Battelle Team 

Dose Reconstruction 

Project for NIOSH

Document Title: 

Site Profiles for Atomic Weapons Employers that 

Worked Uranium and Thorium Metals 

Appendix CD – Seymour Specialty Wire Company 

Document Number: Battelle-TBD-6000 

Appendix CD 

Revision: 0 

Effective Date: 7/16/2007 

Type of Document: TBD Appendix

Supersedes: None 

Subject Experts: R.I. Scherpelz, M.S. Yencken 

Document Owner 

Approval: Signature on file Approval Date: 6/28/2007 

Robert I. Scherpelz, Staff Scientist 

Approval Signature on file Approval Date: 6/28/2007 

Jay A. MacLellan, Battelle PNWD Task Manager 

Concurrence: Signature on file Concurrence Date: 6/28/2007 

Richard J. Traub, Staff Scientist 

Approval: Signature on file Approval Date: 7/16/2007 

James W. Neton, Associate Director of Science 

 New Total Rewrite Revision Page Change 

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION. 
Document No. Battelle-TBD-6000; 

Appendix CD 

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Seymour Specialty Wire Company 

CD.1 Introduction 

This document serves as an appendix to Battelle-TBD-6000, Site Profiles for Atomic 

Weapons Employers that Worked Uranium and Thorium Metals. This appendix 

describes the results of document research specific to this site. Where specific 

information is lacking, research into similar facilities described in the body of this Site 

Profile is used. 

CD.2 Site Description 

The Bridgeport Brass Company performed AEC contract work at its facilities in Seymour 

Connecticut from August 1962 through the summer of 1964. This was developmental 

work which included extrusion and machining and metallurgical laboratory analysis of 

uranium rods, as well as storage of radioactive materials. Thorium was also worked on at 

least two occasions. Twenty-five employees were involved in exposure monitoring 

programs associated with the AWE operations during the estimated 19 months. 

In late 1964 all Bridgeport Brass work was consolidated at the Bridgeport Brass Reactive 

Metals site in Ashtabula, Ohio. From 1985 to 1992 the Seymour site operated as an 

employee-owned company called Seymour Specialty Wire Company. In 1992 operations 

ceased and the company filed for bankruptcy. The building in which AEC work was 

performed under Bridgeport Brass is currently being leased to an electric cable 

manufacturing company. 

CD.2.1 Site Activities 

Process Information 

AWE work appears to have begun at the Seymour facility on August 30, 1962 and 

continued until mid-1964, sometime between April and September of that year. During 

that time the facility extruded uranium and machined natural, enriched and depleted 

uranium (NU, EU and DU) and thorium. No information is available on the total 

quantities handled. Air monitoring worksheets record 16 extrusions occurring during 2 

days of extrusion work. The third day of extrusion air monitoring does not indicate the 

number of extrusions. All AWE work occurred in one location, the Ruffert Building. 

There is little Seymour-specific process information on the uranium and thorium 

operations. Information about the machining of NU, EU and DU comes almost 

exclusively from HASL sample requisition forms (Reference ID 9895, pp.4, 10). No 

thorium quantity information is available. Information about equipment used and work 

areas have come exclusively from HASL sample requisition forms and environmental 

survey reports related to the decontamination of the site (Reference IDs 9895, 9885, 

10847, 9602). 

Because the Seymour facility was a Bridgeport Brass operation – specifically, the Havens 

Lab work relocated to this facility – referring to Bridgeport Brass operations is relevant. 

The Bridgeport Brass Company (BB) performed AEC Contract work at four known 

locations during the 1950’s and 1960’s; 1) Havens Lab and the Housatonic Pilot Plant in 
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Bridgeport, Connecticut; 2) Bridgeport Brass Plant in Adrian, Michigan; 3) Extrusion 

Plant/Reactive Metals in Ashtabula, Ohio; and 4) the Seymour Connecticut facility. 

Havens Lab in Bridgeport, Connecticut was involved in the initial work, which was 

primarily focused on uranium extrusion research and development. The development of 

an extrusion process (cold forming) for natural uranium metal occurred at the Havens 

Lab from November 1950 to August 27, 1962. The U.S. Atomic Energy Commission 

contract described the work as follows: 

Havens Lab work in the 50’s and early 60’s included extrusion of zirconium and 

zirconium alloy tubing, mechanical cladding of uranium with aluminum, zirconium and 

zirconium alloy and the development of slugs and closures. It is not known if this type of 

work was continued at Seymour after the closure of Havens Lab. Reference review does 

support the fact that lab work, similar to that which had been done at the Havens Lab, and 

storage of radioactive material continued at the Seymour facility. 

There are two references to the Mannesman Piercing Experiment occurring at the 

Seymour facility (RefID10847, p. 13, Quarterly Progress Summary April to June 1964, 

RL Bean Reactive Metals Ashtabula, Ohio). There are nine occasions in which process 

waste samples were collected. Urine samples were collected sporadically between 

October 1962 and February 1964. 

Other available process information relates to the Dynapack extrusion process: 

“DYNAPACK extrusion has been successfully employed to produce single slug 

length tubes of the (a) Mark VB-) and (b) I&E sizes, relatively thin and thick 

walled tube types, respectively. Double slug length I&E tubes were produced in 

quantity under production test conditions, however a warpage problem existed.” 

(Quarterly Progress Summary April to June 1964, RL Bean Reactive Metals 

Ashtabula, Ohio)
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Quantities Handled 

No information was found in the Havens Lab references when looking for documentation 

of the material transferred from Havens to Seymour. Sixteen uranium billet extrusions 

are documented in the HASL sample forms. 

HASL Sampling Information 

Seymour HASL sample requisition forms are available beginning on August 30, 1962 for 

a variety of samples (floor smears, urinalysis, air samples and process waste). The last 

set of samples was collected on March 18, 1964. The HASL contamination survey of the 

facility, after operations had ceased, occurred on October 7, 1964. The number of 

sampling occasions that occurred in the approximately two-year period of operation were 

13 sets of urine samples, nine sets of process waste samples, and four days of air 

monitoring samples. Urine sample data are available for dose reconstructions. 

The processing of thorium metal is mentioned on two HASL sample requisition forms 

dated 11/25/63 and 12/17/63 (Reference ID 9895, pp.4, 10). These were process waste 

samples: ‘thorium coolant and thorium chips from Do-All’ saw. There is no definite 

information on the beginning and ending dates of thorium processing, or any indication 

of the total quantity of thorium processed. 

Estimating Work Days based upon Havens Lab 

To estimate the amount of time AWE work was performed, it seems reasonable to refer 

to Bridgeport Brass Havens Laboratory and other Bridgeport Brass operations. In the 

summer of 1962, work at the Havens lab ceased and moved to the Seymour facility. 

References to Havens Lab in the ORAU TBD assume that AEC work was full-time from 

the beginning of the contract, although not all work involved radioactive material. The 

types of supporting documents mentioned in the ORAU TBD for Havens Lab are not 

available for the Seymour operations. Given that Havens Lab operations are the only 

references available to estimate the Seymour operations frequency, and HASL sample 

requisition forms exist for the Seymour facility on 25 occasions, it seems reasonable to 

assume that operations at Seymour were similar to Havens Lab, i.e. work was full-time, 

including zirconium development work and the work with radioactive material (see 

ORAU TBD Bridgeport Brass Havens Lab). 

The working period used for the Bridgeport Brass Havens Lab ORAU TBD is not easily 

determined from reading the TBD. As an approach which is favorable to the claimant, 

50% time in the 22-month period from October 1, 1962, through October 31, 1964. The 

actual end of operations is not stated, but the last process-related samples were collected 

in March 1964, and a clearance survey was performed in October 1964, so this study 

estimated that half the work was with uranium or thorium and the other half with 

zirconium and aluminum. 

CD.2.2 Job Categories 

Each claim will be evaluated to determine the most appropriate Job Category from the list 

below. Because this work was developmental on a large lab/pilot scale, using the 
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Generic Metal TBD is not recommended. There are adequate site-specific data to 

estimate exposures for the anticipated job categories. 

Operators (involved in operations—dose based on site-specific data) 

Extrusion Operator 

Billet Transfer (extrusion process) 

Turret Lathe Operator (machining) 

Grinder Operator (machining) 

Generic Job Titles (for those who do not fit in the 4 operator categories) 

Plant Floor High (Involved directly in operations — external dose based on sitespecific data, uranium internal dose based on urine bioassay data 

and thorium internal dose based on site specific air monitoring 

data) 

Plant Floor Low (Involved in support of operations— internal dose based on 50% of 

plant floor high above) 

Supervisor (Assumed to spend some time in the production areas—internal dose 

based on 25% of plant floor high above) 

Clerk (Assumed to have minimal exposure—dose based on exposure to 2.5% of 

plant floor high above) 

Employed after AWE period 

• Use the four generic job categories. For post-AWE time period up to 1991, assume 

exposures based on resuspension of contamination deposited during the last year of 

AWE operation, assuming no cleanup. 

• After 1991, assume that exposure is zero, based upon FUSRAP surveys which 

indicate no contamination above background. 

CD.3 Occupational Medical Dose 

No information was available describing occupational medical doses received by workers at the 

Seymour facility. Information from Section 3 in the generic TBD should be used to evaluate this 

dose component for workers at this plant. 

From the Havens Lab TBD: 
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CD.4 Occupational Internal Dose 

Intake Estimates based upon Bioassay Monitoring 

Urine bioassay samples were collected from individuals and anayzed for uranium during three 

periods in 1962, four periods in 1963 and one period in 1964 (RefID 9885). If bioassay data is 

available for the claimant, the data should be used to estimate intakes using the IMBA internal 

dosimetry code. If bioassay data is not available an estimate favorable to the claimant may be 

obtained by selecting the highest recorded bioassay result for each period and using that data with 

IMBA. The maximum recorded excretion reported for each period and the calculated daily 

excretion (based on 1.4 L urine excretion per day) were as follows: 

Collection Date mg/L mg/d 

10/8/1962 5.71E-03 8.00E-03 

11/19/1962 2.22E+00 3.11E+00

12/17/1962 3.50E-02 4.90E-02 

2/18/1963 1.12E-02 1.57E-02 

5/23/1963 5.30E-02 7.42E-02 

9/30/1963 1.40E-02 1.96E-02 

12/9/1963 3.40E-02 4.76E-02 

2/11/1964 4.20E-02 5.88E-02 

 

Daily intakes calculated from maximum results for each of the three years were as follows: 

Daily Intake, pCi/d 

Intake Year Absorption Type M Absorption Type S 

1962 1.47E+02 4.86E+3 

1963 2.94E+02 8.95E+03 

1964 1.05E+03 3.47E+4 

Intake estimates from the maximum bioassay results are expected to be favorable to the claimant 

because no correction has been made for uranium intake from environmental sources. The 

intakes should be entered into the IREP probability of causation code with a constant distribution. 

The selection of absorption type should be guided by whether Type M or S provides the organ 

dose most favorable to the claimant. 
Document No. Battelle-TBD-6000; 

Appendix CD 

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Intake Estimates based upon Air Monitoring 

Site specific air sampling and bioassay data are available, and may be used to characterize the 

Seymour operations. Air samples were collected during four measurement campaigns. All 

measurements were reported in RefID 9895. 

• December 10, 1962 and December 20, 1962 while extruding 3 uranium billets 

(12/10) and machining uranium slugs (12/10 & 12/20). On December 10, 1962 the extrusion 

process was performed on Mark V-B tubing. (There are articles written by Carloni at this site 

about this process http://www.osti.gov/energycitations/product.biblio.jsp?osti_id=4171520). 

• May 28, 1963 while extruding 13 billets. Two area samples were collected at two 

different locations in the proximity of the press; one for 4 hours and 35 minutes (13 extrusions) 

and one for 2 hours (3 extrusions). Personal monitoring samples were collected as task samples 

on the extrusion operators and billet transfer men. All the sample times were very short, at only 

one minute each. No machining was sampled on this day. 

• May 31, 1963 three area samples were collected at different locations in proximity of 

the diehead. Sample times ranged from one and a half hours to three hours. No information on 

the number of billets extruded was given. Personal monitoring samples were collected as task 

samples on the transfer men at the various steps in the process. There was no personal sample 

collected on the extrusion operator. All sample times were very short, ranging from 17 seconds to 

58 seconds. No machining operations were sampled. 

During the four air sampling campaigns described above, air sampling times ranged from seconds 

to 4.5 hours. When reasonable breathing zone (BZ) and general area (GA) samples are available, 

the two could be combined to estimate the daily weighted average exposure (DWA) as follows: 

DWA= 75% BZ Average +25% GA Average 

This was the approach used for calculating the Extrusion Operator DWA. 

DWAs calculated in this way result in daily intake estimates for uranium that were lower than 

those based on bioassay data. There it is considered favorable to the claimant to use the bioassay 

based values for dose reconstruction. 

While most exposures were assumed to involve uranium, limited thorium work was performed at 

the site. It was assumed that two job categories, the turret lathe machinist and the grinding 

machinist, were exposed to thorium for a small part of their work year. It was assumed that these 

jobs experienced exposure to thorium for 16 hours of their work year in 1963. 

CD.5 Occupational External Dose 

No data were found in the Site Research database related to occupational external dose during 

AWE work. The work performed at the Seymour Specialty site involved experimental work in 

extrusion and machining uranium and thorium. Therefore, the external dose values in the TBD 

for extrusion and machining should be used (Section 6.0 of TBD-6000). 

Tables CD.3 and CD.4 present these values as a mrem-per-calendar-day value to be used for each 

calendar year listed. 
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CD.6 Residual Contamination 

Several radiation surveys occurred as part of the decontamination process for the Ruffert 

Building. The first was performed by HASL in October of 1964. Several others occurred as part 

of the DOE FUSRAP program. Summaries of the surveys are as follows. 

The initial cleanup occurred during the second or third quarter of 1964. A HASL radiation 

survey was completed at the site on October 21, 1964. At that time all process equipment had 

been removed and the site appeared clean. The survey included beta/gamma and alpha dose rate 

and removable alpha measurements. A value of “M” indicates a measurement was taken but the 

result was below the detection limit. 

refID 

Survey 

Date Survey Type Location 

Beta/Gamma 

mrad/hr 

surface 

contact 

Alpha 

cts/min/60 

cm2 

Alpha 

removable 

dpm/100 

cm2 

10851 Oct-64 

Gamma, Beta, 

Alpha Dose 

Rate and 

removable 

alpha 

Dynapack Area - 

General 0.01-0.03 100-250 14-20 

Oct-64 

Dynapack Area - 

Base if Dynapack 

S end 0.04 400 7 

Oct-64 

Dynapack Area - 

Base if Dynapack 

N end 0.05 200 M 

Oct-64 

Trench at 

Dynapack 0.07 300 M 

Oct-64 

Dynapack Area - 

top of electrical 

box 0.02 250 M 

Oct-64 

Dynapack Area - 

steps into the area 0.02 350 M 

Oct-64 

Dynapack Area - 

Shelf 0.03 400 M 

Oct-64 

Dynapack Area - 

Office Ceiling 0.03 200 M 

10851 Oct-64 

Machine Shop - 

General Area - 5 

randomly selected 0.04 400-900 20-70 

Oct-64 

Machine ShopNear East Wall 0.5 6500 M 

Oct-64 

Machine Shop - 

General Area - 2 

randomly selected 0.05 600 & 800 80 & 90 

Oct-64 

Machine ShopTop of shelf M 100 M 

Oct-64 

Machine Shop - 

Window sill M 300 M 
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10851 Oct-64 

Cutting & Grinding 

Area - General 

Area 0.01-0.04 100-300 30 

Oct-64 

Cutting & Grinding 

Area - Other 

random location 0.01 300 20 

Oct-64 

Cutting & Grinding 

Area - Other 

random location 0.06 200 50 

Oct-64 

Cutting & Grinding 

Area - window sill 0.05 800 M 

Oct-64 

Cutting & Grinding 

Area - window sill 0.02 200 M 

10851 Oct-64 Lab Hood - N part 0.03 200 3 

10851 Oct-64 

Metal Storage 

Area - General 

Area 0.02-0.25 300-700 40-80 

Oct-64 

Metal Storage 

Area - Light 

Fixture M 100 60 

10851 Oct-64 

Metal Storage 

Area - Top of 

Rolling Door M 300 30 

In 1977, a second visit to the site under the FUSRAP program performed another survey. The 

survey concluded that no further action was needed. Gamma, Beta, Alpha Dose Rate 1 cm & 1 m 

above-surface measurements were taken. 

Gamma Gamma Beta/Gamma Alpha 

RefID 

Survey 

Date Location 

μrad/hr 

at 1 cm 

above 

surfaceMAX 

μrad/hr 

at 1 m 

above 

surface 

MAX 

mrad/hr at 1 

cm above 

surface MAX 

dpm/100 

cm2 

MAX 

10851 1977 Dynapack Area 50 9 0.6 300 

10851 1977 

Other side of Ramp just 

outside Extrusion Area (this is 

likely former uranium storage 

area) 30 6 0.2 M 

10851 1977 Former Office Area upstairs 8 0.13 1.75 180 

10851 1977 

Former Office Area 

downstairs <5-10 <5-10 <0.02 < Bkgd 

A resurvey was completed in 1980, measuring gamma/beta dose rates at 1 cm & 1 m; direct alpha 

and removable contamination; and residue samples. Removable radioactive material 

measurements were taken in this survey. The report brought attention to a seam in the concrete 

floor of the former machine shop and floor drains in the former Dynapack and cutting & grinding 

areas. Results were compared to current acceptable surface contamination values and not found 

to exceed any of those limits. No remediation recommendations were included in this survey 

report. 
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Gamma Gamma Beta/Gamma Beta/Gamma

RefID 

Survey 

Date Locations 

μrad/hr 

at 1 cm 

above 

surfaceMAX 

μrad/hr 

general 

area MAX 

mrad/hr at 1 

cm above 

surface MAX 

mrad/hr at 1 

cm general 

area MAX 

16202 1980 

Surface of bricks in 

Dynapack 15 

16202 1980 

Random locations 

elsewhere 10 0.02 

16202 1980 

Former machine 

shop expansion 

joint 1.1 
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Alpha Alpha Beta/Gamma U 

dpm/100 

cm2 

MAX 

removable 

dpm/100 

cm2 MAX 

removable 

dpm/100 

cm2 MAX 

U residue 

pCi/gm 

16202 1980 

Surface of bricks in 

Dynapack 

16202 1980 

Random locations 

elsewhere <260 

16202 1980 

Former machine 

shop expansion 

joint 70 150 

16202 1980 

Floor Drain #1 - 

former Dynapack 

area 520 2860

16202 1980 

Floor Drain #1 - 

former cutting & 

grinding area 1280

16202 1980 

Floor Drain #2- 

former cutting & 

grinding area 15600

 

In May 1992 a team from Oak Ridge performed another survey as part of the FUSRAP program. 

The survey included gamma scanning over a circumscribed area around the building, gamma/beta 

scanning over all indoor surfaces and the collection of outdoor soil samples and dust/debris 

samples from random surfaces inside the building. 

Radionuclides concentrations outdoors were found to exceed DOE FUSRAP program guidelines 

in a few isolated spots. Indoor concentrations exceeded the guidelines at numerous spots 

including floor drains and select locations within the building which were connected with former 

AW work. Remediation was undertaken in August 1992, continuing to February of 1993 and 

verified complete in 1994. Contaminated indoor surfaces were decontaminated and restored. 

Drains and drain lines were cleaned in a three-step process. A subsurface drain system (3 

manholes and 165 m of drain pipe) still contained radionuclide contamination but the 

contamination was not removable and the cost/benefit of removing was determined to be too 

high, with exposure considered unlikely under present-day uses of the facility. 

The radiation levels overall in the building were reported as only slightly above background. 

This is believed to be due to the construction materials, brick in particular. The maximum dose to 

a worker in the building was calculated to be 5.8 μrad/hr above background or an annual dose of 

11 mrem/yr. 
Document No. Battelle-TBD-6000; 

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 Beta/Gamma U 

SUMMARY 

removable 

dpm/100 cm2 

removable 

pCi/gm 

10847 May-92 

Dust/Debris 

samples Former Dynapack Area 270-3900 190-1100 

10847 May-92 

Dust/Debris 

samples 

Former Machine Shop & 

Cutting & Grinding Area 170-520 210-600 

10847 May-92 

Dust/Debris 

samples Former U Storage Area 140-230 73-150 

10847 May-92 

Dust/Debris 

samples 

Other Areas south and 

east of the 3 areas 

above 23-170 7-110 

CD.7 References 

1. DOE Office of Health, Safety and Security, EEOICPA web site. 

http://www.hss.energy.gov/healthsafety/fwsp/advocacy/faclist/findfacility.cfm 

2. RefID10847, p. 13, Quarterly Progress Summary April to June 1964, RL Bean 

Reactive Metals Ashtabula, Ohio 

3. RefID9885, pp. 13, 
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Table CD.1 INTERNAL DOSE PATHWAYS - Inhalation of Airborne Radionuclides Assumptions: Operational Period Daily Weighted Average Air Concentration, Plant Floor High: 56.9 dpm/m3

Residual Period Daily Weighted Average Air Concentration: 0.007 dpm/m3

GSD derived from measurement data Conversion Factor :2.22 dpm/pCi Breathing Rate: 1.2 m^3/hour All intakes and doses assume full-time employment for the given year. Values represent the geometric mean of a lognormal distribution unless the GSD column indicates “constant”. Those repdistribution. 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Inhalation 

Absorption 

Type 

Intake 

(pCi/d) GSD TBD Refer

Plant Floor High 1962 Operations 1000 U234 M 1.466E+02 Constant Calculated from mPlant Floor High 1962 Operations 1000 U234 S 4.856E+03 Constant Calculated from mPlant Floor High 1963 Operations 2000 U234 M 2.945E+02 Constant Calculated from mPlant Floor High 1963 Operations 2000 U234 S 8.947E+03 Constant Calculated from mPlant Floor High 1964 Operations 800 U234 M 1.051E+03 Constant Calculated from mPlant Floor High 1964 Operations 800 U234 S 3.472E+04 Constant Calculated from mPlant Floor High 1965 -'91 Operations 2000 U235 M 2.078E-02 10.0 Resuspension of mPlant Floor High 1965 -'91 Operations 2000 U235 S 2.078E-02 10.0 

Based on resuspecontamination 

Machining - Turret Lathe 1963 Operations 16 Th M/S 4.817E-02 5.0 Measured air concMachining - Grinding 1963 Operations 16 Th M/S 9.102E-02 3.0 Measured air concPlant Floor Low 1962 Operations 1000 U234 M 7.330E+01 Constant Scaled from Plant Plant Floor Low 1962 Operations 1000 U234 S 2.428E+03 Constant Scaled from Plant Plant Floor Low 1963 Operations 2000 U234 M 1.472E+02 Constant Scaled from Plant Plant Floor Low 1963 Operations 2000 U234 S 4.474E+03 Constant Scaled from Plant Plant Floor Low 1964 Operations 800 U234 M 5.254E+02 Constant Scaled from Plant Plant Floor Low 1964 Operations 800 U234 S 1.736E+04 Constant Scaled from Plant Plant Floor Low 1965 -'91 Residual 2000 U234 M 2.078E-02 10.0 

Based on resuspecontamination 

Plant Floor Low 1965 -'91 Residual 2000 U234 S 2.078E-02 10.0 

Based on resuspecontamination 
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Inhalation 

Absorption 

Type 

Intake 

(pCi/d) GSD TBD Refer

Supervisor 1962 Operations 1000 U234 M 7.330E+01 Constant Scaled from Plant Supervisor 1962 Operations 1000 U234 S 2.428E+03 Constant Scaled from Plant Supervisor 1963 Operations 2000 U234 M 1.472E+02 Constant Scaled from Plant Supervisor 1963 Operations 2000 U234 S 4.474E+03 Constant Scaled from Plant Supervisor 1964 Operations 800 U234 M 5.254E+02 Constant Scaled from Plant Supervisor 1964 Operations 800 U234 S 1.736E+04 Constant Scaled from Plant Supervisor 1965 -'91 Residual 2000 U234 M 2.078E-02 10.0 

Based on resuspecontamination 

Supervisor 1965 -'91 Residual 2000 U234 S 2.078E-02 10.0 

Based on resuspecontamination 

Clerical 1962 Operations 1000 U234 M 7.330E+00 Constant Scaled from Plant Clerical 1962 Operations 1000 U234 S 2.428E+02 Constant Scaled from Plant Clerical 1963 Operations 2000 U234 M 1.472E+01 Constant Scaled from Plant Clerical 1963 Operations 2000 U234 S 4.474E+02 Constant Scaled from Plant Clerical 1964 Operations 800 U234 M 5.254E+01 Constant Scaled from Plant Clerical 1964 Operations 800 U234 S 1.736E+03 Constant Scaled from Plant Clerical 1965 -'91 Residual 2000 U234 M 2.078E-02 10.0 

Based on resuspecontamination 

Clerical 1965 -'91 Residual 2000 U234 S 2.078E-02 10.0 

Based on resuspecontamination 
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Table CD.2 INTERNAL DOSE PATHWAYS - Ingestion of Airborne Radionuclides Assumptions: Air Concentration to Intake Conversion Factor: 3.06E-05 (M^3/d)/(hr/y) - see 7.1.6 TBD-6000 Deposition velocity: 0.00075 m/s Resuspension Factor: 1.00E-06 1/mValues represent the geometric mean of a lognormal distribution unless the GSD column indicates “constant”. Those repdistribution. 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Inhalation 

Absorption 

Type

Intake 

(pCi/d) GSD TBD Refere

Plant Floor High 1962 Operations 1000 U234 M 4.68E-01 Constant Calculated from Plant Floor High 1962 Operations 1000 U234 S 1.55E+01 Constant Measured air coPlant Floor High 1963 Operations 2000 U234 M 1.88E+00 Constant Calculated from Plant Floor High 1963 Operations 2000 U234 S 5.71E+01 Constant Measured air coPlant Floor High 1964 Operations 800 U234 M 2.68E+00 Constant Calculated from Plant Floor High 1964 Operations 800 U234 S 8.86E+01 Constant Measured air coPlant Floor High 1965 -'91 Residual 2000 U234 M 1.94E-04 3 

Based on resuspsurface contamin

Plant Floor High 1965 -'91 Residual 2000 U234 S 1.94E-04 10 

Based on resuspsurface contamin

Machining - Turret Lathe 1963 Operations 16 Th M/S 4.49E-04 5 Measured air coMachining - Grinding 1963 Operations 16 Th M/S 8.48E-04 3 Measured air coPlant Floor Low 1962 Operations 1000 U234 M 2.34E-01 Constant Scaled from PlanPlant Floor Low 1962 Operations 1000 U234 S 7.74E+00 Constant Scaled from PlanPlant Floor Low 1963 Operations 2000 U234 M 9.39E-01 Constant Scaled from PlanPlant Floor Low 1963 Operations 2000 U234 S 2.85E+01 Constant Scaled from PlanPlant Floor Low 1964 Operations 800 U234 M 1.34E+00 Constant Scaled from PlanPlant Floor Low 1964 Operations 800 U234 S 4.43E+01 Constant Scaled from PlanPlant Floor Low 1965 -'91 Residual 2000 U234 M 1.94E-04 4 

Based on resuspsurface contamin

Plant Floor Low 1965 -'91 Residual 2000 U234 S 1.94E-04 10 

Based on resuspsurface contamin

Supervisor 1962 Operations 1000 U234 M 2.34E-01 Constant Scaled from Plan
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Inhalation 

Absorption 

Type

Intake 

(pCi/d) GSD TBD Refere

Supervisor 1962 Operations 1000 U234 S 7.74E+00 Constant Scaled from PlanSupervisor 1963 Operations 2000 U234 M 9.39E-01 Constant Scaled from PlanSupervisor 1963 Operations 2000 U234 S 2.85E+01 Constant Scaled from PlanSupervisor 1964 Operations 800 U234 M 1.34E+00 Constant Scaled from PlanSupervisor 1964 Operations 800 U234 S 4.43E+01 Constant Scaled from PlanSupervisor 1965 -'91 Residual 2000 U234 M 1.94E-04 5 

Based on resuspsurface contamin

Supervisor 1965 -'91 Residual 2000 U234 S 1.94E-04 10 

Based on resuspsurface contamin

Clerical 1962 Operations 1000 U234 M 2.34E-02 Constant Scaled from PlanClerical 1962 Operations 1000 U234 S 7.74E-01 Constant Scaled from PlanClerical 1963 Operations 2000 U234 M 9.39E-02 Constant Scaled from PlanClerical 1963 Operations 2000 U234 S 2.85E+00 Constant Scaled from PlanClerical 1964 Operations 800 U234 M 1.34E-01 Constant Scaled from PlanClerical 1964 Operations 800 U234 S 4.43E+00 Constant Scaled from PlanClerical 1965 -'91 Residual 2000 U234 M 1.94E-04 3 

Based on resuspsurface contamin

Clerical 1965 -'91 Residual 2000 U234 S 1.94E-04 10 

Based on resuspsurface contamin
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Table CD.3 EXTERNAL DOSE PATHWAYS - Whole Body Assumptions: Submersion Dose Conversion Factor: 2.462E-09 mrem/h/dpm/m^3 

Deposition velocity: 0.00075 m/s 

Contaminated Surface Dose Conversion Factor: 5.615E-10 mrem/h/dpm/m^2 All external dose from estimated exposure to uranium slugs Residual period: Assume no handling of U metal - only exposure is from residual contamination on floor and in air 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

External 

Whole 

Body 

(mR/d) GSD TBD Reference or Researc

Extrusion Operator 1962 Operations 500 U234 3.90E-01 5 Generic Metal TBD, Section 6.3 Extrusion Operator 1963 Operations 1000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Extrusion Operator 1964 Operations 800 U234 6.25E-01 5 Generic Metal TBD, Section 6.3 Extrusion Billet Transfer 1962 Operations 500 U234 3.90E-01 5 Generic Metal TBD, Section 6.3 Extrusion Billet Transfer 1963 Operations 1000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Extrusion Billet Transfer 1964 Operations 800 U234 6.25E-01 5 Generic Metal TBD, Section 6.3 Machining - Turret Lathe 1962 Operations 500 U234 3.90E-01 5 Generic Metal TBD, Section 6.3 Machining - Turret Lathe 1963 Operations 1000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Machining - Turret Lathe 1963 Operations 16 Th 3.21E-01 5 Generic Metal TBD, Section 6.3 Machining - Turret Lathe 1964 Operations 800 U234 6.25E-01 5 Generic Metal TBD, Section 6.3 Machining - Grinding 1962 Operations 500 U234 3.90E-01 5 Generic Metal TBD, Section 6.3 Machining - Grinding 1963 Operations 1000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Machining - Grinding 1963 Operations 16 Th 3.21E-01 5 Generic Metal TBD, Section 6.3 Machining - Grinding 1964 Operations 800 U234 6.25E-01 5 Generic Metal TBD, Section 6.3 Plant Floor High 1962 Operations 1000 U234 1.26E-02 5 Generic Metal TBD, Section 6.3 Plant Floor High 1963 Operations 2000 U234 7.82E-01 5 Generic Metal TBD, Section 6.3 Plant Floor High 1964 Operations 800 U234 1.56E+00 5 Generic Metal TBD, Section 6.3 Plant Floor High 1965 -'91 Residual 2000 U234 3.39E-06 5 Generic Metal TBD, Section 6.3 
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

External 

Whole 

Body 

(mR/d) GSD TBD Reference or Researc

Plant Floor Low 1962 Operations 1000 U234 1.56E+00 5 Generic Metal TBD, Section 6.3 Plant Floor Low 1963 Operations 2000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Plant Floor Low 1964 Operations 800 U234 1.56E+00 5 Generic Metal TBD, Section 6.3 Plant Floor Low 1965 -'91 Residual 2000 U234 1.76E-06 5 Generic Metal TBD, Section 6.3 Supervisor 1962 Operations 1000 U234 1.56E+00 5 Generic Metal TBD, Section 6.3 Supervisor 1963 Operations 2000 U234 7.81E-01 5 Generic Metal TBD, Section 6.3 Supervisor 1964 Operations 800 U234 1.56E+00 5 Generic Metal TBD, Section 6.3 Supervisor 1965 -'91 Residual 2000 U234 1.76E-06 5 Generic Metal TBD, Section 6.3 Clerical 1962 Operations 1000 U234 7.04E-06 5 Generic Metal TBD, Section 6.3 Clerical 1963 Operations 2000 U234 5.66E-05 5 Generic Metal TBD, Section 6.3 Clerical 1964 Operations 800 U234 3.23E-05 5 Generic Metal TBD, Section 6.3 Clerical 1965 -'91 Residual 2000 U234 2.80E-07 5 Generic Metal TBD, Section 6.3 
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Table CD.4 EXTERNAL DOSE PATHWAYS - Skin 

Assumptions: All assumptions from TBD-6000 Section 6.3 Operational Period: Non-penetrating dose to skin 115 mR/hour (hands and forearms) 10.4 mR/hour (other) 

Plant Floor High: Assume hands in contact with metal 50% of time. Other skin is 100% of dose rate at 1-fPlant Floor Low: 50% of Plant Floor High Supervisor: assume 10% of Plant Floor Low for time in contact with metal Clerical: assume no handling of U metal. 

Residual Period: Non-penetrating dose to skin 3.9E-06 mr/hour 

Assume no handling of U metal. Assume 10x the photon whole body dose rate 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Hands & 

Forearms 

(mR/d) 

Other Skin 

(mR/d) GSD TBD Refer

Extrusion Operator 1962 Operations 500 U234 1.58E+02 1.425E+01 5.000E+00 Generic Metal TExtrusion Operator 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TExtrusion Operator 1964 Operations 800 U234 2.52E+02 2.279E+01 5.000E+00 Generic Metal TExtrusion Billet Transfer 1962 Operations 500 U234 1.58E+02 1.425E+01 5.000E+00 Generic Metal TExtrusion Billet Transfer 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TExtrusion Billet Transfer 1964 Operations 800 U234 2.52E+02 2.279E+01 5.000E+00 Generic Metal TMachining - Turret Lathe 1962 Operations 500 U234 1.58E+02 1.425E+01 5.000E+00 Generic Metal TMachining - Turret Lathe 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TMachining - Turret Lathe 1963 Operations 16 Th 3.38E+00 1.607E+00 5.000E+00 Generic Metal TMachining - Turret Lathe 1964 Operations 800 U234 2.52E+02 2.279E+01 5.000E+00 Generic Metal TMachining - Grinding 1962 Operations 500 U234 1.58E+02 1.425E+01 5.000E+00 Generic Metal TMachining - Grinding 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TMachining - Grinding 1963 Operations 16 Th 3.38E+00 1.607E+00 5.000E+00 Generic Metal TMachining - Grinding 1964 Operations 800 U234 2.52E+02 2.279E+01 5.000E+00 Generic Metal T
Document No. Battelle-TBD-6000; Appendix CD Revision No. 0 Effective Date: 7/16/2007 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Hands & 

Forearms 

(mR/d) 

Other Skin 

(mR/d) GSD TBD Refer

Plant Floor High 1962 Operations 16 U234 5.04E+00 4.559E-01 5.000E+00 Generic Metal TPlant Floor High 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TPlant Floor High 1964 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TPlant Floor High 1965 -'91 Residual 2000 U234 1.17E-06 1.166E-06 5.000E+00 Generic Metal TPlant Floor Low 1962 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TPlant Floor Low 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TPlant Floor Low 1964 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TPlant Floor Low 1965 -'91 Residual 2000 U234 1.17E-06 1.166E-06 5.000E+00 Generic Metal TSupervisor 1962 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TSupervisor 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TSupervisor 1964 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TSupervisor 1965 -'91 Residual 2000 U234 1.17E-06 1.166E-06 5.000E+00 Generic Metal TClerical 1962 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TClerical 1963 Operations 1000 U234 3.15E+02 2.849E+01 5.000E+00 Generic Metal TClerical 1964 Operations 2000 U234 6.30E+02 5.699E+01 5.000E+00 Generic Metal TClerical 1965 -'91 Residual 2000 U234 1.17E-06 1.166E-06 5.000E+00 Generic Metal T