DOE Review Release 03/20/2012

Division of Compensation Analysis and 

Support

Document Number: Battelle-TBD-6000

Appendix D

Effective Date: 09/11/2012

Revision No. 0

Site Profiles for Atomic Weapons Employers that Worked Uranium 

Metals - Appendix D

Bliss and Laughlin Steel 

Page 1 of 9

Document Owner: David Allen

Subject Expert: Sam Glover

Approval: Signature on file Date: _09/11/2012_

 J.W. Neton, Associate Director for Science

Supersedes: None

RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

03/14/2012

09/04/2012

EFFECTIVE 

DATE

03/14/2012

09/04/2012

REV. NO. 

0-A

0-B

DESCRIPTION

Appendix to Battelle-TBD-6000 describing 

the use of the TBD for claims at Bliss and 

Laughlin Steel

Minor changes made including typos and 

clarification of some points.

D.1 Introduction

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

Weapons Employers that Worked Uranium 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.

D.2 Site Description

Under contract to the National Lead Company of Ohio (Fernald), Bliss and Laughlin 

Steel rolled uranium rods for the Atomic Energy Commission (AEC) and also provided 

uranium slug machining services. Bliss and Laughlin was part of a complex called the 

“The Buffalo Works” portions of which were operated by Bliss and Laughlin, Bethlehem 

Steel, and American Car and Foundry, which fashioned components for the early 

weapons program. 

The former Bliss and Laughlin Steel Company site was located at 110 Hopkins Street in 

Buffalo, New York. The facility consisted of a single building with a floor area of 

approximately 129,600 square feet. Bliss and Laughlin operated the site from 1929 to 

1971, producing cold-finished steel bars for heavy equipment such as automobiles, 

appliances, construction machinery, and farm equipment. 

D.2.1 Site Activities

During September and October of 1952 the Bliss and Laughlin Steel Company machined 
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Document Number: Battelle-TBD-6000

Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 2 of 9

and straightened uranium rods for the AEC to improve the rod diameter tolerance. 

Machining operations were performed at a location in the building designated as the 

“Special Finishing Area” which occupied approximately 3,230 square feet of floor space 

and was open (without inside walls or partitions) (ORAUT 1992). The floor in that area 

was characterized as rough surface concrete with several shallow utility trenches 

providing water, electricity, lubricant, and pneumatic plant services. 

Available records indicate that Bliss and Laughlin performed five normal assay rodmachining campaigns for the AEC; one in April 1951 and four in September and October 

1952 (Hershman 1952). During September and October 1952 Bliss and Laughlin was 

under contract to National Lead of Ohio (NLO), a contractor for all operations at the Feed 

Material Production Center at Fernald, Ohio, to machine and straighten uranium rods. 

D.2.1.1 Operations - 1951

On April 24, 1951 at least twenty 1-5/8” diameter rough-rolled rods were shipped from 

Lake Ontario Ordnance Works to Bliss and Laughlin and machined to a slightly smaller 

diameter and then water quenched. That same day the machined rods were shipped back 

to Lake Ontario Ordnance Works (AEC 1951) where they would subsequently be shipped 

to Bethlehem Steel for further rolling. This work resulted in the accumulation of four 

drums of dry uranium oxide (Koenig 1951) that the AEC shipped to Mallinckrodt 

Chemical Works in St. Louis, probably in November or December 1951.

D.2.1.1 Operations - 1952

In September and October 1952 machining operations were conducted on one Friday and 

three Saturdays (ORAUT 1992). Weekend schedules were used to avoid significantly 

impacting normal operations, and possibly, to enhance security and radiological safety. 

The exact quantity of uranium and duration of the operations is not known (ORAUT 

1992), but due to the relatively short duration of the operations, total quantities can be 

assumed to have been somewhat limited.

Rods were shipped from Lake Ontario Ordnance Works to Bliss and Laughlin Steel for 

machining and straightening. The finished rods were shipped to NLO at Fernald, Ohio 

and 53 drums of turnings were sent via AEC trucks to Lake Ontario Ordnance Works for 

packaging. The turnings were then sent from Lake Ontario Ordnance Works to Fernald 

in November of 1952 (ORAUT 1992). 

AEC personnel arranged for the transportation of all raw materials, wastes, and products 

to and from the site. Bliss and Laughlin personnel were not involved with these aspects 

of the operation. 

D.3 Occupational Medical Dose

No information regarding occupational medical dose was found in any of the site 

research. 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. 
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Document Number: Battelle-TBD-6000

Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 3 of 9

D.4 Occupation Internal Dose

Air sample data was collected during the 1952 rod-turning operations at Bliss and 

Laughlin. Air samples were taken on September 26th, September 27th, October 4th, and 

October 11th (NLO 1952). Samples included general area (GA), process (P), and 

breathing zone (BZ) data. 

Two notations in the data in written reports forced some BZ and GA data to be excluded. 

On the air sample data sheets a fan is noted as being used for some samples and is also 

discussed in a memo from NLO. These data were not included in the evaluation of air 

sampling to determine internal dose. Additionally, some samples were noted as being 

obtained when AEC operations were not being conducted. These samples were also 

excluded. 

An analysis of 20 total samples (13 BZs and 7 GAs) was conducted. The measured air 

concentrations from the samples were distributed and produced a geometric mean of

2,602 dpm/m3 with a geometric standard deviation (GSD) of 2.04. This was compared to 

the default air concentration value of 5,800 dpm/m3contained in Table 7.5 of BattelleTBD-6000 for an operator machining uranium. Because fo the limited number of air 

samples, , the air concentration value from Battelle-TBD-6000 was determined to be 

more claimant-favorable and was utilized to determine inhalation and ingestion quantities

during years of AEC operations at Bliss and Laughlin. 

Inhalation quantities for operational days 1951 and 1952 were determined by using the 

air concentration value of 5,800 dpm/m3and multiplying by the number of AEC 

operational days per year and assuming an 8.8 hour work day. 

Inhalation quantities for non-operational days in 1951 and 1952 were determined by 

using the air concentration value of 5,800 dpm/m3to determine a surface contamination

value and applying a contamination decay constant 0.0001888 (0.01888% per day). This

value was calculated using assumptions on the deposition velocity and using claimant 

favorable data from FUSRAP measurements (Battelle 2011). The average air 

concentration for the non-operational days was multiplied by the number of nonoperational days per year and an 8.8 hour workday producing an inhalation quantity for 

non-operational days. 

The residual activity decay factor was determined by assuming an air concentration value 

of 5480 dpm/m3, a deposition velocity of 7.50E-4 m/s, five rolling days of 8.8 hours to 

derive a surface contamination value of 6510 dpm/100 cm2. Since the highest removable 

alpha surface contamination value of 430 dpm/m3, the resulting decay constant was 

determined to be 0.0001888 per day.

The total inhalation values for operational and non-operational days for each year were 

summed and then divided by the number of calendar days in the performance period to 

produce an inhalation rate for each year. Ingestion doses were calculated using OCASTIB-009 (NIOSH 2004). 

All workers at Bliss and Laughlin are assumed to have worked daily in the Special 
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Document Number: Battelle-TBD-6000

Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 4 of 9

Finishing Area during the AEC operational time period. Table D.1 contains inhalation 

and ingestion intakes in dpm per calendar day which are applied as a lognormal 

distribution with a GSD of 5. Solubility types M and S should be considered to 

maximize the radiation dose. The ingestion f1 value used should be the same as that 

used for inhalation. 

D.5 Occupation External Dose

No external dosimetry data are available for the AWE operations conducted at Bliss and 

Laughlin in 1951 and 1952. Therefore, external dose rates from Battelle-TBD-6000, 

contamination surveys conducted at Bliss and Laughlin, and conservative estimates on 

the amount of material that may have been at Bliss and Laughlin were used to estimate 

external dose received during the AEC operations. 

D.5.1 Dose from Contaminated Surfaces and Air Submersion

External dose from residual contamination was received from exposures to contaminated 

surfaces and from submersion in contaminated air. Dose from these sources was

determined by using the default air concentration value of 5,800 dpm/m3to determine the 

initial loading of the surfaces following each AEC production campaign. A deposition 

velocity of 7.5E-04 meters per second and the number of hours of exposure per work day 

were applied to produce surface contamination values in dpm/m2. A contamination 

decay constant of 1.888E-04 per day was applied to the air and surface contamination 

values beginning on April 25, 1951. An 8.8 hour work day is assumed. This dose was 

then normalized for 251 days for 1951 and 365 days for 1952. 

D.5.2 Dose from Uranium Metal

The external whole body dose from exposures to the uranium metal used in the uranium 

machining operations at Bliss and Laughlin were determined by using the dose values in 

Tables 6.2 and 6.3 Battelle-TBD-6000 for an Operator working with or near bare metal 

for 44 hours per week. These dose rates were adjusted to 8.8 hours of contact time per 

work day. For each uranium operations work day, two additional drum handling days are 

also assumed at the same dose rates and hours of contact as the bare metal exposures. 

This dose was then normalized for the number of operational days per year.

All workers at Bliss and Laughlin are assumed to have worked daily in the Special 

Finishing Area during the AEC operational time period. Table D.2 contains external 

dose values in mrem per year which are applied as a lognormal distribution with a GSD 

of 5. Penetrating radiation was assigned as photons 100% in the 30-250 keV energy 

range. Non-penetrating radiation was assigned as 100% electrons with energies >15 keV. 

D.6 Residual Contamination

After the contract period, employees were potentially exposed to residual contamination 

left over from the AEC related operations. The residual contamination time period at 

Bliss and Laughlin was from 1953 through 1998. 

D.6.1 Internal Dose
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Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 5 of 9

Residual radioactivity was determined to be present at Bliss and Laughlin and 

documented in a 1992 Formerly Utilized Site Remediation Action Program (FUSRAP)

report (ORAUT 1992). The surface activity measurements in the Special Finishing Area 

showed several areas had total beta-gamma activity levels ranging from 4,700 dpm/100 

cm2to 700,000 dpm/100 cm2and showed the highest level of removable alpha activity to 

be 430 dpm/100 cm2.

As a claimant-favorable measure the default air concentration value of 5,800 dpm/m3 was 

used to determine the initial loading of the surfaces following each AEC production 

campaign ended in 1952. An initial air concentration was then calculated based on that 

surface contamination value. A contamination decay constant of 0.0001888 per day was 

applied based as described previously instead of the default value (Battelle 2011). This 

value was then multiplied by an 8.8 hour workday for 365 days each year. Ingestion 

doses were calculated using OCAS-TIB-009 (NIOSH 2004). 

All workers at Bliss and Laughlin are assumed to have worked daily in the Special 

Finishing Area during the residual contamination time period. Table D.1 contains 

inhalation and ingestion intakes in dpm per calendar day which are applied as a 

lognormal distribution with a GSD of 5. Solubility types M and S should be considered

to maximize the radiation dose. The ingestion f1 value used should be the same as 

that used for inhalation. 

D.6.2 External Dose

External dose from residual contamination was received from exposures to contaminated 

surfaces and from submersion in contaminated air. Dose from these sources was

determined by using the default air concentration value of 5,800 dpm/m3to determine the 

initial loading of the surfaces following each AEC production campaign. A deposition 

velocity of 7.5E-04 meters per second and the number of hours of exposure per work day 

were applied to produce surface contamination values in dpm/m2. A contamination 

decay constant of 1.888E-04 per day was applied to the air and surface contamination 

values. An 8.8 hour work day is assumed through 1955 and an 8 hour work day from 

1956 through 1998. This dose was then normalized for 251 days for 1951 and 365 days 

for 1952 through 1998. The calculated dose from exposure to contaminated surfaces and 

the calculated dose from submersion in air were combined and applied as a total photon 

dose per year.

All workers at Bliss and Laughlin are assumed to have worked daily in the Special 

Finishing Area during the residual contamination time period. Table D.3 contains 

external dose values in mrem per year which are applied as a lognormal distribution with 

a GSD of 5. Penetrating radiation is assigned as photons 76.7% in the >30 keV energy 

range, 10% in the 30-250 keV energy range, and13.3% in the >250 keV energy range. 

D.7 References

AEC (Atomic Energy Commission), 1951, Memo “Uranium Fabrication Test” to W. 

Kirkman, Director Security Division, Risenbud, Director of Health and Safety, J. Smith, 

Jr., Chief, Operations Branch, Production Division, New York, 1951. (SRDB ID 7016).
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Document Number: Battelle-TBD-6000

Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 6 of 9

Battelle, 2011, Battelle-TBD-6000, Site Profiles for Atomic Weapons Employers that 

Worked Uranium Metals, Rev 1, June 17, 2011.

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

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

Hershman, 1952, Memo “Monthly Progress Report for October 1952 Covering Activities 

Under the Tonawanda Sub-Office” from H. J. Hershman, Chief, Tonawanda Sub-Office, 

to R.J. Smith, Jr. Chief, Operations Branch, Production Division, New York, October 21, 

1952. (SRDB ID 10751).

Koenig, 1951, Memo “Shipment of Uranium Oxide” from J. Koenig, Chief Operations 

Branch, St. Louis Area, St. Louis, MO, to P.W. Malone, Chief, Tonawanda Sub-Office, 

Model City , New York, October 1, 1951. (SRDB ID 59173).

NLO (National Lead Company of Ohio), 1952, Air Sample Data Sheets for Bliss and 

Laughlin for September 26, 1952, September 27, 1952, October 4, 1952, and October 11, 

1952. (SRDB ID 3794).

NIOSH, 2004, Estimation of Ingestion Intakes, Technical Information Bulletin, OCAS 

TIB-009, Rev 0, April 13, 2004.

NIOSH, 2009, SEC Petition Evaluation Report, Petition SEC-00131, National Institute 

for Occupational Safety and Health, June 30, 2009. 

NIOSH, 2010, Radiation Exposures Covered for Dose Reconstructions Under Part B of 

the Energy Employees Occupational Illness Compensation Program Act, Rev 0, DCASIG-003, Division of Compensation Analysis and Support, Cincinnati, Ohio.

ORAUT, 1992, Radiological Survey of the Former Bliss and Laughlin Steel Company 

Facility, Buffalo, New York , J.D. Berger, Environmental Survey and Site Assessment 

Program, Energy/Environmental Systems Division, Oak Ridge Institute for Science and 

Education, June 1992. (SRDB ID 6980).

ORAUT, 2011, Technical Information Bulletin: Dose Reconstruction from 

Occupationally Related Diagnostic X-Ray Procedures, ORAUT-OTIB-0006, Rev 04,

June 20, 2011.
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Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 7 of 9

Table D.1 Internal Dose Pathways – Inhalation of Airborne Radionuclides

Assumptions: 

Derivation of values described in Sections D.4 and D.6.1,

Operations Period: Inhalation and ingestion values were based on an 8.8 hour work day and were normalized for the number of operational days per year.

Residual Period: Inhalation and ingestion values were calculated assuming an 8.8 hour workday through 1955 and an 8 hour work day from 1956 through 1998.

All employees worked in the Special Finishing Area.

Values represent the geometric mean of a lognormal distribution. 

Time Period Operation 

Phase

Nuclide Inhalation 

(dpm/calendar day)

Ingestion 

(dpm/calendar day)

GSD TBD Reference or Research Justification

04/24/1951 –

12/31/1951

Operations U-234 2.315E+02 4.567E+00 5 TBD-6000 Table 7.5 for Operator

1952 Operations U-234 7.947E+02 1.568E+01 5 TBD-6000 Table 7.5 for Operator

1953 Residual U-234 5.284E+00 1.043E-01 5 Residual from operations: assume deposition and resuspension

1954 Residual U-234 4.931E+00 9.729E-02 5 Residual from operations: assume deposition and resuspension

1955 Residual U-234 4.602E+00 9.080E-02 5 Residual from operations: assume deposition and resuspension

1956 Residual U-234 3.904E+00 8.134E-02 5 Residual from operations: assume deposition and resuspension

1957 Residual U-234 3.644E+00 7.591E-02 5 Residual from operations: assume deposition and resuspension

1958 Residual U-234 3.400E+00 7.084E-02 5 Residual from operations: assume deposition and resuspension

1959 Residual U-234 3.173E+00 6.611E-02 5 Residual from operations: assume deposition and resuspension

1960 - 1969 Residual U-234 2.215E+00 4.614E-02 5 Residual from operations: assume deposition and resuspension

1970 - 1979 Residual U-234 1.112E+00 2.316E-02 5 Residual from operations: assume deposition and resuspension

1980 - 1989 Residual U-234 5.579E-01 1.162E-02 5 Residual from operations: assume deposition and resuspension

1990 - 1998 Residual U-234 2.888E-01 6.016E-03 5 Residual from operations: assume deposition and resuspension

*Exposure rates for 1960 – 1998 can be overestimated by using the 1959 data for all later years. 
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Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 8 of 9

Table D.2 External Dose Pathways – Operational Period 

Assumptions:

Derivation of values described in Section D.5. 

Dose values were based on an 8.8 hour work day and were normalized for the number of operational days per year.

All employees worked in the Special Finishing Area.

Values represent the geometric mean of a lognormal distribution. 

Annual Values (mrem)

Year Air Submersion Contaminated 

Surfaces

Whole Body Non-Penetrating 

(hands and 

forearms)

Non-Penetrating 

(other skin)

GSD TBD Reference or Research Justification

1951 1.194E-04 1.574E-01 3.762E+01 4.158E+03 3.780E+02 5 TBD-6000 Section 3.2, Tables 6.2 and 6.3

1952 5.952E-04 3.322E-01 1.881E+02 2.079E+04 1.890E+03 5 TBD-6000 Section 3.2, Tables 6.2 and 6.3
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Appendix D

Effective Date: 09/11/2012 Revision No. 0 Page 9 of 9

Table D.3 External Dose Pathways – Residual Contamination Period

Assumptions:

Derivation of values described in Sections D.6.2.

Dose values were calculated assuming an 8.8 hour workday through 1955 and an 8 hour work day from 1956 through 1998. 

All employees worked in the Special Finishing Area.

Values represent the geometric mean of a lognormal distribution. 

Annual Values (mrem/year)

Year(s) Photon Dose GSD TBD Reference or Research Justification

1953 1.318E+00 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1954 1.230E+00 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1955 1.148E+00 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1956 9.741E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1957 9.082E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1958 8.476E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1959 7.910E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1960 - 1969 5.521E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1970 - 1979 2.771E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1980 - 1989 1.392E-01 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.

1990 - 1998 7.917E-02 5 Residual from operations; air submersion and contaminated floors/surfaces, 

TBD-6000 Section 3.2, Tables 6.2 and 6.3.