Battelle Team 

Dose Reconstruction 

Project for NIOSH

Document Title: 

Site Profiles for Atomic Weapons Employers that 

Worked Uranium and Thorium Metals 

Appendix CO – US Steel, National Tube Division 

Document Number: Battelle-TBD-6000 

Appendix CO

Revision: 0 

Effective Date: 6/15/2007 

Type of Document: TBD Appendix

Supersedes: None 

Subject Experts: R.I. Scherpelz, J.D. Catalano 

Document Owner 

Approval: Signature on file Approval Date: 5/30/2007 

Robert I. Scherpelz, Staff Scientist 

Approval Signature on file Approval Date: 5/30/2007 

Jay A. MacLellan, Battelle PNWD Task Manager 

Concurrence: Signature on file Concurrence Date: 5/30/2007 

Richard J. Traub, Staff Scientist 

Approval: Signature on file Approval Date: 6/8/2007 

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 CO 

Revision No. 0 Effective Date: 6/15/2007 Page 2 

US Steel Co. National Tube Divison 

CO.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. 

CO.2 Site Description 

The National Tube Division of US Steel operated a steel mill and pipe manufacturing 

plant. While there was no information in the site research database concerning overall 

operations at this facility, there were reasonably detailed descriptions of the covered 

processes, i.e. the rotary piercing of uranium bars. The AWE work at this facility was 

experimental, carried out in two 2-week campaigns in 1959 and 1960. 

Tests at the Christy Park Works, National Tube Division of the U. S. Steel Corporation, 

conducted in 1959 and 1960, demonstrated that rotary piercing of uranium was possible. 

The tests were conducted for National Lead of Ohio (Fernald).1

CO.2.1 Site Activities 

The AWE work at this site involved exclusively one study to explore the technique of 

rotary piercing for fabricating tubular fuel elements. The method tested involved rotary 

piercing a solid bar into a tubular section, and elongating and reducing the pierced section 

to a suitable size for machining to a hollow fuel element (machining the tubular elements 

was handled elsewhere under contract with National Lead Co.). Tests were run in two 

separate campaigns: April 14 – April 29, 1959 and February 17 – 26, 1960. In the first 

test, 11 billets were processed. The piercing was unsuccessful and another campaign was 

proposed. Modifications to the equipment included switching to a DC motor on the mill 

in order to permit slower and adjustable rolling speed. In the second test, 24 billets were 

successfully pierced. All equipment was completely decontaminated (the rollers were 

decontaminated by machining in the tool repair shop, to remove the outer contaminated 

layer). There was no residual contamination left at US Steel. 

The AWE work at this facility was extremely limited and would have involved very few 

employees (likely less than 10, including supervision). The layout of the facility and the 

specific location of the AWE work conducted there, are not described in any available 

reference. It is therefore difficult to determine the likelihood that claimants were involved 

in the AWE work at this facility. Nevertheless, employees potentially exposed include 

those operating, inspecting, or repairing furnaces and rolling mill equipment, including 

tool and die makers, and pipe fitters. Crane operators, given their work location (above 

and throughout the facility), are also potentially exposed to airborne dust associated with 

the rotary piercing process. 

CO.2.2 Job Categories 

Table CO.2 assigns all US Steel, National Tube Division claimant job titles as of the 

effective date of this appendix to one of the following four Job Categories. 
Document No. Battelle-TBD-6000; 

Appendix CO 

Revision No. 0 Effective Date: 6/15/2007 Page 3 

Plant Floor High (Involved directly in operations) 

Plant Floor Low (Involved in support of operations) 

Supervisor (Assumed to spend some time in the production areas) 

Clerk (Assumed to have minimal exposure) 

Claims forwarded to NIOSH by the Department of Labor after the effective date of this 

appendix will be evaluated during the dose reconstruction process to determine the most 

appropriate Job Category. 

CO.3 Occupational Medical Dose 

No information regarding occupational medical dose specific to US Steel, National Tube 

Division was found. Information to be used in dose reconstructions for which no specific 

information is available is provided in ORAUT-OTIB-0006, the dose reconstruction 

project technical information bulletin covering diagnostic x-ray procedures. 

CO.4 Occupational Internal Dose 

Limited air sampling and bioassay data were available from the second campaign 

(operations taking place between February 17 - 26, 1960), as well as bioassay data for 

uranium analysis of urine samples collected prior to and after the campaign. Ten 

individuals from US Steel, National Tube Division were monitored with bioassay, but the 

best available copy of the monitoring report is illegible for the names of the individuals. 

As a first estimate of the Plant Floor High exposure level, daily weighted averages for 

both operators whose exposures were monitored (furnace and mill) were calculated by 

assuming exposures at measured BZ values persisted 4 hours per day, with the remainder 

of the day at exposure equal to the average GA level. This is a favorable assumption 

since the time required for complete processing of one billet averages less than 10 

minutes (reference 10541, page 44), and a total of only 35 billets were processed during 

both campaigns (11 billets in the first campaign, and 24 in the second). The average of 

the two operator DWAs was assumed as the arithmetic mean of a lognormal distribution 

of plant floor high exposures. Given the nature of the work at this facility, intake 

estimates were then calculated based on limited exposure consisting of two 40-hour work 

weeks each in 1959 and 1960. Estimated intakes using this method were 13.2 pCi per 

day. 

Intake estimates based on the uranium bioassay data were also evaluated using the IMBA 

internal dosimetry computer code. The twenty bioassay results are shown in Table CO.1: 

Table CO.1. Urine bioassay data 

Sample Collection Date 

2/15/1960 3/17/1960 Net Change 

(mg/l U) (mg/l U) (mg/l U)

Individual 1 0.006 0.003 -0.003 

Individual 2 0.005 0.012 0.007 

Individual 3 0.035 0.011 -0.024 

Individual 4 0.006 0.016 0.010 

Individual 5 0.007 0.015 0.008 

Individual 6 0.005 0.008 0.003 

Individual 7 0.006 0.007 0.001 

Individual 8 0.005 0.014 0.009 

Individual 9 0.005 0.012 0.007 

Individual 10 0.008 0.008 0.000 
Document No. Battelle-TBD-6000; 

Appendix CO 

Revision No. 0 Effective Date: 6/15/2007 Page 4 

Only half the monitored individuals showed a significant increase in excreted uranium 

after the February 1960 campaign. However, because the bioassay results cannot be 

linked to an individual, the highest positive net change was used in the intake estimation 

as an assumption that is favorable to the claimant. The maximum individual net change 

(0.01 mg/L) converts to 9.9 pCi per day excretion. The resultant daily intake estimate 

obtained in this way was 3570 pCi per day assuming absorption of Class M compounds, 

and 123130 pCi per day assuming absorption of Class S compounds. These values are 

the daily intakes during the duration of the campaign. 

The bioassay results from samples collected prior to the 1960 campaign are near levels 

observed in an unexposed population, and cannot be used to estimate intakes during the 

1959 campaign. Doing so results in unrealistically high values. The 1960 intake 

estimates should therefore be used for both 1959 and 1960 even though the 1959 

campaign processed only half as many billets. 

Exposure to residual contamination is considered to be negligible since the work area and 

all equipment was reportedly decontaminated thoroughly after each of the 2-week tests 

was completed. 

Tables CO.3 and CO.4 contain inhalation and ingestion intakes in terms of pCi per day 

for each job category and each year. The absorption class most favorable to the claimant 

should be assumed. 

CO.5 Occupational External Dose 

The site research database contains information related to external dose in the form of 

smear samples collected during the second campaign (Reference 10541, pg 30). The 

average of the smear sample results represents exposure from surfaces during each of the 

2-week campaigns in 1959 and 1960. 

The file also contains badge data (Reference 10541, pg. 49). The badges were worn by 

National Lead Co. employees who were on site to observe the experiments. The badges 

represent the entire external whole body dose associated with the work for each of the 

two campaigns, as they were worn for the 2-week duration of the test. It was assumed 

that the distribution of these dosimeter readings could be used to represent the supervisor 

job category, and the other three generic job category external exposures could be scaled 

from this value. It was assumed that this value would represent the exposure for one 

year. 

Non-penetrating radiation doses were assigned using the assumptions of Section 6.3 of 

this TBD. 

Tables CO.5 and CO.6 contain external doses for whole body (penetrating) and skin 

(non-penetrating). 

CO.6 Residual Contamination 

After each of the two campaigns, the work area and all equipment were thoroughly 

decontaminated and the decontamination was documented. Decontamination after each of 

the campaigns was documented and available for review in the site research database. 

Based on the discussion of the procedures followed, it is unlikely that there was residual 

contamination, either between the two campaigns or after the experiments were 
Document No. Battelle-TBD-6000; 

Appendix CO 

Revision No. 0 Effective Date: 6/15/2007 Page 5 

completed in March 1960. See reference 10541 (pages 99 and 25 for the 1st and 2nd

campaigns respectively). Little potential exists for exposure to residual contamination2

. 

CO.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. Report on Residual Radioactive and Beryllium Contamination at Atomic Weapons 

Employer Facilities and Beryllium Vender Facilities. 

http://www.cdc.gov/niosh/ocas/pdfs/tbd/rescon/rcontam1206.pdf & 

http://www.cdc.gov/niosh/ocas/pdfs/tbd/rescon/appen-a2.pdf 
Document No. Battelle-TBD-6000; 

Appendix CO 

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Table CO.2. Job Categories for all current claimants who worked at US Steel, National Tube Division 

Job Title Exposure Category 

Crane Operator 1 

Crane Operator 1 

Craneman/Electrician 1 

Bricklayer 2 

Peeler Repairman 2 

Pipefitter 2 

Pipefitter 2 

Tool Engineer 2 

Utilities Analyst 2 

Inspector 3 

. 
Document No. Battelle-TBD-6000; Appendix CO Revision No. 0 Effective Date: 6/15/2007 

Table CO.3. INTERNAL DOSE PATHWAYS - Inhalation of Airborne Radionuclides Assumptions: Operational Period Maximum Intake Calculated from Bioassay Data: 9.9 pCi/day Uranium Urine Excretion Residual Period Daily Weighted Average Air Concentration: 0 dpm/m3

TBD GSD Default is 5 Conversion Factor :2.22 dpm/pCi Breathing Rate: 1.2 m3/hour 

All intakes and doses assume full-time employment for the given year (intake during operations spread over calendar yea

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Absorption 

Class 

Intake 

(pCi/d) GSD TBD Reference o

Plant Floor High 1959-‘60 Operations 80 U234 M 9.78E+01 5 Based on measured bPlant Floor High 1959-‘60 Operations 80 U234 S 3.37E+03 5 Based on measured bPlant Floor Low 1959-‘60 Operations 80 U234 M 4.89E+01 5 Based on measured bPlant Floor Low 1959-‘60 Operations 80 U234 S 1.69E+03 5 Based on measured bSupervisor 1959-‘60 Operations 80 U234 M 2.45E+01 5 Based on measured bSupervisor 1959-‘60 Operations 80 U234 S 8.43E+02 5 Based on measured bClerical 1959-‘60 Operations 80 U234 M 2.45E+00 5 Based on measured bClerical 1959-‘60 Operations 80 U234 S 8.43E+01 5 Based on measured b
Document No. Battelle-TBD-6000; Appendix CO Revision No. 0 Effective Date: 6/15/2007 

Table CO.4. INTERNAL DOSE PATHWAYS - Ingestion of Airborne Radionuclides Assumptions: Inhalation to Ingestion Ratio: 0.114 - see 3.5.2 TBD-6000 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Absorption 

Class 

Intake 

(pCi/d) GSD TBD Reference or Rese

Plant Floor High 1959 Operations 80 U234 M 1.12E+01 5 Based on inhalation estimPlant Floor High 1960 Operations 80 U234 S 3.85E+02 5 Based on inhalation estimPlant Floor Low 1959 Operations 80 U234 M 5.58E+00 5 Based on inhalation estimPlant Floor Low 1960 Operations 80 U234 S 1.92E+02 5 Based on inhalation estimSupervisor 1959 Operations 80 U234 M 2.79E+00 5 Based on inhalation estimSupervisor 1960 Operations 80 U234 S 9.61E+01 5 Based on inhalation estimClerical 1959 Operations 80 U234 M 2.79E-01 5 Based on inhalation estimClerical 1960 Operations 80 U234 S 9.61E+00 5 Based on inhalation estim
Document No. Battelle-TBD-6000; Appendix CO Revision No. 0 Effective Date: 6/15/2007 

Table CO.5. EXTERNAL DOSE PATHWAYS - Whole Body Asumptions: Submersion Dose Conversion Factor: 2.462E-09 mrem/h/dpm/m^3 Deposition velocity: 0.0008 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 Research 

Plant Floor High 1959 Operations 80 U234 1.98E+00 1.15 Based on external dosimeter readinPlant Floor High 1960 Operations 80 U234 1.98E+00 1.15 Based on external dosimeter readinPlant Floor Low 1959 Operations 80 U234 9.90E-01 1.15 Based on external dosimeter readinPlant Floor Low 1960 Operations 80 U234 9.90E-01 1.15 Based on external dosimeter readinSupervisor 1959 Operations 80 U234 4.95E-01 1.15 Based on external dosimeter readinSupervisor 1960 Operations 80 U234 4.95E-01 1.15 Based on external dosimeter readinClerical 1959 Operations 80 U234 4.95E-02 1.15 Based on external dosimeter readinClerical 1960 Operations 80 U234 4.95E-02 1.15 Based on external dosimeter readin
Document No. Battelle-TBD-6000; Appendix CO Revision No. 0 Effective Date: 6/15/2007 

Table CO.6. 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-f

Plant 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 

Skin: 

Hands & 

Forearms 

(mR/d) 

Skin – 

Other 

(mR/d) GSD TBD Reference or 

Plant Floor High 1959 Operations 80 U234 2.52E+01 2.28E+00 5 Generic Metal TBD, SePlant Floor High 1960 Operations 80 U234 2.52E+01 2.28E+00 5 Generic Metal TBD, SePlant Floor Low 1959 Operations 80 U234 1.26E+01 1.14E+00 5 Generic Metal TBD, SePlant Floor Low 1960 Operations 80 U234 1.26E+01 1.14E+00 5 Generic Metal TBD, SeSupervisor 1959 Operations 80 U234 1.26E+00 1.14E-01 5 Generic Metal TBD, SeSupervisor 1960 Operations 80 U234 1.26E+00 1.14E-01 5 Generic Metal TBD, SeClerical 1959 Operations 80 U234 0.00E+00 0.00E+00 5 Generic Metal TBD, SeClerical 1960 Operations 80 U234 0.00E+00 0.00E+00 5 Generic Metal TBD, Se