 0.011 0.003 0.000

155 [redacted] chronic alpha Normal 0.01 0.003 0.000

156 [redacted] chronic alpha Normal 0.009 0.003 0.000

157 [redacted] chronic alpha Normal 0.008 0.002 0.000

158 [redacted] chronic alpha Normal 0.008 0.002 0.000

159 [redacted] chronic alpha Normal 0.007 0.002 0.000

160 [redacted] chronic alpha Normal 0.006 0.002 0.000

161 [redacted] chronic alpha Normal 0.006 0.002 0.000

162 [redacted] chronic alpha Normal 0.005 0.002 0.000

163 [redacted] chronic alpha Normal 0.005 0.002 0.000

164 [redacted] chronic alpha Normal 0.005 0.001 0.000

165 [redacted] chronic alpha Normal 0.004 0.001 0.000

166 [redacted] chronic alpha Normal 0.004 0.001 0.000

167 [redacted] chronic alpha Normal 0.004 0.001 0.000

168 [redacted] chronic alpha Normal 0.003 0.001 0.000

169 [redacted] chronic alpha Normal 0.003 0.001 0.000

170 [redacted] chronic alpha Normal 0.063 0.019 0.000

171 [redacted] chronic alpha Normal 0.753 0.226 0.000

172 [redacted] chronic alpha Normal 0.923 0.277 0.000

173 [redacted] chronic alpha Normal 1.038 0.311 0.000

174 [redacted] chronic alpha Normal 1.122 0.336 0.000

175 [redacted] chronic alpha Normal 1.188 0.356 0.000

176 [redacted] chronic alpha Normal 1.232 0.37 0.000

177 [redacted] chronic alpha Normal 1.091 0.327 0.000

178 [redacted] chronic alpha Normal 0.506 0.152 0.000

179 [redacted] chronic alpha Normal 0.379 0.114 0.000

180 [redacted] chronic alpha Normal 0.291 0.087 0.000

181 [redacted] chronic alpha Normal 0.23 0.069 0.000

182 [redacted] chronic alpha Normal 0.187 0.056 0.000

183 [redacted] chronic alpha Normal 0.155 0.047 0.000

184 [redacted] chronic alpha Normal 0.132 0.04 0.000

185 [redacted] chronic alpha Normal 0.114 0.034 0.000

186 [redacted] chronic alpha Normal 0.1 0.03 0.000

187 [redacted] chronic alpha Normal 0.09 0.027 0.000

188 [redacted] chronic alpha Normal 0.08 0.024 0.000
Effective Date:

January 13, 2014

Revision No.

0 (Draft)

Document No. 

SCA-TR-BDR2014-CN[REDACTED]

Page No.

41 of 41

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: IREP Input – Lung (continued) 

189 [redacted] chronic alpha Normal 0.073 0.022 0.000

190 [redacted] chronic alpha Normal 0.066 0.02 0.000

191 [redacted] chronic alpha Normal 0.061 0.018 0.000

192 [redacted] chronic alpha Normal 0.056 0.017 0.000

193 [redacted] chronic alpha Normal 0.052 0.015 0.000

194 [redacted] chronic alpha Normal 0.048 0.014 0.000

195 [redacted] chronic alpha Normal 0.044 0.013 0.000

196 [redacted] chronic alpha Normal 0.041 0.012 0.000

197 [redacted] chronic alpha Normal 0.038 0.011 0.000

198 [redacted] chronic alpha Normal 0.035 0.01 0.000

199 [redacted] chronic alpha Normal 0.032 0.01 0.000

200 [redacted] chronic alpha Normal 0.03 0.009 0.000

201 [redacted] chronic alpha Normal 0.028 0.008 0.000

202 [redacted] chronic alpha Normal 0.022 0.007 0.000