DOE Review 03/24/2014 

Document Number: Battelle-TBD-6000

Division of Compensation Analysis and Appendix C 

Support Effective Date: 04/03/2014 

Revision No. 1 

Site Profiles for Atomic Weapons Employers that Worked Page 1 of 18

Uranium Metals 

Appendix C – Dow Chemical Co. (Madison Site)

Document Owner: David Allen 

Supersedes: 

Approval:__ Signature on file _____ Date: 04/03/2014_ Appendix C rev. 0 

 J.W. Neton, Associate Director for Science 

RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

9/8/2008

EFFECTIVE 

DATE

9/8/2008

REV. NO. 

0

DESCRIPTION

Appendix to Battelle-TBD-6000 describing 

the use of the TBD for uranium exposures 

and presenting information for thorium 

exposures for claims at Dow Chemical Co. 

(Madison Site)

03/10/2014 04/03/2014 1 Revised to incorporate changes made during 

the revision of the base document TBD-6000.

Revisions include changes to inhalation

values during uranium operations, increased 

photon dose from contamination (based on 

30 day deposition) and added beta dose 

values based on contamination. Residual

period uranium inhalation values increased, 

OTIB-70 technique used during residual 

period, The basis for residual period 

ingestion values changed to use operational 

period airborne value and TIB-009 for the 

first year.

DOW CHEMICAL CO. (MADISON SITE) 

C.1 Introduction 

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

Weapons Employers that Worked Uranium Metals (Battelle 2011). This Site Profile 

presents site-specific information for the Dow Chemical Co. Madison, Illinois Site for 

which sufficient information has been found to provide more appropriate estimates of 

worker radiation dose than provided for in the technical basis document (TBD). Where 
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specific information is lacking, research into similar facilities described in the body of 

this Site Profile is used.

C.2 Site Description

From 1954 through 1969, the Dow Madison facility in Madison, Illinois was owned and 

operated by the Dow Metal Products Division of the Dow Chemical Company. Dow sold 

this facility in 1969 to Consolidated Aluminum, which continued to operate the facility 

from 1969 through 1986. Spectrulite subsequently purchased the plant from consolidated 

Aluminum (DOE web site).

From 1957 through 1960 the Dow Madison site performed several campaigns of work 

with uranium metal for the Mallinckrodt Chemical Works. The work involved both 

experimental extrusion of uranium metal and uranium metal rod straightening (DOE, 

1991). These rods were for use in the AEC nuclear weapons program. Therefore, in 

accordance with OCAS-IG-003 (NIOSH 2007a), radiation exposure from these uranium 

rods is covered during the contract period. Exposure from any residual contamination is 

also covered exposure in accordance with OCAS-IG-003.

The Madison site produced and commercially sold magnesium alloy during most of its 

history. Many of these magnesium alloys contained thorium. DOE determined that some 

of this alloyed magnesium was sold to the AEC in 1957 and 1958. DOE further 

concluded that the material sold in 1957 and 1958 may have been used in nuclear 

weapons manufactured between 1956 and 1969 (DOE, 2008). Therefore, in accordance

with OCAS-IG-003, the thorium related to the 1957 and 1958 magnesium alloy 

production is covered radiation exposure during the residual contamination period. Since 

during the contract period, all sources of radiation are covered exposure, all the thorium

work from 1957 to 1960 is covered exposure.

C.2.1 Site Activities

The Dow Madison site performed work with both uranium and thorium metal. The 

thorium work consisted of manufacturing magnesium alloy materials. The uranium work 

consisted of experimental extrusion of uranium billets into metal rods for Mallinckrodt 

Chemical Works. The Madison site also straightened uranium metal rods for 

Mallinckrodt Chemical Works.

C.2.1.1 Thorium Work

From 1958 until 1992, the Dow Chemical Company and the successor companies held 

AEC and State of Illinois licenses for the possession and use of thorium materials for the 

commercial production of magnesium-thorium alloys for various high temperature 

applications, including aeronautics and space programs. Licensed activities included 

storage in the waste sludge disposal area, which remained during the post-production 

period. 
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Magnesium-thorium alloy production at Dow Madison involved a number of 

metallurgical and mechanical operations. Activities included high temperature melting 

and alloying Th pellets or Mg-Th hardener with cell Mg, pouring molten alloy into 

casting pots and molds, breaking sludge out of crucibles, grinding/gouging/sanding, 

rolling, and packaging slabs and sheets of metal alloy (AEC, 1960).

C.2.1.2 Uranium Work

Two phases of uranium work for the U.S. AEC comprise the AWE covered work period:

C.2.1.2.a Uranium Extrusion

In 1957, Dow Madison was subcontracted by Mallinckrodt Chemical Works (MCW) to 

perform research and development work involving gamma-phase extrusion of uranium 

metal. According to the contract (AEC, 1957), the experimental extrusion work consisted 

of 12 consecutive monthly cycles, each consisting of 28 hours of work. Each monthly 

cycle was defined as 6 hours for set-up, 16 hours of extrusion, and 6 hours of clean-up. 

Dow was to provide auxiliary equipment and tool design expertise in addition to the use 

of its press, labor and plant facilities. Mallinckrodt responsibilities included procurement 

and installation of the auxiliary equipment designed and specified by Dow, modifications 

to dust arresting equipment and other protective equipment required by plant surveys 

ostensibly made during the course of the work, arrangement for a complete survey of 

breathing-zone air quality to be conducted periodically by the Health and Safety 

Laboratory, establishment of a program for area clearance after each cycle, supply of the 

billets allocated for each cycle, and clean up of billets or extruded metal after each cycle. 

Each work cycle involved the extrusion of 20 billets of Uranium. A total of 240 billets 

were processed in 12 consecutive months. The contract was signed on March 15th 1957. 

Giving a few months to startup, this appendix will assume this work occurred in six 

months of 1957 and six months of 1958 (168 hours each year).

C.2.1.2.b Uranium Rod Straightening

In March 1960, the Uranium Division of Mallinckrodt Chemical Works issued a purchase 

order (DOE, 1991) with DOW for the straightening of uranium rods supplied by MCW. 

Mallinckrodt personnel delivered the rods to the Dow Madison plant and picked them up 

after the straightening operation. Documentation has been found for two rodstraightening campaigns, one in December 1959 and one in January 1960. The quantities 

of Uranium metal involved in these operations are unknown, however, the total value of 

the purchase order, and the unit cost identified with lot size indicate that the quantity of 

metal involved was probably small (DOE, 1991). The two campaigns were completed a 

month apart (December 1959 and January 1960), therefore, each campaign must have 

lasted less than a few weeks. It therefore appears using the same 168 hour per year 

estimate as the extrusion campaigns would be favorable to the claimant.
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C.2.2 Job Categories

The uranium extrusion and straightening work was comprised of a few relatively short 

campaigns during the covered period. Workers from the regular Dow Madison 

commercial magnesium alloy operations were pulled from those activities to run the 

uranium extrusion and rod straightening campaigns. It is assumed that the workers in the 

uranium operations would have fulfilled job functions similar to their regular jobs in 

magnesium metal and alloy production. 

Four job exposure categories similar to the four generic job titles used in TBD-6000 have 

been determined for assigning radiation dose. 

Operators (Involved directly in operations; includes jobs such as Extrusion 

Press Operator, Saw Operator, Furnace Worker, Metal Caster)

Laborer (Involved in support of operations; includes jobs such as Fork Truck 

Operator, Crane Operator, Janitor Laborer, Pipefitter and other 

maintenance)

Supervisor (Assumed to spend time in the production areas but primarily not in 

a “hands on” job; includes jobs such as Foreman, Supervisor,

Inspector, Security)

Others (Jobs involving little or no time in production areas, primarily office 

jobs)

The job(s) performed by a claimant should be evaluated during the dose reconstruction 

process to determine the most appropriate job exposure category. Note that many 

claimants list more than one job title. If this is the case for a claimant for whom a dose 

reconstruction is being performed, the assigned dose should be prorated according to the 

time spent in each job if that information is available. If not, dose should be assigned 

according to the highest job exposure category applicable to that worker.

C.3 Occupational Medical Dose

No information regarding occupational medical dose specific to the Dow Madison Site 

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

information is available is provided in ORAUT-OTIB-0006 (ORAU, 2011), the dose 

reconstruction project technical information bulletin covering diagnostic x-ray 

procedures. 

C.4 Occupational Internal Dose

C.4.1 Uranium

No air sampling data were available for uranium operations during the period of 1957-

1960. Air concentrations from Table 7.2 of TBD-6000 were used to calculate uranium 

inhalation and ingestion quantities for 1957 and 1958. As described in section C.2.1.2.a, 

these air concentrations were assumed to be present for 168 hours each year.

Exposure from airborne uranium resuspended from surface contamination is also 

estimated. This exposure was assumed for the entire year, not just the uranium 
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operational time. The resuspension was calculated by assuming the uranium airborne 

contamination during operations settled to horizontal surfaces and was later resuspended. 

The contamination was assumed to accumulate for an entire period of time of uranium 

work with no removal mechanisms. Values necessary for this calculation are described 

in the body of TBD-6000. As a favorable assumption, the contamination value calculated 

at the end of this period was used to estimate the resuspended airborne value for the

entire time period.

For 1959 and 1960, air concentrations from Table 7.7 were used. The air concentrations 

in this table are driven by rod straightening and therefore appear to be a good 

representation of this work. As described in section C.2.1.2.b, these air concentrations 

were assumed to be present for 168 hours each year. Exposure from airborne uranium 

resuspended from surface contamination was again estimated using the same techniques 

as described above. However, for this period, the contamination was added to that 

already assumed present from the first two years. Again, the airborne value calculated 

from the contamination present at the end of this period was used for the entire period.

Ingestion doses were calculated using OCAS-TIB-009 (NIOSH 2004) and the operational 

airborne levels discussed above. This produces an ingestion rate equivalent to continuous 

work rather than intermittent work with uranium. Table C.1 contains inhalation and 

ingestion intakes in terms of dpm per day for each job category and each year. 

Contaminates from recycled uranium should be added to the uranium intakes based on 

Table 3.2 in TBD-6000.

C.4.2 Thorium

Data from a number of work area and breathing zone air samples taken during alloy 

production operations involving thorium were found, but NIOSH has determined

(NIOSH, 2007b) that the data are not sufficient to adequately determine the potential 

intake of thorium, making reconstruction of internal thorium doses infeasible.

C.5 Occupational External Dose

C.5.1 Uranium

No data were found related to occupational external dose from the uranium work at the 

Dow Madison site. The work performed at Dow Madison involved extruding uranium 

ingots and uranium rod straightening; therefore, the external dose values for the 

appropriate job category in Table 6.4 of TBD 6000 were used. The values associated 

with working directly with the metal were prorated to 168 hours per year. The values 

associated with submersion in a cloud and surface contamination were assumed to be 

present for the full year.

Table C.2 presents the values for whole body and skin dose to be used for each calendar 

year listed.
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C.5.2 Thorium

Dow conducted an estimate of the external radiation dose received while working in the 

pot room (Levy, 1957). The resulting estimate was 250 to 380 mr/yr when working with 

26% thorium hardener and 100 to 160 mr/yr when working with thorium pellets. 

Addendum 2 of the NIOSH SEC Evaluation Report for the Dow Madison site, estimated 

a bounding exposure of 1400 mr/yr. This estimate was based on 100% occupancy 1 foot 

from the highest area dose rate. TBD-6000 assumes an operator is one foot from the 

material 50% of the time. This adjustment provides an estimate of 700 mr/yr.

Some film badge data is available from Dow’s Bay City plant (Silverstein, 1957). Dow’s 

Bay City plant performed similar operations with similar material. This data was 

collected for a 13 day period during HK31 casting production. When a lognormal 

distribution of this data is assumed, the 95th percentile results in a dose of 1,095 mr/yr. 

This dose will be considered a bounding dose for the operator category. The Laborer 

category will be assumed to be half of this and the Supervisor category will be assumed 

to be half of the Laborer category. That results in an estimate of 274 mr/yr for the 

Supervisor category. This appears to be reasonably bounding since the geometric mean 

of the distribution is 254 mr/yr. The supervisor estimate is therefore higher than half of 

those monitored. For the “others” category, the 5th percentile of the distribution was 

used. The photon engery distribution assumed for thorium is 25% 30 kev – 250 kev and 

75% > 250 kev (General Electric, 1964). 

Various contact and surface measurements for the different materials used in the alloying 

process showed the measured beta component to be slightly less than the gamma 

component and falling to zero with distance (AEC, 1960; Saunders, 1960). Even though 

the beta component falls off with distance, this estimate will assume the beta dose is 

equal to the photon dose at all distances.

C.6 Dose from Residual Contamination

After the contract period, employees could still be exposed to residual contamination left 

over from the AEC related materials. Uranium contamination was discovered in the 

overhead structures and as a result, in 1992 the site was designated as part of the 

Formerly Utilized Site Remediation Action Program (FUSRAP). This program was 

transferred to the Army Corps of Engineers (ACE) in 1997. The ACE completed a 

remediation by mid-July 2000 (USACE web site). Therefore, this appendix will provide 

an estimate of uranium residual contamination dose until the end of July 2000. This 

estimate can then be used for any employees for whom DOL has verified employment 

through July 2000. The dose from residual uranium contamination after July 2000 is 

considered to be zero.

For the first year of the residual period, the estimate for inhalation and ingestion of 

uranium uses the same estimate as the last year of the operational period. After that, the 

intakes are reduced by 9.87% per year. This rate was derived in Addendum 2 of the SEC 

Evaluation Report for the Dow Madison site. The rate was derived for thorium but it is 
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site specific and more favorable than the default rate found in ORAUT-OTIB-0070 

(ORAU, 2012). These values are contained in Tables C.4 and C.5.

The external dose from residual uranium contamination utilizes the Battelle-TBD-6000

Table 6.4 for contamination. The scrape recovery task was used because it included rod 

straightening and was more favorable than extrusion. These values were used for the first 

year of the residual period and decreased each year after that the same as the intakes 

discussed above.

Residual thorium contamination was not part of the FUSRAP cleanup because DOE 

determined it was part of the commercial operations at the site (DOE, 1991). However, 

in January 2008, the DOE notified DOL and NIOSH that after additional research, DOE 

had concluded that Dow Madison did use thorium in AWE operations (DOE, 2008). 

DOE stated that in 1957 and 1958 Dow Madison supplied the AEC (via Mallinckrodt) 

with Mg-Th plates and sheets. DOE further concluded that this alloy may have been used 

to make components for nuclear weapons manufactured between 1956 and 1969. In 

accordance with OCAS-IG-003, all radiation exposure is considered during the AEC 

contract work. Therefore, thorium dose from operations is covered during the entire 

covered period (1957 through 1960). After 1960, only residual thorium contamination 

related to the weapons work is considered. Since reliable documentation is not available 

to distinguish between thorium related to weapons work and that related to commercial 

work, a bounding estimate based on all the thorium work between 1957 and 1958 is used. 

The residual thorium contamination is considered through the last day of the thorium 

cleanup. That date was reported to be October 31, 2006 (Cushman, 2008, NIOSH, 2007). 

However, the Project Closure Report indicated that the last thorium contamination was 

shipped off site in November, 2007 (Pangea, 2008). Therefore, this estimate will be 

applied to any DOL verified covered employment through November 30, 2007.

The thorium and thoron intakes during the residual contamination period are estimated 

using the technique described in Addendum 2 of the SEC Evaluation Report for the Dow 

Madison site (NIOSH, 2007b). That technique assumes the airborne concentrations 

during the first year of the residual period is equal to the airborne concentrations during 

thorium operations. This is considered a bounding estimate because much of the airborne 

contamination during operations is caused by the operation itself and not the resuspension 

of contamination remaining from previous operations. 

It was determined that intakes during the contract period could not be estimated because 

the airborne concentrations available could not be shown to be representative of most of 

the operational period. However, this does not prevent using the assumption that the 

intakes during the operational period bound the intakes caused by the resuspension of 

residual contamination. This is particularly true since some of the operational airborne 

concentration would be caused by the resuspension of contamination from previous 

operations. Also, incidents such as fires or explosions occurring in the residual 

contamination period do not affect this estimate. This is due to the fact that while such 

incidents may have occurred, it is highly unlikely they occurred due to the residual 

thorium contamination. It is much more likely they would have involved the material in 

process at the time. Table C.7 presents these values as thorium intakes to be used for 

each calendar year of the residual contamination period. These values should be assigned 
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as intakes of Thorium-232, Thorium-228, and Radium-228 each receiving a value equal 

to the values in Table C.7. An intake of Thorium-230 should be assigned that is two 

times the values of Table C.7 in accordance with page 30 of Addendum 2 of the SEC 

Evaluation Report for the Dow Madison site (NIOSH, 2007b). 

External dose from residual thorium contamination is accounted for by starting with the 

values indicated in section C.5.2. These are bounding estimates based on film badge data 

from similar operations with similar material. The values presented in section C.5.2 are 

used for the first year of the residual contamination period. For subsequent years, the 

values are decreased at the same rate as the internal intakes. The rate and the derivation 

of that rate are contained in Addendum 2 of the SEC Evaluation Report for the Dow 

Madison site. This effectively assumes that residual thorium is removed (due to fugitive 

emissions, tracking, housekeeping, etc) at the same rate for the internal and the external 

dose estimates. The external estimate is considered a bounding estimate because the 

majority of the external dose recorded on the film badges likely came from the in-process 

thorium material itself rather than residual contamination. Table C.8 presents whole 

body doses to be used for each calendar year of the residual contamination period. As 

with the operational period, the dose to the skin of the whole body will be added at a rate 

equal to the photon dose.

C.7 References

AEC, 1957, Agreement between Mallinckrodt Chemical Works and Dow Chemical 

Company for Experimental Extrusion Work, January 4, 1957 (SRDB ID 10273)

AEC, 1960, Compliance inspection Report: Dow Chemical Co. Site, Madison Illinois; U. 

S. Atomic Energy commission; August 4, 1960 (SRDB ID 29268)

Battelle, 2011, Battelle-TBD-6000 Rev 1, Site Profiles for Atomic Weapons Employers 

that Worked Uranium Metals, June 17, 2011

Cushman, 2008, Email concerning Madison Site, Matt Cushman, Pangea Group, March 

5, 2008 (SRDB ID 41940)

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

https://hsspublic.energy.gov/search/facility/findfacility.aspx

DOE, 1991, Authority Determination – Former Dow Chemical Company site, Madison 

IL, February 21, 1991 (SRDB ID 17484)

DOE, 2008, Letter from Department of Energy to Department of Labor, January 8, 2008 

(SRDB ID 54163)

General Electric, 1964, A comparison of Theoretical and Measured Dose Rates of 

Thorium and Thorium Oxide, J. N. Morgan, L. G. Faust, Radiological Development and 

Calibrations, Hanford Laboratories, General Electric, July 15, 1964. (SRPD ID 46086)

Levy, 1957, Memo from D. J. Levy, Dow Chemical Company, Madison, IL, March 8, 

1957 (SRDB ID 39977)
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NIOSH, 2004, Estimation of Ingestion Intakes, Technical Information Bulletin, OCASTIB-009, Revision 0, April 13, 2004

NIOSH, 2007a Radiation exposures covered for Dose Reconstructions under Part B of 

the Energy Employees Occupational Illness Compensation Program Act Rev. 0, OCASIG-003, National Institute for Occupational Safety and Health, Office of Compensation 

Analysis and Support, Cincinnati, Ohio

NIOSH, 2007b SEC Petition Evaluation Report Petition SEC-00079, National Institute 

for Occupational Safety and Health, April 13, 2007. Addendum 1, August 8, 2007. 

Addendum 2, June 3, 2008

ORAU, 2011, Dose Reconstruction from Occupational Medical X-Ray Procedures, Oak 

Ridge Associated Universities (ORAU), ORAUT-OTIB-0006, Revision 03 PC-1, June 

20, 2011

ORAU, 2012, Dose Reconstruction During Residual Radioactivity Periods at Atomic 

Weapons Employer Facilities, Oak Ridge Associated Universities (ORAU), ORAUTOTIB-0070, Revision 01, March 5, 2012

Pangea, 2008, Project closure Report for the Spectrulite Consortium Inc. Madison, IL 

Facility, Pangea Group, February 2008

Sauders, 1960, Memo from W. P. Sauders, Dow Chemical Company to Eugene D. 

McFall, U. S. Atomic Energy Commission, August 4, 1960 (TDCC 000233) 

Silverstein, 1957, Memo from Lawrence G. Silverstein, Dow Chemical Company to H. 

L. Price U. S. Atomic Energy Commission, June 26, 1957 (TDCC 000362)

USACE web site, U. S. Army Corps of Engineers, St. Louis District, FUSRAP website,

http://www.mvs.usace.army.mil/Missions/CentersofExpertise/FormerlyUtilizedSitesRem

edialActionProgram.aspx
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Table C.1 INTERNAL DOSE PATHWAYS - Inhalation of Airborne Uranium

All intakes and doses assume full-time employment for the given year.

Recycled uranium contaminates should also be assigned based on Table 3.2 of Battelle-TBD-6000

Job 

Category Year

Operation

Phase

Inhalation

(dpm/d)

Ingestion

(dpm/d) GSD TBD Reference or Research Justification

Operators 1957-1958 Operations 553 136 5 Based on Metal TBD for Extrusion

Operators 1959-1960 Operations 948 232 5 Based on Metal TBD for Scrap Recovery

Laborers 1957-1958 Operations 87 20 5 Based on Metal TBD for Extrusion

Laborers 1959-1960 Operations 481 116 5 Based on Metal TBD for Scrap Recovery

Supervisors 1957-1958 Operations 46 10 5 Based on Metal TBD for Extrusion

Supervisors 1959-1960 Operations 248 58 5 Based on Metal TBD for Scrap Recovery

Others 1957-1958 Operations 9 1 5 Based on Metal TBD for Extrusion

Others 1959-1960 Operations 38 6 5 Based on Metal TBD for Scrap Recovery
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Table C.2 EXTERNAL DOSE PATHWAYS - Uranium

Doses assume full-time employment for the given year.

Geometric Standard Deviation of 5 applies to all doses

Job 

Category Year

Operation

Phase

Photon

(mr/yr)

Skin-Whole 

Body

(mrem/yr)

Skin-Hands 

and Forarms

(mrem/yr) TBD Reference or Research Justification

Operators 1957-1960 Operations 177 1998 19571 TBD Table 6.4

Laborers 1957-1960 Operations 33 1000 9786 TBD Table 6.4

Supervisors 1957-1960 Operations 16 150 1029 TBD Table 6.4

Others 1957-1960 Operations 2 6 6 TBD Table 6.4
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Table C.3 EXTERNAL DOSE PATHWAYS - Thorium

Doses assume full-time employment for the given year.

Values are bounding and used as a constant distribution

Job 

Category Year

Operation

Phase

Photon

(mr/yr)

Skin-Whole 

Body

(mrem/yr) TBD Reference or Research Justification

Operators 1957-1960 Operations 1095 1095 Bay City film badge data (ln distrib.)

Laborers 1957-1960 Operations 548 548 Bay City film badge data (ln distrib.)

Supervisors 1957-1960 Operations 274 274 Bay City film badge data (ln distrib.)

Others 1957-1960 Operations 59 59 Bay City film badge data (ln distrib.)
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Table C.4 INHALATION INTAKES – Uranium

All intakes and doses assume full-time employment for the given year.

Recycled uranium contaminates should also be assigned based on Table 3.2 of Battelle-TBD-6000

Geometric Standard Deviation of 5 applies to all doses

Inhalation (dpm/day)

Year Operators Laborers Supervisor Others Year Operators Laborers Supervisor Others

1961 16.00 5.92 2.96 0.29 1984 1.65 0.61 0.31 0.03

1962 14.49 5.36 2.68 0.26 1985 1.50 0.55 0.28 0.03

1963 13.13 4.86 2.43 0.24 1986 1.36 0.50 0.25 0.02

1964 11.90 4.40 2.20 0.22 1987 1.23 0.45 0.23 0.02

1965 10.78 3.99 1.99 0.20 1988 1.11 0.41 0.21 0.02

1966 9.77 3.61 1.81 0.18 1989 1.01 0.37 0.19 0.02

1967 8.85 3.27 1.64 0.16 1990 0.91 0.34 0.17 0.02

1968 8.02 2.97 1.48 0.15 1991 0.83 0.31 0.15 0.02

1969 7.26 2.69 1.34 0.13 1992 0.75 0.28 0.14 0.01

1970 6.58 2.43 1.22 0.12 1993 0.68 0.25 0.13 0.01

1971 5.96 2.21 1.10 0.11 1994 0.62 0.23 0.11 0.01

1972 5.40 2.00 1.00 0.10 1995 0.56 0.21 0.10 0.01

1973 4.89 1.81 0.91 0.09 1996 0.51 0.19 0.09 0.01

1974 4.43 1.64 0.82 0.08 1997 0.46 0.17 0.08 0.01

1975 4.02 1.49 0.74 0.07 1998 0.42 0.15 0.08 0.01

1976 3.64 1.35 0.67 0.07 1999 0.38 0.14 0.07 0.01

1977 3.30 1.22 0.61 0.06 2000 0.34 0.13 0.06 0.01

1978 2.99 1.11 0.55 0.05

1979 2.71 1.00 0.50 0.05

1980 2.45 0.91 0.45 0.04

1981 2.22 0.82 0.41 0.04

1982 2.01 0.74 0.37 0.04

1983 1.82 0.67 0.34 0.03
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Table C.5 INGESTION INTAKES – Uranium

All intakes and doses assume full-time employment for the given year.

Recycled uranium contaminates should also be assigned based on Table 3.2 of Battelle-TBD-6000

Geometric Standard Deviation of 5 applies to all doses

Inhalation (dpm/day)

Year Operators Laborers Supervisor Others Year Operators Laborers Supervisor Others

1961 232 116 57.9 5.75 1984 23.9 12.0 5.99 0.59

1962 210 105 52.5 5.21 1985 21.7 10.8 5.42 0.54

1963 190 95.02 47.6 4.72 1986 19.6 9.82 4.91 0.49

1964 172 86.09 43.1 4.28 1987 17.8 8.89 4.45 0.44

1965 156 78.00 39.0 3.88 1988 16.1 8.06 4.03 0.40

1966 141 70.67 35.4 3.51 1989 14.6 7.30 3.65 0.36

1967 128 64.02 32.1 3.18 1990 13.2 6.61 3.31 0.33

1968 116 58.01 29.0 2.88 1991 12.0 5.99 3.00 0.30

1969 105 52.56 26.3 2.61 1992 10.9 5.43 2.72 0.27

1970 95.2 47.6 23.8 2.37 1993 9.84 4.92 2.46 0.24

1971 86.3 43.1 21.6 2.14 1994 8.91 4.46 2.23 0.22

1972 78.2 39.1 19.6 1.94 1995 8.08 4.04 2.02 0.20

1973 70.8 35.4 17.7 1.76 1996 7.32 3.66 1.83 0.18

1974 64.2 32.1 16.1 1.59 1997 6.63 3.31 1.66 0.16

1975 58.1 29.1 14.6 1.44 1998 6.01 3.00 1.50 0.15

1976 52.7 26.3 13.2 1.31 1999 5.44 2.72 1.36 0.14

1977 47.7 23.9 11.9 1.19 2000 4.93 2.46 1.23 0.12

1978 43.2 21.6 10.8 1.07

1979 39.2 19.6 9.81 0.97

1980 35.5 17.7 8.88 0.88

1981 32.2 16.1 8.05 0.80

1982 29.1 14.6 7.29 0.72

1983 26.4 13.2 6.61 0.66
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Table C.6 EXTERNAL PHOTON DOSE – Uranium

Doses assume full-time employment for the given year.

Geometric Standard Deviation of 5 applies to all doses

Annual Photon Dose (mr/yr)

Year Operators Laborers Supervisor Others Year Operators Laborers Supervisor Others

1961 2.59 1.29 0.65 0.06 1984 0.27 0.13 0.07 0.01

1962 2.35 1.17 0.59 0.06 1985 0.24 0.12 0.06 0.01

1963 2.13 1.06 0.53 0.05 1986 0.22 0.11 0.05 0.01

1964 1.93 0.96 0.48 0.05 1987 0.20 0.10 0.05 0.00

1965 1.75 0.87 0.44 0.04 1988 0.18 0.09 0.05 0.00

1966 1.58 0.79 0.39 0.04 1989 0.16 0.08 0.04 0.00

1967 1.43 0.71 0.36 0.04 1990 0.15 0.07 0.04 0.00

1968 1.30 0.65 0.32 0.03 1991 0.13 0.07 0.03 0.00

1969 1.18 0.59 0.29 0.03 1992 0.12 0.06 0.03 0.00

1970 1.07 0.53 0.27 0.03 1993 0.11 0.05 0.03 0.00

1971 0.97 0.48 0.24 0.02 1994 0.10 0.05 0.02 0.00

1972 0.87 0.44 0.22 0.02 1995 0.09 0.04 0.02 0.00

1973 0.79 0.39 0.20 0.02 1996 0.08 0.04 0.02 0.00

1974 0.72 0.36 0.18 0.02 1997 0.07 0.04 0.02 0.00

1975 0.65 0.32 0.16 0.02 1998 0.07 0.03 0.02 0.00

1976 0.59 0.29 0.15 0.01 1999 0.06 0.03 0.02 0.00

1977 0.53 0.27 0.13 0.01 2000 0.06 0.03 0.01 0.00

1978 0.48 0.24 0.12 0.01

1979 0.44 0.22 0.11 0.01

1980 0.40 0.20 0.10 0.01

1981 0.36 0.18 0.09 0.01

1982 0.33 0.16 0.08 0.01

1983 0.30 0.15 0.07 0.01
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Table C.7 EXTERNAL BETA DOSE – Uranium

Doses assume full-time employment for the given year.

Geometric Standard Deviation of 5 applies to all doses

Annual Beta Dose (mrad/yr)

Year Operators Laborers Supervisor Others Year Operators Laborers Supervisor Others

1961 251 126 63 6 1984 26 13 6 1

1962 227 114 57 6 1985 23 12 6 1

1963 206 103 52 5 1986 21 11 5 1

1964 187 94 47 5 1987 19 10 5 0

1965 169 85 42 4 1988 17 9 4 0

1966 153 77 38 4 1989 16 8 4 0

1967 139 70 35 3 1990 14 7 4 0

1968 126 63 31 3 1991 13 7 3 0

1969 114 57 29 3 1992 12 6 3 0

1970 103 52 26 3 1993 11 5 3 0

1971 94 47 23 2 1994 10 5 2 0

1972 85 43 21 2 1995 9 4 2 0

1973 77 39 19 2 1996 8 4 2 0

1974 70 35 17 2 1997 7 4 2 0

1975 63 32 16 2 1998 7 3 2 0

1976 57 29 14 1 1999 6 3 1 0

1977 52 26 13 1 2000 5 3 1 0

1978 47 24 12 1

1979 42 21 11 1

1980 38 19 10 1

1981 35 18 9 1

1982 32 16 8 1

1983 29 14 7 1
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Table C.8 INTERNAL DOSE PATHWAYS - Thorium

Thorium intakes should be assigned for Th-232, Th-228, and Ra-228. Two times these values for Th-230.

Values are bounding and used as a constant distribution

Year

Inhalation

(dpm/d)

Ingestion

(dpm/d)

Thoron

Year

Inhalation

(dpm/d)

Ingestion

(dpm/d)

Thoron

(pCi/L) (WLM) (pCi/L) (WLM)

1961 123 2.57 0.247 0.391 1984 12.7 0.265 0.026 0.040

1962 112 2.33 0.224 0.354 1985 11.5 0.240 0.023 0.037

1963 101 2.11 0.203 0.321 1986 10.4 0.218 0.021 0.033

1964 91.6 1.91 0.184 0.291 1987 9.47 0.197 0.019 0.030

1965 83.0 1.73 0.166 0.264 1988 8.58 0.179 0.017 0.027

1966 75.2 1.57 0.151 0.239 1989 7.77 0.162 0.016 0.025

1967 68.1 1.42 0.137 0.216 1990 7.04 0.147 0.014 0.022

1968 61.7 1.29 0.124 0.196 1991 6.38 0.133 0.013 0.020

1969 55.9 1.17 0.112 0.178 1992 5.78 0.120 0.012 0.018

1970 50.7 1.06 0.102 0.161 1993 5.24 0.109 0.010 0.017

1971 45.9 0.957 0.092 0.146 1994 4.74 0.099 0.010 0.015

1972 41.6 0.867 0.083 0.132 1995 4.30 0.090 0.009 0.014

1973 37.7 0.785 0.076 0.120 1996 3.89 0.081 0.008 0.012

1974 34.1 0.711 0.068 0.108 1997 3.53 0.073 0.007 0.011

1975 30.9 0.645 0.062 0.098 1998 3.20 0.067 0.006 0.010

1976 28.0 0.584 0.056 0.089 1999 2.90 0.060 0.006 0.009

1977 25.4 0.529 0.051 0.081 2000 2.62 0.055 0.005 0.008

1978 23.0 0.479 0.046 0.073 2001 2.38 0.050 0.005 0.008

1979 20.8 0.434 0.042 0.066 2002 2.15 0.045 0.004 0.007

1980 18.9 0.393 0.038 0.060 2003 1.95 0.041 0.004 0.006

1981 17.1 0.357 0.034 0.054 2004 1.77 0.037 0.004 0.006

1982 15.5 0.323 0.031 0.049 2005 1.60 0.033 0.003 0.005

1983 14.0 0.293 0.028 0.045 2006 1.45 0.030 0.003 0.005
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Appendix C

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Page 18 of 18

Table C.9 EXTERNAL DOSE PATHWAYS – Thorium – Residual period

Values are bounding and used as a constant distribution

Year

Photon (mr/yr)

Year

Photon (mr/yr)

Operators Laborers Supervisor Others Operators Laborers Supervisor Others

1961 1095 548 274 59 1984 113 57 28 6

1962 992 496 248 54 1985 103 51 26 6

1963 899 450 225 49 1986 93 46 23 5

1964 815 407 204 44 1987 84 42 21 5

1965 738 369 185 40 1988 76 38 19 4

1966 669 334 167 36 1989 69 35 17 4

1967 606 303 151 33 1990 63 31 16 3

1968 549 274 137 30 1991 57 28 14 3

1969 497 249 124 27 1992 51 26 13 3

1970 451 225 113 24 1993 47 23 12 3

1971 408 204 102 22 1994 42 21 11 2

1972 370 185 92 20 1995 38 19 10 2

1973 335 168 84 18 1996 35 17 9 2

1974 304 152 76 16 1997 31 16 8 2

1975 275 138 69 15 1998 28 14 7 2

1976 249 125 62 13 1999 26 13 6 1

1977 226 113 56 12 2000 23 12 6 1

1978 205 102 51 11 2001 21 11 5 1

1979 185 93 46 10 2002 19 10 5 1

1980 168 84 42 9 2003 17 9 4 1

1981 152 76 38 8 2004 16 8 4 1

1982 138 69 34 7 2005 14 7 4 1

1983 125 62 31 7 2006 13 6 3 1