ORAU Team

NIOSH Dose Reconstruction Project

Technical Basis Document for the Fernald Environmental 

Management Project (FEMP) – Occupational Environmental Dose

Document Number:

ORAUT-TKBS-0017-4 

Effective Date: 04/06/2004

Revision No.: 00

Controlled Copy No.: ______

Page 1 of 83

Subject Expert: Samuel L.T. Chu

Document Owner

Approval: Signature on File Date: 04/06/2004

Terry A. Kuykendall, TBD Team Leader

Approval: Signature on File Date: 04/06/2004

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Date: 04/06/2004 Richard E. Toohey, Project Director

Approval: Signature on File Date: 04/06/2004 James W. Neton, OCAS Health Science Administrator

Supersedes:

None

TABLE OF CONTENTS

Section

Record of Issue/Revisions ...................................................................................................................

Page

4

Acronyms and Abbreviations ...............................................................................................................5

4.0 Occupational Environmental Dose ..............................................................................................6

4.1 Introduction................................................................................................................................. 7

4.2 Site Background and History.......................................................................................................7

4.3 Internal Doses from Atmospheric Radionuclide Concentrations .................................................. 8

4.3.1 Airborne Radioactive Materials Emissions (from 1951 to 1988) ........................................... 8

4.3.2 Onsite Environmental Radioactive Material Air Concentrations and 

Intake for 1951 to 1988)..................................................................................................... 13

4.3.2.1 Exposure Site Locations ........................................................................................... 13

4.3.2.2 Airborne Radionuclide Concentration Derivation ....................................................... 13

4.3.2.3 Radionuclide Concentrations and Intake from Routine Emissions............................. 19

4.3.3 Onsite Air Monitored Average Concentrations (1989 to 2002) ........................................... 21

4.3.4 Airborne Radionuclide Concentration and Intake Summary for Years 

1951 through 2002 (Table 4-9) .......................................................................................... 25

4.3.5 Site-Wide Average Intake Summary by Isotopes for Years 1951 through 

2002 (Table 4-10) .............................................................................................................. 38

4.4 On-Site external Doses from Ambient Radiation ....................................................................... 39

4.4.1 K-65 and Production Plants External Dose Contribution .................................................... 39

4.4.2 External Dose Contribution from Waste Pits ...................................................................... 42

4.4.3 On-site Ambient Dose rate Estimate.................................................................................. 46

4.4.4 On-site External Ambient Dose rate (Table 4-17)............................................................... 50

References ........................................................................................................................................55

Glossary ............................................................................................................................................57
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 2 of 83

Appendix 4A FEMP radionuclide concentration and intake results by exposure 

area and year ............................................................................................................. 58

Appendix 4A FEMP radionuclide concentration and intake results by exposure 

area and year ................................................................................. .......................... 83 

LIST OF TABLES

Table Page

4-1 FEMP uranium emissions summary by plant............................................................................9

4-2a Fugitive uranium and thorium emissions from wind erosion of Waste Pits 1, 2 and 3.............10

4-2b Fugitive uranium and thorium emissions from wind erosion of Waste Pits 4, 5 and 6.............11

4-3 Thorium emission estimates by year (Kg) ..............................................................................12

4-4 Summary of 222Rn and 222Rn daughter product releases for drummed K-65 material stored on 

the Plant 1 Pad........ .............................................................................................................12

4-5 Facilities and buildings in each Exposure Area ......................................................................13

4-6 (χ/Q) values versus distances from the emission source........................................................15

4-7 Receptor downwind distances from contributing emission sources (m).................................. 16 

4-8 Percentage of time that the wind blew in the direction of the EAs...........................................17

4-9a Radionuclide concentration and intake summary for 1951 to 1988.........................................20

4-9b Radionuclide concentration and intake from 1989 to 1996 .....................................................26

4-9c Radionuclide concentration and intake summary from 1997 to 2002......................................28

4-9d Conversion factors and isotopic content for values in Table 4-9 .............................................29

4-10 Site-wide intakes of each uranium and each non-uranium radionuclides in Bq/yr and radon in 

WLM for 1951 through 2002....................................................................................30

4-11 Radiation dose rates at site boundary ................................................................................ ...33

4-12 TLD measurement summary..................................................................................................34

4-13 External occupational environmental dose summary..............................................................37

4-14 Direct radiation (TLD) measurement summary.........................................................................38

4-15 Comparison of the estimated dose rate in EAs and the aerial survey results...........................39

4-16 Site-wide average dose rate comparison..................................................................................40

4-17 External occupational environmental dose rate summary (mrem/hour)....................................42

LIST OF FIGURES

Figure

4-1 Estimate of total 222Rn releases from K-65 silos .....................................................................

Page

12

4-2 Exposure Areas ......... ..........................................................................................................13

4-3 Horizontal diffusion, σy, versus downwind distance from a point source for Pasquill's stability 

categories................................................................................................................................ 16

4-4 Horizontal diffusion, σz, versus downwind distance from a continually emitting point source for 

Pasquill's stability categories.....................................................................................................17

4-5 Wind rose for a 10-m height for 2000 .....................................................................................16

4-6 Air monitoring station locations ..............................................................................................18

4-7 Average on-site uranium concentrations (1989 to 1996) ........................................................19

4-8 Average onsite thorium concentrations (1989 to 1996) ..........................................................19

4-9 FEMP fenceline TLD locations (1976-1995).......................................................................... 32

4-10 TLD monitoring locations (1996-2002)......................................... ........................................... 33
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4-11 1976 exposure rate contour map of the FEMP survey area.................................................... 35

4-12 1985 exposure rate contour map of the FEMP survey area.....................................................36

4-13 Beta gamma dose rate contours in the waste pit area..............................................................37

4-14 Waste pit dose rate profiles...................................................................................................... 38

4-15 Project site-wide direct radiation dose rates based on metal production rate........................... 41
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 4 of 83

RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

EFFECTIVE 

DATE

REV. 

NO. DESCRIPTION

12/30/2003 12/30/2003 00-A New Technical Basis Document for the Fernald 

Environmental Management Project (FEMP) – 

Occupational Environmental Dose. Initiated by 

Samuel L.T. Chu.

03/25/2004 03/25/2004 00-B Incorporates OCAS and reviewers’ comments. 

Initiated by Samuel L.T. Chu. 

04/06/2004 04/06/2004 00 First approved issue. Initiated by Samuel L.T. 

Chu.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 5 of 83

ACRONYMS AND ABBREVIATIONS

AMS air monitoring station

Ci curie

EA exposure area

FEMP Fernald Environmental Management Project

FEMP Feed Material Production Center

ft foot

ft2 square foot

g gram

kg kilogram

l liter

m meter

m3 cubic meter

mg milligram

mR milliroentgen

mrad millirad

mrem millirem

MTU metric ton of uranium

NLO National Lead of Ohio, Inc.

pCi picoCurie

s second

TBD technical basis document

TLD thermoluminescent dosimeter

U.S.C. United States Code 

WL working level, a unit of measurement for radon daughter exposure rate, 

1 WL≈ 100 pCi/L of radon in 100%.

WLM working level-month is the exposure of an individual to 1 WL for 170 hours (working

Month).

yr year

μCi microCurie
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 6 of 83

4.0

This section provides the technical basis for estimation of historic radiological doses to workers from 

the U.S. Department of Energy Fernald Environmental Management Project (FEMP; previously known 

as the Feed Material Production Center, or FMPC) based on exposure to occupational environmental 

radiation sources.

OCCUPATIONAL ENVIRONMENTAL DOSE

Technical Basis Documents and Site Profile Documents are general working documents that provide 

guidance concerning the preparation of dose reconstructions at particular sites or categories of sites. 

They will be revised in the event additional relevant information is obtained about the affected site(s). 

These documents may be used to assist NIOSH in the completion of the individual work required for 

each dose reconstruction.

In this document the word “facility” is used as a general term for an area, building or group of buildings 

that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “ Department of Energy facility” as defined in the Energy Employee 

Occupational Illness Compensation Program Act of 2000 (42 U.S.C. § 7384l (5) and (12)).

For the National Institute for Occupational Safety and Health dose reconstruction program and this 

technical basis document (TBD), the following criteria are applicable:

• TBDs are being developed to support radiological dose reconstructions. Therefore, the only 

information included in the TBDs is that which may relate to site-specific occupational dose 

reconstruction.

• The information gathered for the TBDs takes into consideration that the Energy Employees 

Occupational Illness Compensation Program Act of 2000 (Public Law 106-398) requires the 

consideration of the type of cancer, past health-related activities, the risk of developing a 

radiation-related cancer from workplace exposure, and other relevant factors 

[42 U.S.C. 7384n(c)].

• The TBDs are intended to support dose reconstruction efforts that involve determining or 

assuming specific characteristics of the monitoring procedures, identifying events or processes 

that were unmonitored, identifying the types and quantities of radioactive materials involved, 

evaluating production processes and safety procedures employed, identifying the locations 

and activities of exposed persons, and identifying comparable exposure circumstances for 

which data is available to make assumptions regarding exposure of others.

• Occupational environmental dose refers to the dose received by a person who was or is 

occupationally employed at the FEMP while that person was on the site but outside a facility or 

building. The dose can be external or internal, depending upon the characteristics of the 

source of the radiation. The radiation can be direct, as from radioactive material fixed in place 

(e.g., process equipment), or from radioactive materials deposited on the ground or other 

objects outside buildings. The radiation can be from radioactive gases or from airborne 

radioactive contamination.

• Radiation exposure from offsite sources are not occupational exposures.

• Accidents were not considered when compiling the data for this Section of the FEMP TBD. 

Dose reconstructors will handle accidents as special cases. Decisions on how to handle 

accidents will be made on a case-by-case basis.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 7 of 83

• The contribution of food chain vectors will not be considered in establishing dose values.

• Fallout will not be considered a contributing factor in dose reconstruction.

4.1 INTRODUCTION 

The occupational environmental dose is the dose received by individuals working outside the 

production facilities and silos in the radioactive waste areas or in the administration areas inside or 

outside the fenced production areas. Records review showed that the personnel likely to receive 

occupational environmental dose include construction workers, contractors, security guards, 

environmental monitoring personnel, personnel involved with outdoor work duties, and administrative 

personnel. For these individuals, the primary radiation exposure pathways are inhalation of airborne 

radionuclides, exposure to direct radiation from emission plumes, exposure to radioactive materials in 

the process plants, and exposure to radioactive substances deposited on the ground or surfaces. The 

internal dose from the inhalation of radioactive materials can be determined from radionuclide air 

concentrations. The external dose from exposure to radioactive materials outside the body can be 

determined from historic data of external dosimetry monitoring. 

This TBD of the FEMP Site Profile shows the derivation of radionuclide air concentrations and 

subsequent radionuclide intakes by an individual on the site and presents historic external dose area 

radiation monitoring data for the reconstruction of occupational environmental doses for unmonitored 

claimants.

4.2 SITE BACKGROUND AND HISTORY

The FEMP began operations in 1952 and was fully operational by the end of 1954. The primary 

function of the FEMP was to convert uranium ore concentrates and recycled materials to either 

uranium oxides or highly purified uranium ingots and billets for machining or extrusion into tubular 

forms of assorted standard isotopic assays. These products were for use as production reactor fuel 

cores and target fuel element fabrication. Small amounts of thorium also were processed. 

Uranium metal deliveries peaked in 1960 at approximately 10,000 metric tons of uranium (MTU). 

Deliveries began to decline in 1964 to a low of approximately 1,230 MTU in 1975. During the 1970s 

consideration was given to closing the FEMP. The staffing level, which peaked at 2,891 in 1956, 

slowly declined from 662 in 1972 to 538 in 1979. Starting in 1981, production output increased to 

three times the 1979 level and staff increased from 538 to more than 1,000.

The production of uranium metal at the FEMP ended in July 1988, and site personnel began to 

concentrate on cleanup efforts. Current operations at the FEMP are limited to site remediation and 

restoration. 

The production area facilities included nine separate plants, a pilot plant, ancillary buildings, and 

administrative buildings connected by a network of roadways. These facilities, along with concrete 

storage pads, gravel ground cover, railroad access, sanitary landfill, and metal scrap piles, were 

surrounded by security fencing (as are the remaining facilities). The Waste Storage Area outside the 

136-acre fenced production area includes six low-level radioactive waste storage pits, two earthenbermed concrete silos containing K-65 residues (high specific activity, low-level radium-bearing 

residues), one concrete silo containing metal oxides, and all affected adjoining areas. This area 

includes two fly-ash piles about 3,000 ft south-southwest of the waste storage area, as well as a burn 

pit between Pits 3 and 4. Production operations occurred in Plants 1 through 9 and the Pilot Plant. 

The FEMP site is currently undergoing remediation, and some of the plants and buildings that existed 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 8 of 83

while the site was in operation no longer exist. As of 2002, Plants 1, 4, 5, 6, 7, and 9 had been 

dismantled; other facilities are planned for or in various phases of dismantlement.

4.3 INTERNAL DOSES FROM ATMOSPHERIC RADIONUCLIDE CONCENTRATIONS

Radionuclide emissions from the operating years of FEMP were evaluated in History of FMOS 

Radionuclide Discharges (Boback et al. 1987) and The Fernald Dosimetry Reconstruction Project, 

Tasks 2 and 3, Radionuclide Source Terms and Uncertainties (RAC 1995). The values for uranium 

and thorium discharges from routine operations during the FEMP operating years (from 1951 through 

1988) are from Dolan and Dolan (1988), the addendum to Boback et al. 1987. The values for 

releases of 222Rn and its daughter products are from RAC 1995. 

This section shows the derivation of radionuclide concentrations within the general plant areas for 

each of the production years for the unmonitored worker dose reconstruction effort using the plant 

emission data. For 1989 and after, emissions quantities from remediation and decommissioning 

activities are not readily available; however, there is information and data relevant to environmental 

dose in the Site Annual Environmental Reports. Therefore, this TBD reports occupational 

environmental dose information available in FEMP site environmental reports for this period (for 

example, WEMCO 1990 to 1992; FERMCO 1993 to 1996; Fluor 1997 to 2001).

4.3.1

During the course of FEMP production operations, 175,130 kg of uranium and 8,769 kg of thorium 

were released to the atmosphere from various emissions sources due to routine operations. Table 4-

1 provides annual airborne uranium emissions due to FEMP site operations throughout the operating 

history (from 1951 through 1988) of the site from each production plant and processing facility. The 

values in Table 4-1 include:

Airborne Radioactive Materials Emissions (from 1951 to 1988)

• Monitored source emissions as reported in FEMP-2082

• Emissions from Plant 2/3 UO3 gulping

• Emissions from the processes

• Building exhaust emissions due to normal operating conditions

• Emission approximations for laboratory hoods.

Tables 4-2a and 4-2b provide summaries of annual fugitive uranium and thorium emissions from wind 

erosion of the waste storage area. The estimated radon fluxes at the waste pits are also included. 

Table 4-3 provides annual airborne thorium emissions due to thorium operations at Plants 8 and 9 

and the Pilot Plant from 1951 through 1988. Thorium process emissions represent the best 

approximation possible given the lack of specific production information. At best this estimate is 

accurate within an order of magnitude; however, because of the conservative assumptions used for 

scrubber and dust collector efficiencies and the intake of material to the collection equipment, the 

actual thorium emissions should not exceed those in Table 4-3.

Appendix J of Radionuclide Source Terms and Uncertainties (RAC 1988) estimated the emissions of 

222Rn and radon daughters primarily from the K-65 Silos and from other stored K-65 materials. Figure 

4-1 summarizes the 222Rn emission quantity estimates. Table 4-4 lists the emissions of radon and its 

daughters from drummed K-65 materials at the Plant 1 pad for 1951 to 1953.
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9 of 83

 Table 4-1. FEMP uranium emissions summary by plant (kg). 

Year Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9

Pilot 

Plant Lab

Oil & 

graphite 

burner

Solid & 

liquid waste 

incineration

N.A.R

.

Cooling 

towers Year total

1951 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 123.0 0.0 0.0 0.0 0.0 2.9 125.9

1952 0.0 0.0 0.0 0.0 6.0 0.0 0.0 0.0 493.0 0.0 0.0 0.0 3.0 2.9 504.9

1953 3.8 6.0 1,473.0 90.0 14.1 0.0 0.0 0.0 493.0 1.9 0.0 0.0 3.0 2.9 2,087.7

1954 46.2 281.4 5,891.0 4,119.1 34.3 4,261.0 418.1 0.0 271.0 1.9 0.0 15 3.0 2.9 15,345.0

1955 46.2 1,115.1 12,452.0 10,410.4 65.3 7,268.0 1,825.4 0.0 443.0 1.9 0.0 118 3.0 2.9 33,751.2

1956 43.4 1,981.4 5,148.1 3,501.5 42.2 1,743.0 2,758.6 0.0 32.0 1.9 0.0 118 3.0 2.9 15,376.0

1957 49.4 3,735.4 819.7 3,664.8 51.8 0.0 2,366.7 0.4 18.0 1.9 0.0 118 3.0 2.9 10,814.0

1958 407.4 3,526.5 668.4 715.5 177.3 0.0 2,525.7 681.0 27.0 1.9 0.0 118 3.0 2.9 8,854.6

1959 46.0 3,936.4 1,433.8 478.9 143.1 0.0 2,360.9 420.5 34.0 1.9 0.0 118 3.0 2.9 8,979.4

1960 20.0 4,240.9 219.0 203.4 288.5 0.0 2,903.1 222.8 718.0 1.9 0.0 118 3.0 2.9 8,941.5

1961 52.8 3,714.1 268.5 76.7 136.0 0.0 2,581.0 74.0 174.0 1.9 0.0 118 3.0 2.9 7,202.9

1962 14.0 2,141.1 708.8 356.5 76.6 0.0 2,923.0 142.5 174.0 1.9 20 118 3.0 2.9 6,682.3

1963 82.6 0.0 1,475.4 783.6 199.7 0.0 3,165.9 169.2 51.8 1.9 27 118 0.0 2.9 6,078.0

1964 18.0 0.0 549.4 330.8 50.9 0.0 3,917.2 266.8 13.0 1.9 27 118 0.0 2.9 5,295.9

1965 4.1 193.1 338.9 226.9 59.0 0.0 6,200.7 83.02 10.0 1.9 28.2 118 0.3 2.9 7,267.0

1966 12.2 514.9 230.9 77.1 23.7 0.0 1,253.6 52.72 18.1 1.9 34.0 118 0.3 2.9 2,340.3

1967 20.4 648.0 284.16 148.3 14.3 0.0 2,207.6 80.64 11.8 1.9 34.0 118 0.3 2.9 3,572.3

1968 0.5 1,121.6 271.1 88.4 39.0 0.0 3,983.8 121.9 3.6 1.9 34.0 118 0.3 2.9 5,787.0

1969 27.2 699.5 52.0 119.6 9.83 0.0 3,547.4 13.63 3.6 1.9 34.0 94 0.3 2.9 4,605.9

1970 4.5 357.3 31.7 53.3 5.84 0.0 1,235.2 14.15 0.0 1.9 34.0 71 0.3 2.9 1,812.1

1971 9.0 306.5 0.89 0.1 2.7 0.0 632.1 0.65 0.0 1.9 34.0 71 0.3 2.9 1,062.0

1972 28.4 1,361.8 9.8 33.1 1.61 0.0 5.04 24.6 0.0 1.9 34.0 71 0.3 2.9 1,574.5

1973 1.0 1,398.3 58.2 79.1 3.03 0.0 53.02 15.87 0.0 1.9 34.0 71 0.3 2.9 1,718.6

1974 1.4 2,449.6 25.2 40.1 1.69 0.0 11.0 38.8 0.0 1.9 34.0 71 0.3 2.9 2,677.9

1975 5.6 2,850.0 120.9 19.1 1.25 0.0 3.51 0.68 0.4 1.9 34.0 71 0.3 2.9 3,111.5

1976 2.7 3,345.5 26.9 13.8 4.17 0.0 7.22 3.37 0.0 2.4 34.0 71 0.4 2.9 3,514.4

1977 0.6 757.61 130.0 53.4 1.89 0.0 4.73 0.61 10.4 1.9 34.0 71 0.3 2.9 1,069.3

1978 1.8 0.0 13.30 29.2 1.92 0.0 0.04 72.6 2.2 1.9 34.0 71 0.0 2.9 230.8

1979 0.8 0.0 47.23 12.4 1.5 0.0 0.06 2.84 0.0 1.9 22.0 71 0.0 2.9 162.6

1980 13.4 2.7 135.4 89.6 1.64 0.0 16.14 0.54 3.3 1.9 7.0 0.7 0.0 2.9 275.2

1981 1.3 30.1 424.7 135.7 2.10 0.0 10.01 0.75 0.0 1.9 7.0 1.2 0.3 2.9 618.0

1982 2.1 52.4 23.68 122.0 3.91 0.0 118.33 6.23 0.0 1.9 7.0 1.8 0.3 2.9 342.6

1983 6.4 130.2 45.81 41.6 3.87 0.0 82.8 1.43 0.0 1.9 2.4 5.4 0.3 2.9 325.0

1984 12.1 574.5 43.93 84.1 5.05 0.0 46.19 171.4 2.8 1.9 6.4 10.4 0.3 2.9 962.0

1985 130.1 3.33 0.22 3.42 0.0 0.06 1.12 1.9 0.3 2.9 218.72

1986 0.0 3.75 0.24 3.77 0.0 0.06 1.46 1.9 0.3 2.9 43.72

1987 200.1 3.29 0.18 2.09 0.0 0.37 0.36 1.9 0.3 2.9 246.92

1988 90.1 1.09 0.12 0.80 0.0 0.09 0.18 1.9 0.3 2.9 97.5

Total 985.3 41,892.21 33,433.26 26,198.86 1483.88 13,272 47,164.67 2686.75 3131 68.9 596 2490.5 39.4 110.2 173,675.16
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Table 4-2a. Fugitive uranium and thorium emissions from wind erosion of Waste Pits 1, 2 and 3. 

Year

Pit 1a Pit 2b Pit 3c

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

1953 4,293 0.15 -- -- -- -- -- -- --

1954 6,868 0.25 -- -- -- -- -- -- --

1955 38,633 1.4 -- -- -- -- -- -- --

1956 55,803 2.0 -- -- -- -- -- -- --

1957 60,095 2.16 -- 17,781 46.4 0.014 -- -- --

1958 60,095 2.16 -- 35,562 92.7 0.032 -- -- --

1959 60,095 2.16 -- 35,562 92.7 0.032 0 0.0 0.0

1960 60,095 2.16 -- 40,008 104.3 0.032 0 0.0 0.0

1961 51,510 1.85 -- 44,453 115.9 0.036 0 0.0 0.0

1962 42,925 1.54 -- 44,453 115.9 0.036 44,431 0.63 0.0

1963 17,170 0.62 -- 44,453 115.9 0.036 44,431 0.63 0.0

1964 8,585 0.31 -- 44,453 115.9 0.036 236,966 3.36 0.01

1965 8,585 0.31 -- 22,227 57.95 0.018 266,587 3.78 0.014

1966 8,585 0.31 -- 13,336 34.8 0.01 266,587 3.78 0.014

1967 8,585 0.31 -- 0 0 0.0 0 0.0 0.0

1968 12,878 0.46 -- 0 0 0.0 0 0.0 0.0

1969 68,680 2.5 -- -- -- -- 103,673 1.47 0.005

1970 60,095 2.15 -- -- -- -- 177,725 2.52 0.01

1971 51,510 1.85 -- -- -- -- 177,725 2.52 0.01

1972 42,925 1.54 -- -- -- -- 88,862 1.26 0.005

1973 34,340 1.23 -- -- -- -- 88,862 1.26 0.005

1974 25,755 0.92 -- -- -- -- 29,621 0.42 0.0

1975 17,170 0.62 -- -- -- -- 236,966 3.35 0.01

1976 8,585 0.31 -- -- -- -- 236,966 3.35 0.01

1977 -- -- -- -- -- -- 236,966 3.35 0.01

1978 -- -- -- -- -- -- 207,346 2.94 0.01

1979 -- -- -- -- -- -- 177,725 2.52 0.01

1980 -- -- -- -- -- -- 133,294 1.89 0.005

1981 -- -- -- -- -- -- 103,673 1.47 0.005

1982 -- -- -- -- -- -- 44,431 0.63 0.0

1983 -- -- -- -- -- -- 0 0.0 0.0

1984 -- -- -- -- -- -- -- -- --

1985 -- -- -- -- -- -- -- -- --

1986 -- -- -- -- -- -- -- -- --

1987 -- -- -- -- -- -- -- -- --

1988 -- -- -- -- -- -- -- -- --

Total 29.2 -- 892.45 0.282 41.13 0.133 a

 Radon Flux - average 9.1 pCi/m3/sec and maximum 75 pCi/m3/sec

b

 Radon Flux - average 6.0 pCi/m3/sec and maximum 81.1 pCi/m3/sec c

 Radon Flux - average 2.6 pCi/m3/sec and maximum 48 pCi/m3/sec
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 11 of 83

Table 4-2b. Fugitive uranium and thorium emissions from wind erosion of Waste Pits 4, 5 and 6. 

Year

Pit 4d Pit 5 d Pit 6 d

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

Exposed 

pit area

(ft2)

Uranium 

emission

(kg/yr)

Thorium 

emission

(kg/yr)

1953 -- -- -- -- -- -- -- -- --

1954 -- -- -- -- -- -- -- -- --

1955 -- -- -- -- -- -- -- -- --

1956 -- -- -- -- -- -- -- -- --

1957 -- -- -- -- -- -- -- -- --

1958 -- -- -- -- -- -- -- -- --

1959 -- -- -- -- -- -- -- -- --

1960 9,583 1.9 0.38 -- -- -- -- -- --

1961 19,166 3.79 0.76 -- -- -- -- -- --

1962 38,333 7.58 1.53 -- -- -- -- -- --

1963 43,124 8.52 1.72 -- -- -- -- -- --

1964 47,916 9.47 1.91 -- -- -- -- -- --

1965 47,916 9.47 1.91 -- -- -- -- -- --

1966 52,708 10.42 2.1 -- -- -- -- -- --

1967 52,708 10.42 2.1 -- -- -- -- -- --

1968 57,499 11.36 2.3 0 0.0 0.0 -- -- --

1969 57,499 11.36 2.3 0 0.0 0.0 -- -- --

1970 57,499 11.36 2.3 0 0.0 0.0 -- -- --

1971 57,499 11.36 2.3 0 0.0 0.0 -- -- --

1972 62,291 12.3 2.49 0 0.0 0.0 -- -- --

1973 62,291 12.3 2.49 0 0.0 0.0 -- -- --

1974 62,291 12.3 2.49 17,860 0.28 0.1 -- -- --

1975 67,082 13.26 2.68 44,649 0.71 0.24 -- -- --

1976 71,874 14.2 2.87 142,877 2.27 0.76 -- -- --

1977 81,457 16.1 3.25 53,579 0.85 0.29 -- -- --

1978 91,040 18.0 3.64 53,579 0.85 0.29 -- -- --

1979 95,832 18.94 3.83 53,579 0.85 0.29 3,240 8.26 --

1980 95,832 18.94 3.83 53,579 0.85 0.29 4,860 12.4 --

1981 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1982 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1983 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1984 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1985 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1986 95,832 18.94 3.83 53,579 0.85 0.29 8,100 20.7 --

1987 95,832 18.94 3.83 89,296 1.42 0.48 8,100 20.7 --

1988 95,832 18.94 3.83 119,124 1.9 0.64 8,100 20.7 --

Total 394.9 79.8 15.1 5.1 186 -- d

 Radon Flux – less than 0.1 pCi/m3/sec

Since 1972, the FEMP has served as the thorium materials repository for DOE. The thorium metal 

and residues stored on site are primarily 232Th. Since most of the material and residues have been 

stored for quite some time, there is a significant amount of 224Rn present, which results in the 

generation of thoron gas (220Rn). The average thoron activity concentration in outside air has been 

reported to be comparable to the environmental background concentration of the radon; therefore, it 

can be assumed that the FEMP thoron environmental concentrations vary with fluctuations in radon 

concentrations (Tomes 1997). The bulk of the thorium materials are stored in Buildings 64, 65, 67, 

68, and 69. Since thoron has a half-life of 55.6 seconds, significant accumulation occurs only in 

areas in the proximity of the buildings where the thorium is stored. Therefore, for 1972 and 

subsequent years, an activity concentration equal to that of radon background concentration is 

assigned to the areas close to buildings where thorium was stored.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 12 of 83

Table 4-3. Thorium emission estimates by year (kg)

Year Plant 8 Plant 9 Pilot Plant Yearly total

1953 0 0 0 0

1954 0 1028 0 1028

1955 0 1176 0 1176

1956 0 0 0 0

1957 0 0 0 0

1958 0 0 0 0

1959 0 0 0 0

1960 0 0 0 0

1961 0 0 0 0

1962 0 0 0 0

1963 0 0 0 0

1964 0 0 344 344

1965 0 0 344 344

1966 118 0 344 462

1967 0 0 344 344

1968 0 0 344 344

1969 1040 0 394 1434

1970 699 0 499 1198

1971 430 0 62 492

Year Plant 8 Plant 9 Pilot Plant Yearly total

1972 0 0 141 141

1973 0 0 50 50

1974 0 0 100 100

1975 0 0 3 3

1976 0 0 0 0

1977 0 0 408 408

1978 0 0 408 408

1979 0 0 408 408

1980 0 0 0 0

1981 0 0 0 0

1982 0 0 0 0

1983 0 0 0 0

1984 0 0 0 0

1985 0 0 0 0

1986 0 0 0 0

1987 0 0 0 0

1988 0 0 0 0

Total 2,204 2,287 4,193 8,684

100

1000

10000

1951 1954 1957 1960 1963 197219691966 1975 1978 1981 1984 1987

Time Period

Total Rn222 Release Rate (Ci/Yr)

1952-1953

1953-1958 1959-1979 1980-1987

1988

95th Percentile

Median

Figure 4-1. Estimate of total 222Rn releases from K-65 silos. 

Table 4-4. Summary of 222Rn and 222Rn daughter product releases 

(Ci) for drummed K-65 material stored on the Plant 1 Pad. 

Years

Rn-222 release Rn-222 daughters releasea

5th Median 95th 5th Median 95th 

1951b 2.6 35 170 0.24 6.2 45

1952 42 580 2,800 3.9 100 730

1953c 6.9 95 450 0.63 17 120

a. The quantities given for 222Rn daughters are comprised of quantities of each shortlived daughter: 218Po, 214Pb, 214Bi, and 214Po.

b. Releases for 1951 are assumed to have occurred from October to December.

c. Releases for 1953 are assumed to have occurred from January to June.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 13 of 83

4.3.2

This section presents the derivation of the on-site radioactivity concentrations at various locations of 

the FEMP based on discharges from routine operations during the plant’s operating years.

Onsite Environmental Radioactive Material Air Concentrations and Intake for 1951 to 

1988)

4.3.2.1 Exposure Site Locations

The airborne emissions data indicate that the quantity of normal releases at FEMP has varied 

significantly from facility to facility. It is assumed that the radioactive aerosol concentration varies 

significantly in various sections of the plant site. The dose received by the worker is highly dependent 

on the amount of time spent in specific work areas. For the purpose of providing supportive

information for dose reconstruction, this TBD has divided the FEMP into smaller areas, designated as 

Exposure Areas (EAs), on a grid that provides a realistic estimated representation of the radiological 

conditions where the employees may have worked. Figure 4-2 shows the FEMP site plan depicting 

the grids. There are 11 EAs for which this TBD presents airborne radionuclide concentrations from 

routine operations. Table 4-5 lists the major facilities in each of EA-1 through EA-11.

4.3.2.2 Airborne Radionuclide Concentration Derivation

The radioactive aerosol concentrations at distances from a continuous source in each EA can be

obtained by:

∑ ( ) 













 = i

i

di

EA i f RF

Q

RC χ (4-1)

where

CEA = radionuclide concentration in EA (g/m3

) 

Ri

 = radionuclide emission rate from source i (g/s) where i can be Plant 1, 2/3, 4, etc. 

(χ/Q)di = atmospheric dilution factor at distance d from source i (s/m3

) 

fi = fraction of time that the wind blew in the EA direction from source i 

(RF) = respirable fraction of the source aerosol (<10 μm)

Airborne radionuclide concentrations for each of the EAs are the sum of the contributions of all the 

emission sources to the most probable occupied area within the EA.

Radionuclide Emission Rates (Ri)×(RF) 

The average annualized emission rates are derived by dividing emission quantities in Tables 4-1, 4-2, 

4-3 and Figure 4-1 by 3.154 × 107 s per average year. In 1951 and 1953, 222Rn and radon daughters 

were released from stored drums of K-65 materials at the Plant 1 pad in three months in one case and 

six months in another (Table 4-4). However, their release rates were respectively annualized as if the 

total emission quantities were released over a one-year period. The radon daughter releases in 

Table 4-4 represent a equilibrium factor ranging from 1% to 27% for the years 1951 through 1953. 

For dose reconstruction purposes, the EPA default equilibrium factor of 70% for outdoor is used for 

the intake calculation. The 70% equilibrium factor is claimant favorable. Therefore, the radon 

daughter releases in Table 4-4 were not used in the Rn intake calculations.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 14 of 83

EA-1 EA-2

EA-4 EA-3

EA-8

EA-5

EA-6

EA-11 EA-7

EA-9

EA-10

Figure 4-2. Exposure Areas. 

Table 4-5. Facilities and buildings in each Exposure Area. 

EA Facilities and buildings

EA-1 Plants 1, Buildings 67 and 68

EA-2 Plant 9, Buildings 64 and 65

EA-3 Plants 4, 5, 6, and 7

EA-4 Plant 2/3 and Plant 8

EA-5 Waste Pit Area

EA-6 K-65 Silos

EA-7 Pilot Plant, Building 69, Laboratory Building Waste Water Treatment Facility, Storm 

Water Retention Basins, Administrative Area (Expanded into this EA in the 1990s)

EA-8 Administrative Area, Industrial Relations and Security Buildings

EA-9 Onsite Disposal Facility, Sewage Treatment Plant

EA-10 Railroad

EA-11 Waste Haul Road
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 15 of 83

For internal dose assessment, the particle sizes of interest are those below 10 μm. Particle sizes 

below 10 μm are considered respirable and sufficiently small to remain airborne during transport. 

Appendix E of the Fernald Dosimetry Reconstruction Project (RAC 1988) states that the size 

distribution of emissions released from various processes involving uranium compounds involve 

particle sizes below 10 μm in the 60th to 70th percentile, weighted more in the 60th percentile. The 

average particle size distribution from the stack is derived from Table E-1 of the RAC 1988 report and 

shows 7.8-μm particle size at the 55th percentile and 9.78 μm at the 65th percentile. Therefore, a 

value of 65% is used for (RF) and the emission rate is reduced 35% to account for respirable size 

portion of the release.

Atmospheric Dilution Factor (χ/Q) 

The dilution factor (χ/Q) is calculable using the Pasquill-Gifford equation:































 = +− 2

2

2

2

2

1

exp 1),(

zy zy

Hy

Q u

yx

σπσ σσ

χ (4-2)

where 

χ(x, y) = ground level concentration at point x, y (g/m3

) 

x = downwind distance on plume center line (m)

y = cross-wind distance (m)

Q = emission rate (g/s)

σy, σz = horizontal and vertical standard deviations of contaminant concentration in the 

plume (m), Figures 4-3 and 4-4, respectively.

u = mean wind speed at level of plume center line (m/s)

H = effective chimney height (m)

For particulates, the (χ/Q) equation becomes:































 = +− 2

2

2

2

2

1

exp 2

1),(

zy zy

Hy

Q u

yx

σπσ σσ

χ (4-3)

Equation 4-2 yields the ground-level concentration of a gas that is continuously emitted from a point 

source and is based on total reflection of the gas by the ground. If the pollutant in the plume were 

retained on the ground, as in the case of particulates (Equation 4-3), then the ground-level 

concentration would be approximately one-half that in Equation 4-3.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 16 of 83

Figure 4-3. Horizontal diffusion, σy, versus downwind 

distance from a point source for Pasquill’s 

stability categories.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 17 of 83

Figure 4-4. Horizontal diffusion, σz, versus downwind 

distance from a continuously emitting point 

source for Pasquill’s stability categories.

Table 4-6 shows the χ/Q values with respect to the receptor distances downwind on the plume center 

line using a wind speed of 3.2 m/s, Pasquill stability class F, ground release, and elevated releases 

assuming an average stack height of 10 m (Parsons date unknown). Because U and Th emissions 

from the production plants were particulates released through the stacks, elevated release χ/Q is used

for uranium and thorium releases. Ground release χ/Q is used for U and Th fugitive emissions from 

the waste pits. Rn-222 is treated as elevated gaseous release primarily from the head space of the K65 Silos.

The maximum ground level concentration occurs at the downwind distance where the vertical

standard deviation is:

H 2/ σ z = = 7.1 (4-4)

This corresponds to a distance of approximately 500 m downwind from the source for Pasquill 

Stability Class F.

Table 4-7 provides the EA receptor downwind distance estimation (m) from each of the contributing 

emission sources used for the radioactivity concentration calculations. The distances were estimated

based on emission sources to the most likely occupied location in each of the EAs. Distances slightly 

higher (approaching the 500m maximum concentration distance) than those scaled from plot plan 

reproductions were assigned to ensure claimant favorable. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 18 of 83

Table 4-6. χ/Q values versus distances from the 

emission source. 

Distance (m)

(χ/Q) (s/m3)

a

Ground release 10-m release height

100 0.02 5.12 × 10-11

150 8.29 × 10-3 3.37 × 10-8

200 4.14 × 10-3 1.60 × 10-5

250 2.48 × 10-3 1.09 × 10-4

300 1.69 × 10-3 2.11 × 10-4

350 1.21 × 10-3 2.31 × 10-4

400 8.85 × 10-4 2.71 × 10-4

450 7.68 × 10-4 2.77 × 10-4

500 6.98 × 10-4 2.87 × 10-4

550 5.92 × 10-4 2.71 × 10-4

600 4.61 × 10-4 2.48 × 10-4

650 4.19 × 10-4 2.41 × 10-4

700 3.51 × 10-4 2.23 × 10-4

750 2.84 × 10-4 2.02 × 10-4

1,000 1.75 × 10-4 1.40 × 10-4

2,000 6.46 × 10-5 5.83 × 10-5

5,000 1.63 × 10-5 1.56 × 10-5

a For U and Th particulate aerosol, 0.5 × the values in the table. 

Table 4-7. Receptor downwind estimated distances from contributing emission sources (m).

EA

Contributing emission sources

Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9

Pilot 

Plant

Waste 

pits

K-65 

silos

1 150 250 300 500 600 350 500 500 350 500 400

2 500 500 400 300 500 500 600 250 500 1,000 1,000

3 500 500 200 150 250 250 500 350 450 1,000 1,000

4 300 150 250 500 500 250 150 500 200 600 450

5 300 400 600 2,000 2,000 600 500 2,000 600 150 300

6 500 400 550 2,000 2,000 550 400 2,000 500 300 250

7 500 400 450 400 500 400 300 550 300 700 500

8 500 450 300 300 300 250 450 500 300 1,000 1,000

9 2,000 2,000 500 450 300 500 2,000 500 2,000 2,000 2,000

10 400 500 500 600 650 550 550 450 600 500 1,000

11 2,000 2,000 5,000 2,000 2,000 700 700 2,000 700 700 450

Effects of Wind Direction (fi) 

Wind direction plays a key role in predicting the amount of aerosol that arrives at an EA. Figure 4-5 

shows a wind rose at the 10-m level from 2000. The prevailing winds were from the west through 

south-southwest about 40% of the time. 

Table 4-8 lists the fraction of the time that the wind blew toward the EAs from a contributing emission 

source, as determined using Figures 4-2 and 4-5. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 19 of 83

Figure 4-5. Wind rose for a 10-m height for 2000. 

Table 4-8. Percentage of time that the wind blew in the direction of the Exposure Areas. 

EA

Contributing emission sources (%)

Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9

Pilot 

Plant

Waste 

pits

K-65 

silos

1 36 34 11 11 11 11 22 12 22 20 20

2 36 37 44 49 12 36 24 41 37 18 20

3 19 25 15 54 8 34 34 16 34 15 18

4 26 26 15 13 15 11 34 11 11 8 25

5 18 9 9 9 9 8 7 16 9 15 30

6 13 11 13 14 6 8 8 13 8 13 19

7 13 13 10 7 11 11 24 13 15 11 11

8 19 19 23 26 14 23 8 12 19 11 15

9 18 18 18 18 18 21 21 18 29 18 18

10 35 33 10 12 7 23 33 5 12 24 23

11 10 14 17 13 13 11 11 11 11 13 8

4.3.2.3 Radionuclide Concentrations and Intake from Routine Emissions

Table 4-9a lists estimates of the radionuclide concentrations and the amount of radionuclide intake for 

a claimant who spent a year within an EA for 1951 to 1988. The median radon releases values in 

Figure 4-1 and Table 4-4 were used for the estimates. Appendix 4A lists the detailed results. Table 

4-9a also provides concentration values that include the background radon concentrations. The 

background radon concentrations used were the average background concentrations measured in 

1989 to 2000 of 0.47 pCi/L. (Fluor, 2001). The background concentration measurements are shown in 

Appendix 4B. The intake calculation assumed that an individual would breathe in 2,400 m3 of air in a 

year. The concentration and annual intake values for uranium and thorium in Table 4-9a are in 

milligrams per cubic meter and milligrams respectively. Table 4-9d lists the specific activities and 

isotopic content (or activity fraction of an isotope) for converting milligrams to Becquerel of individual 

isotopes. Radon (222Rn) and thoron (220Rn) concentration values are in pCi/L. The 222Rn and 220Rn 

intake levels are expressed in Working Level Months. For 222Rn, 1 WL= 100pCi/L and the WLM is 

derived based on an individual continuously breathed air at the FEMP for 2,000 hrs for the year and 

an assumed environmental radon daughter product equilibrium factor of 70% (This ratio for ambient 

outside air is in accordance with widespread sampling conducted throughout the United States that is 

referenced in the NCRP report). For 220Rn, 1 WL=7.47 pCi/L and the equilibrium factor have been 

documented to range between 0.02 to 0.1 at several locations (Tomes, 1997). 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 20 of 83

Therefore, 

Rn-222 WLM = L

pCi × Concentration

×

×

170100

20007.0 = 8.24×10-2 × (Rn concentration in pCi/L), 

and

Rn-220 WLM = L

pCi × Concentration

×

×

17047.7

20001.0 = 1.58×10-1 × (thoron concentration in pCi/L)

The average concentration of radon emissions from the waste pits (EA-5) typically was an order of 

magnitude lower than those from the K-65 silos. Therefore, the results for EA-5 do not include the 

radon emitted from the waste pits.

The following example demonstrates the use of Equation 4-1 to calculate the 1955 radionuclide 

(uranium and radon) concentrations and intake at an administrative building location (EA-8). 

Step 1. Calculate the concentration of uranium in EA-8 from each of the emission sources (i.e., 

Pilot Plant, Plant 1, 2/3, etc.) using Equation 4-5:

 i

di

EA ii f Q

RC RF × 















×= χ )( 8 (4-5)

Where

CEA8i

 = uranium concentration in EA-8 as a consequent of emission from 

source i, where i can be Plant 1, 2/3, 4, and etc.

Ri

 = uranium emission rate of source i. Table 4-1, 4-2a, and 4-2b values for 

U emission source i ÷ by number of seconds per year. For 222Rn 

releases, Figure 4-1 was used. 

Q di















 χ = atmospheric dilution factor at distance d, where d is the distance from 

EA-8 to emission source i using Table 4-6 values based on distance 

values in Table 4-7.

RF = respirable fraction of the uranium aerosol. 65% as discussed in 

Section 4.3.2.2.

 fi = fraction of time that the wind blew in EA-8 direction from emission 

source i using Table 4-8 percentages.

The following data presents the inputs and results of application of Eq. 4-5. The resulting 

CEA8i appear in Appendix 4A, table for 1955 Row EA-8 and Columns 3 through 10 for U 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 21 of 83

release, and Column 15 in the unit of Ci/m3 and Column 16 in the unit of pCi/ m3 for radon 

release. 

1955 g/sec m sec/m3 % g/m3

I R×( RF) d (χ/Q)di fi CEA8i

Plant 1 3.38E-03a 500 1.44E-04 19 9.23E-08

Plant 2/3 2.29E-02 450 1.39E-04 19 6.04E-07

Plant 4 2.56E-01 300 1.06E-04 23 6.22E-06

Plant 5 2.14E-01 300 1.06E-04 26 5.90E-06

Plant 6 1.34E-03 300 1.06E-04 14 1.99E-08

Plant 7 1.50E-01 250 5.45E-05 23 1.88E-06

Plant 8 3.75E-02 450 1.39E-04 8 4.16E-07

Plant 9 0.0 500 1.44E-04 12 0.0

Pilot Plant 9.11E-03 300 1.06E-04 19 1.84E-07

Waste Pits 4.43E-05b 1,000 8.75E-05 b 11 4.26E-10

Silos (Rn) 1.58E-04 Ci/sec c 1,000 1.40E-04 c 15 3.32E-09 c

Notes:

a

 Plant 1 release included the solid and liquid waste incineration and Oil & Graphite releases. (46.2kg 

+ 118kg) b

 RF=1.0 for Waste Pits releases and ground release diffusion factor was used. c

 RF=1.0 and gaseous elevated release diffusion factor was used. The unit for radon release is 

Ci/m3.

Step 2. Sum CEA8i for all the radionuclide emission sources and obtain total radionuclide intake for 

the year by multiplying the concentration by 2,400 m3

: 

35

8 * CC /1053.1 mg

i

EA EA i

−

∑ ×== or 1.53×10-2 mg/ m3

 and

U intake = (1.53×10-2 mg/m3

)(2400 m3) = 36.7 mg

The U concentration and intake results are in Appendix 4A, 1955 table, columns 13 and 

14, respectively.

Step 3. Transfer the total U concentration and annual intake in EA-8 forward to Table 4-9a. 

Calculate the Rn intake in WLM by adding the average background concentration and 

using the conversion factor given in Table 4-9d as shown in the following:

Rn intake (WLM) = ((3.32×10-9 Ci/m3

)(109 pCi/L per Ci/m3) + (0.47 pCi/L))( 8.24×10-2

WLM/(pCi/m3

) 

 = 0.312 WLM

The above radon WLM result for EA-8 are presented in column 10 of Table 4-9a for the 

year 1955.

4.3.3

On-site average radionuclide concentrations for 1989 to 1996 were obtained from continuous, highvolume air monitoring stations (AMS) as part of the various sampling programs at FEMP to monitor 

Onsite Air Monitored Average Concentrations (1989 to 2002)
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 22 of 83

releases to the environment. The air monitoring results were reported in the annual site 

environmental reports for the years covered in this TBD section.

Figure 4-6 shows the AMS locations. On-site average radionuclide concentrations were derived from 

data in the Annual Site Environmental Reports from AMS 8 and AMS 9. Figures 4-7 and 4-8 provide 

the average uranium and thorium concentrations, respectively, at AMS 8 and AMS 9 by year. The 

radon concentrations is taken from the average monitoring results from six fence line AMS locations 

along Paddy’s Run Road closest to the K-65 Silos.

N

Center at

Plant 4

Plant Perimeter

Production Area

Perimeter

FEMP

Waste

Pit

Area

1

2

3

4

5

6

7 8

9

10

Figure 4-6. Air monitoring station locations. 

In about 1997, in recognition that the primary source of air emissions at the FEMP had changed under 

full-scale remediation from point sources to fugitive emissions from diffuse sources, the FEMP 

Radiological Air Particulate Monitoring Program defined a new approach for demonstrating NESHAP 

Subpart H compliance. The approach utilizes radiological air particulate monitoring results rather than 

computer modeling to estimate the dose from airborne particulates. The onsite monitors were 

positioned to provide surveillance of the fugitive emissions generated by the remediation activities. 

The annual environmental reports reported the maximum and minimum radionuclide concentrations 

obtained by these monitors. This TBD uses the maximum concentration values reported at the 

monitor locations as the technical basis for internal occupational environmental dose assessment. 

Onsite Radionuclide Concentrations and Intakes (1989–1996)

The values in Figure 4-5 were used to estimate the radionuclide concentrations at each of the EAs. 

By using Equation 4-1, the radionuclide release rates were calculated using average radionuclide 

concentrations obtained from AMS 8 and AMS 9. AMS 8 and 9 are located approximately 750 m and 

500 m from the center of the Production Area (Plant 4), downwind of the prevailing wind direction 

(40% of the time), respectively. The radionuclide release rates used to estimate EA concentration 

were the average of those release rates calculated for AMS 8 and AMS 9, using ground release 

(χ/Q)s . The source of release was assumed to be at the center of the Production Area (Plant 4). The 

EA concentrations and intakes were calculated using these input data. The average radon 

concentrations measured from the various AMS locations reported in the Environmental Reports are 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 23 of 83

directly used as the average EA radon concentrations in accordance with the following. These radon 

concentrations included the ambient concentration.

• Average AMS M, L, K and J values were applied to EA-1, EA-3, EA-4, and EA-8. 

• Average AMS M and L values corrected for distance were applied to EA-6.

• Average AMS 6, O, and N values were applied to EA-5.

• AMS 9 value was applied to EA-2, EA-7, and EA-11.

• AMS 8 value was applied to EA-9 and EA-10. 

Table 4-9b lists a summary of the results; Appendix 4A contains more detail.

Onsite Radionuclide Concentrations and Intakes (1997 to 2002)

The onsite radionuclide concentrates reported in the Integrated Site Environmental Reports (Fluor 

1997, 1998, 1999, 2000, 2001) form the technical basis for the occupational environmental dose 

calculations. Table 4-9c lists the maximum concentration values from 1997 to 2002. 3 -6

× Concentration (pCi/m 10 )

Years

1989 1990 1991 1992 1993 1994 1995 1996

500

1,000

1,500

2,000

0

RMS-9

RMS-8

uranium

Figure 4-7. Average onsite uranium concentrations (1989 - 1996). 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 24 of 83 3 -6

× Concentration (pCi/m 10 )

Years

1989 1990 1991 1992 1993 1994 1995 1996

5

10

15

20

0

RMS-9

RMS-8

25

Not Sampled

Th-232

Figure 4-8. Average onsite thorium concentrations (1989 -1996).
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 25 of 83

4.3.4

Table 4-9a. Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-9d) 

Airborne Radionuclide Concentration and Intake Summary for Years 1951 through 2002 (Table 4-9)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1951

Uranium Conc. (mg/m3) 6.44E-05 1.35E-04 1.19E-04 2.23E-06 2.83E-05 2.91E-05 4.01E-05 5.08E-05 2.14E-05 3.77E-05 3.11E-05

Intake (mg) 1.55E-01 3.23E-01 2.86E-01 5.35E-03 6.79E-02 6.98E-02 9.63E-02 1.22E-01 5.14E-02 9.05E-02 7.46E-02

Thorium Conc. (mg/m3) 0 0 0 0 0 0 0 0 0 0 0

Intake (mg) 0 0 0 0 0 0 0 0 0 0 0 

Rn-222 Conc. (pCi/L) 3.31E+00 2.79E-01 1.47E-01 4.88E-01 3.38E-01 1.01E-01 1.01E-01 1.47E-01 3.50E-02 3.44E-01 1.94E-02

Conc.+ Backgrd 3.78E+00 7.49E-01 6.17E-01 9.58E-01 8.08E-01 5.71E-01 5.71E-01 6.17E-01 5.05E-01 8.14E-01 4.89E-01

Intake (WLM) 3.11E-01 6.17E-02 5.08E-02 7.89E-02 6.66E-02 4.71E-02 4.71E-02 5.08E-02 4.16E-02 6.71E-02 4.03E-02

1952

Uranium Conc. (mg/m3) 2.60E-04 5.42E-04 4.79E-04 1.16E-05 1.14E-04 1.17E-04 1.63E-04 2.05E-04 8.82E-05 1.52E-04 1.25E-04

Intake (mg) 6.24E-01 1.30E+00 1.15E+00 2.78E-02 2.73E-01 2.80E-01 3.91E-01 4.93E-01 2.12E-01 3.65E-01 3.00E-01

Thorium Conc. (mg/m3) 0 0 0 0 0 0 0 0 0 0 0 

Intake (mg) 0 0 0 0 0 0 0 0 0 0 0

Rn-222 Conc. (pCi/L) 5.83E+01 6.40E+00 4.04E+00 1.25E+01 9.61E+00 2.98E+00 3.67E+00 3.77E+00 1.24E+00 7.74E+00 1.73E+00

Conc.+ Backgrd 5.88E+01 6.87E+00 4.51E+00 1.30E+01 1.01E+01 3.45E+00 4.14E+00 4.24E+00 1.71E+00 8.21E+00 2.20E+00

Intake (WLM) 4.84E+00 5.66E-01 3.72E-01 1.07E+00 8.31E-01 2.84E-01 3.41E-01 3.49E-01 1.41E-01 6.77E-01 1.81E-01

1953

Uranium Conc. (mg/m3) 6.46E-04 2.46E-03 5.22E-04 3.00E-04 4.61E-04 6.63E-04 6.07E-04 1.00E-03 9.23E-04 6.26E-04 2.84E-04

Intake (mg) 1.55E+00 5.91E+00 1.25E+00 7.20E-01 1.11E+00 1.59E+00 1.46E+00 2.40E+00 2.21E+00 1.50E+00 6.81E-01

Thorium Conc. (mg/m3) 0 0 0 0 0 0 0 0 0 0 0

Intake (mg) 0 0 0 0 0 0 0 0 0 0 0

Rn-222 Conc. (pCi/L) 1.24E+01 2.53E+00 2.00E+00 5.71E+00 4.93E+00 1.59E+00 2.28E+00 1.73E+00 7.60E-01 2.97E+00 1.46E+00

Conc.+ Backgrd 1.29E+01 3.00E+00 2.47E+00 6.18E+00 5.40E+00 2.06E+00 2.75E+00 2.20E+00 1.23E+00 3.44E+00 1.93E+00

Intake (WLM) 1.06E+00 2.47E-01 2.04E-01 5.09E-01 4.45E-01 1.70E-01 2.27E-01 1.81E-01 1.01E-01 2.83E-01 1.59E-01

1954

Uranium Conc. (mg/m3) 4.49E-03 1.72E-02 2.79E-03 3.25E-03 2.83E-03 3.73E-03 3.10E-03 6.88E-03 8.19E-03 6.59E-03 2.22E-03

Intake (mg) 1.08E+01 4.13E+01 6.70E+00 7.79E+00 6.80E+00 8.95E+00 7.43E+00 1.65E+01 1.97E+01 1.58E+01 5.33E+00

Thorium Conc. (mg/m3) 3.65E-04 4.73E-04 3.92E-04 3.34E-04 9.88E-05 2.15E-05 3.73E-04 3.65E-04 5.47E-04 1.47E-04 6.79E-05

Intake (mg) 8.76E-01 1.14E+00 9.40E-01 8.03E-01 2.37E-01 5.16E-02 8.96E-01 8.76E-01 1.31E+00 3.52E-01 1.63E-01

Rn-222 Conc. (pCi/L) 8.59E+00 4.44E+00 3.99E+00 1.10E+01 1.00E+01 3.28E+00 5.00E+00 3.33E+00 1.66E+00 5.10E+00 3.51E+00

Conc.+ Backgrd 9.06E+00 4.91E+00 4.46E+00 1.15E+01 1.05E+01 3.75E+00 5.47E+00 3.80E+00 2.13E+00 5.57E+00 3.98E+00

Intake (WLM) 7.47E-01 4.05E-01 3.68E-01 9.45E-01 8.63E-01 3.09E-01 4.51E-01 3.13E-01 1.76E-01 4.59E-01 3.28E-01

1955

Uranium Conc. (mg/m3) 1.01E-02 3.72E-02 6.22E-03 7.13E-03 5.95E-03 7.95E-03 7.47E-03 1.53E-02 1.70E-02 1.46E-02 4.60E-03

Intake (mg) 2.43E+01 8.92E+01 1.49E+01 1.71E+01 1.43E+01 1.91E+01 1.79E+01 3.67E+01 4.07E+01 3.51E+01 1.11E+01

Thorium Conc. (mg/m3) 4.17E-04 5.42E-04 4.48E-04 3.83E-04 1.13E-04 2.46E-05 4.27E-04 4.17E-04 6.26E-04 1.68E-04 7.77E-05

Intake (mg) 1.00E+00 1.30E+00 1.07E+00 9.18E-01 2.71E-01 5.90E-02 1.02E+00 1.00E+00 1.50E+00 4.03E-01 1.87E-01

Rn-222 Conc. (pCi/L) 8.59E+00 4.44E+00 3.99E+00 1.10E+01 1.00E+01 3.28E+00 5.00E+00 3.33E+00 1.66E+00 5.10E+00 3.51E+00

Conc.+ Backgrd 9.06E+00 4.91E+00 4.46E+00 1.15E+01 1.05E+01 3.75E+00 5.47E+00 3.80E+00 2.13E+00 5.57E+00 3.98E+00

Intake (WLM) 7.47E-01 4.05E-01 3.68E-01 9.45E-01 8.63E-01 3.09E-01 4.51E-01 3.13E-01 1.76E-01 4.59E-01 3.28E-01
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 26 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1956

Uranium Conc. (mg/m3) 5.41E-03 1.60E-02 5.07E-03 2.54E-03 2.96E-03 3.86E-03 4.85E-03 6.83E-03 6.22E-03 8.37E-03 2.13E-03

Intake (mg) 1.30E+01 3.84E+01 1.22E+01 6.10E+00 7.09E+00 9.25E+00 1.16E+01 1.64E+01 1.49E+01 2.01E+01 5.10E+00

Thorium Conc. (mg/m3) 0 0 0 0 0 0 0 0 0 0 0

Intake (mg) 0 0 0 0 0 0 0 0 0 0 0 

Rn-222 Conc. (pCi/L) 8.59E+00 4.44E+00 3.99E+00 1.10E+01 1.00E+01 3.28E+00 5.00E+00 3.33E+00 1.66E+00 5.10E+00 3.51E+00

Conc.+ Backgrd 9.06E+00 4.91E+00 4.46E+00 1.15E+01 1.05E+01 3.75E+00 5.47E+00 3.80E+00 2.13E+00 5.57E+00 3.98E+00

Intake (WLM) 7.47E-01 4.05E-01 3.68E-01 9.45E-01 8.63E-01 3.09E-01 4.51E-01 3.13E-01 1.76E-01 4.59E-01 3.28E-01

1957

Uranium Conc. (mg/m3) 4.49E-03 1.07E-02 5.14E-03 1.69E-03 2.85E-03 2.52E-03 4.04E-03 5.18E-03 3.07E-03 7.50E-03 1.34E-03

Intake (mg) 1.08E+01 2.57E+01 1.23E+01 4.07E+00 6.83E+00 6.05E+00 9.71E+00 1.24E+01 7.37E+00 1.80E+01 3.21E+00

Thorium Conc. (mg/m3) 2.01E-08 4.54E-09 3.79E-09 5.32E-09 1.79E-07 3.17E-08 5.57E-09 2.78E-09 1.68E-09 2.42E-08 6.58E-09

Intake (mg) 4.83E-05 1.09E-05 9.09E-06 1.28E-05 4.31E-04 7.61E-05 1.34E-05 6.66E-06 4.03E-06 5.80E-05 1.58E-05

Rn-222 Conc. (pCi/L) 8.59E+00 4.44E+00 3.99E+00 1.10E+01 1.00E+01 3.28E+00 5.00E+00 3.33E+00 1.66E+00 5.10E+00 3.51E+00

Conc.+ Backgrd 9.06E+00 4.91E+00 4.46E+00 1.15E+01 1.05E+01 3.75E+00 5.47E+00 3.80E+00 2.13E+00 5.57E+00 3.98E+00

Intake (WLM) 7.47E-01 4.05E-01 3.68E-01 9.45E-01 8.63E-01 3.09E-01 4.51E-01 3.13E-01 1.76E-01 4.59E-01 3.28E-01

1958

Uranium Conc. (mg/m3) 3.90E-03 8.00E-03 5.64E-03 1.04E-03 3.76E-03 2.55E-03 3.91E-03 3.86E-03 1.93E-03 7.09E-03 1.23E-03

Intake (mg) 9.36E+00 1.92E+01 1.35E+01 2.50E+00 9.02E+00 6.12E+00 9.40E+00 9.26E+00 4.64E+00 1.70E+01 2.94E+00

Thorium Conc. (mg/m3) 4.60E-08 1.04E-08 8.66E-09 1.22E-08 4.10E-07 7.24E-08 1.27E-08 6.35E-09 3.83E-09 5.52E-08 1.50E-08

Intake (mg) 1.10E-04 2.49E-05 2.08E-05 2.92E-05 9.84E-04 1.74E-04 3.06E-05 1.52E-05 9.20E-06 1.33E-04 3.61E-05

Rn-222 Conc. (pCi/L) 8.59E+00 4.44E+00 3.99E+00 1.10E+01 1.00E+01 3.28E+00 5.00E+00 3.33E+00 1.66E+00 5.10E+00 3.51E+00

Conc.+ Backgrd 9.06E+00 4.91E+00 4.46E+00 1.15E+01 1.05E+01 3.75E+00 5.47E+00 3.80E+00 2.13E+00 5.57E+00 3.98E+00

Intake (WLM) 7.47E-01 4.05E-01 3.68E-01 9.45E-01 8.63E-01 3.09E-01 4.51E-01 3.13E-01 1.76E-01 4.59E-01 3.28E-01

1959

Uranium Conc. (mg/m3) 3.96E-03 8.53E-03 5.49E-03 7.75E-04 3.82E-03 2.74E-03 3.88E-03 3.99E-03 2.05E-03 7.10E-03 1.24E-03

Intake (mg) 9.49E+00 2.05E+01 1.32E+01 1.86E+00 9.18E+00 6.57E+00 9.31E+00 9.57E+00 4.93E+00 1.70E+01 2.97E+00

Thorium Conc. (mg/m3) 4.60E-08 1.04E-08 8.66E-09 1.22E-08 4.10E-07 7.24E-08 1.27E-08 6.35E-09 3.83E-09 5.52E-08 1.50E-08

Intake (mg) 1.10E-04 2.49E-05 2.08E-05 2.92E-05 9.84E-04 1.74E-04 3.06E-05 1.52E-05 9.20E-06 1.33E-04 3.61E-05

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1960

Uranium Conc. (mg/m3) 4.40E-03 8.10E-03 6.81E-03 4.71E-04 4.12E-03 2.68E-03 4.16E-03 3.76E-03 1.44E-03 7.67E-03 1.43E-03

Intake (mg) 3.61E+00 5.76E-01 4.94E-01 1.64E+00 5.83E+00 1.23E+01 1.20E+00 3.02E-01 1.82E-01 6.31E-01 8.75E-01

Thorium Conc. (mg/m3) 5.93E-07 1.34E-07 1.11E-07 1.57E-07 5.28E-06 9.33E-07 1.64E-07 8.17E-08 4.94E-08 7.11E-07 1.94E-07

Intake (mg) 1.42E-03 3.21E-04 2.67E-04 3.76E-04 1.27E-02 2.24E-03 3.93E-04 1.96E-04 1.18E-04 1.71E-03 4.65E-04

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 27 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1961

Uranium Conc. (mg/m3) 3.61E-03 6.57E-03 5.55E-03 3.31E-04 4.05E-03 2.36E-03 3.48E-03 3.05E-03 1.07E-03 6.68E-03 1.16E-03

Intake (mg) 8.67E+00 1.58E+01 1.33E+01 7.93E-01 9.72E+00 5.67E+00 8.34E+00 7.33E+00 2.58E+00 1.60E+01 2.77E+00

Thorium Conc. (mg/m3) 1.61E-06 3.64E-07 3.03E-07 4.26E-07 1.44E-05 2.54E-06 4.46E-07 2.22E-07 1.34E-07 1.93E-06 5.27E-07

Intake (mg) 3.87E-03 8.72E-04 7.27E-04 1.02E-03 3.44E-02 6.09E-03 1.07E-03 5.33E-04 3.22E-04 4.64E-03 1.26E-03

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1962

Uranium Conc. (mg/m3) 3.45E-03 5.89E-03 4.81E-03 5.00E-04 3.92E-03 2.15E-03 3.32E-03 2.65E-03 1.34E-03 5.67E-03 1.18E-03

Intake (mg) 8.27E+00 1.41E+01 1.16E+01 1.20E+00 9.41E+00 5.16E+00 7.97E+00 6.37E+00 3.21E+00 1.36E+01 2.83E+00

Thorium Conc. (mg/m3) 2.26E-06 5.10E-07 4.25E-07 5.97E-07 2.01E-05 3.55E-06 6.25E-07 3.11E-07 1.88E-07 2.71E-06 7.38E-07

Intake (mg) 5.42E-03 1.22E-03 1.02E-03 1.43E-03 4.83E-02 8.53E-03 1.50E-03 7.47E-04 4.51E-04 6.50E-03 1.77E-03

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1963

Uranium Conc. (mg/m3) 3.09E-03 5.10E-03 3.53E-03 8.97E-04 3.64E-03 1.87E-03 3.05E-03 2.21E-03 1.81E-03 4.23E-03 1.16E-03

Intake (mg) 7.41E+00 1.22E+01 8.46E+00 2.15E+00 8.74E+00 4.48E+00 7.32E+00 5.31E+00 4.35E+00 1.01E+01 2.78E+00

Thorium Conc. (mg/m3) 2.53E-06 5.71E-07 4.76E-07 6.69E-07 2.26E-05 3.98E-06 7.00E-07 3.49E-07 2.11E-07 3.04E-06 8.28E-07

Intake (mg) 6.08E-03 1.37E-03 1.14E-03 1.61E-03 5.41E-02 9.56E-03 1.68E-03 8.38E-04 5.06E-04 7.29E-03 1.99E-03

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1964

Uranium Conc. (mg/m3) 3.19E-03 3.83E-03 4.21E-03 4.99E-04 3.59E-03 1.64E-03 3.16E-03 1.60E-03 1.16E-03 4.43E-03 1.20E-03

Intake (mg) 7.65E+00 9.18E+00 1.01E+01 1.20E+00 8.63E+00 3.94E+00 7.60E+00 3.85E+00 2.79E+00 1.06E+01 2.88E+00

Thorium Conc. (mg/m3) 1.83E-04 3.77E-04 3.34E-04 6.98E-06 1.04E-04 8.58E-05 1.13E-04 1.42E-04 6.02E-05 1.09E-04 8.79E-05

Intake (mg) 4.39E-01 9.05E-01 8.02E-01 1.68E-02 2.50E-01 2.06E-01 2.71E-01 3.42E-01 1.44E-01 2.61E-01 2.11E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1965

Uranium Conc. (mg/m3) 4.47E-03 4.94E-03 6.53E-03 3.25E-04 2.90E-03 1.90E-03 4.61E-03 1.98E-03 1.20E-03 6.43E-03 1.71E-03

Intake (mg) 1.07E+01 1.19E+01 1.57E+01 7.80E-01 6.97E+00 4.57E+00 1.11E+01 4.74E+00 2.88E+00 1.54E+01 4.10E+00

Thorium Conc. (mg/m3) 1.83E-04 3.77E-04 3.34E-04 6.98E-06 1.04E-04 8.58E-05 1.13E-04 1.42E-04 6.02E-05 1.09E-04 8.79E-05

Intake (mg) 4.39E-01 9.05E-01 8.02E-01 1.67E-02 2.50E-01 2.06E-01 2.71E-01 3.42E-01 1.44E-01 2.61E-01 2.11E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 28 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1966

Uranium Conc. (mg/m3) 1.24E-03 1.95E-03 1.77E-03 2.18E-04 1.49E-03 7.73E-04 1.25E-03 8.65E-04 4.44E-04 2.06E-03 4.45E-04

Intake (mg) 2.97E+00 4.68E+00 4.26E+00 5.24E-01 3.58E+00 1.85E+00 3.01E+00 2.08E+00 1.06E+00 4.94E+00 1.07E+00

Thorium Conc. (mg/m3) 2.60E-04 4.49E-04 4.53E-04 7.06E-06 1.31E-04 1.13E-04 1.94E-04 1.69E-04 7.51E-05 2.18E-04 1.18E-04

Intake (mg) 6.24E-01 1.08E+00 1.09E+00 1.69E-02 3.14E-01 2.70E-01 4.65E-01 4.07E-01 1.80E-01 5.23E-01 2.83E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1967

Uranium Conc. (mg/m3) 1.86E-03 2.81E-03 2.82E-03 2.42E-04 9.83E-04 9.21E-04 1.97E-03 1.22E-03 6.47E-04 3.01E-03 6.81E-04

Intake (mg) 4.47E+00 6.75E+00 6.76E+00 5.80E-01 2.36E+00 2.21E+00 4.72E+00 2.93E+00 1.55E+00 7.23E+00 1.63E+00

Thorium Conc. (mg/m3) 1.83E-04 3.77E-04 3.34E-04 7.04E-06 1.06E-04 8.61E-05 1.13E-04 1.43E-04 6.02E-05 1.09E-04 8.79E-05

Intake (mg) 4.40E-01 9.05E-01 8.03E-01 1.69E-02 2.54E-01 2.07E-01 2.71E-01 3.42E-01 1.44E-01 2.62E-01 2.11E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1968

Uranium Conc. (mg/m3) 3.20E-03 4.34E-03 4.93E-03 2.30E-04 1.48E-03 1.45E-03 3.35E-03 1.85E-03 9.13E-04 5.08E-03 1.17E-03

Intake (mg) 7.67E+00 1.04E+01 1.18E+01 5.53E-01 3.55E+00 3.48E+00 8.05E+00 4.44E+00 2.19E+00 1.22E+01 2.80E+00

Thorium Conc. (mg/m3) 1.83E-04 3.77E-04 3.34E-04 7.11E-06 1.09E-04 8.66E-05 1.13E-04 1.43E-04 6.02E-05 1.09E-04 8.80E-05

Intake (mg) 4.40E-01 9.05E-01 8.03E-01 1.71E-02 2.61E-01 2.08E-01 2.71E-01 3.42E-01 1.44E-01 2.63E-01 2.11E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1969

Uranium Conc. (mg/m3) 2.67E-03 3.32E-03 4.15E-03 1.61E-04 1.29E-03 1.15E-03 2.80E-03 1.38E-03 6.44E-04 4.20E-03 9.93E-04

Intake (mg) 6.41E+00 7.97E+00 9.97E+00 3.86E-01 3.11E+00 2.76E+00 6.72E+00 3.32E+00 1.54E+00 1.01E+01 2.38E+00

Thorium Conc. (mg/m3) 8.86E-04 1.07E-03 1.43E-03 8.15E-06 3.36E-04 3.31E-04 8.42E-04 4.01E-04 2.00E-04 1.08E-03 3.64E-04

Intake (mg) 2.13E+00 2.57E+00 3.43E+00 1.96E-02 8.05E-01 7.94E-01 2.02E+00 9.62E-01 4.80E-01 2.60E+00 8.73E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1970

Uranium Conc. (mg/m3) 1.01E-03 1.38E-03 1.56E-03 1.04E-04 7.16E-04 5.01E-04 1.05E-03 5.95E-04 2.63E-04 1.67E-03 3.69E-04

Intake (mg) 2.42E+00 3.31E+00 3.75E+00 2.51E-01 1.72E+00 1.20E+00 2.53E+00 1.43E+00 6.32E-01 4.00E+00 8.86E-01

Thorium Conc. (mg/m3) 7.19E-04 9.75E-04 1.19E-03 1.00E-05 2.89E-04 2.79E-04 6.42E-04 3.66E-04 1.75E-04 8.01E-04 3.04E-04

Intake (mg) 1.73E+00 2.34E+00 2.85E+00 2.40E-02 6.94E-01 6.71E-01 1.54E+00 8.79E-01 4.21E-01 1.92E+00 7.29E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 29 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1971

Uranium Conc. (mg/m3) 5.64E-04 8.55E-04 9.17E-04 7.53E-05 5.62E-04 3.34E-04 5.99E-04 3.81E-04 1.30E-04 1.04E-03 2.04E-04

Intake (mg) 1.35E+00 2.05E+00 2.20E+00 1.81E-01 1.35E+00 8.02E-01 1.44E+00 9.14E-01 3.12E-01 2.49E+00 4.90E-01

Thorium Conc. (mg/m3) 3.16E-04 3.32E-04 4.93E-04 2.05E-06 1.33E-04 1.16E-04 3.16E-04 1.24E-04 6.53E-05 4.19E-04 1.25E-04

Intake (mg) 7.57E-01 7.98E-01 1.18E+00 4.93E-03 3.19E-01 2.78E-01 7.58E-01 2.98E-01 1.57E-01 1.01E+00 3.01E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

1972

Uranium Conc. (mg/m3) 5.79E-04 1.70E-03 1.04E-03 1.07E-04 7.00E-04 5.32E-04 5.77E-04 8.52E-04 2.01E-04 1.52E-03 1.40E-04

Intake (mg) 1.39E+00 4.08E+00 2.50E+00 2.58E-01 1.68E+00 1.28E+00 1.38E+00 2.04E+00 4.83E-01 3.65E+00 3.36E-01

Thorium Conc. (mg/m3) 7.74E-05 1.55E-04 1.38E-04 3.51E-06 6.45E-05 3.90E-05 4.70E-05 5.87E-05 2.49E-05 4.76E-05 3.68E-05

Intake (mg) 1.86E-01 3.72E-01 3.30E-01 8.42E-03 1.55E-01 9.36E-02 1.13E-01 1.41E-01 5.97E-02 1.14E-01 8.84E-02

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1973

Uranium Conc. (mg/m3) 6.47E-04 1.85E-03 1.10E-03 1.15E-04 7.15E-04 5.63E-04 6.33E-04 9.15E-04 2.53E-04 1.60E-03 1.61E-04

Intake (mg) 1.55E+00 4.43E+00 2.64E+00 2.77E-01 1.72E+00 1.35E+00 1.52E+00 2.20E+00 6.08E-01 3.84E+00 3.88E-01

Thorium Conc. (mg/m3) 2.98E-05 5.55E-05 4.92E-05 1.85E-06 4.34E-05 1.75E-05 1.73E-05 2.11E-05 9.01E-06 1.96E-05 1.38E-05

Intake (mg) 7.14E-02 1.33E-01 1.18E-01 4.45E-03 1.04E-01 4.19E-02 4.15E-02 5.08E-02 2.16E-02 4.71E-02 3.31E-02

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1974

Uranium Conc. (mg/m3) 1.01E-03 2.90E-03 1.80E-03 1.02E-04 9.45E-04 8.60E-04 9.76E-04 1.44E-03 3.36E-04 2.57E-03 2.34E-04

Intake (mg) 2.42E+00 6.96E+00 4.32E+00 2.44E-01 2.27E+00 2.06E+00 2.34E+00 3.47E+00 8.06E-01 6.16E+00 5.61E-01

Thorium Conc. (mg/m3) 5.61E-05 1.10E-04 9.77E-05 2.80E-06 5.62E-05 2.95E-05 3.36E-05 4.18E-05 1.77E-05 3.51E-05 2.65E-05

Intake (mg) 1.35E-01 2.65E-01 2.35E-01 6.71E-03 1.35E-01 7.09E-02 8.07E-02 1.00E-01 4.26E-02 8.43E-02 6.36E-02

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 30 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

1975

Uranium Conc. (mg/m3) 1.17E-03 3.42E-03 2.06E-03 1.02E-04 1.14E-03 1.03E-03 1.13E-03 1.69E-03 3.99E-04 2.98E-03 2.74E-04

Intake (mg) 2.80E+00 8.20E+00 4.95E+00 2.44E-01 2.74E+00 2.46E+00 2.71E+00 4.05E+00 9.58E-01 7.16E+00 6.58E-01

Thorium Conc. (mg/m3) 5.79E-06 4.23E-06 3.70E-06 1.17E-06 3.82E-05 7.34E-06 2.14E-06 1.82E-06 8.74E-07 5.98E-06 2.14E-06

Intake (mg) 1.39E-02 1.02E-02 8.89E-03 2.80E-03 9.18E-02 1.76E-02 5.15E-03 4.37E-03 2.10E-03 1.43E-02 5.13E-03

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1976

Uranium Conc. (mg/m3) 1.34E-03 3.84E-03 2.41E-03 8.57E-05 1.29E-03 1.15E-03 1.29E-03 1.91E-03 4.03E-04 3.44E-03 3.09E-04

Intake (mg) 3.22E+00 9.22E+00 5.79E+00 2.06E-01 3.09E+00 2.76E+00 3.09E+00 4.58E+00 9.67E-01 8.26E+00 7.41E-01

Thorium Conc. (mg/m3) 5.24E-06 1.18E-06 9.85E-07 1.38E-06 4.66E-05 8.24E-06 1.45E-06 7.22E-07 4.36E-07 6.28E-06 1.71E-06

Intake (mg) 1.26E-02 2.84E-03 2.36E-03 3.32E-03 1.12E-01 1.98E-02 3.48E-03 1.73E-03 1.05E-03 1.51E-02 4.11E-03

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1977

Uranium Conc. (mg/m3) 3.92E-04 1.18E-03 6.12E-04 1.15E-04 6.68E-04 3.99E-04 3.83E-04 5.78E-04 1.97E-04 9.59E-04 1.06E-04

Intake (mg) 9.41E-01 2.84E+00 1.47E+00 2.77E-01 1.60E+00 9.58E-01 9.19E-01 1.39E+00 4.73E-01 2.30E+00 2.55E-01

Thorium Conc. (mg/m3) 2.18E-04 4.48E-04 3.97E-04 8.67E-06 1.37E-04 1.04E-04 1.34E-04 1.69E-04 7.15E-05 1.31E-04 1.05E-04

Intake (mg) 5.24E-01 1.07E+00 9.52E-01 2.08E-02 3.28E-01 2.50E-01 3.23E-01 4.06E-01 1.72E-01 3.14E-01 2.51E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1978

Uranium Conc. (mg/m3) 8.84E-05 2.09E-04 9.61E-05 1.11E-04 4.84E-04 1.31E-04 9.16E-05 1.17E-04 7.74E-05 1.87E-04 3.13E-05

Intake (mg) 2.12E-01 5.01E-01 2.31E-01 2.67E-01 1.16E+00 3.13E-01 2.20E-01 2.81E-01 1.86E-01 4.48E-01 7.52E-02

Thorium Conc. (mg/m3) 2.19E-04 4.48E-04 3.97E-04 8.90E-06 1.44E-04 1.05E-04 1.35E-04 1.69E-04 7.16E-05 1.32E-04 1.05E-04

Intake (mg) 5.26E-01 1.07E+00 9.53E-01 2.14E-02 3.46E-01 2.53E-01 3.23E-01 4.06E-01 1.72E-01 3.17E-01 2.52E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 31 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1979

Uranium Conc. (mg/m3) 8.45E-05 1.88E-04 6.49E-05 8.52E-05 6.51E-04 1.61E-04 7.22E-05 9.41E-05 4.94E-05 1.91E-04 3.39E-05

Intake (mg) 2.03E-01 4.52E-01 1.56E-01 2.05E-01 1.56E+00 3.86E-01 1.73E-01 2.26E-01 1.19E-01 4.59E-01 8.13E-02

Thorium Conc. (mg/m3) 2.20E-04 4.48E-04 3.97E-04 8.97E-06 1.47E-04 1.06E-04 1.35E-04 1.69E-04 7.16E-05 1.32E-04 1.05E-04

Intake (mg) 5.27E-01 1.07E+00 9.53E-01 2.15E-02 3.52E-01 2.54E-01 3.23E-01 4.06E-01 1.72E-01 3.17E-01 2.52E-01

Rn-222 Conc. (pCi/L) 1.03E+01 5.33E+00 4.79E+00 1.32E+01 1.20E+01 3.94E+00 6.01E+00 3.99E+00 2.00E+00 6.13E+00 4.22E+00

Conc.+ Backgrd 1.08E+01 5.80E+00 5.26E+00 1.37E+01 1.25E+01 4.41E+00 6.48E+00 4.46E+00 2.47E+00 6.60E+00 4.69E+00

Intake (WLM) 8.87E-01 4.78E-01 4.33E-01 1.13E+00 1.03E+00 3.63E-01 5.34E-01 3.68E-01 2.04E-01 5.44E-01 3.86E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1980

Uranium Conc. (mg/m3) 1.51E-04 3.21E-04 5.16E-05 9.13E-05 7.21E-04 1.90E-04 9.98E-05 1.49E-04 1.31E-04 2.00E-04 5.22E-05

Intake (mg) 3.62E-01 7.70E-01 1.24E-01 2.19E-01 1.73E+00 4.55E-01 2.40E-01 3.58E-01 3.14E-01 4.79E-01 1.25E-01

Thorium Conc. (mg/m3) 2.37E-05 5.36E-06 4.46E-06 6.27E-06 2.11E-04 3.74E-05 6.56E-06 3.27E-06 1.98E-06 2.85E-05 7.76E-06

Intake (mg) 5.70E-02 1.29E-02 1.07E-02 1.50E-02 5.07E-01 8.96E-02 1.58E-02 7.86E-03 4.74E-03 6.84E-02 1.86E-02

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1981

Uranium Conc. (mg/m3) 2.57E-04 7.38E-04 6.46E-05 1.55E-04 9.46E-04 3.27E-04 1.96E-04 3.27E-04 3.10E-04 3.27E-04 9.02E-05

Intake (mg) 6.18E-01 1.77E+00 1.55E-01 3.72E-01 2.27E+00 7.85E-01 4.70E-01 7.84E-01 7.45E-01 7.85E-01 2.16E-01

Thorium Conc. (mg/m3) 5.94E-06 1.34E-06 1.12E-06 1.57E-06 5.29E-05 9.35E-06 1.64E-06 8.19E-07 4.95E-07 7.13E-06 1.94E-06

Intake (mg) 1.43E-02 3.22E-03 2.68E-03 3.77E-03 1.27E-01 2.24E-02 3.94E-03 1.97E-03 1.19E-03 1.71E-02 4.66E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1982

Uranium Conc. (mg/m3) 2.37E-04 3.25E-04 1.82E-04 8.49E-05 8.65E-04 2.09E-04 1.64E-04 1.58E-04 1.09E-04 3.26E-04 7.74E-05

Intake (mg) 5.68E-01 7.81E-01 4.36E-01 2.04E-01 2.08E+00 5.03E-01 3.93E-01 3.80E-01 2.63E-01 7.82E-01 1.86E-01

Thorium Conc. (mg/m3) 5.93E-06 1.34E-06 1.11E-06 1.57E-06 5.28E-05 9.33E-06 1.64E-06 8.17E-07 4.94E-07 7.11E-06 1.94E-06

Intake (mg) 1.42E-02 3.21E-03 2.67E-03 3.76E-03 1.27E-01 2.24E-02 3.93E-03 1.96E-03 1.18E-03 1.71E-02 4.65E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 32 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1983

Uranium Conc. (mg/m3) 2.19E-04 3.31E-04 2.01E-04 5.76E-05 8.67E-04 2.25E-04 1.57E-04 1.58E-04 8.16E-05 3.52E-04 7.04E-05

Intake (mg) 5.26E-01 7.95E-01 4.82E-01 1.38E-01 2.08E+00 5.41E-01 3.77E-01 3.79E-01 1.96E-01 8.45E-01 1.69E-01

Thorium Conc. (mg/m3) 5.93E-06 1.34E-06 1.11E-06 1.57E-06 5.28E-05 9.33E-06 1.64E-06 8.17E-07 4.94E-07 7.11E-06 1.94E-06

Intake (mg) 1.42E-02 3.21E-03 2.67E-03 3.76E-03 1.27E-01 2.24E-02 3.93E-03 1.96E-03 1.18E-03 1.71E-02 4.65E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1984

Uranium Conc. (mg/m3) 4.41E-04 9.35E-04 5.49E-04 1.38E-04 9.95E-04 3.76E-04 3.70E-04 4.84E-04 2.39E-04 8.04E-04 1.15E-04

Intake (mg) 1.06E+00 2.24E+00 1.32E+00 3.31E-01 2.39E+00 9.03E-01 8.88E-01 1.16E+00 5.73E-01 1.93E+00 2.75E-01

Thorium Conc. (mg/m3) 5.93E-06 1.34E-06 1.11E-06 1.57E-06 5.28E-05 9.33E-06 1.64E-06 8.17E-07 4.94E-07 7.11E-06 1.94E-06

Intake (mg) 1.42E-02 3.21E-03 2.67E-03 3.76E-03 1.27E-01 2.24E-02 3.93E-03 1.96E-03 1.18E-03 1.71E-02 4.65E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1985

Uranium Conc. (mg/m3) 1.42E-04 1.69E-04 1.09E-04 2.62E-05 8.32E-04 1.82E-04 7.46E-05 8.62E-05 2.54E-05 2.36E-04 4.09E-05

Intake (mg) 3.40E-01 4.05E-01 2.61E-01 6.29E-02 2.00E+00 4.38E-01 1.79E-01 2.07E-01 6.09E-02 5.67E-01 9.83E-02

Thorium Conc. (mg/m3) 5.93E-06 1.34E-06 1.11E-06 1.57E-06 5.28E-05 9.33E-06 1.64E-06 8.17E-07 4.94E-07 7.11E-06 1.94E-06

Intake (mg) 1.42E-02 3.21E-03 2.67E-03 3.76E-03 1.27E-01 2.24E-02 3.93E-03 1.96E-03 1.18E-03 1.71E-02 4.65E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1986

Uranium Conc. (mg/m3) 9.22E-05 2.71E-05 1.79E-05 2.65E-05 7.99E-04 1.43E-04 2.77E-05 1.60E-05 1.18E-05 1.10E-04 3.01E-05

Intake (mg) 2.21E-01 6.51E-02 4.30E-02 6.37E-02 1.92E+00 3.42E-01 6.65E-02 3.85E-02 2.84E-02 2.63E-01 7.22E-02

Thorium Conc. (mg/m3) 5.93E-06 1.34E-06 1.11E-06 1.57E-06 5.28E-05 9.33E-06 1.64E-06 8.17E-07 4.94E-07 7.11E-06 1.94E-06

Intake (mg) 1.42E-02 3.21E-03 2.67E-03 3.76E-03 1.27E-01 2.24E-02 3.93E-03 1.96E-03 1.18E-03 1.71E-02 4.65E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 33 of 83

Table 4-9a (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988. (g to Bq Conversion factors are in Table 4-

9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1987

Uranium Conc. (mg/m3) 1.69E-04 2.45E-04 1.58E-04 2.57E-05 8.61E-04 2.06E-04 9.98E-05 1.24E-04 3.21E-05 3.06E-04 4.72E-05

Intake (mg) 4.06E-01 5.88E-01 3.78E-01 6.17E-02 2.07E+00 4.94E-01 2.40E-01 2.97E-01 7.71E-02 7.35E-01 1.13E-01

Thorium Conc. (mg/m3) 6.20E-06 1.40E-06 1.17E-06 1.64E-06 5.52E-05 9.76E-06 1.71E-06 8.55E-07 5.16E-07 7.44E-06 2.03E-06

Intake (mg) 1.49E-02 3.36E-03 2.80E-03 3.93E-03 1.33E-01 2.34E-02 4.12E-03 2.05E-03 1.24E-03 1.79E-02 4.86E-03

Rn-222 Conc. (pCi/L) 2.06E+00 1.07E+00 9.59E-01 2.63E+00 2.41E+00 7.88E-01 1.20E+00 7.99E-01 3.99E-01 1.23E+00 8.43E-01

Conc.+ Backgrd 2.53E+00 1.54E+00 1.43E+00 3.10E+00 2.88E+00 1.26E+00 1.67E+00 1.27E+00 8.69E-01 1.70E+00 1.31E+00

Intake (WLM) 2.08E-01 1.27E-01 1.18E-01 2.55E-01 2.37E-01 1.04E-01 1.38E-01 1.05E-01 7.16E-02 1.40E-01 1.08E-01

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

1988

Uranium Conc. (mg/m3) 1.27E-04 1.21E-04 8.04E-05 2.49E-05 8.42E-04 1.73E-04 5.89E-05 6.25E-05 1.85E-05 1.99E-04 3.78E-05

Intake (mg) 3.05E-01 2.91E-01 1.93E-01 5.99E-02 2.02E+00 4.15E-01 1.41E-01 1.50E-01 4.43E-02 4.77E-01 9.08E-02

Thorium Conc. (mg/m3) 6.43E-06 1.45E-06 1.21E-06 1.70E-06 5.73E-05 1.01E-05 1.78E-06 8.87E-07 5.36E-07 7.72E-06 2.10E-06

Intake (mg) 1.54E-02 3.48E-03 2.90E-03 4.08E-03 1.37E-01 2.43E-02 4.27E-03 2.13E-03 1.29E-03 1.85E-02 5.04E-03

Rn-222 Conc. (pCi/L) 8.59E-01 4.44E-01 3.99E-01 1.10E+00 1.00E+00 3.28E-01 5.00E-01 3.33E-01 1.66E-01 5.10E-01 3.51E-01

Conc.+ Backgrd 1.33E+00 9.14E-01 8.69E-01 1.57E+00 1.47E+00 7.98E-01 9.70E-01 8.03E-01 6.36E-01 9.80E-01 8.21E-01

Intake (WLM) 1.10E-01 7.53E-02 7.16E-02 1.29E-01 1.21E-01 6.58E-02 7.99E-02 6.62E-02 5.24E-02 8.08E-02 6.77E-02

Rn-220 Conc. (pCi/L) 4.70E-01 4.70E-01 0.0 0.0 0.0 0.0 4.70E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.43E-02 7.43E-02 0.0 0.0 0.0 0.0 7.43E-02 0.0 0.0 0.0 0.0

Table 4-9b. Radionuclide concentration (Bq/m3

, pCi/L for Rn) and intake (Bq, WLM for Rn) from 1989 to 1996. (Breakdown of 

transuranic components of recycled uranium is in Table 4-9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1989

Uranium Conc. (Bq/m3) 5.33E-06 2.74E-05 5.51E-07 3.76E-06 5.13E-06 8.10E-06 6.37E-06 1.12E-05 1.19E-05 6.59E-06 2.28E-06

Intake (Bq) 1.28E-02 6.58E-02 1.32E-03 9.02E-03 1.23E-02 1.94E-02 1.53E-02 2.68E-02 2.85E-02 1.58E-02 5.47E-03

Thorium Conc. (Bq/m3) 8.72E-08 4.48E-07 6.14E-08 6.14E-08 8.39E-08 1.32E-07 1.04E-07 1.82E-07 1.94E-07 1.08E-07 3.72E-08

Intake (Bq) 2.09E-04 1.08E-03 1.47E-04 1.47E-04 2.01E-04 3.18E-04 2.50E-04 4.38E-04 4.66E-04 2.59E-04 8.94E-05

Rn-222 Conc. (pCi/L) 7.75E-01 8.00E-01 7.75E-01 7.75E-01 8.33E-01 9.50E+00 8.00E-01 7.75E-01 6.00E-01 6.00E-01 8.00E-01

Intake (WLM) 6.39E-02 6.59E-02 6.39E-02 6.39E-02 6.87E-02 7.83E-01 6.59E-02 6.39E-02 4.94E-02 4.94E-02 6.59E-02

Rn-220 Conc. (pCi/L) 5.00E-01 5.00E-01 0.0 0.0 0.0 0.0 5.00E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.90E-02 7.90E-02 0.0 0.0 0.0 0.0 7.90E-02 0.0 0.0 0.0 0.0

1990

Uranium Conc. (Bq/m3) 2.87E-06 1.47E-05 2.96E-07 2.02E-06 2.76E-06 4.35E-06 3.42E-06 5.99E-06 6.38E-06 3.55E-06 1.22E-06

Intake (Bq) 6.88E-03 3.54E-02 7.12E-04 4.85E-03 6.62E-03 1.04E-02 8.21E-03 1.44E-02 1.53E-02 8.51E-03 2.94E-03

Thorium Conc. (Bq/m3) 3.90E-08 2.00E-07 2.75E-08 2.75E-08 3.75E-08 5.92E-08 4.66E-08 8.16E-08 8.69E-08 4.83E-08 1.67E-08

Intake (Bq) 9.37E-05 4.81E-04 6.60E-05 6.60E-05 9.01E-05 1.42E-04 1.12E-04 1.96E-04 2.08E-04 1.16E-04 4.00E-05

Rn-222 Conc. (pCi/L) 8.00E-01 6.00E-01 8.00E-01 8.00E-01 7.00E-01 7.72E+00 6.00E-01 8.00E-01 5.00E-01 5.00E-01 6.00E-01

Intake (WLM) 6.59E-02 4.94E-02 6.59E-02 6.59E-02 5.77E-02 6.36E-01 4.94E-02 6.59E-02 4.12E-02 4.12E-02 4.94E-02

Rn-220 Conc. (pCi/L) 5.00E-01 5.00E-01 0.0 0.0 0.0 0.0 5.00E-01 0.0 0.0 0.0 0.0

Intake (WLM) 7.90E-02 7.90E-02 0.0 0.0 0.0 0.0 7.90E-02 0.0 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 34 of 83

Table 4-9b (Cont’d). Radionuclide concentration (Bq/m3, pCi/L for Rn) and intake (Bq, WLM for Rn) summary from 1989 to 1996. . 

(Breakdown of transuranic components of recycled uranium is in Table 4-9d)

Radionuclide EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1991

Uranium Conc. (Bq/m3) 4.13E-06 2.12E-05 4.27E-07 2.91E-06 3.97E-06 6.27E-06 4.93E-06 8.64E-06 9.20E-06 5.11E-06 1.76E-06

Intake (Bq) 9.92E-03 5.10E-02 1.03E-03 6.99E-03 9.54E-03 1.51E-02 1.18E-02 2.07E-02 2.21E-02 1.23E-02 4.24E-03

Thorium Conc. (Bq/m3) 1.30E-08 6.68E-08 9.16E-09 9.16E-09 1.25E-08 1.97E-08 1.55E-08 2.72E-08 2.90E-08 1.61E-08 5.55E-09

Intake (Bq) 3.12E-05 1.60E-04 2.20E-05 2.20E-05 3.00E-05 4.74E-05 3.73E-05 6.53E-05 6.95E-05 3.86E-05 1.33E-05

Rn-222 Conc. (pCi/L) 8.00E-01 6.00E-01 8.00E-01 8.00E-01 9.67E-01 8.31E+00 6.00E-01 8.00E-01 6.00E-01 6.00E-01 6.00E-01

Intake (WLM) 6.59E-02 4.94E-02 6.59E-02 6.59E-02 7.97E-02 6.85E-01 4.94E-02 6.59E-02 4.94E-02 4.94E-02 4.94E-02

Rn-220 Conc. (pCi/L) 5.80E-01 5.80E-01 0.0 0.0 0.0 0.0 5.80E-01 0.0 0.0 0.0 0.0

Intake (WLM) 9.16E-02 9.16E-02 0.0 0.0 0.0 0.0 9.16E-02 0.0 0.0 0.0 0.0

1992

Uranium Conc. (Bq/m3) 3.70E-06 1.90E-05 3.82E-07 2.61E-06 3.56E-06 5.61E-06 4.41E-06 7.73E-06 8.23E-06 4.57E-06 1.58E-06

Intake (Bq) 8.88E-03 4.56E-02 9.18E-04 6.25E-03 8.54E-03 1.35E-02 1.06E-02 1.86E-02 1.98E-02 1.10E-02 3.79E-03

Thorium Conc. (Bq/m3) 3.65E-08 1.87E-07 2.57E-08 2.57E-08 3.51E-08 5.53E-08 4.35E-08 7.62E-08 8.11E-08 4.51E-08 1.56E-08

Intake (Bq) 8.75E-05 4.50E-04 6.16E-05 6.16E-05 8.41E-05 1.33E-04 1.04E-04 1.83E-04 1.95E-04 1.08E-04 3.74E-05

Rn-222 Conc. (pCi/L) 6.25E-01 6.00E-01 6.25E-01 6.25E-01 4.33E-01 7.13E+00 6.00E-01 6.25E-01 5.00E-01 5.00E-01 6.00E-01

Intake (WLM) 5.15E-02 4.94E-02 5.15E-02 5.15E-02 3.57E-02 5.87E-01 4.94E-02 5.15E-02 4.12E-02 4.12E-02 4.94E-02

Rn-220 Conc. (pCi/L) 4.00E-01 4.00E-01 0.0 0.0 0.0 0.0 4.00E-01 0.0 0.0 0.0 0.0

Intake (WLM) 6.32E-02 6.32E-02 0.0 0.0 0.0 0.0 6.32E-02 0.0 0.0 0.0 0.0

1993

Uranium Conc. (Bq/m3) 4.44E-06 2.28E-05 4.59E-07 3.13E-06 4.27E-06 6.74E-06 5.30E-06 9.29E-06 9.89E-06 5.49E-06 1.90E-06

Intake (Bq) 1.07E-02 5.48E-02 1.10E-03 7.51E-03 1.03E-02 1.62E-02 1.27E-02 2.23E-02 2.37E-02 1.32E-02 4.55E-03

Thorium Conc. (Bq/m3) 3.50E-08 1.80E-07 2.46E-08 2.46E-08 3.36E-08 5.31E-08 4.17E-08 7.31E-08 7.78E-08 4.32E-08 1.49E-08

Intake (Bq) 8.39E-05 4.31E-04 5.91E-05 5.91E-05 8.07E-05 1.27E-04 1.00E-04 1.75E-04 1.87E-04 1.04E-04 3.58E-05

Rn-222 Conc. (pCi/L) 7.75E-01 6.90E-01 7.75E-01 7.75E-01 7.77E-01 1.00E+01 6.90E-01 7.75E-01 3.70E-01 3.70E-01 6.90E-01

Intake (WLM) 6.39E-02 5.69E-02 6.39E-02 6.39E-02 6.40E-02 8.27E-01 5.69E-02 6.39E-02 3.05E-02 3.05E-02 5.69E-02

Rn-220 Conc. (pCi/L) 9.50E-01 9.50E-01 0.0 0.0 0.0 0.0 9.50E-01 0.0 0.0 0.0 0.0

Intake (WLM) 1.50E-01 1.50E-01 0.0 0.0 0.0 0.0 1.50E-01 0.0 0.0 0.0 0.0

1994

Uranium Conc. (Bq/m3) 1.17E-06 6.00E-06 1.21E-07 8.23E-07 1.12E-06 1.77E-06 1.39E-06 2.44E-06 2.60E-06 1.44E-06 4.99E-07

Intake (Bq) 2.80E-03 1.44E-02 2.90E-04 1.97E-03 2.70E-03 4.26E-03 3.35E-03 5.86E-03 6.24E-03 3.47E-03 1.20E-03

Thorium Conc. (Bq/m3) 2.67E-08 1.37E-07 1.88E-08 1.88E-08 2.57E-08 4.06E-08 3.19E-08 5.59E-08 5.95E-08 3.30E-08 1.14E-08

Intake (Bq) 6.41E-05 3.30E-04 4.52E-05 4.52E-05 6.17E-05 9.74E-05 7.65E-05 1.34E-04 1.43E-04 7.93E-05 2.74E-05

Rn-222 Conc. (pCi/L) 7.00E-01 5.00E-01 7.00E-01 7.00E-01 8.50E-01 7.13E+00 5.00E-01 7.00E-01 5.00E-01 5.00E-01 5.00E-01

Intake (WLM) 5.77E-02 4.12E-02 5.77E-02 5.77E-02 7.00E-02 5.87E-01 4.12E-02 5.77E-02 4.12E-02 4.12E-02 4.12E-02

Rn-220 Conc. (pCi/L) 1.00E+00 1.00E+00 0.0 0.0 0.0 0.0 1.00E+00 0.0 0.0 0.0

Intake (WLM) 1.58E-01 1.58E-01 0.0 0.0 0.0 0.0 1.58E-01 0.0 0.0 0.0

1995

Uranium Conc. (Bq/m3) 7.62E-07 3.91E-06 7.88E-08 5.37E-07 7.33E-07 1.16E-06 9.09E-07 1.59E-06 1.70E-06 9.42E-07 3.25E-07

Intake (Bq) 1.83E-03 9.39E-03 1.89E-04 1.29E-03 1.76E-03 2.78E-03 2.18E-03 3.82E-03 4.07E-03 2.26E-03 7.81E-04

Thorium Conc. (Bq/m3) 1.03E-08 5.27E-08 7.23E-09 7.23E-09 9.87E-09 1.56E-08 1.23E-08 2.15E-08 2.28E-08 1.27E-08 4.38E-09

Intake (Bq) 2.46E-05 1.27E-04 1.74E-05 1.74E-05 2.37E-05 3.74E-05 2.94E-05 5.15E-05 5.48E-05 3.05E-05 1.05E-05

Rn-222 Conc. (pCi/L) 9.00E-01 8.00E-01 9.00E-01 9.00E-01 7.00E-01 1.01E+01 8.00E-01 9.00E-01 7.00E-01 7.00E-01 8.00E-01

Intake (WLM) 7.42E-02 6.59E-02 7.42E-02 7.42E-02 5.77E-02 8.32E-01 6.59E-02 7.42E-02 5.77E-02 5.77E-02 6.59E-02

Rn-220 Conc. (pCi/L) 8.00E-01 8.00E-01 0.0 0.0 0.0 0.0 8.00E-01 0.0 0.0 0.0

Intake (WLM) 1.26E-01 1.26E-01 0.0 0.0 0.0 0.0 1.26E-01 0.0 0.0 0.0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 35 of 83

Table 4-9b (Cont’d). Radionuclide concentration (Bq/m3, pCi/L for Rn) and intake (Bq, WLM for Rn) summary from 1989 to 1996. . 

(Breakdown of transuranic components of recycled uranium is in Table 4-9d)

1996

Uranium Conc. (Bq/m3) 7.70E-07 3.96E-06 7.96E-08 5.42E-07 7.40E-07 1.17E-06 9.19E-07 1.61E-06 1.71E-06 9.52E-07 3.29E-07

Intake (Bq) 1.85E-03 9.49E-03 1.91E-04 1.30E-03 1.78E-03 2.80E-03 2.21E-03 3.86E-03 4.11E-03 2.28E-03 7.89E-04

Thorium Conc. (Bq/m3) 0 0 0 0 0 0 0 0 0 0 0

Intake (Bq) 0 0 0 0 0 0 0 0 0 0 0

Rn-222 Conc. (pCi/L) 1.58E+00 1.80E+00 1.58E+00 1.58E+00 1.63E+00 2.02E+01 1.80E+00 1.58E+00 1.50E+00 1.50E+00 1.80E+00

Intake (WLM) 1.30E-01 1.48E-01 1.30E-01 1.30E-01 1.35E-01 1.66E+00 1.48E-01 1.30E-01 1.24E-01 1.24E-01 1.48E-01

Rn-220 Conc. (pCi/L) 7.00E-01 7.00E-01 0.0 0.0 0.0 0.0 7.00E-01 0.0 0.0 0.0

Intake (WLM) 1.11E-01 1.11E-01 0.0 0.0 0.0 0.0 1.11E-01 0.0 0.0 0.0

Table 4-9c. Radionuclide concentration (Bq/m3

, pCi/L for Rn) and 

intake (Bq, WLM for Rn) from 1997 to 2002. 

(Breakdown of transuranic components of recycled 

uranium is in Table 4-9d)

Radionuclide

Onsite general 

locations (all EAs)

K-65

Exclusion fence

(EA-6)

1997

Uranium Conc. (Bq/m3) 4.44E-05

Intake (Bq) 1.07E-01

Thorium Conc. (Bq/m3) 0

Intake (Bq) 0

Rn-222 Conc. (pCi/L) 1.0 3.5

Exposure (WLM) 8.24E-02 0.29

Rn-220 Conc. (pCi/L) 5.45E-02

Exposure (WLM) 8.61E-03

1998

Uranium Conc. (Bq/m3) 2.81E-05

Intake (Bq) 6.74E-02

Thorium Conc. (Bq/m3) 0

Intake (Bq) 0 

Rn-222 Conc. (pCi/L) 0.8 5.2

Exposure (WLM) 0.066 0.43

Rn-220 Conc. (pCi/L) 8.18E-02

Exposure (WLM) 1.29E-02

1999

Uranium Conc. (Bq/m3) 4.07E-05

Intake (Bq) 9.77E-02

Thorium-230 Conc. (Bq/m3) 9.25E-07

Intake (Bq) 2.23E-03

Rn-222 Conc. (pCi/L) 0.8 5.5

Exposure (WLM) 0.066 0.45

Rn-220 Conc. (pCi/L) 8.18E-02

Exposure (WLM) 1.29E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 36 of 83

Table 4-9c. (Cont’d). Radionuclide concentration (Bq/m

3

, pCi/L for 

Rn) and intake (Bq, WLM for Rn) from 1997 

to 2002. (Breakdown of transuranic 

components of recycled uranium is in Table 

4-9d)

Radionuclide

Onsite general 

locations (all EAs)

K-65

Exclusion fence

(EA-6)

2000

Uranium Conc. (Bq/m

3

) 3.66E-05

Intake (Bq) 8.80E-02

Thorium-230 Conc. (Bq/m

3

) 7.03E-06

Intake (Bq) 1.69E-02

Rn-222 Conc. (pCi/L) 0.6 2.0

Exposure (WLM) 0.049 0.16

Rn-220 Conc. (pCi/L) 5.45E-02

Exposure (WLM) 8.61E-03

2001

Uranium Conc. (Bq/m

3

) 3.66E-05

Intake (Bq) 8.80E-02

Thorium Conc. (Bq/m

3

) 2.77E-05

Intake (Bq) 6.59E-02

Rn-222 Conc. (pCi/L) 0.4 1.7

Exposure (WLM) 0.033 0.14

Rn-220 Conc. (pCi/L) 5.45E-02

Exposure (WLM) 8.61E-03

2002

Uranium Conc. (Bq/m

3

) 7.03E-05

Intake (Bq) 1.69E-01

Thorium-230 Conc. (Bq/m

3

) 2.15E-05

Intake (Bq) 5.15E-02

Rn-222 Conc. (pCi/L) 0.5 2.1

Exposure (WLM) 0.041 0.17

Rn-220 Conc. (pCi/L) 5.45E-02

Exposure (WLM) 8.61E-03
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 37 of 83

Table 4-9d. Conversion factors and isotopic content for values in Table 4-9a. 

Specific Activities for Recycled Uranium:

Uranium 

Enrichmt

U+Cont.

(Bq/mg)

U Pu - 80ppb Np – 300 ppb Tc- 5000 ppb

Bq/mg f act. Bq/mg f act. Bq/mg f act. Bq/mg f act.

Depleted 4.53E+01 1.38E+01 0.305 1.83E-01 0.004 7.77E-03 1.72E-04 3.13E+00 0.069

Natural 5.76E+01 2.61E+01 0.453 1.83E-01 0.003 7.77E-03 1.35E-04 3.13E+00 0.054

2% 

Enriched 9.14E+01 6.03E+01 0.66 1.83E-01 0.002 7.77E-03 8.50E-05 3.13E+00 0.034

2% Enriched recycled uranium that is claimant favorable would be used as the default value for mass to activities 

conversion. 

From Table 4-9a and year 1955, an intake of 24.3 mg for an individual in Exposure Area 1 for a year.

Conversion Example:

From column 2, for 2% enrichment, 24.3 mg × 91.4 Bq/mg = 2.22E+03 Bq of recycled U.

Using the fractions in Column 4 for U, Column 6 for Pu, Column 8 for Np, and Column 10 for Tc, the individual would 

have inhaled:

1,466 Bq 2% enrich U, or 1,129 Bq U-234 (for further breakdown of U isotopes, see next table)

4.44 Bq Pu

0.189 Bq Np

75.5 Bq Tc

Specific Activities for Enriched Uranium:

Uranium Enrichment Isotopes Mass % f activities

Depleted U-234

U-235

U-238

05

0.25

99.75

0.083

0.014

0.903

Natural U-234

U-235

U-238

0.0057

0.7204

99.273

0.504

0.023

0.473

2% Enrich U-234

U-235

U-238

0.02

2.0

97.98

0.770

0.026

0.204

Specific Activities for Thorium:

Thorium-232 would be the default isotope. The degree of equilibrium is impossible to estimate, due to the variation in 

times since chemical separation of the feed stock. The specific activity value for 232Th and daughters is 1.11E-07 Ci/gm 

or 4.11Bq/mg.

Working Level (WL) Conversion Factor for Rn daughters:

1 WL = 100 pCi/L for 100% Rn daughter equilibrium

1 WLM (100% equilibrium) = 1.70E+04 pCi/L-hr

No. of RnConcentration

WLM

Equalibriu Factorm Exposure Time

WLM × × =

100

0.1

, , L

pCi × Concentration × =

17000

20007.0

WLM = 8.24E-02 × Rn-222 concentration in pCi/L for 70% equilibrium and 2,000 hrs exposure time.

Working Level (WL) Conversion Factor for thoron daughters:

1 WL = 7.47 pCi/L for 100% Rn-220 daughter equilibrium

1 WLM (100% equilibrium) = 7.47pCi/L × 170 hr = 1.27E+03 pCi/L-hr

No. of Thoron Concentration

WLM

Equalibriu Factionm Exposure Time

WLM × × =

100

0.1

, , L

pCi × Concentration × =

1270

20001.0

WLM = 1.57E-01 × Rn-220 concentration in pCi/L for 10% equilibrium and 2,000 hrs exposure time.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 38 of 83

4.3.5

The FEMP site-wide intakes (averaging over the EAs) of each uranium and each non-uranium 

radionuclide were developed, using the conversion factors in Table 4-9d. These annual site-wide 

intakes are listed in Table 4-10 by each radionuclide. 

Site-Wide Average Intake Summary by Isotopes for Years 1951 through 2002 (Table 

4-10)

Table 4-10. Site-wide intakes of each uranium and each non-uranium radionuclides in Bq/yr and 

radon in WLM for 1951 through 2002.

Tc-99a Th-232 U-234 a Np-237 a Pu-239 a Rn-222 b Rn-220

Year Bq/yr Bq/yr Bq/yr Bq/yr Bq/yr WLM WLM

1951 3.82E-01 0 5.66E+00 9.48E-04 2.23E-02 7.88E-02 -- 

1952 1.54E+00 0 2.28E+01 3.83E-03 9.01E-02 8.78E-01 --

1953 5.80E+00 0 8.60E+01 1.44E-02 3.39E-01 3.26E-01 --

1954 4.19E+01 2.86E+00 6.20E+02 1.04E-01 2.45E+00 4.88E-01 --

1955 9.12E+01 3.26E+00 1.35E+03 2.26E-01 5.33E+00 4.88E-01 --

1956 4.39E+01 0 6.50E+02 1.09E-01 2.56E+00 4.88E-01 --

1957 3.31E+01 2.56E-04 4.91E+02 8.22E-02 1.94E+00 4.88E-01 --

1958 2.93E+01 5.85E-04 4.34E+02 7.27E-02 1.71E+00 4.88E-01 --

1959 2.98E+01 5.85E-04 4.41E+02 7.39E-02 1.74E+00 5.78E-01 --

1960 7.86E+00 7.55E-03 1.02E+01 1.95E-02 4.60E-01 5.78E-01 --

1961 2.59E+01 2.05E-02 3.84E+02 6.43E-02 1.51E+00 5.78E-01 --

1962 2.38E+01 2.87E-02 3.53E+02 5.91E-02 1.39E+00 5.78E-01 --

1963 2.09E+01 3.22E-02 3.09E+02 5.18E-02 1.22E+00 5.78E-01 --

1964 1.95E+01 1.44E+00 2.89E+02 4.83E-02 1.14E+00 5.78E-01 --

1965 2.53E+01 1.44E+00 3.75E+02 6.28E-02 1.48E+00 5.78E-01 --

1966 8.54E+00 1.96E+00 1.27E+02 2.12E-02 4.99E-01 5.78E-01 --

1967 1.17E+01 1.44E+00 1.74E+02 2.91E-02 6.85E-01 5.78E-01 --

1968 1.91E+01 1.44E+00 2.83E+02 4.74E-02 1.12E+00 5.78E-01 --

1969 1.56E+01 6.23E+00 2.31E+02 3.86E-02 9.09E-01 5.78E-01 --

1970 6.30E+00 5.16E+00 9.33E+01 1.56E-02 3.68E-01 5.78E-01 --

1971 3.86E+00 2.19E+00 5.73E+01 9.59E-03 2.26E-01 5.78E-01 --

1972 5.43E+00 6.21E-01 8.05E+01 1.35E-02 3.17E-01 5.78E-01 2.03E-02

1973 5.84E+00 2.49E-01 8.66E+01 1.45E-02 3.41E-01 5.78E-01 2.03E-02

1974 8.99E+00 4.55E-01 1.33E+02 2.23E-02 5.26E-01 5.78E-01 2.03E-02

1975 1.05E+01 6.58E-02 1.56E+02 2.61E-02 6.14E-01 5.78E-01 2.03E-02

1976 1.19E+01 6.67E-02 1.77E+02 2.96E-02 6.97E-01 5.78E-01 2.03E-02

1977 3.82E+00 1.72E+00 5.66E+01 9.48E-03 2.23E-01 5.78E-01 2.03E-02

1978 1.11E+00 1.73E+00 1.64E+01 2.75E-03 6.48E-02 5.78E-01 2.03E-02

1979 1.14E+00 1.74E+00 1.70E+01 2.84E-03 6.69E-02 5.78E-01 2.03E-02

1980 1.47E+00 3.02E-01 2.18E+01 3.66E-03 8.61E-02 1.47E-01 2.03E-02

1981 2.55E+00 7.56E-02 3.78E+01 6.34E-03 1.49E-01 1.47E-01 2.03E-02

1982 1.87E+00 7.55E-02 2.77E+01 4.65E-03 1.09E-01 1.47E-01 2.03E-02

1983 1.86E+00 7.55E-02 2.75E+01 4.61E-03 1.09E-01 1.47E-01 2.03E-02

1984 3.72E+00 7.55E-02 5.51E+01 9.23E-03 2.17E-01 1.47E-01 2.03E-02

1985 1.31E+00 7.55E-02 1.95E+01 3.26E-03 7.68E-02 1.47E-01 2.03E-02

1986 8.89E-01 7.55E-02 1.32E+01 2.21E-03 5.20E-02 1.47E-01 2.03E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 39 of 83

Table 4-10. (Cont’d) Site-wide intakes of each uranium and each non-uranium 

radionuclides in Bq/yr and radon in WLM for 1951 through 2002.

Tc-99 Th-232 U-234 Np-237 Pu-239 Rn-222 Rn-220

Year Bq/yr Bq/yr Bq/yr Bq/yr Bq/yr WLM WLM

1987 1.55E+00 7.90E-02 2.30E+01 3.86E-03 9.08E-02 1.47E-01 2.03E-02

1988 1.19E+00 8.16E-02 1.77E+01 2.96E-03 6.97E-02 8.39E-02 2.03E-02

1989 6.57E-04 3.28E-04 9.81E-03 1.64E-06 3.86E-05 1.28E-01 2.15E-02

1990 3.53E-04 1.46E-04 5.27E-03 8.83E-07 2.08E-05 1.08E-01 2.15E-02

1991 5.09E-04 4.88E-05 7.61E-03 1.27E-06 2.99E-05 1.16E-01 2.50E-02

1992 4.56E-04 1.37E-04 6.81E-03 1.14E-06 2.68E-05 9.63E-02 1.72E-02

1993 5.47E-04 1.31E-04 8.18E-03 1.37E-06 3.22E-05 1.25E-01 4.09E-02

1994 1.44E-04 1.00E-04 2.15E-03 3.60E-07 8.46E-06 9.94E-02 4.31E-02

1995 9.38E-05 3.86E-05 1.40E-03 2.35E-07 5.52E-06 1.36E-01 3.44E-02

1996 9.48E-05 0 1.42E-03 2.37E-07 5.57E-06 2.73E-01 3.03E-02

1997 3.64E-03 0 5.44E-02 9.10E-06 2.14E-04 1.86E-01 8.61E-03

1998 2.29E-03 0 3.42E-02 5.73E-06 1.35E-04 2.48E-01 1.29E-02

1999 3.32E-03 2.23E-03 4.96E-02 8.30E-06 1.95E-04 2.58E-01 1.29E-02

2000 2.99E-03 1.69E-02 4.47E-02 7.48E-06 1.76E-04 1.05E-01 8.61E-03

2001 2.99E-03 6.59E-02 4.47E-02 7.48E-06 1.76E-04 8.70E-02 8.61E-03

2002 5.75E-03 5.15E-02 8.59E-02 1.44E-05 3.38E-04 2.90E-02 8.61E-03 a Based on 2% enriched recycled uranium b Background included.

4.4 ON-SITE EXTERNAL DOSES FROM AMBIENT RADIATION

External environmental radiation dose at FEMP is the result of photon radiation (i.e., gamma and Xrays) emitted from radionuclides stored on the site. For unmonitored personnel who worked in the 

administration areas, the largest source of direct radiation at FEMP was the waste stored in the K-65 

Silos and the radionuclides in the Production Plants and facilities. To a lesser extend, the radioactive 

waste pit area is another direct radiation source for unmonitored personnel who worked in this area.

4.4.1

There were three significant external radiation sources at FEMP, but by far the largest source was the 

wastes stored in the K-65 Silos. The ambient dose rates at the FEMP started to increase to 

measurable levels starting in 1955 when the wastes from Niagara Falls, New York, were relocated to 

the K-65 Silos. This elevation in ambient dose was due to the radium content of these wastes. Direct 

radiation occurred not only from the radium but from the radon-thoron daughter products as well, 

which with time continued to increase within the structures. This condition prevailed until the 

structures became such a significant source of radiation that the site found it necessary to construct 

reinforcement beams and coat the exterior surfaces of the silos in an attempt both to strengthen the 

structures and to reduce the radiation. While these actions provided some benefit, the radon-thoron 

dose contribution continued to increase as the gaseous radionuclides emanated and accumulated in 

the voided space under the domes. The source strength increased to the point that in 1991 it became 

necessary to add a bentonite layer (Fluor 2001) to the surface of the stored material in an attempt to 

contain the radioactive gases. This was effective, as evidenced by an immediate reduction in direct 

radiation dose rates, due to the shielding afforded by the solid materials in the silos. An immediate 

dose rate reduction of approximately one order of magnitude occurred as a result of the bentonite 

layer. However, the bentonite has provided only a temporary reduction. Dose rates have slowly 

K-65 and Production Plants External Dose Contribution
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 40 of 83

increased again, and in 2002 monitoring showed an increase of about a factor of four in the external 

radiation. 

The reference materials found and reviewed for external radiation information has yielded useful data 

back to 1975 (NLO 1975 to 1985, WEMCO 1990 to 1992, FERMCO 1993 to 1996, and Fluor 1997 to 

2001). The data collection, consisting of thermoluminescent dosimeter (TLD) measurements, became 

possible with the advances in the development of the TLD as a useful dose measurement device. 

These technology developments made it possible to measure radiation doses over long periods, in 

the exposure environment, and without power. TLDs became a popular and accurate tool for 

measuring doses in the environment over extended periods. 

Before 1975 the only data found (Klein 1963) consisted of contact radiation readings using a Juno 

survey meter for measurements of exposure rates in the vicinity of the North and South Tanks (i.e., 

the K-65 Silos). The dose rates ranged from 10 to 20 mR/hr and 10 to 30 mR/hr, respectively. Later 

data (Boback 1978) provided readings using TLDs from inside the South Tank that ranged from 590 

mR/hr at the surface of the residue to 650 mR/hr at 10 ft and 470 mR/hr at 13 ft above the surface of 

the residue. These data are indicative of the magnitude of the primary sources of ambient radiation 

and are presented here only to provide the reconstructor with background information.

Starting in 1976, gamma radiation at the site boundary sampling stations was measured with TLDs 

which were changed and processed every three months. Table 4-11 is a summary table of dose rates 

measured at the monitoring stations for years 1976 through 1995. Figure 4-9 shows the locations of 

the monitoring stations. 

Since 1996, the FEMP expanded its direct radiation monitoring system to continuously measure at 32 

locations including a numbers of on-site monitoring locations. Figure 4-10 identifies the location of the 

TLD stations. Table 4-12 provides summary level information pertaining to direct radiation 

measurements for 1996 through 2002.

N

Center at

Plant 4

Plant Perimeter

Production Area Perimeter

FEMP

Waste

Pit Area

BS1

BS2

BS3

BS4

BS5

On Site

BS7 BS8

BS9

BS10

8

8 EA No.

9

1 2

10

5

6

11 7

4 3

LTD Locations

Radiation Source

BS6

BS1A

Figure 4-9. FEMP fence line TLD locations (1976 – 1995) 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 41 of 83

Table 4-11. Radiation dose rates at site boundary

Maximum Measured Dose @ TLD Stations (mR/hr or mrem/hr)

Year BS1 BS2 BS3 BS4 BS5 BS6 BS7 BS8 BS9

OnSiteBackgrd

1976 0.010 0.012 0.012 0.011 0.012 0.015 NA NA NA NA 0.010

1977 0.011 0.010 0.011 0.011 0.011 0.012 NA NA NA NA 0.009

1978 0.010 0.011 0.011 0.010 0.011 0.013 NA NA NA NA 0.009

1979 0.012 0.012 0.010 0.010 0.011 0.018 NA NA NA NA 0.009

1980 0.012 0.014 0.014 0.013 0.012 0.023 NA NA NA NA 0.011

1981 0.010 0.012 0.012 0.012 0.012 0.021 0.013 NA NA NA 0.009

1982 0.011 0.014 0.013 0.013 0.014 0.019 0.013 NA NA NA 0.010

1983 0.012 0.013 0.013 0.013 0.013 0.020 0.014 NA NA NA 0.010

1984 0.010 0.0113 0.0114 0.011 0.0115 0.0171 0.0123 NA NA NA 0.010

1985 0.0123 0.0129 0.0125 0.0122 0.0127 0.0191 0.0138 NA NA NA 0.0118

1986 0.0127 0.011 0.0111 0.0111 0.0116 0.015 0.0104 NA NA NA 0.009

1987 0.0096 0.0107 0.0103 0.0104 0.010 0.0157 0.0108 NA NA NA 0.0106

1988 0.0144 0.0164 0.0169 0.0155 0.015 0.0235 0.0158 0.0148 0.0186 NA 0.0151

1989 0.0135 0.0131 0.0161 0.0126 0.0127 0.0197 0.0132 0.0116 0.0175 NA 0.0128

1990 0.0079 0.0079 0.0076 0.0078 0.0073 0.013 0.0075 0.0074 0.010 NA 0.0075

1991 0.0081 0.0085 0.0077 0.0082 0.0077 0.013 0.008 0.0078 0.010 0.258 0.0069

1992 0.0080 0.0094 0.009 0.009 0.0091 0.0087 0.0083 0.0084 0.0115 0.0205 0.0082

1993 0.0089 0.0084 0.0077 0.0078 0.0077 0.0077 0.0075 0.0079 0.0107 0.0239 0.0068

1994a 0.0128 0.0082 0.0071 0.0074 0.0081 0.0079 0.0072 0.0079 0.0107 0.0239 0.0068

1995 a 0.0157 0.0085 0.0075 0.0074 0.0079 0.0085 0.0077 0.0077 0.0108 0.0420 0.0074

NA – Not available a Dose rate values in column 2 is from TLD station BS1A

N

Center at

Plant 4

Plant Perimeter

Production Area Perimeter

FEMP

Waste

Pit Area

8

8 EA No.

9

1 2

10

5

6

11 7

4 3

Fenceline LTD Locations

Radiation Source

Onsite LTD Locations

Silo

2

Silo

1

Figure 4-10. TLD monitoring locations (1996 – 2002). 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 42 of 83

Table 4-12. TLD measurement summary. 

TLD Monitoring Results (mrem/hr)

Fence line Onsite Offsite

Back-grd

Min. Max. Avg.

Min.

(Health & Safety 

Bldg)

Max.

(K-65 Silos) Min. Max.

1996 0.008 0.0104 0.0069 0.0789 0.0069 0.0084 0.0088

1997 0.0082 0.0103 0.0070 0.101 0.0068 0.0085 0.0087

1998 0.0072 0.0096 0.0063 0.0093 NA NA 0.0079

1999 0.0072 0.0093 0.0063 0.0103 NA NA 0.0079

2000 0.0074 0.0097 0.0066 0.124 NA NA 0.0079

2001 0.0079 0.0103 0.0066 0.137 NA NA 0.0083

2002 0.0081 0.0111 0.0064 0.139 NA NA 0.0087

The above measurement data were used to estimate the dose rate distribution to each of the 

Exposure Areas (EAs). 

In 1985, EG&G, Inc. conducted an on-site and off-site aerial survey of the FEMP and surrounding 

areas for radiation due to gamma emission. The survey resulted in dose rate contour maps of the site 

for 1976 and 1985 that are shown in Figures 4-11 and 4-12, respectively. The aerial survey data were 

used to correlate the dose rates estimated for the EAs using the site TLD measurements. The aerial 

survey data particularly important because the 1976 data represent a low annual production rate of 

approximately 1,230 MTU while 1985 represent a modest annual production rate of about 3,700 MTU. 

The peak production rate of FEMP was 10,000 MTU in 1960.

Other relevant direct radiation exposure measurements are those called “background” measurements 

conducted using TLDs, starting in 1988 and extending through the first quarter of 2003, and covering 

up to 15 locations1

4.4.2

. All the locations were not monitored throughout this period; some new ones were 

added and others deleted so that there were approximated 8 monitored sites at all times which 

provided adequate coverage for the site. The individual locations for each year were averaged since 

the data did not identify the specific locations and instead used general identifiers such as “men’s

locker,” “Health and Safety Laboratory,” etc. Table 4-13 provides the average values in mrem/month. 

These on-site “background” dose rate measurements were compared with the EA dose rate estimates 

derived from on-site and fence line TLD measurement for the purpose of validating the EA dose rate

estimates.

The Waste Pit Area is in EA-5. Figure 4-13 presents the beta gamma dose rate contours within the 

Waste Pit area. Table 4-14 lists the operational periods and the direct dose rate for each pit. Figure 

4-14 depicts the radiation profile of the Waste Pit Area, taking into account the development of each 

pit (i.e., increasing dose rates as the pits were filled with wastes).

External Dose Contribution from Waste Pits

The beta and gamma radiation at the waste pits area is emitted from radionuclides buried in the 

ground. The gamma radiation is emitted at the ground level toward the atmosphere, and scattered 

from the atmosphere to reach receptor location at some distance from the waste pit area. This is 

known as the “skyshine” phenomena. Typically, radiation from “sky shine” is approximately 1% of the 

dose rate at the receptor location.

 

1

 From the ORAU O-Drive located on O:\DOE Site Images\FEMP\07-28-03-Data Capture\010001026 through 010001036.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 43 of 83

Figure 4-11. 1976 exposure rate contour map of the FEMP survey area
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 44 of 83

Figure 4-12. 1985 exposure rate contour map of the FEMP survey area.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 45 of 83

Table 4-13. Average on-site “background” 

dose rates 

Year Average Dose 

rates 

(mrem/month)

1988 12.4

1989 11.33

1991 7.24

1992 7.79

1993 5.89

1994 5.64

1995 5.08

1996 5.01

1997 5.14

1998 4.98

1999 4.98

2000 5.15

2001 5.28

2002 5.41

Figure 4-13. Beta gamma dose rate contours in the waste pit area.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 46 of 83

Table 4-14. Waste pits dose rate data. 

Waste pit Operation period

Average ambient 

dose rate (mRad /hr)

1 1952-1959 1.0

2 1957-1964 1.2

3 1958-1977 2.0

4 1960-1986 16.0

5 1968-1987 1.0

6 1979-1985 1.3

Clearwell 1960s and 1970s 1.0

Burn pit 1957-1984 1.3

 

Average Ambient Dose Rates

(mRad/hr)

Years

1952 1954 1958 1962 1966 1970 1974 1978

0

5

10

15

20

1982 1986 1990

25

Pit 1 Pit 2

Pit 3

Pit 4

Pit 5 Pit 6

Clearwell

Burn Pit

Waste Pit

Area Total

Figure 4-14. Waste pits dose rate profiles. 

4.4.3

The dose rate at each EA is estimated by summing the dose rates coming from the major direct dose 

contributors (i.e., K-65 silos, production facilities and the waste pits) and the background radiation and 

can be represented by Equation 4-5 below: 

On-site Ambient Dose rate Estimate

( ) ( ) bkg

EAki

k

pit

EAji

BSj

bkg

EAsi

BSs

i bkg D

d

d D

d

d

Average BSj D

d

d D BSs D +

































+ × 































+ ×− 















×−=

2 2 2

.0 01 (4-5)

Where

 Di = Estimated dose rate at EAi.

 Dbkg = Background dose rate. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 47 of 83

 BSs = Measured dose rate at TLD stations closest to the K-65 silos.

 dbss = Distance from TLD stations to the K-65 silos.

 dEAsi = Distance from Silos to EAi. 

 BSj = Measured dose rate at fence line TLD stations. j is the combination of BS1, 2, 3, 4, 5, 7 

and 9 correlated to the aerial survey results. Starting in 1996, the onsite TLD station 

BS32 (Health and Safety Building) was used. 

 dbsj = Distance from TLD stations to production plants.

 dEAji = Distance from production plants to EAi. 

 Dpit = Average dose rate at the waste pit area.

 dk = Distance from center of waste pit area to edge of waste pit area.

 dEAki = Distance from waste pit area to EAi. 

Measured dose rate values in Tables 4-11, 4-12 and Figure 4-14 were used for Equation 4-5. Table 

4-17 summarizes the Equation 4-5 results. The Equation 4-5 results were also correlated to the direct 

dose rate contour maps (Figures 4-11 and 4-12) resulting from the aerial survey conducted by EG&G, 

Inc. in 1976 and 1985. The correlations have resulted in closely matched dose rate in each EA as 

shown in Table 4-15. 

Table 4-15. Comparison of the estimated dose rates in EAs and the 

aerial survey results.

Exposure 

Areas

Estimated Dose Rates Compared to Aerial Surveys 

(mrem/hr)

1976 1985

Eq 4-5 Aerial Survey Eq 4-5 Aerial Survey

EA-1 0.203 0.170-0.350 (L) 0.304 >0.350 (M)

EA-2 0.143 0.085-0.170 (K) 0.213 >0.350 (M)

EA-3 0.142 0.045-0.085 (J) 0.212 0.170-0.350 (L)

EA-4 0.201 0.085-0.170 (K) 0.302 0.170-0.350 (L)

EA-5 0.0843 0.065-0.128 (K,J) 0.0491 0.065-0.128 (K,J)

EA-6 0.456 >0.350 (M) 0.663 >0.350 (M)

EA-7 0.0167 0.015-0.019 (G) 0.0218 0.019-0.027 (H)

EA-8 0.0226 0.019-0.027 (H) 0.0309 0.027-0.045 (I)

EA-9 0.0181 0.015-0.019 (G) 0.0240 0.019-0.027 (H)

EA-10 0.0167 0.019-0.027 (H) 0.0219 0.027-0.045 (I)

EA-11 0.0149 0.019-0.027 (H) 0.0191 0.015-0.019 (G)

Starting in 1988, Equation 4-5 results were also compared with the measured onsite “background” 

dose rate in Table 4-13. For this comparison, the onsite “background” TLDs were assumed to be 

located inside buildings. One-half of the background dose rate was added to the values in Table 4-13 

in order to correct for the building shielding. Background radiation from building penetrating cosmic 

ray accounts for half of the background dose rate. The Equation 4-5 results for comparison are dose 

rate values averaging over all EAs but excluding EA-6 that contains the K-65 silos. Because EA-6 

has the highest dose rate, excluding its dose rate from the site-wide averaging ensures a truer

equivalent comparison. Table 4-16 presents the results of the comparison. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 48 of 83

Table 4-16. Site-wide average dose rates comparison.

Years Eq. 4-5 

(mrem/hour)

“Background” TLD 

Measurement

(mrem/hour)

1988 0.052 0.024

1989 0.060 0.022

1991 0.038 0.013

1992 0.040 0.015

1993 0.044 0.015

1994 0.044 0.011

1995 0.040 0.011

1996 0.015 0.013

1997 0.015 0.014

1998 0.013 0.018

1999 0.013 0.018

2000 0.014 0.010

2001 0.015 0.014

2002 0.014 0.018

Although the Equation 4-5 results show moderately higher dose rates during production years and 

slightly elevated dose rates for some of the subsequent post-production years, the dose rates are in 

the same order of magnitude values. Higher dose rates are expected during production years 1988 

and 1989. The comparison illustrates that the extrapolated dose rate values are reasonably valid. 

Since no usable direct radiation measurements were identified in the available reference materials for 

the time period prior to 1976, the ambient dose rates in the plant site for those years were estimated

by proportioning the metal production rate of the plant. Figure 4-15 overlays the projected site-wide 

average dose rate on the FEMP metal production rate profile.

In the 1980s, the plant processing systems were at about 75% capacity with an annual production 

rate of about 3,700 MTU of metal products. The plant process systems were at 100% capacity in the 

years back to the 1970s, 1960s and part of the 1950s. The on-site ambient direct radiation dose rates 

for those years were estimated by the ratio of the annual plant production rates, therefore a factor of 

1.35 increase of the highest average ambient dose rates in the 80s. Using the same methodology 

resulted in the following ambient dose rate projections:

1951 to 1953 0.015 mrem/hr,

1954 and1955 1.8 mrem/hr, and 

1956 to 1970 0.3 mrem/hr

Table 4-17 summarizes the on site ambient dose rates (mrem/hour) by EAs and the years. Site-wide 

average ambient dose rate also listed in Table 4-17. EA-6 which includes the K-65 Silos was

purposefully excluded from the site average since that area has the highest dose rate and infrequently 

occupied. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 49 of 83

10,000 MTU (2 shifts

@ 100% system

capacity)

1,230 MTU (1 shift

@ 24.6%

capacity)

3,690 MTU (1 shift

@ 74% capacity

1960 1964 1968 1975 1981 1989

5,000 MTU (1 shift

@ 100% system

capacity)

1970 1973

2,000

4,000

6,000

8,000

10,000

 Metric Ton Uranium

Years

1951 1953 1956

Plants 1, 2/3, 4, 5, 6, 8

Plants 7, 9

Pilot Plant

9,000 MTU (2 shifts @

90% system capacity)

7,000 MTU (2 shifts @

70% system capacity)

3,000 MTU (1 shift

@ 60% system

capacity)

0.05

0.10

0.50

1.00

1.50

Estimated on-site environmental doserates

based on production rates.

Legend

Estimated on-site environmental doserates

derived from environmental TLD data.

Measured average background

0.01

Average Onsite Environmental Doserates

(mrem/hour)

Figure 4-15. Projected site-wide direct radiation dose rates based on metal production rate.

. 

 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 50 of 83

4.4.4

Table 4-17. External occupational environmental dose rates summary (mrem/hr). 

On-site External Ambient Dose rate (Table 4-17) 

Dose contributors EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1951-1953

Totals(net above bkgd) 8.06E-03 5.60E-03 5.51E-03 7.99E-03 2.30E-03 2.39E-02 2.90E-04 5.31E-04 3.39E-04 2.79E-04 2.25E-04

EA totals 2.38E-02 1.67E-02 1.65E-02 2.36E-02 7.21E-03 6.95E-02 1.42E-03 2.11E-03 1.56E-03 1.38E-03 1.23E-03

FEMP Site Average 9.55E-03

1954-1955

Totals(net above bkgd) 2.74E-01 1.90E-01 1.87E-01 2.72E-01 7.82E-02 8.12E-01 9.86E-03 1.81E-02 1.15E-02 9.48E-03 7.66E-03

EA totals 2.86E-01 2.01E-01 1.98E-01 2.83E-01 8.65E-02 8.34E-01 1.70E-02 2.53E-02 1.87E-02 1.66E-02 1.47E-02

FEMP Site Average 1.15E-01

1956-1970

Totals(net above bkgd) 4.67E-01 3.25E-01 3.20E-01 4.63E-01 1.33E-01 1.38E+00 1.68E-02 3.08E-02 1.97E-02 1.62E-02 1.31E-02

EA totals 4.76E-01 3.35E-01 3.29E-01 4.72E-01 1.44E-01 1.39E+00 2.83E-02 4.22E-02 3.11E-02 2.77E-02 2.46E-02

FEMP Site Average 1.91E-01

1971-1975

Totals(net above bkgd) 1.93E-01 1.33E-01 1.32E-01 1.91E-01 7.43E-02 4.46E-01 6.67E-03 1.26E-02 8.06E-03 6.68E-03 4.92E-03

EA totals 2.03E-01 1.43E-01 1.42E-01 2.01E-01 8.43E-02 4.56E-01 1.67E-02 2.26E-02 1.81E-02 1.67E-02 1.49E-02

FEMP Site Average 8.62E-02

1976

Waste pit area 8.59E-04 2.81E-04 2.15E-04 3.82E-04 1.37E-02 1.53E-03 1.70E-04 1.70E-04 1.27E-04 2.81E-04 1.70E-04

K-65 silos 2.81E-03 1.25E-03 7.03E-04 1.80E-03 7.20E-03 4.39E-01 1.25E-03 6.23E-04 3.72E-04 3.72E-04 1.80E-03

Production Plants 1.89E-01 1.31E-01 1.31E-01 1.89E-01 5.33E-02 5.25E-03 5.25E-03 1.18E-02 7.56E-03 6.03E-03 2.95E-03

Totals(net above bkgd) 1.93E-01 1.33E-01 1.32E-01 1.91E-01 7.43E-02 4.46E-01 6.67E-03 1.26E-02 8.06E-03 6.68E-03 4.92E-03

EA totals 2.03E-01 1.43E-01 1.42E-01 2.01E-01 8.43E-02 4.56E-01 1.67E-02 2.26E-02 1.81E-02 1.67E-02 1.49E-02

FEMP Site Average 8.62E-02

1977

Waste pit area 8.95E-04 2.92E-04 2.24E-04 3.98E-04 1.43E-02 1.59E-03 1.77E-04 1.77E-04 1.32E-04 2.92E-04 1.77E-04

K-65 silos 1.69E-03 7.50E-04 4.22E-04 1.08E-03 4.32E-03 2.64E-01 7.50E-04 3.74E-04 2.23E-04 2.23E-04 1.08E-03

Production Plants 1.41E-01 9.79E-02 9.79E-02 1.41E-01 5.20E-02 3.92E-03 3.92E-03 8.81E-03 5.64E-03 4.50E-03 2.20E-03

Totals(net above bkgd) 1.44E-01 9.90E-02 9.86E-02 1.42E-01 7.06E-02 2.69E-01 4.84E-03 9.36E-03 6.00E-03 5.01E-03 3.46E-03

EA totals 1.53E-01 1.08E-01 1.08E-01 1.51E-01 7.96E-02 2.78E-01 1.38E-02 1.84E-02 1.50E-02 1.40E-02 1.25E-02

FEMP Site Average 6.73E-02

1978

Waste pit area 9.31E-04 3.04E-04 2.33E-04 4.14E-04 1.49E-02 1.66E-03 1.84E-04 1.84E-04 1.38E-04 3.04E-04 1.84E-04

K-65 silos 2.25E-03 1.00E-03 5.63E-04 1.44E-03 5.76E-03 3.52E-01 1.00E-03 4.98E-04 2.98E-04 2.98E-04 1.44E-03

Production Plants 1.89E-01 1.31E-01 1.31E-01 1.89E-01 5.33E-02 5.25E-03 5.25E-03 1.18E-02 7.56E-03 6.03E-03 2.95E-03

Totals(net above bkgd) 1.92E-01 1.33E-01 1.32E-01 1.91E-01 7.40E-02 3.58E-01 6.43E-03 1.25E-02 8.00E-03 6.63E-03 4.58E-03

EA totals 2.01E-01 1.42E-01 1.41E-01 2.00E-01 8.30E-02 3.67E-01 1.54E-02 2.15E-02 1.70E-02 1.56E-02 1.36E-02

FEMP Site Average 8.50E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 51 of 83

Table 4-17. (Cont’d) External occupational environmental dose rates summary (mrem/hr). 

Dose contributors EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1979

Waste pit area 9.73E-04 3.18E-04 2.43E-04 4.32E-04 1.56E-02 1.73E-03 1.92E-04 1.92E-04 1.44E-04 3.18E-04 1.92E-04

K-65 silos 5.06E-03 2.25E-03 1.27E-03 3.24E-03 1.30E-02 7.91E-01 2.25E-03 1.12E-03 6.69E-04 6.69E-04 3.24E-03

Production Plants 2.27E-01 1.57E-01 1.57E-01 2.27E-01 5.44E-02 6.29E-03 6.29E-03 1.42E-02 9.06E-03 7.22E-03 3.54E-03

Totals(net above bkgd) 2.33E-01 1.60E-01 1.59E-01 2.30E-01 8.29E-02 7.99E-01 8.74E-03 1.55E-02 9.88E-03 8.21E-03 6.97E-03

EA totals 2.42E-01 1.69E-01 1.68E-01 2.39E-01 9.19E-02 8.08E-01 1.77E-02 2.45E-02 1.89E-02 1.72E-02 1.60E-02

FEMP Site Average 1.00E-01

1980

Waste pit area 1.02E-03 3.34E-04 2.56E-04 4.55E-04 1.64E-02 1.82E-03 2.02E-04 2.02E-04 1.52E-04 3.34E-04 2.02E-04

K-65 silos 6.75E-03 3.00E-03 1.69E-03 4.32E-03 1.73E-02 1.05E+00 3.00E-03 1.49E-03 8.93E-04 8.93E-04 4.32E-03

Production Plants 2.11E-01 1.47E-01 1.47E-01 2.11E-01 2.99E-02 5.87E-03 5.87E-03 1.32E-02 8.46E-03 6.74E-03 3.30E-03

Totals(net above bkgd) 2.19E-01 1.50E-01 1.49E-01 2.16E-01 6.36E-02 1.06E+00 9.07E-03 1.49E-02 9.50E-03 7.97E-03 7.83E-03

EA totals 2.30E-01 1.61E-01 1.60E-01 2.27E-01 7.46E-02 1.07E+00 2.01E-02 2.59E-02 2.05E-02 1.90E-02 1.88E-02

FEMP Site Average 9.57E-02

1981

Waste pit area 1.07E-03 3.50E-04 2.68E-04 4.76E-04 1.71E-02 1.90E-03 2.11E-04 2.11E-04 1.58E-04 3.50E-04 2.11E-04

K-65 silos 6.75E-03 3.00E-03 1.69E-03 4.32E-03 1.73E-02 1.05E+00 3.00E-03 1.49E-03 8.93E-04 8.93E-04 4.32E-03

Production Plants 3.53E-01 2.47E-01 2.45E-01 3.53E-01 6.86E-02 9.82E-03 9.82E-03 2.21E-02 1.41E-02 1.13E-02 5.52E-03

Totals(net above bkgd) 3.61E-01 2.51E-01 2.47E-01 3.58E-01 1.03E-01 1.07E+00 1.30E-02 2.38E-02 1.52E-02 1.25E-02 1.01E-02

EA totals 3.70E-01 2.60E-01 2.56E-01 3.67E-01 1.12E-01 1.08E+00 2.20E-02 3.28E-02 2.42E-02 2.15E-02 1.91E-02

FEMP Site Average 1.48E-01

1982

Waste pit area 1.12E-03 3.65E-04 2.79E-04 4.97E-04 1.79E-02 1.99E-03 2.21E-04 2.21E-04 1.65E-04 3.65E-04 2.21E-04

K-65 silos 5.06E-03 2.25E-03 1.27E-03 3.24E-03 1.30E-02 7.91E-01 2.25E-03 1.12E-03 6.69E-04 6.69E-04 3.24E-03

Production Plants 3.61E-01 2.52E-01 2.51E-01 3.61E-01 6.88E-02 1.00E-02 1.00E-02 2.26E-02 1.44E-02 1.15E-02 5.64E-03

Totals(net above bkgd) 3.67E-01 2.55E-01 2.52E-01 3.65E-01 9.97E-02 8.03E-01 1.25E-02 2.39E-02 1.53E-02 1.25E-02 9.10E-03

EA totals 3.77E-01 2.65E-01 2.62E-01 3.75E-01 1.10E-01 8.13E-01 2.25E-02 3.39E-02 2.53E-02 2.25E-02 1.91E-02

FEMP Site Average 1.51E-01

1983

Waste pit area 1.16E-03 3.80E-04 2.91E-04 5.17E-04 1.86E-02 2.07E-03 2.30E-04 2.30E-04 1.72E-04 3.80E-04 2.30E-04

K-65 silos 5.63E-03 2.50E-03 1.41E-03 3.60E-03 1.44E-02 8.79E-01 2.50E-03 1.25E-03 7.44E-04 7.44E-04 3.60E-03

Production Plants 3.66E-01 2.58E-01 2.54E-01 3.66E-01 6.90E-02 1.02E-02 1.02E-02 2.29E-02 1.47E-02 1.17E-02 5.72E-03

Totals(net above bkgd) 3.73E-01 2.61E-01 2.56E-01 3.70E-01 1.02E-01 8.91E-01 1.29E-02 2.44E-02 1.56E-02 1.28E-02 9.55E-03

EA totals 3.83E-01 2.71E-01 2.66E-01 3.80E-01 1.12E-01 9.01E-01 2.29E-02 3.44E-02 2.56E-02 2.28E-02 1.96E-02

FEMP Site Average 1.54E-01

1984

Waste pit area 1.14E-03 3.73E-04 2.86E-04 5.08E-04 1.83E-02 2.03E-03 2.26E-04 2.26E-04 1.69E-04 3.73E-04 2.26E-04

K-65 silos 3.99E-03 1.78E-03 9.98E-04 2.56E-03 1.02E-02 6.24E-01 1.78E-03 8.84E-04 5.28E-04 5.28E-04 2.56E-03

Production Plants 2.75E-01 1.91E-01 1.91E-01 2.75E-01 7.65E-03 7.65E-03 7.65E-03 1.72E-02 1.10E-02 8.78E-03 4.30E-03

Totals(net above bkgd) 2.81E-01 1.93E-01 1.93E-01 2.79E-01 3.62E-02 6.34E-01 9.65E-03 1.83E-02 1.17E-02 9.69E-03 7.09E-03

EA totals 2.91E-01 2.03E-01 2.03E-01 2.89E-01 4.62E-02 6.44E-01 1.97E-02 2.83E-02 2.17E-02 1.97E-02 1.71E-02

FEMP Site Average 1.14E-01
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 52 of 83

Table 4-17. (Cont’d) External occupational environmental dose rates summary (mrem/hr).

Dose contributors EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1985

Waste pit area 1.18E-03 3.84E-04 2.94E-04 5.23E-04 1.88E-02 2.09E-03 2.33E-04 2.33E-04 1.74E-04 3.84E-04 2.33E-04

K-65 silos 4.11E-03 1.83E-03 1.03E-03 2.63E-03 1.05E-02 6.42E-01 1.83E-03 9.09E-04 5.43E-04 5.43E-04 2.63E-03

Production Plants 2.87E-01 1.99E-01 1.99E-01 2.87E-01 7.96E-03 7.96E-03 7.96E-03 1.79E-02 1.15E-02 9.14E-03 4.48E-03

Totals(net above bkgd) 2.92E-01 2.01E-01 2.00E-01 2.90E-01 3.73E-02 6.52E-01 1.00E-02 1.91E-02 1.22E-02 1.01E-02 7.34E-03

EA totals 3.04E-01 2.13E-01 2.12E-01 3.02E-01 4.91E-02 6.63E-01 2.18E-02 3.09E-02 2.40E-02 2.19E-02 1.91E-02

FEMP Site Average 1.20E-01

1986

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 3.38E-03 1.50E-03 8.44E-04 2.16E-03 8.64E-03 5.27E-01 1.50E-03 7.47E-04 4.46E-04 4.46E-04 2.16E-03

Production Plants 2.80E-01 1.94E-01 1.94E-01 2.80E-01 7.78E-03 7.78E-03 7.78E-03 1.75E-02 1.12E-02 8.93E-03 4.38E-03

Totals(net above bkgd) 2.85E-01 1.96E-01 1.96E-01 2.83E-01 3.53E-02 5.37E-01 9.51E-03 1.85E-02 1.18E-02 9.76E-03 6.77E-03

EA totals 2.94E-01 2.05E-01 2.05E-01 2.92E-01 4.43E-02 5.46E-01 1.85E-02 2.75E-02 2.08E-02 1.88E-02 1.58E-02

FEMP Site Average 1.14E-01

1987

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 2.87E-03 1.28E-03 7.17E-04 1.84E-03 7.34E-03 4.48E-01 1.28E-03 6.35E-04 3.79E-04 3.79E-04 1.84E-03

Production Plants 4.15E-02 2.88E-02 2.88E-02 4.15E-02 1.15E-03 1.15E-03 1.15E-03 2.59E-03 1.66E-03 1.32E-03 6.48E-04

Totals(net above bkgd) 4.55E-02 3.05E-02 2.98E-02 4.38E-02 2.74E-02 4.51E-01 2.66E-03 3.46E-03 2.21E-03 2.09E-03 2.72E-03

EA totals 5.61E-02 4.11E-02 4.04E-02 5.44E-02 3.80E-02 4.62E-01 1.33E-02 1.41E-02 1.28E-02 1.27E-02 1.33E-02

FEMP Site Average 2.96E-02

1988

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 4.73E-03 2.10E-03 1.18E-03 3.02E-03 1.21E-02 7.38E-01 2.10E-03 1.05E-03 6.25E-04 6.25E-04 3.02E-03

Production Plants 8.75E-02 6.08E-02 6.08E-02 8.75E-02 2.43E-03 2.43E-03 2.43E-03 5.47E-03 3.50E-03 2.79E-03 1.37E-03

Totals(net above bkgd) 9.34E-02 6.32E-02 6.22E-02 9.10E-02 3.34E-02 7.43E-01 4.76E-03 6.75E-03 4.30E-03 3.80E-03 4.62E-03

EA totals 1.09E-01 7.83E-02 7.73E-02 1.06E-01 4.85E-02 7.58E-01 1.99E-02 2.18E-02 1.94E-02 1.89E-02 1.97E-02

FEMP Site Average 5.19E-02

1989

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 3.88E-03 1.73E-03 9.70E-04 2.48E-03 9.94E-03 6.06E-01 1.73E-03 8.60E-04 5.13E-04 5.13E-04 2.48E-03

Production Plants 1.18E-01 8.16E-02 8.16E-02 1.18E-01 3.26E-03 3.26E-03 3.26E-03 7.34E-03 4.70E-03 3.75E-03 1.84E-03

Totals(net above bkgd) 1.23E-01 8.37E-02 8.29E-02 1.21E-01 3.21E-02 6.12E-01 5.22E-03 8.44E-03 5.39E-03 4.65E-03 4.55E-03

EA totals 1.35E-01 9.65E-02 9.57E-02 1.33E-01 4.49E-02 6.25E-01 1.80E-02 2.12E-02 1.82E-02 1.74E-02 1.74E-02

FEMP Site Average 5.97E-02

1990

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 3.09E-03 1.38E-03 7.73E-04 1.98E-03 7.92E-03 4.83E-01 1.38E-03 6.85E-04 4.09E-04 4.09E-04 1.98E-03

Production Plants 6.25E-02 4.34E-02 4.34E-02 6.25E-02 1.74E-03 1.74E-03 1.74E-03 3.91E-03 2.50E-03 1.99E-03 9.77E-04

Totals(net above bkgd) 6.68E-02 4.52E-02 4.45E-02 6.50E-02 2.85E-02 4.87E-01 3.34E-03 4.82E-03 3.08E-03 2.79E-03 3.19E-03

EA totals 7.43E-02 5.27E-02 5.20E-02 7.25E-02 3.60E-02 4.95E-01 1.08E-02 1.23E-02 1.06E-02 1.03E-02 1.07E-02

FEMP Site Average 3.42E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 53 of 83

Table 4-17. (Cont’d) External occupational environmental dose rates summary (mrem/hr).

Dose contributors EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1991

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 1.61E-03 7.14E-04 4.02E-04 1.03E-03 4.11E-03 2.51E-01 7.14E-04 3.56E-04 2.13E-04 2.13E-04 1.03E-03

Production Plants 7.75E-02 5.38E-02 5.38E-02 7.75E-02 2.15E-03 2.15E-03 2.15E-03 4.84E-03 3.10E-03 2.47E-03 1.21E-03

Totals(net above bkgd) 8.03E-02 5.49E-02 5.45E-02 7.91E-02 2.51E-02 2.55E-01 3.10E-03 5.43E-03 3.49E-03 3.07E-03 2.47E-03

EA totals 8.72E-02 6.18E-02 6.14E-02 8.60E-02 3.20E-02 2.62E-01 1.00E-02 1.23E-02 1.04E-02 9.97E-03 9.37E-03

FEMP Site Average 3.80E-02

1992

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 7.87E-05 3.50E-05 1.97E-05 5.04E-05 2.02E-04 1.23E-02 3.50E-05 1.74E-05 1.04E-05 1.04E-05 5.04E-05

Production Plants 8.25E-02 5.73E-02 5.73E-02 8.25E-02 2.29E-03 2.29E-03 2.29E-03 5.16E-03 3.30E-03 2.63E-03 1.29E-03

Totals(net above bkgd) 8.38E-02 5.77E-02 5.76E-02 8.31E-02 2.14E-02 1.67E-02 2.56E-03 5.41E-03 3.48E-03 3.03E-03 1.57E-03

EA totals 9.20E-02 6.59E-02 6.58E-02 9.13E-02 2.96E-02 2.49E-02 1.08E-02 1.36E-02 1.17E-02 1.12E-02 9.77E-03

FEMP Site Average 4.02E-02

1993

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 1.09E-04 4.86E-05 2.74E-05 7.00E-05 2.80E-04 1.71E-02 4.86E-05 2.42E-05 1.45E-05 1.45E-05 7.00E-05

Production Plants 9.75E-02 6.77E-02 6.77E-02 9.75E-02 2.71E-03 2.71E-03 2.71E-03 6.09E-03 3.90E-03 3.11E-03 1.52E-03

Totals(net above bkgd) 9.88E-02 6.81E-02 6.80E-02 9.81E-02 2.19E-02 2.19E-02 2.99E-03 6.35E-03 4.09E-03 3.51E-03 1.83E-03

EA totals 1.06E-01 7.49E-02 7.48E-02 1.05E-01 2.87E-02 2.87E-02 9.79E-03 1.32E-02 1.09E-02 1.03E-02 8.63E-03

FEMP Site Average 4.42E-02

1994

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 1.09E-04 4.86E-05 2.74E-05 7.00E-05 2.80E-04 1.71E-02 4.86E-05 2.42E-05 1.45E-05 1.45E-05 7.00E-05

Production Plants 9.75E-02 6.77E-02 6.77E-02 9.75E-02 2.71E-03 2.71E-03 2.71E-03 6.09E-03 3.90E-03 3.11E-03 1.52E-03

Totals(net above bkgd) 9.88E-02 6.81E-02 6.80E-02 9.81E-02 2.19E-02 2.19E-02 2.99E-03 6.35E-03 4.09E-03 3.51E-03 1.83E-03

EA totals 1.06E-01 7.49E-02 7.48E-02 1.05E-01 2.87E-02 2.87E-02 9.79E-03 1.32E-02 1.09E-02 1.03E-02 8.63E-03

FEMP Site Average 4.42E-02

1995

Waste pit area 1.18E-03 3.85E-04 2.95E-04 5.24E-04 1.89E-02 2.10E-03 2.33E-04 2.33E-04 1.74E-04 3.85E-04 2.33E-04

K-65 silos 2.21E-04 9.84E-05 5.54E-05 1.42E-04 5.67E-04 3.46E-02 9.84E-05 4.90E-05 2.93E-05 2.93E-05 1.42E-04

Production Plants 8.50E-02 5.90E-02 5.90E-02 8.50E-02 2.36E-03 2.36E-03 2.36E-03 5.31E-03 3.40E-03 2.71E-03 1.33E-03

Totals(net above bkgd) 8.64E-02 5.95E-02 5.94E-02 8.57E-02 2.18E-02 3.91E-02 2.69E-03 5.59E-03 3.60E-03 3.12E-03 1.70E-03

EA totals 9.38E-02 6.69E-02 6.68E-02 9.31E-02 2.92E-02 4.65E-02 1.01E-02 1.30E-02 1.10E-02 1.05E-02 9.10E-03

FEMP Site Average 4.04E-02

1996

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 4.49E-04 1.99E-04 1.12E-04 2.87E-04 1.15E-03 7.01E-02 1.99E-04 9.94E-05 5.93E-05 5.93E-05 2.87E-04

Production Plants 1.00E-02 6.94E-03 6.94E-03 1.00E-02 2.78E-04 2.78E-04 2.78E-04 6.25E-04 4.00E-04 3.19E-04 1.56E-04

Totals(net above bkgd) 1.16E-02 7.51E-03 7.34E-03 1.08E-02 1.95E-02 7.24E-02 7.00E-04 9.47E-04 6.26E-04 7.47E-04 6.67E-04

EA totals 2.04E-02 1.63E-02 1.61E-02 1.96E-02 2.83E-02 8.12E-02 9.50E-03 9.75E-03 9.43E-03 9.55E-03 9.47E-03

FEMP Site Average 1.48E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 54 of 83

Table 4-17. (Cont’d) External occupational environmental dose rates summary (mrem/hr).

Dose contributors EA-1 EA-2 EA-3 EA-4 EA-5 EA-6 EA-7 EA-8 EA-9 EA-10 EA-11

1997

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 5.91E-04 2.63E-04 1.48E-04 3.78E-04 1.51E-03 9.23E-02 2.63E-04 1.31E-04 7.81E-05 7.81E-05 3.78E-04

Production Plants 1.06E-02 7.36E-03 7.36E-03 1.06E-02 2.94E-04 2.94E-04 2.94E-04 6.63E-04 4.24E-04 3.38E-04 1.66E-04

Totals(net above bkgd) 1.23E-02 7.99E-03 7.79E-03 1.15E-02 1.99E-02 9.46E-02 7.80E-04 1.02E-03 6.69E-04 7.85E-04 7.67E-04

EA totals 2.10E-02 1.67E-02 1.65E-02 2.02E-02 2.86E-02 1.03E-01 9.48E-03 9.72E-03 9.37E-03 9.48E-03 9.47E-03

FEMP Site Average 1.51E-02

1998

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 8.96E-06 3.98E-06 2.24E-06 5.73E-06 2.29E-05 1.40E-03 3.98E-06 1.98E-06 1.18E-06 1.18E-06 5.73E-06

Production Plants 9.40E-03 6.53E-03 6.53E-03 9.40E-03 2.61E-04 2.61E-04 2.61E-04 5.88E-04 3.76E-04 3.00E-04 1.47E-04

Totals(net above bkgd) 1.05E-02 6.90E-03 6.81E-03 9.91E-03 1.84E-02 3.67E-03 4.88E-04 8.13E-04 5.44E-04 6.70E-04 3.76E-04

EA totals 1.84E-02 1.48E-02 1.47E-02 1.78E-02 2.63E-02 1.16E-02 8.39E-03 8.71E-03 8.44E-03 8.57E-03 8.28E-03

FEMP Site Average 1.34E-02

1999

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 1.54E-05 6.83E-06 3.84E-06 9.83E-06 3.93E-05 2.40E-03 6.83E-06 3.40E-06 2.03E-06 2.03E-06 9.83E-06

Production Plants 9.40E-03 6.53E-03 6.53E-03 9.40E-03 2.61E-04 2.61E-04 2.61E-04 5.88E-04 3.76E-04 3.00E-04 1.47E-04

Totals(net above bkgd) 1.05E-02 6.90E-03 6.81E-03 9.91E-03 1.84E-02 4.67E-03 4.91E-04 8.14E-04 5.45E-04 6.71E-04 3.80E-04

EA totals 1.84E-02 1.48E-02 1.47E-02 1.78E-02 2.63E-02 1.26E-02 8.39E-03 8.71E-03 8.45E-03 8.57E-03 8.28E-03

FEMP Site Average 1.34E-02

2000

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 7.43E-04 3.30E-04 1.86E-04 4.76E-04 1.90E-03 1.16E-01 3.30E-04 1.65E-04 9.83E-05 9.83E-05 4.76E-04

Production Plants 1.06E-02 7.36E-03 7.36E-03 1.06E-02 2.94E-04 2.94E-04 2.94E-04 6.63E-04 4.24E-04 3.38E-04 1.66E-04

Totals(net above bkgd) 1.25E-02 8.06E-03 7.83E-03 1.16E-02 2.03E-02 1.18E-01 8.48E-04 1.05E-03 6.89E-04 8.05E-04 8.64E-04

EA totals 2.04E-02 1.60E-02 1.57E-02 1.95E-02 2.82E-02 1.26E-01 8.75E-03 8.95E-03 8.59E-03 8.71E-03 8.76E-03

FEMP Site Average 1.44E-02

2001

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 8.24E-04 3.66E-04 2.06E-04 5.27E-04 2.11E-03 1.29E-01 3.66E-04 1.82E-04 1.09E-04 1.09E-04 5.27E-04

Production Plants 9.80E-03 6.81E-03 6.81E-03 9.80E-03 2.72E-04 2.72E-04 2.72E-04 6.13E-04 3.92E-04 3.13E-04 1.53E-04

Totals(net above bkgd) 1.18E-02 7.54E-03 7.29E-03 1.08E-02 2.05E-02 1.31E-01 8.61E-04 1.02E-03 6.68E-04 7.90E-04 9.03E-04

EA totals 2.01E-02 1.58E-02 1.56E-02 1.91E-02 2.88E-02 1.39E-01 9.16E-03 9.32E-03 8.97E-03 9.09E-03 9.20E-03

FEMP Site Average 1.45E-02

2002

Waste pit area 1.13E-03 3.69E-04 2.82E-04 5.02E-04 1.81E-02 2.01E-03 2.23E-04 2.23E-04 1.67E-04 3.69E-04 2.23E-04

K-65 silos 8.34E-04 3.71E-04 2.08E-04 5.34E-04 2.13E-03 1.30E-01 3.71E-04 1.85E-04 1.10E-04 1.10E-04 5.34E-04

Production Plants 8.20E-03 5.69E-03 5.69E-03 8.20E-03 2.28E-04 2.28E-04 2.28E-04 5.13E-04 3.28E-04 2.61E-04 1.28E-04

Totals(net above bkgd) 1.02E-02 6.43E-03 6.19E-03 9.24E-03 2.04E-02 1.33E-01 8.22E-04 9.20E-04 6.05E-04 7.41E-04 8.85E-04

EA totals 1.89E-02 1.51E-02 1.49E-02 1.79E-02 2.91E-02 1.41E-01 9.52E-03 9.62E-03 9.31E-03 9.44E-03 9.58E-03

FEMP Site Average 1.43E-02
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 55 of 83

REFERENCES

Boback, M. W., 1978, Gamma Levels Inside K-65 Tank, letter to R. C. Heatherton, September 11.

Boback, M. W., T. A. Dugan, D. A. Flaming, R. B. Grant, and R. W. Keys, 1987, History of FEMP 

Radionuclide Discharges, FEMP-2082, Feed Materials Production Center, Fernald, Ohio.

Dolan, L.C., and C.A. Dolan, December 1988, History of FEMP Radionuclide Discharges, Addendum 

to FEMP-2082, Special UC-11, Feed Materials Production Center, Fernald, Ohio.

EG&G, Energy Measurements, 1985, An Aerial Radiological Survey of the Feed Material Production 

Center and Surrounding Areas, EGG-10282-1084, Fernald, Ohio.

FEMP (Feed Materials Production Center), 1994, Remedial Investigation Report for Operable Unit 1 

of the Fernald Environmental Management Project (FEMP), FEMP-OU01-6 FINAL, Fernald, 

Ohio.

FERMCO (Fernald Environment Restoration Management Company), 1993, Feed Materials 

Production Center, Annual Environmental Report for Calendar Year 1992, Environmental 

Management Department, Fluor-Daniel Fernald Environment Restoration Management 

Corporation, Fernald, Ohio.

FERMCO (Fernald Environment Restoration Management Company), 1994, Feed Materials 

Production Center, Annual Environmental Report for Calendar Year 1993, Environmental 

Management Department, Fluor-Daniel Fernald Environment Restoration Management 

Corporation, Fernald, Ohio.

FERMCO (Fernald Environment Restoration Management Company), 1995, Feed Materials 

Production Center, Annual Environmental Report for Calendar Year 1994, Environmental 

Management Department, Fluor-Daniel Fernald Environment Restoration Management 

Corporation, Fernald, Ohio.

FERMCO (Fernald Environment Restoration Management Company), 1996, 1995 Fernald Site 

Environmental Report, Site Restoration Services Department, Fluor-Daniel Fernald 

Environment Restoration Management Corporation, Fernald, Ohio.

Fluor (Fluor Daniel Fernald), 1997, 1996 Fernald Site Environmental Report, The Environmental 

Monitoring Project, Fluor-Daniel Fernald, Fernald, Ohio.

Fluor (Fluor Daniel Fernald), 1998, 1997 Integrated Site Environmental Report, 51350-RP-0001, 

Fernald, Ohio.

Fluor (Fluor Daniel Fernald), 1999, 1998 Integrated Site Environmental Report, 51350-RP-0005, 

Fernald, Ohio.

Fluor (Fluor Daniel Fernald), 2000, 1999 Integrated Site Environmental Report, 51350-RP-0010, 

Fernald, Ohio.

Fluor (Fluor Daniel Fernald), 2001, 2000 Integrated Site Environmental Report, 51350-RP-0015, 

Fernald, Ohio.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 56 of 83

Fluor (Fluor Daniel Fernald), 2003, 2002 Integrated Site Environmental Report, 51350-RP-0015, 

Fernald, Ohio.

Klein, F. J., 1963, Contact Radiation Levels From K-65 Tanks, letter to R. L. Bischoff, October 16.

NLO (National Lead of Ohio, Inc.), 1975, FEMP Environmental Report for 1975, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1976, FEMP Environmental Report for 1976, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1977, FEMP Environmental Report for 1977, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1978, FEMP Environmental Report for 1978, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1979, FEMP Environmental Report for 1978, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1980, FEMP Environmental Report for 1980, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1981, FEMP Environmental Report for 1981, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1982, FEMP Environmental Report for 1982, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1983, FEMP Environmental Report for 1983, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1984, FEMP Environmental Report for 1984, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1985, FEMP Environmental Report for 1985, Fernald, Ohio.

Parsons, date unknown, Safety Analysis Report for the Warehoused Thorium Overpacking Building 

65, Fernald Environmental Restoration Management Company, Fernald, Ohio.

RAC (Radiological Assessments Corporation), 1995, The Fernald Dosimetry Reconstruction Project, 

Tasks 2 and 3 Radionuclide Source Terms and Uncertainties, RAC Report No. CDC-5. 

Tomes, T., 1997, Technical Basis for Internal Dosimetry at the FEMP, SD-2008, Rev.1, Fluor Fernald, 

Inc., Fernald, Ohio.

WEMCO (Westinghouse Materials Company of Ohio), 1990, Feed Materials Production Center 

Annual Environmental Report for Calendar Year 1989, Environmental Management 

Department, Fernald, Ohio.

WEMCO (Westinghouse Materials Company of Ohio), 1991, Feed Materials Production Center 

Annual Environmental Report for Calendar Year 1990, Environmental Management 

Department, Fernald, Ohio.

WEMCO (Westinghouse Materials Company of Ohio), 1992, Feed Materials Production Center 

Annual Environmental Report for Calendar Year 1991, Environmental Management 

Department, Fernald, Ohio.
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 57 of 83

GLOSSARY

curie

A special unit of activity. One curie exactly equals 3.7 × 1010 nuclear transitions per second.

dosimeter

A device used to measure the quantity of radiation received. A holder with radiation-absorbing 

elements (filters) and an insert with radiation-sensitive elements packaged to provide a record 

of absorbed dose or dose equivalent received by an individual. (see thermoluminescent 

dosimeter.)

dosimetry

The science of assessing absorbed dose, dose equivalent, effective dose equivalent, etc., 

from external and/or internal sources of radiation. 

dosimetry system

A system used to assess dose equivalent from external radiation to the whole body, skin, 

and/or extremities. This includes the fabrication, assignment, and processing of the 

dosimeters as well as interpretation and documentation of the results.

exposure

As used in the technical sense, exposure refers to a measure expressed in roentgens of the 

ionization produced by photon radiation (i.e., gamma rays) in air. 

gamma rays 

Electromagnetic radiation (photons) originating in atomic nuclei and accompanying many 

nuclear reactions (e.g., fission, radioactive decay, and neutron capture). 

photon

A unit or particle of electromagnetic radiation consisting of X- and/or gamma rays. 

radiation

Alpha, beta, neutron, and photon radiation. 

rem

A unit of dose equivalent equal to the product of the number of rad absorbed and the quality 

factor.

roentgen

A unit of exposure to gamma or X-ray radiation. It is defined precisely as the quantity of 

gamma or X-ray radiation that will produce a total charge of 2.58 × 10-4 coulomb in 1 kilogram 

of dry air STP. An exposure of 1 roentgen is approximately equivalent to an absorbed dose of 

1 rad in soft tissue for higher (more than about 100 kilovolts-electron) energy photons.

thermoluminescence

Property of a material that causes it to emit light as a result of being excited by heat.

thermoluminescent dosimeter (TLD)

A holder containing solid chips of material that when heated will release the stored energy as 

light. The measurement of this light provides a measurement of absorbed dose. 
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 58 of 83

Appendix 4A. FEMP radionuclide concentration and intake results by exposure area and year.

1951 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

silos

Rn-222 

intake 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant Waste Pit (Ci)

EA-1 Uranium 0 0 0 0 0 0 0 0 6.44E-08 0 6.44E-08 1.55E-01 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Uranium 0 0 0 0 0 0 0 0 1.35E-07 0 1.35E-07 3.23E-01 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Uranium 0 0 0 0 0 0 0 0 1.19E-07 0 1.19E-07 2.86E-01 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Uranium 0 0 0 0 0 0 0 0 2.23E-09 0 2.23E-09 5.35E-03 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Uranium 0 0 0 0 0 0 0 0 2.83E-08 0 2.83E-08 6.79E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Uranium 0 0 0 0 0 0 0 0 2.91E-08 0 2.91E-08 6.98E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Uranium 0 0 0 0 0 0 0 0 4.01E-08 0 4.01E-08 9.63E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Uranium 0 0 0 0 0 0 0 0 5.08E-08 0 5.08E-08 1.22E-01 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Uranium 0 0 0 0 0 0 0 0 2.14E-08 0 2.14E-08 5.14E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Uranium 0 0 0 0 0 0 0 0 3.77E-08 0 3.77E-08 9.05E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Uranium 0 0 0 0 0 0 0 0 3.11E-08 0 3.11E-08 7.46E-02 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

1951/Rn Concentration contribution from emission sources (Ci/m3) Total conc.

(Ci/m3)

Conc. in

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant Waste Pit (pCi/L)

EA-1 Rn-222 1.61E-08 0 0 0 0 0 0 0 0 0 3.31E-09 3.31E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Rn-222 1.35E-09 0 0 0 0 0 0 0 0 0 2.79E-10 2.79E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Rn-222 7.15E-10 0 0 0 0 0 0 0 0 0 1.47E-10 1.47E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Rn-222 2.37E-09 0 0 0 0 0 0 0 0 0 4.88E-10 4.88E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Rn-222 1.64E-09 0 0 0 0 0 0 0 0 0 3.38E-10 3.38E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Rn-222 4.89E-10 0 0 0 0 0 0 0 0 0 1.01E-10 1.01E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Rn-222 4.89E-10 0 0 0 0 0 0 0 0 0 1.01E-10 1.01E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Rn-222 7.15E-10 0 0 0 0 0 0 0 0 0 1.47E-10 1.47E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Rn-222 1.70E-10 0 0 0 0 0 0 0 0 0 3.50E-11 3.50E-02

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Rn-222 1.67E-09 0 0 0 0 0 0 0 0 0 3.44E-10 3.44E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Rn-222 9.43E-11 0 0 0 0 0 0 0 0 0 1.94E-11 1.94E-02

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 59 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1952 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant (pCi/L)

Waste 

Pit

EA-1 Uranium 0 0 0 0 1.69E-09 0 0 0 2.58E-07 0 2.60E-07 6.24E-01 3.44E-09 3.44E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Uranium 0 0 0 0 2.13E-09 0 0 0 5.39E-07 0 5.42E-07 1.30E+00 1.78E-09 1.78E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Uranium 0 0 0 0 5.39E-10 0 0 0 4.78E-07 0 4.79E-07 1.15E+00 1.60E-09 1.60E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Uranium 0 0 0 0 2.66E-09 0 0 0 8.94E-09 0 1.16E-08 2.78E-02 4.39E-09 4.39E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Uranium 0 0 0 0 3.24E-10 0 0 0 1.13E-07 0 1.14E-07 2.73E-01 4.01E-09 4.01E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Uranium 0 0 0 0 2.16E-10 0 0 0 1.17E-07 0 1.17E-07 2.80E-01 1.31E-09 1.31E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Uranium 0 0 0 0 1.95E-09 0 0 0 1.61E-07 0 1.63E-07 3.91E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Uranium 0 0 0 0 1.83E-09 0 0 0 2.04E-07 0 2.05E-07 4.93E-01 1.33E-09 1.33E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Uranium 0 0 0 0 2.35E-09 0 0 0 8.59E-08 0 8.82E-08 2.12E-01 6.65E-10 6.65E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Uranium 0 0 0 0 1.04E-09 0 0 0 1.51E-07 0 1.52E-07 3.65E-01 2.04E-09 2.04E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Uranium 0 0 0 0 4.69E-10 0 0 0 1.25E-07 0 1.25E-07 3.00E-01 1.41E-09 1.41E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

1952/Rn Concentration contribution from emission sources (Ci/m3) Total conc.

(Ci/m3)

Conc. in

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant Waste Pit (pCi/L)

EA-1 Rn-222 2.65E-07 0 0 0 0 0 0 0 0 0 5.49E-08 5.49E+01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Rn-222 2.23E-08 0 0 0 0 0 0 0 0 0 4.62E-09 4.62E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Rn-222 1.18E-08 0 0 0 0 0 0 0 0 0 2.44E-09 2.44E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Rn-222 3.90E-08 0 0 0 0 0 0 0 0 0 8.08E-09 8.08E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Rn-222 2.70E-08 0 0 0 0 0 0 0 0 0 5.59E-09 5.59E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Rn-222 8.06E-09 0 0 0 0 0 0 0 0 0 1.67E-09 1.67E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Rn-222 8.06E-09 0 0 0 0 0 0 0 0 0 1.67E-09 1.67E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Rn-222 1.18E-08 0 0 0 0 0 0 0 0 0 2.44E-09 2.44E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Rn-222 2.80E-09 0 0 0 0 0 0 0 0 0 5.79E-10 5.79E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Rn-222 2.75E-08 0 0 0 0 0 0 0 0 0 5.70E-09 5.70E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Rn-222 1.55E-09 0 0 0 0 0 0 0 0 0 3.22E-10 3.22E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 60 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1953 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant Waste Pit (pCi/L)

EA-1 Uranium 7.22E-16 2.29E-09 3.52E-07 2.93E-08 3.96E-09 0 0 0 2.58E-07 0 6.46E-07 1.55E+00 3.44E-09 3.44E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Uranium 4.05E-09 6.57E-09 1.81E-06 9.59E-08 5.00E-09 0 0 0 5.39E-07 0 2.46E-06 5.91E+00 1.78E-09 1.78E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Uranium 2.02E-09 4.19E-09 3.64E-08 1.69E-11 1.27E-09 0 0 0 4.78E-07 0 5.22E-07 1.25E+00 1.60E-09 1.60E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Uranium 2.15E-09 5.42E-13 2.48E-07 3.46E-08 6.25E-09 0 0 0 8.94E-09 0 3.00E-07 7.20E-01 4.39E-09 4.39E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Uranium 1.49E-09 1.51E-09 3.39E-07 4.87E-09 7.62E-10 0 0 0 1.13E-07 0 4.61E-07 1.11E+00 4.01E-09 4.01E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Uranium 1.46E-09 1.84E-09 5.35E-07 7.57E-09 5.08E-10 0 0 0 1.17E-07 0 6.63E-07 1.59E+00 1.31E-09 1.31E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Uranium 1.46E-09 2.18E-09 4.20E-07 1.76E-08 4.59E-09 0 0 0 1.61E-07 0 6.07E-07 1.46E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Uranium 2.14E-09 3.25E-09 7.37E-07 5.09E-08 4.29E-09 0 0 0 2.04E-07 0 1.00E-06 2.40E+00 1.33E-09 1.33E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Uranium 4.11E-10 6.49E-10 7.84E-07 4.62E-08 5.52E-09 0 0 0 8.59E-08 0 9.23E-07 2.21E+00 6.65E-10 6.65E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Uranium 3.71E-09 5.86E-09 4.36E-07 2.76E-08 2.45E-09 0 0 0 1.51E-07 0 6.26E-07 1.50E+00 2.04E-09 2.04E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0.0

EA-11 Uranium 2.28E-10 5.05E-10 1.50E-07 7.03E-09 1.10E-09 0 0 0 1.25E-07 0 2.84E-07 6.81E-01 1.41E-09 1.41E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0.0

1953/Rn Concentration contribution from emission sources (Ci/m3) Total conc.

(Ci/m3)

Conc. in

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 Pilot Plant Waste Pit (pCi/L)

EA-1 Rn-222 4.26E-08 0 0 0 0 0 0 0 0 0 8.99E-09 8.99E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Rn-222 3.59E-09 0 0 0 0 0 0 0 0 0 7.57E-10 7.57E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Rn-222 1.89E-09 0 0 0 0 0 0 0 0 0 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Rn-222 6.27E-09 0 0 0 0 0 0 0 0 0 1.32E-09 1.32E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Rn-222 4.34E-09 0 0 0 0 0 0 0 0 0 9.16E-10 9.16E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Rn-222 1.29E-09 0 0 0 0 0 0 0 0 0 2.73E-10 2.73E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Rn-222 1.29E-09 0 0 0 0 0 0 0 0 0 2.73E-10 2.73E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Rn-222 1.89E-09 0 0 0 0 0 0 0 0 0 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Rn-222 4.49E-10 0 0 0 0 0 0 0 0 0 9.49E-11 9.49E-02

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Rn-222 4.42E-09 0 0 0 0 0 0 0 0 0 9.33E-10 9.33E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Rn-222 2.50E-10 0 0 0 0 0 0 0 0 0 5.27E-11 5.27E-02

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 61 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1954 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 1.16E-14 1.07E-07 1.41E-06 1.34E-06 9.64E-09 1.12E-06 2.72E-07 9.62E-08 1.42E-07 5.53E-10 4.49E-06 1.08E+01 8.59E-09 8.59E+00

Thorium 0 0 0 0 0 0 0 3.65E-07 0 0 3.65E-07 8.76E-01 0 0

EA-2 Uranium 6.52E-08 3.08E-07 7.24E-06 4.39E-06 1.22E-08 4.54E-06 2.56E-07 1.25E-07 2.97E-07 1.25E-10 1.72E-05 4.13E+01 4.44E-09 4.44E+00

Thorium 0 0 0 0 0 0 0 4.73E-07 0 0 4.73E-07 1.14E+00 0 0

EA-3 Uranium 3.25E-08 1.96E-07 1.46E-07 7.72E-10 3.08E-09 1.63E-06 4.20E-07 1.03E-07 2.63E-07 1.04E-10 2.79E-06 6.70E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 3.92E-07 0 0 3.92E-07 9.40E-01 0 0

EA-4 Uranium 3.46E-08 2.54E-11 9.92E-07 1.58E-06 1.52E-08 5.26E-07 4.94E-11 8.82E-08 4.91E-09 1.46E-10 3.25E-06 7.79E+00 1.10E-08 1.10E+01

Thorium 0 0 0 0 0 0 0 3.34E-07 0 0 3.34E-07 8.03E-01 0 0

EA-5 Uranium 2.40E-08 7.07E-08 1.35E-06 2.23E-07 1.85E-09 9.80E-07 8.65E-08 2.60E-08 6.23E-08 4.93E-09 2.83E-06 6.80E+00 1.00E-08 1.00E+01

Thorium 0 0 0 0 0 0 0 9.88E-08 0 0 9.88E-08 2.37E-01 0 0

EA-6 Uranium 2.35E-08 8.64E-08 2.14E-06 3.46E-07 1.24E-09 9.52E-07 9.34E-08 2.12E-08 6.41E-08 8.71E-10 3.73E-06 8.95E+00 3.28E-09 3.28E+00

Thorium 0 0 0 0 0 0 0 2.15E-08 0 0 2.15E-08 5.16E-02 0 0

EA-7 Uranium 2.35E-08 1.02E-07 1.68E-06 8.05E-07 1.12E-08 0 2.86E-07 9.84E-08 8.84E-08 1.53E-10 3.10E-06 7.43E+00 5.00E-09 5.00E+00

Thorium 0 0 0 0 0 0 0 3.73E-07 0 0 3.73E-07 8.96E-01 0 0

EA-8 Uranium 3.44E-08 1.53E-07 2.95E-06 2.33E-06 1.04E-08 1.10E-06 9.54E-08 9.62E-08 1.12E-07 7.63E-11 6.88E-06 1.65E+01 3.33E-09 3.33E+00

Thorium 0 0 0 0 0 0 0 3.65E-07 0 0 3.65E-07 8.76E-01 0 0

EA-9 Uranium 6.62E-09 3.04E-08 3.14E-06 2.12E-06 1.34E-08 2.65E-06 5.27E-08 1.44E-07 4.72E-08 4.61E-11 8.19E-06 1.97E+01 1.66E-09 1.66E+00

Thorium 0 0 0 0 0 0 0 5.47E-07 0 0 5.47E-07 1.31E+00 0 0

EA-10 Uranium 5.98E-08 2.75E-07 1.74E-06 1.26E-06 5.96E-09 2.74E-06 3.85E-07 3.87E-08 8.31E-08 6.64E-10 6.59E-06 1.58E+01 5.10E-09 5.10E+00

Thorium 0 0 0 0 0 0 0 1.47E-07 0 0 1.47E-07 3.52E-01 0 0

EA-11 Uranium 3.68E-09 2.37E-08 6.02E-07 3.22E-07 2.68E-09 1.08E-06 1.06E-07 1.79E-08 6.85E-08 1.81E-10 2.22E-06 5.33E+00 3.51E-09 3.51E+00

Thorium 0 0 0 0 0 0 0 6.79E-08 0 0 6.79E-08 1.63E-01 0 0

1955 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.12E-14 4.26E-07 2.98E-06 3.39E-06 1.84E-08 1.90E-06 1.19E-06 0 2.32E-07 3.10E-09 1.01E-05 2.43E+01 8.59E-09 8.59E+00

Thorium 0 0 0 0 0 0 0 4.17E-07 0 0 4.17E-07 1.00E+00 0 0

EA-2 Uranium 1.75E-07 1.22E-06 1.53E-05 1.11E-05 2.32E-08 7.74E-06 1.12E-06 0 4.85E-07 6.99E-10 3.72E-05 8.92E+01 4.44E-09 4.44E+00

Thorium 0 0 0 0 0 0 0 5.42E-07 0 0 5.42E-07 1.30E+00 0 0

EA-3 Uranium 8.71E-08 7.78E-07 3.08E-07 1.95E-09 5.87E-09 2.78E-06 1.84E-06 0 4.30E-07 5.83E-10 6.22E-06 1.49E+01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 4.48E-07 0 0 4.48E-07 1.07E+00 0 0

EA-4 Uranium 9.28E-08 1.01E-10 2.10E-06 4.00E-06 2.90E-08 8.98E-07 2.16E-10 0 8.03E-09 8.19E-10 7.13E-06 1.71E+01 1.10E-08 1.10E+01

Thorium 0 0 0 0 0 0 0 3.83E-07 0 0 3.83E-07 9.18E-01 0 0

EA-5 Uranium 6.43E-08 2.80E-07 2.86E-06 5.63E-07 3.53E-09 1.67E-06 3.78E-07 0 1.02E-07 2.76E-08 5.95E-06 1.43E+01 1.00E-08 1.00E+01

Thorium 0 0 0 0 0 0 0 1.13E-07 0 0 1.13E-07 2.71E-01 0 0

EA-6 Uranium 6.31E-08 3.43E-07 4.52E-06 8.76E-07 2.35E-09 1.62E-06 4.08E-07 0 1.05E-07 4.88E-09 7.95E-06 1.91E+01 3.28E-09 3.28E+00

Thorium 0 0 0 0 0 0 0 2.46E-08 0 0 2.46E-08 5.90E-02 0 0

EA-7 Uranium 6.31E-08 4.05E-07 3.55E-06 2.03E-06 2.12E-08 0 1.25E-06 0 1.44E-07 8.57E-10 7.47E-06 1.79E+01 5.00E-09 5.00E+00

Thorium 0 0 0 0 0 0 0 4.27E-07 0 0 4.27E-07 1.02E+00 0 0

EA-8 Uranium 9.23E-08 6.05E-07 6.23E-06 5.88E-06 1.99E-08 1.88E-06 4.17E-07 0 1.83E-07 4.27E-10 1.53E-05 3.67E+01 3.33E-09 3.33E+00

Thorium 0 0 0 0 0 0 0 4.17E-07 0 0 4.17E-07 1.00E+00 0 0

EA-9 Uranium 1.78E-08 1.21E-07 6.63E-06 5.35E-06 2.56E-08 4.51E-06 2.30E-07 0 7.72E-08 2.58E-10 1.70E-05 4.07E+01 1.66E-09 1.66E+00

Thorium 0 0 0 0 0 0 0 6.26E-07 0 0 6.26E-07 1.50E+00 0 0

EA-10 Uranium 1.60E-07 1.09E-06 3.68E-06 3.19E-06 1.14E-08 4.67E-06 1.68E-06 0 1.36E-07 3.72E-09 1.46E-05 3.51E+01 5.10E-09 5.10E+00

Thorium 0 0 0 0 0 0 0 1.68E-07 0 0 1.68E-07 4.03E-01 0 0

EA-11 Uranium 9.86E-09 9.38E-08 1.27E-06 8.13E-07 5.10E-09 1.84E-06 4.61E-07 0 1.12E-07 1.01E-09 4.60E-06 1.11E+01 3.51E-09 3.51E+00

Thorium 0 0 0 0 0 0 0 7.77E-08 0 0 7.77E-08 1.87E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 62 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1956 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.07E-14 7.57E-07 1.23E-06 1.14E-06 1.19E-08 4.56E-07 1.79E-06 0 1.68E-08 4.43E-09 5.41E-06 1.30E+01 8.59E-09 8.59E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Uranium 1.72E-07 2.17E-06 6.33E-06 3.73E-06 1.50E-08 1.86E-06 1.69E-06 0 3.50E-08 9.99E-10 1.60E-05 3.84E+01 4.44E-09 4.44E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Uranium 8.56E-08 1.38E-06 1.27E-07 6.57E-10 3.79E-09 6.66E-07 2.77E-06 0 3.11E-08 8.32E-10 5.07E-06 1.22E+01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Uranium 9.12E-08 1.79E-10 8.67E-07 1.35E-06 1.87E-08 2.15E-07 3.26E-10 0 5.80E-10 1.17E-09 2.54E-06 6.10E+00 1.10E-08 1.10E+01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Uranium 6.32E-08 4.98E-07 1.18E-06 1.89E-07 2.28E-09 4.01E-07 5.71E-07 0 7.36E-09 3.94E-08 2.96E-06 7.09E+00 1.00E-08 1.00E+01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Uranium 6.21E-08 6.09E-07 1.87E-06 2.94E-07 1.52E-09 3.89E-07 6.16E-07 0 7.57E-09 6.97E-09 3.86E-06 9.25E+00 3.28E-09 3.28E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Uranium 6.21E-08 7.19E-07 1.47E-06 6.84E-07 1.37E-08 0 1.89E-06 0 1.04E-08 1.22E-09 4.85E-06 1.16E+01 5.00E-09 5.00E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Uranium 9.07E-08 1.07E-06 2.57E-06 1.98E-06 1.28E-08 4.50E-07 6.30E-07 0 1.32E-08 6.10E-10 6.83E-06 1.64E+01 3.33E-09 3.33E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Uranium 1.75E-08 2.14E-07 2.74E-06 1.80E-06 1.65E-08 1.08E-06 3.48E-07 0 5.57E-09 3.69E-10 6.22E-06 1.49E+01 1.66E-09 1.66E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Uranium 1.58E-07 1.93E-06 1.52E-06 1.07E-06 7.34E-09 1.12E-06 2.54E-06 0 9.81E-09 5.31E-09 8.37E-06 2.01E+01 5.10E-09 5.10E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Uranium 9.70E-09 1.67E-07 5.26E-07 2.73E-07 3.30E-09 4.41E-07 6.97E-07 0 8.09E-09 1.45E-09 2.13E-06 5.10E+00 3.51E-09 3.51E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

1957 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.18E-14 1.43E-06 1.96E-07 1.19E-06 1.46E-08 0 1.54E-06 1.42E-10 9.43E-09 1.08E-07 4.49E-06 1.08E+01 8.59E-09 8.59E+00

Thorium 0 0 0 0 0 0 0 0 0 2.01E-11 2.01E-11 4.83E-05 0 0

EA-2 Uranium 1.78E-07 4.09E-06 1.01E-06 3.90E-06 1.84E-08 0 1.45E-06 1.84E-10 1.97E-08 2.43E-08 1.07E-05 2.57E+01 4.44E-09 4.44E+00

Thorium 0 0 0 0 0 0 0 0 0 4.54E-12 4.54E-12 1.09E-05 0 0

EA-3 Uranium 8.88E-08 2.61E-06 2.03E-08 6.87E-10 4.65E-09 0 2.38E-06 1.52E-10 1.75E-08 2.02E-08 5.14E-06 1.23E+01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 3.79E-12 3.79E-12 9.09E-06 0 0

EA-4 Uranium 9.46E-08 3.37E-10 1.38E-07 1.41E-06 2.30E-08 0 2.79E-10 1.30E-10 3.26E-10 2.84E-08 1.69E-06 4.07E+00 1.10E-08 1.10E+01

Thorium 0 0 0 0 0 0 0 0 0 5.32E-12 5.32E-12 1.28E-05 0 0

EA-5 Uranium 6.55E-08 9.39E-07 1.89E-07 1.98E-07 2.80E-09 0 4.90E-07 3.84E-11 4.14E-09 9.58E-07 2.85E-06 6.83E+00 1.00E-08 1.00E+01

Thorium 0 0 0 0 0 0 0 0 0 1.79E-10 1.79E-10 4.31E-04 0 0

EA-6 Uranium 6.44E-08 1.15E-06 2.98E-07 3.08E-07 1.87E-09 0 5.29E-07 3.12E-11 4.26E-09 1.69E-07 2.52E-06 6.05E+00 3.28E-09 3.28E+00

Thorium 0 0 0 0 0 0 0 0 0 3.17E-11 3.17E-11 7.61E-05 0 0

EA-7 Uranium 6.44E-08 1.36E-06 2.34E-07 7.16E-07 1.69E-08 0 1.62E-06 1.45E-10 5.87E-09 2.97E-08 4.04E-06 9.71E+00 5.00E-09 5.00E+00

Thorium 0 0 0 0 0 0 0 0 0 5.57E-12 5.57E-12 1.34E-05 0 0

EA-8 Uranium 9.41E-08 2.03E-06 4.10E-07 2.07E-06 1.58E-08 0 5.40E-07 1.42E-10 7.44E-09 1.48E-08 5.18E-06 1.24E+01 3.33E-09 3.33E+00

Thorium 0 0 0 0 0 0 0 0 0 2.78E-12 2.78E-12 6.66E-06 0 0

EA-9 Uranium 1.81E-08 4.04E-07 4.36E-07 1.88E-06 2.03E-08 0 2.99E-07 2.13E-10 3.14E-09 8.96E-09 3.07E-06 7.37E+00 1.66E-09 1.66E+00

Thorium 0 0 0 0 0 0 0 0 0 1.68E-12 1.68E-12 4.03E-06 0 0

EA-10 Uranium 1.64E-07 3.65E-06 2.42E-07 1.12E-06 9.00E-09 0 2.18E-06 5.71E-11 5.52E-09 1.29E-07 7.50E-06 1.80E+01 5.10E-09 5.10E+00

Thorium 0 0 0 0 0 0 0 0 0 2.42E-11 2.42E-11 5.80E-05 0 0

EA-11 Uranium 1.01E-08 3.14E-07 8.37E-08 2.86E-07 4.05E-09 0 5.98E-07 2.64E-11 4.55E-09 3.52E-08 1.34E-06 3.21E+00 3.51E-09 3.51E+00

Thorium 0 0 0 0 0 0 0 0 0 6.58E-12 6.58E-12 1.58E-05 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 63 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1958 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 9.98E-14 1.35E-06 1.60E-07 2.33E-07 4.98E-08 0 1.64E-06 2.42E-07 1.41E-08 2.10E-07 3.90E-06 9.36E+00 8.59E-09 8.59E+00

Thorium 0 0 0 0 0 0 0 0 0 4.60E-11 4.60E-11 1.10E-04 0 0

EA-2 Uranium 5.59E-07 3.86E-06 8.21E-07 7.62E-07 6.29E-08 0 1.55E-06 3.14E-07 2.95E-08 4.74E-08 8.00E-06 1.92E+01 4.44E-09 4.44E+00

Thorium 0 0 0 0 0 0 0 0 0 1.04E-11 1.04E-11 2.49E-05 0 0

EA-3 Uranium 2.79E-07 2.46E-06 1.65E-08 1.34E-10 1.59E-08 0 2.54E-06 2.59E-07 2.62E-08 3.95E-08 5.64E-06 1.35E+01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 8.66E-12 8.66E-12 2.08E-05 0 0

EA-4 Uranium 2.97E-07 3.18E-10 1.13E-07 2.75E-07 7.87E-08 0 2.98E-10 2.22E-07 4.90E-10 5.55E-08 1.04E-06 2.50E+00 1.10E-08 1.10E+01

Thorium 0 0 0 0 0 0 0 0 0 1.22E-11 1.22E-11 2.92E-05 0 0

EA-5 Uranium 2.06E-07 8.86E-07 1.54E-07 3.87E-08 9.59E-09 0 5.23E-07 6.55E-08 6.21E-09 1.87E-06 3.76E-06 9.02E+00 1.00E-08 1.00E+01

Thorium 0 0 0 0 0 0 0 0 0 4.10E-10 4.10E-10 9.84E-04 0 0

EA-6 Uranium 2.02E-07 1.08E-06 2.43E-07 6.02E-08 6.39E-09 0 5.64E-07 5.32E-08 6.39E-09 3.31E-07 2.55E-06 6.12E+00 3.28E-09 3.28E+00

Thorium 0 0 0 0 0 0 0 0 0 7.24E-11 7.24E-11 1.74E-04 0 0

EA-7 Uranium 2.02E-07 1.28E-06 1.91E-07 1.40E-07 5.77E-08 0 1.73E-06 2.47E-07 8.81E-09 5.81E-08 3.91E-06 9.40E+00 5.00E-09 5.00E+00

Thorium 0 0 0 0 0 0 0 0 0 1.27E-11 1.27E-11 3.06E-05 0 0

EA-8 Uranium 2.95E-07 1.91E-06 3.34E-07 4.04E-07 5.40E-08 0 5.77E-07 2.42E-07 1.12E-08 2.90E-08 3.86E-06 9.26E+00 3.33E-09 3.33E+00

Thorium 0 0 0 0 0 0 0 0 0 6.35E-12 6.35E-12 1.52E-05 0 0

EA-9 Uranium 5.68E-08 3.81E-07 3.56E-07 3.68E-07 6.94E-08 0 3.19E-07 3.63E-07 4.70E-09 1.75E-08 1.93E-06 4.64E+00 1.66E-09 1.66E+00

Thorium 0 0 0 0 0 0 0 0 0 3.83E-12 3.83E-12 9.20E-06 0 0

EA-10 Uranium 5.14E-07 3.44E-06 1.98E-07 2.19E-07 3.08E-08 0 2.33E-06 9.72E-08 8.28E-09 2.52E-07 7.09E-06 1.70E+01 5.10E-09 5.10E+00

Thorium 0 0 0 0 0 0 0 0 0 5.52E-11 5.52E-11 1.33E-04 0 0

EA-11 Uranium 3.16E-08 2.97E-07 6.83E-08 5.59E-08 1.38E-08 0 6.38E-07 4.50E-08 6.82E-09 6.86E-08 1.23E-06 2.94E+00 3.51E-09 3.51E+00

Thorium 0 0 0 0 0 0 0 0 0 1.50E-11 1.50E-11 3.61E-05 0 0

1959 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.11E-14 1.50E-06 3.43E-07 1.56E-07 4.02E-08 0 1.54E-06 1.49E-07 1.78E-08 2.10E-07 3.96E-06 9.49E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 4.60E-11 4.60E-11 1.10E-04 0 0

EA-2 Uranium 1.75E-07 4.31E-06 1.76E-06 5.10E-07 5.08E-08 0 1.45E-06 1.94E-07 3.72E-08 4.74E-08 8.53E-06 2.05E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.04E-11 1.04E-11 2.49E-05 0 0

EA-3 Uranium 8.70E-08 2.75E-06 3.55E-08 8.98E-11 1.29E-08 0 2.37E-06 1.60E-07 3.30E-08 3.95E-08 5.49E-06 1.32E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 8.66E-12 8.66E-12 2.08E-05 0 0

EA-4 Uranium 9.27E-08 3.55E-10 2.42E-07 1.84E-07 6.35E-08 0 2.79E-10 1.37E-07 6.17E-10 5.55E-08 7.75E-07 1.86E+00 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 1.22E-11 1.22E-11 2.92E-05 0 0

EA-5 Uranium 6.42E-08 9.89E-07 3.30E-07 2.59E-08 7.74E-09 0 4.89E-07 4.04E-08 7.82E-09 1.87E-06 3.82E-06 9.18E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 4.10E-10 4.10E-10 9.84E-04 0 0

EA-6 Uranium 6.31E-08 1.21E-06 5.21E-07 4.03E-08 5.16E-09 0 5.27E-07 3.28E-08 8.04E-09 3.31E-07 2.74E-06 6.57E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 7.24E-11 7.24E-11 1.74E-04 0 0

EA-7 Uranium 6.31E-08 1.43E-06 4.09E-07 9.36E-08 4.66E-08 0 1.62E-06 1.53E-07 1.11E-08 5.81E-08 3.88E-06 9.31E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 1.27E-11 1.27E-11 3.06E-05 0 0

EA-8 Uranium 9.22E-08 2.13E-06 7.17E-07 2.71E-07 4.36E-08 0 5.39E-07 1.49E-07 1.40E-08 2.90E-08 3.99E-06 9.57E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 6.35E-12 6.35E-12 1.52E-05 0 0

EA-9 Uranium 1.77E-08 4.26E-07 7.63E-07 2.46E-07 5.60E-08 0 2.98E-07 2.24E-07 5.92E-09 1.75E-08 2.05E-06 4.93E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 3.83E-12 3.83E-12 9.20E-06 0 0

EA-10 Uranium 1.60E-07 3.84E-06 4.24E-07 1.47E-07 2.49E-08 0 2.18E-06 6.00E-08 1.04E-08 2.52E-07 7.10E-06 1.70E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 5.52E-11 5.52E-11 1.33E-04 0 0

EA-11 Uranium 9.85E-09 3.31E-07 1.46E-07 3.74E-08 1.12E-08 0 5.97E-07 2.78E-08 8.59E-09 6.86E-08 1.24E-06 2.97E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 1.50E-11 1.50E-11 3.61E-05 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 64 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1960 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.62E-14 1.62E-06 5.24E-08 6.62E-08 8.11E-08 0 1.89E-06 7.91E-08 3.76E-07 2.40E-07 4.40E-06 1.06E+01 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 5.93E-10 5.93E-10 1.42E-03 0 0

EA-2 Uranium 1.47E-07 4.64E-06 2.69E-07 2.17E-07 1.02E-07 0 1.78E-06 1.03E-07 7.86E-07 5.41E-08 8.10E-06 1.94E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-10 1.34E-10 3.21E-04 0 0

EA-3 Uranium 7.32E-08 2.96E-06 5.42E-09 3.81E-11 2.59E-08 0 2.92E-06 8.49E-08 6.97E-07 4.51E-08 6.81E-06 1.63E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 1.11E-10 1.11E-10 2.67E-04 0 0

EA-4 Uranium 7.80E-08 3.83E-10 3.69E-08 7.82E-08 1.28E-07 0 3.43E-10 7.25E-08 1.30E-08 6.34E-08 4.71E-07 1.13E+00 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 1.57E-10 1.57E-10 3.76E-04 0 0

EA-5 Uranium 5.40E-08 1.07E-06 5.04E-08 1.10E-08 1.56E-08 0 6.01E-07 2.14E-08 1.65E-07 2.14E-06 4.12E-06 9.89E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 5.28E-09 5.28E-09 1.27E-02 0 0

EA-6 Uranium 5.31E-08 1.30E-06 7.95E-08 1.71E-08 1.04E-08 0 6.49E-07 1.74E-08 1.70E-07 3.78E-07 2.68E-06 6.42E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 9.33E-10 9.33E-10 2.24E-03 0 0

EA-7 Uranium 5.31E-08 1.54E-06 6.25E-08 3.98E-08 9.39E-08 0 1.99E-06 8.09E-08 2.34E-07 6.63E-08 4.16E-06 9.98E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-10 1.64E-10 3.93E-04 0 0

EA-8 Uranium 7.75E-08 2.30E-06 1.10E-07 1.15E-07 8.78E-08 0 6.63E-07 7.91E-08 2.97E-07 3.31E-08 3.76E-06 9.03E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 8.17E-11 8.17E-11 1.96E-04 0 0

EA-9 Uranium 1.49E-08 4.59E-07 1.17E-07 1.05E-07 1.13E-07 0 3.66E-07 1.19E-07 1.25E-07 2.00E-08 1.44E-06 3.45E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 4.94E-11 4.94E-11 1.18E-04 0 0

EA-10 Uranium 1.35E-07 4.14E-06 6.48E-08 6.24E-08 5.02E-08 0 2.68E-06 3.18E-08 2.20E-07 2.88E-07 7.67E-06 1.84E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-10 7.11E-10 1.71E-03 0 0

EA-11 Uranium 8.29E-09 3.57E-07 2.24E-08 1.59E-08 2.25E-08 0 7.34E-07 1.47E-08 1.81E-07 7.84E-08 1.43E-06 3.44E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-10 1.94E-10 4.65E-04 0 0

1961 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.24E-14 1.42E-06 6.42E-08 2.50E-08 3.82E-08 0 1.68E-06 2.63E-08 9.11E-08 2.69E-07 3.61E-06 8.67E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 1.61E-09 1.61E-09 3.87E-03 0 0

EA-2 Uranium 1.82E-07 4.06E-06 3.30E-07 8.17E-08 4.83E-08 0 1.58E-06 3.41E-08 1.90E-07 6.07E-08 6.57E-06 1.58E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 3.64E-10 3.64E-10 8.72E-04 0 0

EA-3 Uranium 9.06E-08 2.59E-06 6.64E-09 1.44E-11 1.22E-08 0 2.60E-06 2.82E-08 1.69E-07 5.06E-08 5.55E-06 1.33E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 3.03E-10 3.03E-10 7.27E-04 0 0

EA-4 Uranium 9.66E-08 3.35E-10 4.52E-08 2.95E-08 6.03E-08 0 3.05E-10 2.41E-08 3.16E-09 7.11E-08 3.31E-07 7.93E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 4.26E-10 4.26E-10 1.02E-03 0 0

EA-5 Uranium 6.68E-08 9.33E-07 6.18E-08 4.15E-09 7.35E-09 0 5.34E-07 7.11E-09 4.00E-08 2.40E-06 4.05E-06 9.72E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 1.44E-08 1.44E-08 3.44E-02 0 0

EA-6 Uranium 6.57E-08 1.14E-06 9.75E-08 6.45E-09 4.90E-09 0 5.77E-07 5.78E-09 4.12E-08 4.23E-07 2.36E-06 5.67E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 2.54E-09 2.54E-09 6.09E-03 0 0

EA-7 Uranium 6.57E-08 1.35E-06 7.66E-08 1.50E-08 4.42E-08 0 1.77E-06 2.69E-08 5.67E-08 7.44E-08 3.48E-06 8.34E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 4.46E-10 4.46E-10 1.07E-03 0 0

EA-8 Uranium 9.60E-08 2.01E-06 1.34E-07 4.34E-08 4.14E-08 0 5.89E-07 2.63E-08 7.19E-08 3.71E-08 3.05E-06 7.33E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 2.22E-10 2.22E-10 5.33E-04 0 0

EA-9 Uranium 1.85E-08 4.02E-07 1.43E-07 3.94E-08 5.32E-08 0 3.26E-07 3.94E-08 3.03E-08 2.24E-08 1.07E-06 2.58E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-10 1.34E-10 3.22E-04 0 0

EA-10 Uranium 1.67E-07 3.62E-06 7.94E-08 2.35E-08 2.36E-08 0 2.38E-06 1.06E-08 5.34E-08 3.23E-07 6.68E-06 1.60E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 1.93E-09 1.93E-09 4.64E-03 0 0

EA-11 Uranium 1.03E-08 3.12E-07 2.74E-08 5.99E-09 1.06E-08 0 6.52E-07 4.89E-09 4.40E-08 8.79E-08 1.16E-06 2.77E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 5.27E-10 5.27E-10 1.26E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 65 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1962 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.89E-14 8.18E-07 1.70E-07 1.16E-07 2.15E-08 0 1.90E-06 5.06E-08 9.11E-08 2.78E-07 3.45E-06 8.27E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 2.26E-09 2.26E-09 5.42E-03 0 0

EA-2 Uranium 1.62E-07 2.34E-06 8.71E-07 3.80E-07 2.72E-08 0 1.79E-06 6.56E-08 1.90E-07 6.28E-08 5.89E-06 1.41E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 5.10E-10 5.10E-10 1.22E-03 0 0

EA-3 Uranium 8.06E-08 1.49E-06 1.75E-08 6.69E-11 6.88E-09 0 2.94E-06 5.43E-08 1.69E-07 5.23E-08 4.81E-06 1.16E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 4.25E-10 4.25E-10 1.02E-03 0 0

EA-4 Uranium 8.59E-08 1.93E-10 1.19E-07 1.37E-07 3.40E-08 0 3.45E-10 4.64E-08 3.16E-09 7.35E-08 5.00E-07 1.20E+00 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 5.97E-10 5.97E-10 1.43E-03 0 0

EA-5 Uranium 5.95E-08 5.38E-07 1.63E-07 1.93E-08 4.14E-09 0 6.05E-07 1.37E-08 4.00E-08 2.48E-06 3.92E-06 9.41E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 2.01E-08 2.01E-08 4.83E-02 0 0

EA-6 Uranium 5.84E-08 6.58E-07 2.57E-07 3.00E-08 2.76E-09 0 6.53E-07 1.11E-08 4.12E-08 4.38E-07 2.15E-06 5.16E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 3.55E-09 3.55E-09 8.53E-03 0 0

EA-7 Uranium 5.84E-08 7.77E-07 2.02E-07 6.97E-08 2.49E-08 0 2.00E-06 5.17E-08 5.67E-08 7.69E-08 3.32E-06 7.97E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 6.25E-10 6.25E-10 1.50E-03 0 0

EA-8 Uranium 8.54E-08 1.16E-06 3.54E-07 2.02E-07 2.33E-08 0 6.67E-07 5.06E-08 7.19E-08 3.84E-08 2.65E-06 6.37E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 3.11E-10 3.11E-10 7.47E-04 0 0

EA-9 Uranium 1.64E-08 2.32E-07 3.77E-07 1.83E-07 3.00E-08 0 3.69E-07 7.59E-08 3.03E-08 2.32E-08 1.34E-06 3.21E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 1.88E-10 1.88E-10 4.51E-04 0 0

EA-10 Uranium 1.49E-07 2.09E-06 2.10E-07 1.09E-07 1.33E-08 0 2.69E-06 2.03E-08 5.34E-08 3.34E-07 5.67E-06 1.36E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 2.71E-09 2.71E-09 6.50E-03 0 0

EA-11 Uranium 9.13E-09 1.80E-07 7.24E-08 2.78E-08 5.98E-09 0 7.39E-07 9.42E-09 4.40E-08 9.09E-08 1.18E-06 2.83E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 7.38E-10 7.38E-10 1.77E-03 0 0

1963 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 4.32E-14 0 3.53E-07 2.55E-07 5.61E-08 0 2.06E-06 6.00E-08 2.71E-08 2.78E-07 3.09E-06 7.41E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 2.53E-09 2.53E-09 6.08E-03 0 0

EA-2 Uranium 2.42E-07 0 1.81E-06 8.35E-07 7.09E-08 0 1.94E-06 7.79E-08 5.67E-08 6.28E-08 5.10E-06 1.22E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 5.71E-10 5.71E-10 1.37E-03 0 0

EA-3 Uranium 1.21E-07 0 3.65E-08 1.47E-10 1.79E-08 0 3.18E-06 6.44E-08 5.03E-08 5.23E-08 3.53E-06 8.46E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 4.76E-10 4.76E-10 1.14E-03 0 0

EA-4 Uranium 1.29E-07 0 2.49E-07 3.01E-07 8.86E-08 0 3.74E-10 5.50E-08 9.39E-10 7.35E-08 8.97E-07 2.15E+00 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 6.69E-10 6.69E-10 1.61E-03 0 0

EA-5 Uranium 8.91E-08 0 3.39E-07 4.24E-08 1.08E-08 0 6.55E-07 1.63E-08 1.19E-08 2.48E-06 3.64E-06 8.74E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 2.26E-08 2.26E-08 5.41E-02 0 0

EA-6 Uranium 8.75E-08 0 5.36E-07 6.59E-08 7.20E-09 0 7.07E-07 1.32E-08 1.23E-08 4.38E-07 1.87E-06 4.48E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 3.98E-09 3.98E-09 9.56E-03 0 0

EA-7 Uranium 8.75E-08 0 4.21E-07 1.53E-07 6.50E-08 0 2.17E-06 6.14E-08 1.69E-08 7.69E-08 3.05E-06 7.32E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 7.00E-10 7.00E-10 1.68E-03 0 0

EA-8 Uranium 1.28E-07 0 7.38E-07 4.43E-07 6.08E-08 0 7.23E-07 6.00E-08 2.14E-08 3.84E-08 2.21E-06 5.31E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 3.49E-10 3.49E-10 8.38E-04 0 0

EA-9 Uranium 2.46E-08 0 7.85E-07 4.03E-07 7.82E-08 0 3.99E-07 9.01E-08 9.02E-09 2.32E-08 1.81E-06 4.35E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 2.11E-10 2.11E-10 5.06E-04 0 0

EA-10 Uranium 2.22E-07 0 4.36E-07 2.40E-07 3.47E-08 0 2.92E-06 2.41E-08 1.59E-08 3.34E-07 4.23E-06 1.01E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 3.04E-09 3.04E-09 7.29E-03 0 0

EA-11 Uranium 1.37E-08 0 1.51E-07 6.12E-08 1.56E-08 0 8.00E-07 1.12E-08 1.31E-08 9.09E-08 1.16E-06 2.78E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 8.28E-10 8.28E-10 1.99E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 66 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1964 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.13E-14 0 1.31E-07 1.08E-07 1.43E-08 0 2.55E-06 9.47E-08 6.81E-09 2.85E-07 3.19E-06 7.65E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 1.80E-07 2.82E-09 1.83E-07 4.39E-01 0 0

EA-2 Uranium 1.76E-07 0 6.75E-07 3.52E-07 1.81E-08 0 2.40E-06 1.23E-07 1.42E-08 6.44E-08 3.83E-06 9.18E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 3.76E-07 6.36E-10 3.77E-07 9.05E-01 0 0

EA-3 Uranium 8.75E-08 0 1.36E-08 6.20E-11 4.57E-09 0 3.94E-06 1.02E-07 1.26E-08 5.37E-08 4.21E-06 1.01E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.34E-07 5.30E-10 3.34E-07 8.02E-01 0 0

EA-4 Uranium 9.33E-08 0 9.26E-08 1.27E-07 2.26E-08 0 4.62E-10 8.68E-08 2.36E-10 7.54E-08 4.99E-07 1.20E+00 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 6.24E-09 7.45E-10 6.98E-09 1.68E-02 0 0

EA-5 Uranium 6.46E-08 0 1.26E-07 1.79E-08 2.75E-09 0 8.11E-07 2.56E-08 2.99E-09 2.54E-06 3.59E-06 8.63E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 7.91E-08 2.51E-08 1.04E-07 2.50E-01 0 0

EA-6 Uranium 6.34E-08 0 1.99E-07 2.78E-08 1.83E-09 0 8.75E-07 2.08E-08 3.08E-09 4.49E-07 1.64E-06 3.94E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 8.14E-08 4.44E-09 8.58E-08 2.06E-01 0 0

EA-7 Uranium 6.34E-08 0 1.57E-07 6.47E-08 1.66E-08 0 2.68E-06 9.69E-08 4.24E-09 7.90E-08 3.16E-06 7.60E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.12E-07 7.80E-10 1.13E-07 2.71E-01 0 0

EA-8 Uranium 9.27E-08 0 2.75E-07 1.87E-07 1.55E-08 0 8.94E-07 9.47E-08 5.37E-09 3.94E-08 1.60E-06 3.85E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.42E-07 3.89E-10 1.42E-07 3.42E-01 0 0

EA-9 Uranium 1.78E-08 0 2.92E-07 1.70E-07 1.99E-08 0 4.94E-07 1.42E-07 2.26E-09 2.38E-08 1.16E-06 2.79E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 5.99E-08 2.35E-10 6.02E-08 1.44E-01 0 0

EA-10 Uranium 1.61E-07 0 1.62E-07 1.01E-07 8.85E-09 0 3.61E-06 3.81E-08 3.99E-09 3.43E-07 4.43E-06 1.06E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.05E-07 3.38E-09 1.09E-07 2.61E-01 0 0

EA-11 Uranium 9.91E-09 0 5.61E-08 2.58E-08 3.98E-09 0 9.90E-07 1.76E-08 3.29E-09 9.33E-08 1.20E-06 2.88E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.22E-10 8.79E-08 2.11E-01 0 0

1965 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.85E-14 7.37E-08 8.11E-08 7.38E-08 1.66E-08 0 4.03E-06 2.95E-08 5.24E-09 1.58E-07 4.47E-06 1.07E+01 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 1.80E-07 2.79E-09 1.83E-07 4.39E-01 0 0

EA-2 Uranium 1.60E-07 2.11E-07 4.16E-07 2.42E-07 2.09E-08 0 3.80E-06 3.82E-08 1.09E-08 3.57E-08 4.94E-06 1.19E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 3.76E-07 6.30E-10 3.77E-07 9.05E-01 0 0

EA-3 Uranium 7.97E-08 1.35E-07 8.38E-09 4.25E-11 5.30E-09 0 6.23E-06 3.16E-08 9.70E-09 2.98E-08 6.53E-06 1.57E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.34E-07 5.25E-10 3.34E-07 8.02E-01 0 0

EA-4 Uranium 8.50E-08 1.74E-11 5.71E-08 8.72E-08 2.62E-08 0 7.32E-10 2.70E-08 1.81E-10 4.18E-08 3.25E-07 7.80E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 6.24E-09 7.37E-10 6.98E-09 1.67E-02 0 0

EA-5 Uranium 5.88E-08 4.85E-08 7.79E-08 1.23E-08 3.19E-09 0 1.28E-06 7.98E-09 2.30E-09 1.41E-06 2.90E-06 6.97E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 7.91E-08 2.49E-08 1.04E-07 2.50E-01 0 0

EA-6 Uranium 5.78E-08 5.93E-08 1.23E-07 1.91E-08 2.13E-09 0 1.39E-06 6.48E-09 2.37E-09 2.49E-07 1.90E-06 4.57E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 8.14E-08 4.39E-09 8.58E-08 2.06E-01 0 0

EA-7 Uranium 5.78E-08 7.01E-08 9.67E-08 4.44E-08 1.92E-08 0 4.25E-06 3.01E-08 3.26E-09 4.38E-08 4.61E-06 1.11E+01 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.12E-07 7.72E-10 1.13E-07 2.71E-01 0 0

EA-8 Uranium 8.45E-08 1.05E-07 1.69E-07 1.28E-07 1.80E-08 0 1.42E-06 2.95E-08 4.13E-09 2.18E-08 1.98E-06 4.74E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.42E-07 3.85E-10 1.42E-07 3.42E-01 0 0

EA-9 Uranium 1.63E-08 2.09E-08 1.80E-07 1.17E-07 2.31E-08 0 7.82E-07 4.42E-08 1.74E-09 1.32E-08 1.20E-06 2.88E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 5.99E-08 2.32E-10 6.02E-08 1.44E-01 0 0

EA-10 Uranium 1.47E-07 1.88E-07 1.00E-07 6.96E-08 1.03E-08 0 5.71E-06 1.18E-08 3.07E-09 1.90E-07 6.43E-06 1.54E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.05E-07 3.35E-09 1.09E-07 2.61E-01 0 0

EA-11 Uranium 9.03E-09 1.62E-08 3.46E-08 1.77E-08 4.61E-09 0 1.57E-06 5.49E-09 2.53E-09 5.17E-08 1.71E-06 4.10E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.12E-10 8.79E-08 2.11E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 67 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1966 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.12E-14 1.97E-07 5.52E-08 2.51E-08 6.66E-09 0 8.16E-07 1.87E-08 9.48E-09 1.09E-07 1.24E-06 2.97E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 7.68E-08 0 1.80E-07 3.05E-09 2.60E-07 6.24E-01 0 0

EA-2 Uranium 1.75E-07 5.63E-07 2.84E-07 8.21E-08 8.41E-09 0 7.69E-07 2.43E-08 1.98E-08 2.46E-08 1.95E-06 4.68E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 7.24E-08 0 3.76E-07 6.88E-10 4.49E-07 1.08E+00 0 0

EA-3 Uranium 8.71E-08 3.59E-07 5.71E-09 1.45E-11 2.13E-09 0 1.26E-06 2.01E-08 1.76E-08 2.05E-08 1.77E-06 4.26E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 1.19E-07 0 3.34E-07 5.73E-10 4.53E-07 1.09E+00 0 0

EA-4 Uranium 9.28E-08 4.65E-11 3.89E-08 2.96E-08 1.05E-08 0 1.48E-10 1.72E-08 3.28E-10 2.88E-08 2.18E-07 5.24E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 1.39E-11 0 6.24E-09 8.06E-10 7.06E-09 1.69E-02 0 0

EA-5 Uranium 6.43E-08 1.29E-07 5.31E-08 4.17E-09 1.28E-09 0 2.60E-07 5.07E-09 4.16E-09 9.72E-07 1.49E-06 3.58E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 2.44E-08 0 7.91E-08 2.72E-08 1.31E-07 3.14E-01 0 0

EA-6 Uranium 6.31E-08 1.58E-07 8.38E-08 6.48E-09 8.54E-10 0 2.80E-07 4.12E-09 4.28E-09 1.72E-07 7.73E-07 1.85E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 2.64E-08 0 8.14E-08 4.80E-09 1.13E-07 2.70E-01 0 0

EA-7 Uranium 6.31E-08 1.87E-07 6.59E-08 1.51E-08 7.71E-09 0 8.59E-07 1.91E-08 5.90E-09 3.02E-08 1.25E-06 3.01E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 8.08E-08 0 1.12E-07 8.43E-10 1.94E-07 4.65E-01 0 0

EA-8 Uranium 9.23E-08 2.79E-07 1.15E-07 4.36E-08 7.21E-09 0 2.86E-07 1.87E-08 7.48E-09 1.50E-08 8.65E-07 2.08E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 2.69E-08 0 1.42E-07 4.21E-10 1.69E-07 4.07E-01 0 0

EA-9 Uranium 1.78E-08 5.57E-08 1.23E-07 3.96E-08 9.28E-09 0 1.58E-07 2.81E-08 3.15E-09 9.09E-09 4.44E-07 1.06E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 1.49E-08 0 5.99E-08 2.54E-10 7.51E-08 1.80E-01 0 0

EA-10 Uranium 1.60E-07 5.03E-07 6.83E-08 2.36E-08 4.12E-09 0 1.16E-06 7.52E-09 5.55E-09 1.31E-07 2.06E-06 4.94E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 1.09E-07 0 1.05E-07 3.66E-09 2.18E-07 5.23E-01 0 0

EA-11 Uranium 9.86E-09 4.33E-08 2.36E-08 6.02E-09 1.85E-09 0 3.17E-07 3.48E-09 4.58E-09 3.57E-08 4.45E-07 1.07E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 2.98E-08 0 8.70E-08 9.97E-10 1.18E-07 2.83E-01 0 0

1967 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 3.27E-14 2.47E-07 6.80E-08 4.82E-08 4.02E-09 0 1.44E-06 2.86E-08 6.18E-09 2.37E-08 1.86E-06 4.47E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 1.80E-07 3.02E-09 1.83E-07 4.40E-01 0 0

EA-2 Uranium 1.84E-07 7.09E-07 3.49E-07 1.58E-07 5.07E-09 0 1.35E-06 3.71E-08 1.29E-08 5.34E-09 2.81E-06 6.75E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 3.76E-07 6.82E-10 3.77E-07 9.05E-01 0 0

EA-3 Uranium 9.15E-08 4.52E-07 7.03E-09 2.78E-11 1.28E-09 0 2.22E-06 3.07E-08 1.15E-08 4.45E-09 2.82E-06 6.76E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.34E-07 5.68E-10 3.34E-07 8.03E-01 0 0

EA-4 Uranium 9.75E-08 5.85E-11 4.79E-08 5.70E-08 6.34E-09 0 2.61E-10 2.62E-08 2.14E-10 6.26E-09 2.42E-07 5.80E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 6.24E-09 7.98E-10 7.04E-09 1.69E-02 0 0

EA-5 Uranium 6.75E-08 1.63E-07 6.54E-08 8.02E-09 7.73E-10 0 4.57E-07 7.75E-09 2.71E-09 2.11E-07 9.83E-07 2.36E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 7.91E-08 2.69E-08 1.06E-07 2.54E-01 0 0

EA-6 Uranium 6.63E-08 1.99E-07 1.03E-07 1.25E-08 5.15E-10 0 4.93E-07 6.30E-09 2.79E-09 3.73E-08 9.21E-07 2.21E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 8.14E-08 4.75E-09 8.61E-08 2.07E-01 0 0

EA-7 Uranium 6.63E-08 2.35E-07 8.11E-08 2.90E-08 4.65E-09 0 1.51E-06 2.93E-08 3.85E-09 6.55E-09 1.97E-06 4.72E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.12E-07 8.35E-10 1.13E-07 2.71E-01 0 0

EA-8 Uranium 9.69E-08 3.51E-07 1.42E-07 8.38E-08 4.35E-09 0 5.04E-07 2.86E-08 4.87E-09 3.27E-09 1.22E-06 2.93E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.42E-07 4.17E-10 1.43E-07 3.42E-01 0 0

EA-9 Uranium 1.86E-08 7.01E-08 1.51E-07 7.62E-08 5.60E-09 0 2.79E-07 4.29E-08 2.06E-09 1.97E-09 6.47E-07 1.55E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 5.99E-08 2.52E-10 6.02E-08 1.44E-01 0 0

EA-10 Uranium 1.68E-07 6.32E-07 8.40E-08 4.55E-08 2.49E-09 0 2.03E-06 1.15E-08 3.62E-09 2.84E-08 3.01E-06 7.23E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.05E-07 3.62E-09 1.09E-07 2.62E-01 0 0

EA-11 Uranium 1.04E-08 5.45E-08 2.90E-08 1.16E-08 1.12E-09 0 5.58E-07 5.33E-09 2.98E-09 7.74E-09 6.81E-07 1.63E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.87E-10 8.79E-08 2.11E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 68 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1968 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.90E-14 4.28E-07 6.48E-08 2.88E-08 1.10E-08 0 2.59E-06 4.33E-08 1.89E-09 2.62E-08 3.20E-06 7.67E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 1.80E-07 3.31E-09 1.83E-07 4.40E-01 0 0

EA-2 Uranium 1.62E-07 1.23E-06 3.33E-07 9.42E-08 1.38E-08 0 2.44E-06 5.61E-08 3.94E-09 5.90E-09 4.34E-06 1.04E+01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 3.76E-07 7.47E-10 3.77E-07 9.05E-01 0 0

EA-3 Uranium 8.09E-08 7.83E-07 6.70E-09 1.66E-11 3.50E-09 0 4.01E-06 4.64E-08 3.49E-09 4.92E-09 4.93E-06 1.18E+01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.34E-07 6.22E-10 3.34E-07 8.03E-01 0 0

EA-4 Uranium 8.62E-08 1.01E-10 4.57E-08 3.40E-08 1.73E-08 0 4.70E-10 3.97E-08 6.53E-11 6.91E-09 2.30E-07 5.53E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 6.24E-09 8.74E-10 7.11E-09 1.71E-02 0 0

EA-5 Uranium 5.97E-08 2.82E-07 6.24E-08 4.78E-09 2.11E-09 0 8.25E-07 1.17E-08 8.28E-10 2.33E-07 1.48E-06 3.55E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 7.91E-08 2.95E-08 1.09E-07 2.61E-01 0 0

EA-6 Uranium 5.86E-08 3.45E-07 9.84E-08 7.43E-09 1.41E-09 0 8.90E-07 9.52E-09 8.52E-10 4.12E-08 1.45E-06 3.48E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 8.14E-08 5.21E-09 8.66E-08 2.08E-01 0 0

EA-7 Uranium 5.86E-08 4.07E-07 7.74E-08 1.73E-08 1.27E-08 0 2.73E-06 4.43E-08 1.17E-09 7.23E-09 3.35E-06 8.05E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.12E-07 9.15E-10 1.13E-07 2.71E-01 0 0

EA-8 Uranium 8.57E-08 6.08E-07 1.36E-07 5.00E-08 1.19E-08 0 9.10E-07 4.33E-08 1.49E-09 3.61E-09 1.85E-06 4.44E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.42E-07 4.56E-10 1.43E-07 3.42E-01 0 0

EA-9 Uranium 1.65E-08 1.21E-07 1.44E-07 4.54E-08 1.53E-08 0 5.03E-07 6.49E-08 6.27E-10 2.18E-09 9.13E-07 2.19E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 5.99E-08 2.76E-10 6.02E-08 1.44E-01 0 0

EA-10 Uranium 1.49E-07 1.09E-06 8.02E-08 2.71E-08 6.78E-09 0 3.67E-06 1.74E-08 1.10E-09 3.14E-08 5.08E-06 1.22E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.05E-07 3.97E-09 1.09E-07 2.63E-01 0 0

EA-11 Uranium 9.16E-09 9.43E-08 2.77E-08 6.90E-09 3.05E-09 0 1.01E-06 8.06E-09 9.10E-10 8.55E-09 1.17E-06 2.80E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 1.08E-09 8.80E-08 2.11E-01 0 0

1969 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.95E-14 2.67E-07 1.24E-08 3.89E-08 2.76E-09 0 2.31E-06 4.84E-09 1.89E-09 3.39E-08 2.67E-06 6.41E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 6.77E-07 0 2.06E-07 3.32E-09 8.86E-07 2.13E+00 0 0

EA-2 Uranium 1.65E-07 7.65E-07 6.39E-08 1.27E-07 3.49E-09 0 2.18E-06 6.28E-09 3.94E-09 7.66E-09 3.32E-06 7.97E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 6.38E-07 0 4.31E-07 7.50E-10 1.07E-06 2.57E+00 0 0

EA-3 Uranium 8.23E-08 4.88E-07 1.29E-09 2.24E-11 8.83E-10 0 3.57E-06 5.19E-09 3.49E-09 6.38E-09 4.15E-06 9.97E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 1.05E-06 0 3.82E-07 6.25E-10 1.43E-06 3.43E+00 0 0

EA-4 Uranium 8.77E-08 6.32E-11 8.76E-09 4.60E-08 4.36E-09 0 4.19E-10 4.43E-09 6.53E-11 8.96E-09 1.61E-07 3.86E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 1.23E-10 0 7.15E-09 8.78E-10 8.15E-09 1.96E-02 0 0

EA-5 Uranium 6.07E-08 1.76E-07 1.20E-08 6.47E-09 5.31E-10 0 7.34E-07 1.31E-09 8.28E-10 3.02E-07 1.29E-06 3.11E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 2.15E-07 0 9.06E-08 2.96E-08 3.36E-07 8.05E-01 0 0

EA-6 Uranium 5.97E-08 2.15E-07 1.89E-08 1.01E-08 3.54E-10 0 7.92E-07 1.06E-09 8.52E-10 5.34E-08 1.15E-06 2.76E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 2.32E-07 0 9.32E-08 5.23E-09 3.31E-07 7.94E-01 0 0

EA-7 Uranium 5.97E-08 2.54E-07 1.48E-08 2.34E-08 3.20E-09 0 2.43E-06 4.95E-09 1.17E-09 9.38E-09 2.80E-06 6.72E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 7.12E-07 0 1.28E-07 9.19E-10 8.42E-07 2.02E+00 0 0

EA-8 Uranium 8.72E-08 3.79E-07 2.60E-08 6.76E-08 2.99E-09 0 8.10E-07 4.84E-09 1.49E-09 4.68E-09 1.38E-06 3.32E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 2.37E-07 0 1.63E-07 4.58E-10 4.01E-07 9.62E-01 0 0

EA-9 Uranium 1.68E-08 7.56E-08 2.77E-08 6.14E-08 3.85E-09 0 4.48E-07 7.26E-09 6.27E-10 2.83E-09 6.44E-07 1.54E+00 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 1.31E-07 0 6.86E-08 2.77E-10 2.00E-07 4.80E-01 0 0

EA-10 Uranium 1.52E-07 6.83E-07 1.54E-08 3.67E-08 1.71E-09 0 3.27E-06 1.95E-09 1.10E-09 4.07E-08 4.20E-06 1.01E+01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 9.58E-07 0 1.21E-07 3.99E-09 1.08E-06 2.60E+00 0 0

EA-11 Uranium 9.32E-09 5.88E-08 5.31E-09 9.34E-09 7.68E-10 0 8.97E-07 9.01E-10 9.10E-10 1.11E-08 9.93E-07 2.38E+00 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 2.63E-07 0 9.96E-08 1.09E-09 3.64E-07 8.73E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 69 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1970 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.08E-14 1.36E-07 7.58E-09 1.73E-08 1.64E-09 0 8.04E-07 5.02E-09 0 3.55E-08 1.01E-06 2.42E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 4.55E-07 0 2.61E-07 3.32E-09 7.19E-07 1.73E+00 0 0

EA-2 Uranium 1.17E-07 3.91E-07 3.89E-08 5.68E-08 2.07E-09 0 7.58E-07 6.52E-09 0 8.00E-09 1.38E-06 3.31E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 4.29E-07 0 5.46E-07 7.50E-10 9.75E-07 2.34E+00 0 0

EA-3 Uranium 5.81E-08 2.49E-07 7.84E-10 9.99E-12 5.25E-10 0 1.24E-06 5.39E-09 0 6.67E-09 1.56E-06 3.75E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 7.03E-07 0 4.84E-07 6.25E-10 1.19E-06 2.85E+00 0 0

EA-4 Uranium 6.19E-08 3.23E-11 5.34E-09 2.05E-08 2.59E-09 0 1.46E-10 4.60E-09 0 9.37E-09 1.04E-07 2.51E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 8.25E-11 0 9.05E-09 8.78E-10 1.00E-08 2.40E-02 0 0

EA-5 Uranium 4.29E-08 8.98E-08 7.29E-09 2.88E-09 3.16E-10 0 2.56E-07 1.36E-09 0 3.16E-07 7.16E-07 1.72E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 1.45E-07 0 1.15E-07 2.96E-08 2.89E-07 6.94E-01 0 0

EA-6 Uranium 4.21E-08 1.10E-07 1.15E-08 4.48E-09 2.11E-10 0 2.76E-07 1.11E-09 0 5.58E-08 5.01E-07 1.20E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 1.56E-07 0 1.18E-07 5.23E-09 2.79E-07 6.71E-01 0 0

EA-7 Uranium 4.21E-08 1.30E-07 9.05E-09 1.04E-08 1.90E-09 0 8.46E-07 5.14E-09 0 9.81E-09 1.05E-06 2.53E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 4.79E-07 0 1.63E-07 9.19E-10 6.42E-07 1.54E+00 0 0

EA-8 Uranium 6.15E-08 1.94E-07 1.59E-08 3.01E-08 1.78E-09 0 2.82E-07 5.02E-09 0 4.89E-09 5.95E-07 1.43E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 1.60E-07 0 2.06E-07 4.58E-10 3.66E-07 8.79E-01 0 0

EA-9 Uranium 1.18E-08 3.86E-08 1.69E-08 2.74E-08 2.29E-09 0 1.56E-07 7.53E-09 0 2.95E-09 2.63E-07 6.32E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 8.82E-08 0 8.69E-08 2.77E-10 1.75E-07 4.21E-01 0 0

EA-10 Uranium 1.07E-07 3.49E-07 9.37E-09 1.63E-08 1.02E-09 0 1.14E-06 2.02E-09 0 4.26E-08 1.67E-06 4.00E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 6.44E-07 0 1.53E-07 3.99E-09 8.01E-07 1.92E+00 0 0

EA-11 Uranium 6.58E-09 3.01E-08 3.24E-09 4.16E-09 4.56E-10 0 3.12E-07 9.35E-10 0 1.16E-08 3.69E-07 8.86E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 1.77E-07 0 1.26E-07 1.09E-09 3.04E-07 7.29E-01 0 0

1971 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.17E-14 1.17E-07 2.13E-10 3.25E-11 7.59E-10 0 4.11E-07 2.31E-10 0 3.47E-08 5.64E-07 1.35E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 2.80E-07 0 3.25E-08 3.32E-09 3.16E-07 7.57E-01 0 0

EA-2 Uranium 1.21E-07 3.35E-07 1.09E-09 1.07E-10 9.58E-10 0 3.88E-07 2.99E-10 0 7.84E-09 8.55E-07 2.05E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 2.64E-07 0 6.78E-08 7.50E-10 3.32E-07 7.98E-01 0 0

EA-3 Uranium 6.05E-08 2.14E-07 2.20E-11 1.88E-14 2.43E-10 0 6.36E-07 2.48E-10 0 6.53E-09 9.17E-07 2.20E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 4.32E-07 0 6.02E-08 6.25E-10 4.93E-07 1.18E+00 0 0

EA-4 Uranium 6.44E-08 2.77E-11 1.50E-10 3.84E-11 1.20E-09 0 7.46E-11 2.11E-10 0 9.18E-09 7.53E-08 1.81E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 5.08E-11 0 1.12E-09 8.78E-10 2.05E-09 4.93E-03 0 0

EA-5 Uranium 4.46E-08 7.70E-08 2.05E-10 5.41E-12 1.46E-10 0 1.31E-07 6.25E-11 0 3.09E-07 5.62E-07 1.35E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 8.90E-08 0 1.43E-08 2.96E-08 1.33E-07 3.19E-01 0 0

EA-6 Uranium 4.38E-08 9.41E-08 3.23E-10 8.41E-12 9.73E-11 0 1.41E-07 5.08E-11 0 5.47E-08 3.34E-07 8.02E-01 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 9.61E-08 0 1.47E-08 5.23E-09 1.16E-07 2.78E-01 0 0

EA-7 Uranium 4.38E-08 1.11E-07 2.54E-10 1.95E-11 8.78E-10 0 4.33E-07 2.36E-10 0 9.61E-09 5.99E-07 1.44E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 2.95E-07 0 2.02E-08 9.19E-10 3.16E-07 7.58E-01 0 0

EA-8 Uranium 6.41E-08 1.66E-07 4.45E-10 5.65E-11 8.22E-10 0 1.44E-07 2.31E-10 0 4.79E-09 3.81E-07 9.14E-01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 9.82E-08 0 2.56E-08 4.58E-10 1.24E-07 2.98E-01 0 0

EA-9 Uranium 1.23E-08 3.31E-08 4.74E-10 5.14E-11 1.06E-09 0 7.97E-08 3.46E-10 0 2.89E-09 1.30E-07 3.12E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 5.42E-08 0 1.08E-08 2.77E-10 6.53E-08 1.57E-01 0 0

EA-10 Uranium 1.11E-07 2.99E-07 2.63E-10 3.07E-11 4.69E-10 0 5.82E-07 9.28E-11 0 4.17E-08 1.04E-06 2.49E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 3.96E-07 0 1.90E-08 3.99E-09 4.19E-07 1.01E+00 0 0

EA-11 Uranium 6.85E-09 2.58E-08 9.09E-11 7.81E-12 2.11E-10 0 1.60E-07 4.30E-11 0 1.14E-08 2.04E-07 4.90E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 1.09E-07 0 1.57E-08 1.09E-09 1.25E-07 3.01E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 70 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1972 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.53E-14 5.20E-07 2.34E-09 1.08E-08 4.53E-10 0 3.28E-09 8.73E-09 0 3.34E-08 5.79E-07 1.39E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 7.38E-08 3.60E-09 7.74E-08 1.86E-01 0 0

EA-2 Uranium 1.42E-07 1.49E-06 1.20E-08 3.53E-08 5.71E-10 0 3.09E-09 1.13E-08 0 7.54E-09 1.70E-06 4.08E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 1.54E-07 8.11E-10 1.55E-07 3.72E-01 0 0

EA-3 Uranium 7.08E-08 9.51E-07 2.42E-10 6.21E-12 1.45E-10 0 5.07E-09 9.37E-09 0 6.28E-09 1.04E-06 2.50E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 1.37E-07 6.76E-10 1.38E-07 3.30E-01 0 0

EA-4 Uranium 7.54E-08 1.23E-10 1.65E-09 1.27E-08 7.14E-10 0 5.95E-13 8.00E-09 0 8.83E-09 1.07E-07 2.58E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 2.56E-09 9.50E-10 3.51E-09 8.42E-03 0 0

EA-5 Uranium 5.22E-08 3.42E-07 2.25E-09 1.79E-09 8.70E-11 0 1.04E-09 2.36E-09 0 2.98E-07 7.00E-07 1.68E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 3.24E-08 3.20E-08 6.45E-08 1.55E-01 0 0

EA-6 Uranium 5.13E-08 4.18E-07 3.56E-09 2.78E-09 5.80E-11 0 1.13E-09 1.92E-09 0 5.26E-08 5.32E-07 1.28E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 3.34E-08 5.66E-09 3.90E-08 9.36E-02 0 0

EA-7 Uranium 5.13E-08 4.94E-07 2.80E-09 6.47E-09 5.24E-10 0 3.45E-09 8.93E-09 0 9.24E-09 5.77E-07 1.38E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 4.60E-08 9.95E-10 4.70E-08 1.13E-01 0 0

EA-8 Uranium 7.50E-08 7.39E-07 4.90E-09 1.87E-08 4.90E-10 0 1.15E-09 8.73E-09 0 4.61E-09 8.52E-07 2.04E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 5.82E-08 4.96E-10 5.87E-08 1.41E-01 0 0

EA-9 Uranium 1.44E-08 1.47E-07 5.22E-09 1.70E-08 6.30E-10 0 6.36E-10 1.31E-08 0 2.78E-09 2.01E-07 4.83E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 2.46E-08 3.00E-10 2.49E-08 5.97E-02 0 0

EA-10 Uranium 1.30E-07 1.33E-06 2.90E-09 1.02E-08 2.80E-10 0 4.64E-09 3.51E-09 0 4.01E-08 1.52E-06 3.65E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 4.32E-08 4.32E-09 4.76E-08 1.14E-01 0 0

EA-11 Uranium 8.01E-09 1.15E-07 1.00E-09 2.59E-09 1.26E-10 0 1.27E-09 1.63E-09 0 1.09E-08 1.40E-07 3.36E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 3.56E-08 1.18E-09 3.68E-08 8.84E-02 0 0

1973 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.01E-14 5.34E-07 1.39E-08 2.57E-08 8.52E-10 0 3.45E-08 5.63E-09 0 3.28E-08 6.47E-07 1.55E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 2.62E-08 3.58E-09 2.98E-08 7.14E-02 0 0

EA-2 Uranium 1.13E-07 1.53E-06 7.15E-08 8.43E-08 1.08E-09 0 3.25E-08 7.31E-09 0 7.39E-09 1.85E-06 4.43E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 5.47E-08 8.08E-10 5.55E-08 1.33E-01 0 0

EA-3 Uranium 5.62E-08 9.76E-07 1.44E-09 1.48E-11 2.72E-10 0 5.33E-08 6.04E-09 0 6.16E-09 1.10E-06 2.64E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 4.85E-08 6.74E-10 4.92E-08 1.18E-01 0 0

EA-4 Uranium 5.99E-08 1.26E-10 9.81E-09 3.04E-08 1.34E-09 0 6.26E-12 5.16E-09 0 8.65E-09 1.15E-07 2.77E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 9.07E-10 9.46E-10 1.85E-09 4.45E-03 0 0

EA-5 Uranium 4.15E-08 3.51E-07 1.34E-08 4.28E-09 1.64E-10 0 1.10E-08 1.53E-09 0 2.92E-07 7.15E-07 1.72E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 1.15E-08 3.19E-08 4.34E-08 1.04E-01 0 0

EA-6 Uranium 4.08E-08 4.30E-07 2.11E-08 6.65E-09 1.09E-10 0 1.18E-08 1.24E-09 0 5.15E-08 5.63E-07 1.35E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 1.18E-08 5.64E-09 1.75E-08 4.19E-02 0 0

EA-7 Uranium 4.08E-08 5.08E-07 1.66E-08 1.55E-08 9.86E-10 0 3.63E-08 5.76E-09 0 9.06E-09 6.33E-07 1.52E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.63E-08 9.91E-10 1.73E-08 4.15E-02 0 0

EA-8 Uranium 5.96E-08 7.58E-07 2.91E-08 4.47E-08 9.22E-10 0 1.21E-08 5.63E-09 0 4.52E-09 9.15E-07 2.20E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 2.07E-08 4.94E-10 2.11E-08 5.08E-02 0 0

EA-9 Uranium 1.15E-08 1.51E-07 3.10E-08 4.06E-08 1.19E-09 0 6.69E-09 8.45E-09 0 2.73E-09 2.53E-07 6.08E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 8.71E-09 2.98E-10 9.01E-09 2.16E-02 0 0

EA-10 Uranium 1.04E-07 1.36E-06 1.72E-08 2.43E-08 5.27E-10 0 4.89E-08 2.26E-09 0 3.93E-08 1.60E-06 3.84E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.53E-08 4.30E-09 1.96E-08 4.71E-02 0 0

EA-11 Uranium 6.37E-09 1.18E-07 5.94E-09 6.18E-09 2.37E-10 0 1.34E-08 1.05E-09 0 1.07E-08 1.61E-07 3.88E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 1.26E-08 1.17E-09 1.38E-08 3.31E-02 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 71 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1974 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.02E-14 9.35E-07 6.03E-09 1.30E-08 4.75E-10 0 7.16E-09 1.38E-08 0 3.08E-08 1.01E-06 2.42E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 5.24E-08 3.73E-09 5.61E-08 1.35E-01 0 0

EA-2 Uranium 1.13E-07 2.68E-06 3.10E-08 4.27E-08 6.00E-10 0 6.75E-09 1.79E-08 0 6.94E-09 2.90E-06 6.96E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 1.09E-07 8.41E-10 1.10E-07 2.65E-01 0 0

EA-3 Uranium 5.65E-08 1.71E-06 6.23E-10 7.52E-12 1.52E-10 0 1.11E-08 1.48E-08 0 5.78E-09 1.80E-06 4.32E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 9.70E-08 7.01E-10 9.77E-08 2.35E-01 0 0

EA-4 Uranium 6.01E-08 2.21E-10 4.25E-09 1.54E-08 7.50E-10 0 1.30E-12 1.26E-08 0 8.13E-09 1.02E-07 2.44E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 1.81E-09 9.84E-10 2.80E-09 6.71E-03 0 0

EA-5 Uranium 4.16E-08 6.16E-07 5.80E-09 2.17E-09 9.14E-11 0 2.28E-09 3.73E-09 0 2.74E-07 9.45E-07 2.27E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 2.30E-08 3.32E-08 5.62E-08 1.35E-01 0 0

EA-6 Uranium 4.09E-08 7.52E-07 9.15E-09 3.37E-09 6.09E-11 0 2.46E-09 3.03E-09 0 4.84E-08 8.60E-07 2.06E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 2.37E-08 5.86E-09 2.95E-08 7.09E-02 0 0

EA-7 Uranium 4.09E-08 8.89E-07 7.19E-09 7.84E-09 5.50E-10 0 7.54E-09 1.41E-08 0 8.51E-09 9.76E-07 2.34E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 3.26E-08 1.03E-09 3.36E-08 8.07E-02 0 0

EA-8 Uranium 5.98E-08 1.33E-06 1.26E-08 2.27E-08 5.14E-10 0 2.51E-09 1.38E-08 0 4.24E-09 1.44E-06 3.47E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 4.13E-08 5.14E-10 4.18E-08 1.00E-01 0 0

EA-9 Uranium 1.15E-08 2.65E-07 1.34E-08 2.06E-08 6.61E-10 0 1.39E-09 2.07E-08 0 2.56E-09 3.36E-07 8.06E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 1.74E-08 3.10E-10 1.77E-08 4.26E-02 0 0

EA-10 Uranium 1.04E-07 2.39E-06 7.45E-09 1.23E-08 2.94E-10 0 1.01E-08 5.54E-09 0 3.69E-08 2.57E-06 6.16E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 3.07E-08 4.47E-09 3.51E-08 8.43E-02 0 0

EA-11 Uranium 6.39E-09 2.06E-07 2.57E-09 3.13E-09 1.32E-10 0 2.78E-09 2.56E-09 0 1.01E-08 2.34E-07 5.61E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 2.53E-08 1.22E-09 2.65E-08 6.36E-02 0 0

1975 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.10E-14 1.09E-06 2.89E-08 6.21E-09 3.51E-10 0 2.28E-09 2.41E-10 2.09E-10 3.96E-08 1.17E-06 2.80E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 1.57E-09 4.21E-09 5.79E-09 1.39E-02 0 0

EA-2 Uranium 1.18E-07 3.12E-06 1.49E-07 2.03E-08 4.44E-10 0 2.15E-09 3.13E-10 4.38E-10 8.94E-09 3.42E-06 8.20E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 3.28E-09 9.51E-10 4.23E-09 1.02E-02 0 0

EA-3 Uranium 5.87E-08 1.99E-06 2.99E-09 3.58E-12 1.12E-10 0 3.53E-09 2.59E-10 3.88E-10 7.45E-09 2.06E-06 4.95E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 2.91E-09 7.93E-10 3.70E-09 8.89E-03 0 0

EA-4 Uranium 6.25E-08 2.57E-10 2.04E-08 7.34E-09 5.55E-10 0 4.14E-13 2.21E-10 7.25E-12 1.05E-08 1.02E-07 2.44E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 5.44E-11 1.11E-09 1.17E-09 2.80E-03 0 0

EA-5 Uranium 4.33E-08 7.16E-07 2.78E-08 1.03E-09 6.76E-11 0 7.27E-10 6.54E-11 9.20E-11 3.53E-07 1.14E-06 2.74E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 6.90E-10 3.75E-08 3.82E-08 9.18E-02 0 0

EA-6 Uranium 4.25E-08 8.75E-07 4.39E-08 1.61E-09 4.51E-11 0 7.84E-10 5.31E-11 9.46E-11 6.23E-08 1.03E-06 2.46E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 7.10E-10 6.63E-09 7.34E-09 1.76E-02 0 0

EA-7 Uranium 4.25E-08 1.03E-06 3.45E-08 3.73E-09 4.07E-10 0 2.40E-09 2.47E-10 1.30E-10 1.10E-08 1.13E-06 2.71E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 9.78E-10 1.17E-09 2.14E-09 5.15E-03 0 0

EA-8 Uranium 6.21E-08 1.55E-06 6.05E-08 1.08E-08 3.80E-10 0 8.01E-10 2.41E-10 1.65E-10 5.46E-09 1.69E-06 4.05E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.24E-09 5.81E-10 1.82E-09 4.37E-03 0 0

EA-9 Uranium 1.20E-08 3.08E-07 6.44E-08 9.81E-09 4.89E-10 0 4.43E-10 3.62E-10 6.97E-11 3.30E-09 3.99E-07 9.58E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 5.23E-10 3.51E-10 8.74E-10 2.10E-03 0 0

EA-10 Uranium 1.08E-07 2.78E-06 3.58E-08 5.86E-09 2.17E-10 0 3.23E-09 9.70E-11 1.23E-10 4.75E-08 2.98E-06 7.16E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 9.20E-10 5.06E-09 5.98E-09 1.43E-02 0 0

EA-11 Uranium 6.64E-09 2.40E-07 1.23E-08 1.49E-09 9.76E-11 0 8.87E-10 4.49E-11 1.01E-10 1.29E-08 2.74E-07 6.58E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 7.58E-10 1.38E-09 2.14E-09 5.13E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 72 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1976 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.05E-14 1.28E-06 6.43E-09 4.49E-09 1.17E-09 0 4.70E-09 1.20E-09 0 4.45E-08 1.34E-06 3.22E+00 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 0 5.24E-09 5.24E-09 1.26E-02 0 0

EA-2 Uranium 1.15E-07 3.66E-06 3.31E-08 1.47E-08 1.48E-09 0 4.43E-09 1.55E-09 0 1.00E-08 3.84E-06 9.22E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.18E-09 1.18E-09 2.84E-03 0 0

EA-3 Uranium 5.71E-08 2.34E-06 6.65E-10 2.59E-12 3.75E-10 0 7.26E-09 1.28E-09 0 8.36E-09 2.41E-06 5.79E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 0 9.85E-10 9.85E-10 2.36E-03 0 0

EA-4 Uranium 6.09E-08 3.02E-10 4.53E-09 5.31E-09 1.85E-09 0 8.52E-13 1.10E-09 0 1.18E-08 8.57E-08 2.06E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 0 1.38E-09 1.38E-09 3.32E-03 0 0

EA-5 Uranium 4.21E-08 8.41E-07 6.19E-09 7.46E-10 2.25E-10 0 1.49E-09 3.24E-10 0 3.96E-07 1.29E-06 3.09E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 0 4.66E-08 4.66E-08 1.12E-01 0 0

EA-6 Uranium 4.14E-08 1.03E-06 9.77E-09 1.16E-09 1.50E-10 0 1.61E-09 2.63E-10 0 7.00E-08 1.15E-06 2.76E+00 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 0 8.24E-09 8.24E-09 1.98E-02 0 0

EA-7 Uranium 4.14E-08 1.21E-06 7.68E-09 2.70E-09 1.36E-09 0 4.95E-09 1.22E-09 0 1.23E-08 1.29E-06 3.09E+00 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 0 1.45E-09 1.45E-09 3.48E-03 0 0

EA-8 Uranium 6.05E-08 1.81E-06 1.35E-08 7.80E-09 1.27E-09 0 1.65E-09 1.20E-09 0 6.13E-09 1.91E-06 4.58E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 0 7.22E-10 7.22E-10 1.73E-03 0 0

EA-9 Uranium 1.16E-08 3.62E-07 1.43E-08 7.09E-09 1.63E-09 0 9.11E-10 1.79E-09 0 3.71E-09 4.03E-07 9.67E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 0 4.36E-10 4.36E-10 1.05E-03 0 0

EA-10 Uranium 1.05E-07 3.26E-06 7.96E-09 4.23E-09 7.25E-10 0 6.65E-09 4.81E-10 0 5.34E-08 3.44E-06 8.26E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 0 6.28E-09 6.28E-09 1.51E-02 0 0

EA-11 Uranium 6.47E-09 2.81E-07 2.75E-09 1.08E-09 3.26E-10 0 1.82E-09 2.23E-10 0 1.45E-08 3.09E-07 7.41E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 0 1.71E-09 1.71E-09 4.11E-03 0 0

1977 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.01E-14 2.89E-07 3.11E-08 1.74E-08 5.31E-10 0 3.08E-09 2.16E-10 5.45E-09 4.49E-08 3.92E-07 9.41E-01 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 2.14E-07 4.82E-09 2.18E-07 5.24E-01 0 0

EA-2 Uranium 1.12E-07 8.29E-07 1.60E-07 5.69E-08 6.71E-10 0 2.90E-09 2.81E-10 1.14E-08 1.01E-08 1.18E-06 2.84E+00 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 4.46E-07 1.09E-09 4.48E-07 1.07E+00 0 0

EA-3 Uranium 5.60E-08 5.29E-07 3.21E-09 1.00E-11 1.70E-10 0 4.76E-09 2.32E-10 1.01E-08 8.45E-09 6.12E-07 1.47E+00 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.96E-07 9.06E-10 3.97E-07 9.52E-01 0 0

EA-4 Uranium 5.97E-08 6.84E-11 2.19E-08 2.05E-08 8.38E-10 0 5.58E-13 1.98E-10 1.89E-10 1.19E-08 1.15E-07 2.77E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 7.40E-09 1.27E-09 8.67E-09 2.08E-02 0 0

EA-5 Uranium 4.13E-08 1.90E-07 2.99E-08 2.89E-09 1.02E-10 0 9.79E-10 5.86E-11 2.39E-09 4.00E-07 6.68E-07 1.60E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 9.38E-08 4.29E-08 1.37E-07 3.28E-01 0 0

EA-6 Uranium 4.06E-08 2.33E-07 4.72E-08 4.49E-09 6.81E-11 0 1.06E-09 4.76E-11 2.46E-09 7.07E-08 3.99E-07 9.58E-01 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 9.65E-08 7.58E-09 1.04E-07 2.50E-01 0 0

EA-7 Uranium 4.06E-08 2.75E-07 3.71E-08 1.04E-08 6.15E-10 0 3.24E-09 2.21E-10 3.39E-09 1.24E-08 3.83E-07 9.19E-01 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.33E-07 1.33E-09 1.34E-07 3.23E-01 0 0

EA-8 Uranium 5.93E-08 4.11E-07 6.50E-08 3.02E-08 5.75E-10 0 1.08E-09 2.16E-10 4.30E-09 6.19E-09 5.78E-07 1.39E+00 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.69E-07 6.65E-10 1.69E-07 4.06E-01 0 0

EA-9 Uranium 1.14E-08 8.19E-08 6.92E-08 2.74E-08 7.40E-10 0 5.97E-10 3.25E-10 1.81E-09 3.74E-09 1.97E-07 4.73E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 7.11E-08 4.01E-10 7.15E-08 1.72E-01 0 0

EA-10 Uranium 1.03E-07 7.39E-07 3.84E-08 1.64E-08 3.29E-10 0 4.36E-09 8.71E-11 3.19E-09 5.39E-08 9.59E-07 2.30E+00 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.25E-07 5.78E-09 1.31E-07 3.14E-01 0 0

EA-11 Uranium 6.34E-09 6.37E-08 1.33E-08 4.17E-09 1.48E-10 0 1.20E-09 4.03E-11 2.63E-09 1.47E-08 1.06E-07 2.55E-01 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.58E-09 1.05E-07 2.51E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 73 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1978 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.03E-14 0 3.18E-09 9.50E-09 5.40E-10 0 2.60E-11 2.58E-08 1.15E-09 4.82E-08 8.84E-08 2.12E-01 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 2.14E-07 5.67E-09 2.19E-07 5.26E-01 0 0

EA-2 Uranium 1.14E-07 0 1.63E-08 3.11E-08 6.81E-10 0 2.45E-11 3.34E-08 2.41E-09 1.09E-08 2.09E-07 5.01E-01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 4.46E-07 1.28E-09 4.48E-07 1.07E+00 0 0

EA-3 Uranium 5.67E-08 0 3.29E-10 5.48E-12 1.73E-10 0 4.02E-11 2.76E-08 2.14E-09 9.07E-09 9.61E-08 2.31E-01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.96E-07 1.07E-09 3.97E-07 9.53E-01 0 0

EA-4 Uranium 6.04E-08 0 2.24E-09 1.12E-08 8.52E-10 0 4.72E-15 2.36E-08 3.99E-11 1.27E-08 1.11E-07 2.67E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 7.40E-09 1.50E-09 8.90E-09 2.14E-02 0 0

EA-5 Uranium 4.18E-08 0 3.06E-09 1.58E-09 1.04E-10 0 8.28E-12 6.98E-09 5.06E-10 4.30E-07 4.84E-07 1.16E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 9.38E-08 5.05E-08 1.44E-07 3.46E-01 0 0

EA-6 Uranium 4.11E-08 0 4.83E-09 2.46E-09 6.92E-11 0 8.94E-12 5.67E-09 5.20E-10 7.59E-08 1.31E-07 3.13E-01 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 9.65E-08 8.92E-09 1.05E-07 2.53E-01 0 0

EA-7 Uranium 4.11E-08 0 3.80E-09 5.71E-09 6.25E-10 0 2.74E-11 2.64E-08 7.17E-10 1.33E-08 9.16E-08 2.20E-01 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.33E-07 1.57E-09 1.35E-07 3.23E-01 0 0

EA-8 Uranium 6.00E-08 0 6.65E-09 1.65E-08 5.84E-10 0 9.13E-12 2.58E-08 9.09E-10 6.65E-09 1.17E-07 2.81E-01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.69E-07 7.82E-10 1.69E-07 4.06E-01 0 0

EA-9 Uranium 1.15E-08 0 7.08E-09 1.50E-08 7.51E-10 0 5.05E-12 3.86E-08 3.83E-10 4.02E-09 7.74E-08 1.86E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 7.11E-08 4.72E-10 7.16E-08 1.72E-01 0 0

EA-10 Uranium 1.04E-07 0 3.93E-09 8.95E-09 3.34E-10 0 3.69E-11 1.04E-08 6.75E-10 5.79E-08 1.87E-07 4.48E-01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.25E-07 6.80E-09 1.32E-07 3.17E-01 0 0

EA-11 Uranium 6.42E-09 0 1.36E-09 2.28E-09 1.50E-10 0 1.01E-11 4.80E-09 5.56E-10 1.58E-08 3.13E-08 7.52E-02 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.85E-09 1.05E-07 2.52E-01 0 0

1979 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 1.78E-14 0 1.13E-08 4.03E-09 4.22E-10 0 3.90E-11 1.01E-09 0 6.77E-08 8.45E-08 2.03E-01 1.03E-08 1.03E+01

Thorium 0 0 0 0 0 0 0 0 2.14E-07 5.94E-09 2.20E-07 5.27E-01 0 0

EA-2 Uranium 9.99E-08 0 5.80E-08 1.32E-08 5.32E-10 0 3.68E-11 1.31E-09 0 1.53E-08 1.88E-07 4.52E-01 5.33E-09 5.33E+00

Thorium 0 0 0 0 0 0 0 0 4.46E-07 1.34E-09 4.48E-07 1.07E+00 0 0

EA-3 Uranium 4.98E-08 0 1.17E-09 2.33E-12 1.35E-10 0 6.03E-11 1.08E-09 0 1.27E-08 6.49E-08 1.56E-01 4.79E-09 4.79E+00

Thorium 0 0 0 0 0 0 0 0 3.96E-07 1.12E-09 3.97E-07 9.53E-01 0 0

EA-4 Uranium 5.30E-08 0 7.96E-09 4.77E-09 6.65E-10 0 7.08E-15 9.24E-10 0 1.79E-08 8.52E-08 2.05E-01 1.32E-08 1.32E+01

Thorium 0 0 0 0 0 0 0 0 7.40E-09 1.57E-09 8.97E-09 2.15E-02 0 0

EA-5 Uranium 3.67E-08 0 1.09E-08 6.70E-10 8.11E-11 0 1.24E-11 2.73E-10 0 6.03E-07 6.51E-07 1.56E+00 1.20E-08 1.20E+01

Thorium 0 0 0 0 0 0 0 0 9.38E-08 5.29E-08 1.47E-07 3.52E-01 0 0

EA-6 Uranium 3.61E-08 0 1.71E-08 1.04E-09 5.41E-11 0 1.34E-11 2.22E-10 0 1.06E-07 1.61E-07 3.86E-01 3.94E-09 3.94E+00

Thorium 0 0 0 0 0 0 0 0 9.65E-08 9.35E-09 1.06E-07 2.54E-01 0 0

EA-7 Uranium 3.61E-08 0 1.35E-08 2.42E-09 4.88E-10 0 4.11E-11 1.03E-09 0 1.87E-08 7.22E-08 1.73E-01 6.01E-09 6.01E+00

Thorium 0 0 0 0 0 0 0 0 1.33E-07 1.64E-09 1.35E-07 3.23E-01 0 0

EA-8 Uranium 5.27E-08 0 2.36E-08 7.01E-09 4.57E-10 0 1.37E-11 1.01E-09 0 9.33E-09 9.41E-08 2.26E-01 3.99E-09 3.99E+00

Thorium 0 0 0 0 0 0 0 0 1.69E-07 8.19E-10 1.69E-07 4.06E-01 0 0

EA-9 Uranium 1.01E-08 0 2.51E-08 6.37E-09 5.87E-10 0 7.57E-12 1.51E-09 0 5.64E-09 4.94E-08 1.19E-01 2.00E-09 2.00E+00

Thorium 0 0 0 0 0 0 0 0 7.11E-08 4.95E-10 7.16E-08 1.72E-01 0 0

EA-10 Uranium 9.17E-08 0 1.40E-08 3.80E-09 2.61E-10 0 5.53E-11 4.05E-10 0 8.12E-08 1.91E-07 4.59E-01 6.13E-09 6.13E+00

Thorium 0 0 0 0 0 0 0 0 1.25E-07 7.13E-09 1.32E-07 3.17E-01 0 0

EA-11 Uranium 5.63E-09 0 4.82E-09 9.68E-10 1.17E-10 0 1.52E-11 1.88E-10 0 2.21E-08 3.39E-08 8.13E-02 4.22E-09 4.22E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.94E-09 1.05E-07 2.52E-01 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 74 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1980 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 4.43E-15 1.03E-09 3.24E-08 2.91E-08 4.61E-10 0 1.05E-08 1.92E-10 1.73E-09 7.53E-08 1.51E-07 3.62E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 2.37E-08 2.37E-08 5.70E-02 0 0

EA-2 Uranium 2.48E-08 2.95E-09 1.66E-07 9.55E-08 5.82E-10 0 9.90E-09 2.49E-10 3.61E-09 1.70E-08 3.21E-07 7.70E-01 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 5.36E-09 5.36E-09 1.29E-02 0 0

EA-3 Uranium 1.24E-08 1.88E-09 3.35E-09 1.68E-11 1.47E-10 0 1.62E-08 2.06E-10 3.20E-09 1.42E-08 5.16E-08 1.24E-01 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 4.46E-09 4.46E-09 1.07E-02 0 0

EA-4 Uranium 1.32E-08 2.44E-13 2.28E-08 3.44E-08 7.28E-10 0 1.91E-12 1.76E-10 5.98E-11 1.99E-08 9.13E-08 2.19E-01 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 6.27E-09 6.27E-09 1.50E-02 0 0

EA-5 Uranium 9.12E-09 6.79E-10 3.11E-08 4.84E-09 8.87E-11 0 3.34E-09 5.19E-11 7.59E-10 6.71E-07 7.21E-07 1.73E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 2.11E-07 2.11E-07 5.07E-01 0 0

EA-6 Uranium 8.96E-09 8.29E-10 4.92E-08 7.54E-09 5.91E-11 0 3.61E-09 4.22E-11 7.81E-10 1.19E-07 1.90E-07 4.55E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 3.74E-08 3.74E-08 8.96E-02 0 0

EA-7 Uranium 8.96E-09 9.80E-10 3.86E-08 1.75E-08 5.34E-10 0 1.11E-08 1.96E-10 1.08E-09 2.08E-08 9.98E-08 2.40E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 6.56E-09 6.56E-09 1.58E-02 0 0

EA-8 Uranium 1.31E-08 1.46E-09 6.77E-08 5.07E-08 4.99E-10 0 3.69E-09 1.92E-10 1.36E-09 1.04E-08 1.49E-07 3.58E-01 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 3.27E-09 3.27E-09 7.86E-03 0 0

EA-9 Uranium 2.52E-09 2.92E-10 7.21E-08 4.60E-08 6.42E-10 0 2.04E-09 2.87E-10 5.75E-10 6.27E-09 1.31E-07 3.14E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 1.98E-09 1.98E-09 4.74E-03 0 0

EA-10 Uranium 2.28E-08 2.64E-09 4.00E-08 2.75E-08 2.85E-10 0 1.49E-08 7.71E-11 1.01E-09 9.04E-08 2.00E-07 4.79E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 2.85E-08 2.85E-08 6.84E-02 0 0

EA-11 Uranium 1.40E-09 2.27E-10 1.38E-08 7.00E-09 1.28E-10 0 4.08E-09 3.57E-11 8.34E-10 2.46E-08 5.22E-08 1.25E-01 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 7.76E-09 7.76E-09 1.86E-02 0 0

1981 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 1.80E-15 1.15E-08 1.02E-07 4.41E-08 5.90E-10 0 6.51E-09 2.66E-10 0 9.29E-08 2.57E-07 6.18E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.94E-09 5.94E-09 1.43E-02 0 0

EA-2 Uranium 1.01E-08 3.29E-08 5.22E-07 1.45E-07 7.45E-10 0 6.14E-09 3.45E-10 0 2.10E-08 7.38E-07 1.77E+00 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.22E-03 0 0

EA-3 Uranium 5.04E-09 2.10E-08 1.05E-08 2.54E-11 1.89E-10 0 1.01E-08 2.86E-10 0 1.75E-08 6.46E-08 1.55E-01 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.12E-09 1.12E-09 2.68E-03 0 0

EA-4 Uranium 5.37E-09 2.72E-12 7.16E-08 5.22E-08 9.32E-10 0 1.18E-12 2.44E-10 0 2.45E-08 1.55E-07 3.72E-01 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.77E-03 0 0

EA-5 Uranium 3.72E-09 7.56E-09 9.77E-08 7.34E-09 1.14E-10 0 2.07E-09 7.21E-11 0 8.27E-07 9.46E-07 2.27E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.29E-08 5.29E-08 1.27E-01 0 0

EA-6 Uranium 3.65E-09 9.25E-09 1.54E-07 1.14E-08 7.57E-11 0 2.24E-09 5.86E-11 0 1.46E-07 3.27E-07 7.85E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.35E-09 9.35E-09 2.24E-02 0 0

EA-7 Uranium 3.65E-09 1.09E-08 1.21E-07 2.65E-08 6.83E-10 0 6.86E-09 2.72E-10 0 2.57E-08 1.96E-07 4.70E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.94E-03 0 0

EA-8 Uranium 5.34E-09 1.63E-08 2.12E-07 7.67E-08 6.39E-10 0 2.29E-09 2.66E-10 0 1.28E-08 3.27E-07 7.84E-01 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.19E-10 8.19E-10 1.97E-03 0 0

EA-9 Uranium 1.03E-09 3.25E-09 2.26E-07 6.97E-08 8.22E-10 0 1.26E-09 3.99E-10 0 7.73E-09 3.10E-07 7.45E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.95E-10 4.95E-10 1.19E-03 0 0

EA-10 Uranium 9.29E-09 2.94E-08 1.26E-07 4.16E-08 3.65E-10 0 9.22E-09 1.07E-10 0 1.11E-07 3.27E-07 7.85E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.13E-09 7.13E-09 1.71E-02 0 0

EA-11 Uranium 5.71E-10 2.53E-09 4.34E-08 1.06E-08 1.64E-10 0 2.53E-09 4.96E-11 0 3.04E-08 9.02E-08 2.16E-01 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.66E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 75 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1982 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.07E-15 2.00E-08 5.66E-09 3.97E-08 1.10E-09 0 7.70E-08 2.21E-09 0 9.10E-08 2.37E-07 5.68E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.93E-09 5.93E-09 1.42E-02 0 0

EA-2 Uranium 1.16E-08 5.73E-08 2.91E-08 1.30E-07 1.39E-09 0 7.26E-08 2.87E-09 0 2.05E-08 3.25E-07 7.81E-01 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.21E-03 0 0

EA-3 Uranium 5.78E-09 3.66E-08 5.86E-10 2.29E-11 3.51E-10 0 1.19E-07 2.37E-09 0 1.71E-08 1.82E-07 4.36E-01 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.11E-09 1.11E-09 2.67E-03 0 0

EA-4 Uranium 6.16E-09 4.73E-12 3.99E-09 4.69E-08 1.73E-09 0 1.40E-11 2.03E-09 0 2.40E-08 8.49E-08 2.04E-01 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.76E-03 0 0

EA-5 Uranium 4.27E-09 1.32E-08 5.45E-09 6.60E-09 2.11E-10 0 2.45E-08 5.99E-10 0 8.11E-07 8.65E-07 2.08E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.28E-08 5.28E-08 1.27E-01 0 0

EA-6 Uranium 4.19E-09 1.61E-08 8.60E-09 1.03E-08 1.41E-10 0 2.64E-08 4.87E-10 0 1.43E-07 2.09E-07 5.03E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.33E-09 9.33E-09 2.24E-02 0 0

EA-7 Uranium 4.19E-09 1.90E-08 6.76E-09 2.38E-08 1.27E-09 0 8.11E-08 2.26E-09 0 2.52E-08 1.64E-07 3.93E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.93E-03 0 0

EA-8 Uranium 6.12E-09 2.84E-08 1.18E-08 6.90E-08 1.19E-09 0 2.70E-08 2.21E-09 0 1.25E-08 1.58E-07 3.80E-01 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.17E-10 8.17E-10 1.96E-03 0 0

EA-9 Uranium 1.18E-09 5.67E-09 1.26E-08 6.27E-08 1.53E-09 0 1.49E-08 3.32E-09 0 7.58E-09 1.09E-07 2.63E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.94E-10 4.94E-10 1.18E-03 0 0

EA-10 Uranium 1.07E-08 5.11E-08 7.00E-09 3.74E-08 6.80E-10 0 1.09E-07 8.89E-10 0 1.09E-07 3.26E-07 7.82E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-09 7.11E-09 1.71E-02 0 0

EA-11 Uranium 6.55E-10 4.41E-09 2.42E-09 9.53E-09 3.05E-10 0 2.99E-08 4.12E-10 0 2.97E-08 7.74E-08 1.86E-01 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0

1983 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 2.70E-15 4.98E-08 1.10E-08 1.35E-08 1.09E-09 0 5.39E-08 5.07E-10 0 8.96E-08 2.19E-07 5.26E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.93E-09 5.93E-09 1.42E-02 0 0

EA-2 Uranium 1.51E-08 1.43E-07 5.63E-08 4.43E-08 1.37E-09 0 5.08E-08 6.59E-10 0 2.02E-08 3.31E-07 7.95E-01 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.21E-03 0 0

EA-3 Uranium 7.53E-09 9.10E-08 1.13E-09 7.80E-12 3.48E-10 0 8.33E-08 5.45E-10 0 1.68E-08 2.01E-07 4.82E-01 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.11E-09 1.11E-09 2.67E-03 0 0

EA-4 Uranium 8.03E-09 1.18E-11 7.72E-09 1.60E-08 1.72E-09 0 9.78E-12 4.65E-10 0 2.37E-08 5.76E-08 1.38E-01 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.76E-03 0 0

EA-5 Uranium 5.56E-09 3.27E-08 1.05E-08 2.25E-09 2.09E-10 0 1.71E-08 1.37E-10 0 7.98E-07 8.67E-07 2.08E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.28E-08 5.28E-08 1.27E-01 0 0

EA-6 Uranium 5.46E-09 4.00E-08 1.66E-08 3.50E-09 1.39E-10 0 1.85E-08 1.12E-10 0 1.41E-07 2.25E-07 5.41E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.33E-09 9.33E-09 2.24E-02 0 0

EA-7 Uranium 5.46E-09 4.73E-08 1.31E-08 8.13E-09 1.26E-09 0 5.67E-08 5.19E-10 0 2.48E-08 1.57E-07 3.77E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.93E-03 0 0

EA-8 Uranium 7.98E-09 7.07E-08 2.29E-08 2.35E-08 1.18E-09 0 1.89E-08 5.07E-10 0 1.24E-08 1.58E-07 3.79E-01 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.17E-10 8.17E-10 1.96E-03 0 0

EA-9 Uranium 1.54E-09 1.41E-08 2.44E-08 2.14E-08 1.51E-09 0 1.04E-08 7.61E-10 0 7.46E-09 8.16E-08 1.96E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.94E-10 4.94E-10 1.18E-03 0 0

EA-10 Uranium 1.39E-08 1.27E-07 1.35E-08 1.28E-08 6.73E-10 0 7.63E-08 2.04E-10 0 1.08E-07 3.52E-07 8.45E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-09 7.11E-09 1.71E-02 0 0

EA-11 Uranium 8.53E-10 1.10E-08 4.68E-09 3.25E-09 3.02E-10 0 2.09E-08 9.45E-11 0 2.93E-08 7.04E-08 1.69E-01 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 76 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1984 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 5.49E-15 2.19E-07 1.05E-08 2.74E-08 1.42E-09 0 3.01E-08 6.08E-08 1.47E-09 8.96E-08 4.41E-07 1.06E+00 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.93E-09 5.93E-09 1.42E-02 0 0

EA-2 Uranium 3.08E-08 6.29E-07 5.40E-08 8.96E-08 1.79E-09 0 2.83E-08 7.89E-08 3.06E-09 2.02E-08 9.35E-07 2.24E+00 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.21E-03 0 0

EA-3 Uranium 1.53E-08 4.01E-07 1.09E-09 1.58E-11 4.54E-10 0 4.64E-08 6.53E-08 2.72E-09 1.68E-08 5.49E-07 1.32E+00 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.11E-09 1.11E-09 2.67E-03 0 0

EA-4 Uranium 1.63E-08 5.19E-11 7.40E-09 3.23E-08 2.24E-09 0 5.45E-12 5.58E-08 5.08E-11 2.37E-08 1.38E-07 3.31E-01 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.76E-03 0 0

EA-5 Uranium 1.13E-08 1.44E-07 1.01E-08 4.55E-09 2.73E-10 0 9.56E-09 1.65E-08 6.44E-10 7.98E-07 9.95E-07 2.39E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.28E-08 5.28E-08 1.27E-01 0 0

EA-6 Uranium 1.11E-08 1.76E-07 1.59E-08 7.07E-09 1.82E-10 0 1.03E-08 1.34E-08 6.62E-10 1.41E-07 3.76E-07 9.03E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.33E-09 9.33E-09 2.24E-02 0 0

EA-7 Uranium 1.11E-08 2.09E-07 1.25E-08 1.64E-08 1.64E-09 0 3.16E-08 6.22E-08 9.13E-10 2.48E-08 3.70E-07 8.88E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.93E-03 0 0

EA-8 Uranium 1.62E-08 3.12E-07 2.20E-08 4.75E-08 1.54E-09 0 1.05E-08 6.08E-08 1.16E-09 1.24E-08 4.84E-07 1.16E+00 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.17E-10 8.17E-10 1.96E-03 0 0

EA-9 Uranium 3.13E-09 6.21E-08 2.34E-08 4.32E-08 1.98E-09 0 5.83E-09 9.12E-08 4.88E-10 7.46E-09 2.39E-07 5.73E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.94E-10 4.94E-10 1.18E-03 0 0

EA-10 Uranium 2.82E-08 5.61E-07 1.30E-08 2.58E-08 8.78E-10 0 4.26E-08 2.45E-08 8.59E-10 1.08E-07 8.04E-07 1.93E+00 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-09 7.11E-09 1.71E-02 0 0

EA-11 Uranium 1.74E-09 4.83E-08 4.49E-09 6.57E-09 3.94E-10 0 1.17E-08 1.13E-08 7.08E-10 2.93E-08 1.15E-07 2.75E-01 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0

1985 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 4.97E-08 7.96E-10 7.16E-11 9.61E-10 0 3.90E-11 3.97E-10 0 8.96E-08 1.42E-07 3.40E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.93E-09 5.93E-09 1.42E-02 0 0

EA-2 Uranium 0 1.42E-07 4.09E-09 2.34E-10 1.21E-09 0 3.68E-11 5.16E-10 0 2.02E-08 1.69E-07 4.05E-01 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.21E-03 0 0

EA-3 Uranium 0 9.08E-08 8.24E-11 4.13E-14 3.07E-10 0 6.03E-11 4.27E-10 0 1.68E-08 1.09E-07 2.61E-01 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.11E-09 1.11E-09 2.67E-03 0 0

EA-4 Uranium 0 1.17E-11 5.61E-10 8.46E-11 1.52E-09 0 7.08E-15 3.64E-10 0 2.37E-08 2.62E-08 6.29E-02 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.76E-03 0 0

EA-5 Uranium 0 3.27E-08 7.66E-10 1.19E-11 1.85E-10 0 1.24E-11 1.08E-10 0 7.98E-07 8.32E-07 2.00E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.28E-08 5.28E-08 1.27E-01 0 0

EA-6 Uranium 0 4.00E-08 1.21E-09 1.85E-11 1.23E-10 0 1.34E-11 8.75E-11 0 1.41E-07 1.82E-07 4.38E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.33E-09 9.33E-09 2.24E-02 0 0

EA-7 Uranium 0 4.72E-08 9.50E-10 4.30E-11 1.11E-09 0 4.11E-11 4.07E-10 0 2.48E-08 7.46E-08 1.79E-01 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.93E-03 0 0

EA-8 Uranium 0 7.06E-08 1.67E-09 1.24E-10 1.04E-09 0 1.37E-11 3.97E-10 0 1.24E-08 8.62E-08 2.07E-01 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.17E-10 8.17E-10 1.96E-03 0 0

EA-9 Uranium 0 1.41E-08 1.77E-09 1.13E-10 1.34E-09 0 7.57E-12 5.96E-10 0 7.46E-09 2.54E-08 6.09E-02 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.94E-10 4.94E-10 1.18E-03 0 0

EA-10 Uranium 0 1.27E-07 9.85E-10 6.75E-11 5.95E-10 0 5.53E-11 1.60E-10 0 1.08E-07 2.36E-07 5.67E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-09 7.11E-09 1.71E-02 0 0

EA-11 Uranium 0 1.09E-08 3.40E-10 1.72E-11 2.67E-10 0 1.52E-11 7.40E-11 0 2.93E-08 4.09E-08 9.83E-02 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 77 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1986 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 8.97E-10 7.81E-11 1.06E-09 0 3.90E-11 5.18E-10 0 8.96E-08 9.22E-08 2.21E-01 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 5.93E-09 5.93E-09 1.42E-02 0 0

EA-2 Uranium 0 0 4.61E-09 2.56E-10 1.34E-09 0 3.68E-11 6.72E-10 0 2.02E-08 2.71E-08 6.51E-02 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 1.34E-09 1.34E-09 3.21E-03 0 0

EA-3 Uranium 0 0 9.27E-11 4.50E-14 3.39E-10 0 6.03E-11 5.56E-10 0 1.68E-08 1.79E-08 4.30E-02 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 1.11E-09 1.11E-09 2.67E-03 0 0

EA-4 Uranium 0 0 6.32E-10 9.23E-11 1.67E-09 0 7.08E-15 4.75E-10 0 2.37E-08 2.65E-08 6.37E-02 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 1.57E-09 1.57E-09 3.76E-03 0 0

EA-5 Uranium 0 0 8.62E-10 1.30E-11 2.04E-10 0 1.24E-11 1.40E-10 0 7.98E-07 7.99E-07 1.92E+00 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 5.28E-08 5.28E-08 1.27E-01 0 0

EA-6 Uranium 0 0 1.36E-09 2.02E-11 1.36E-10 0 1.34E-11 1.14E-10 0 1.41E-07 1.43E-07 3.42E-01 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 9.33E-09 9.33E-09 2.24E-02 0 0

EA-7 Uranium 0 0 1.07E-09 4.69E-11 1.23E-09 0 4.11E-11 5.30E-10 0 2.48E-08 2.77E-08 6.65E-02 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 3.93E-03 0 0

EA-8 Uranium 0 0 1.88E-09 1.36E-10 1.15E-09 0 1.37E-11 5.18E-10 0 1.24E-08 1.60E-08 3.85E-02 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 8.17E-10 8.17E-10 1.96E-03 0 0

EA-9 Uranium 0 0 2.00E-09 1.23E-10 1.48E-09 0 7.57E-12 7.77E-10 0 7.46E-09 1.18E-08 2.84E-02 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 4.94E-10 4.94E-10 1.18E-03 0 0

EA-10 Uranium 0 0 1.11E-09 7.36E-11 6.55E-10 0 5.53E-11 2.08E-10 0 1.08E-07 1.10E-07 2.63E-01 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 7.11E-09 7.11E-09 1.71E-02 0 0

EA-11 Uranium 0 0 3.83E-10 1.87E-11 2.94E-10 0 1.52E-11 9.65E-11 0 2.93E-08 3.01E-08 7.22E-02 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0

1987 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 7.64E-08 7.87E-10 5.86E-11 5.88E-10 0 2.41E-10 1.28E-10 0 9.09E-08 1.69E-07 2.06E-09 2.06E+00

Thorium 0 0 0 0 0 0 0 0 0 0 6.20E-09 6.20E-09 0 0

EA-2 Uranium 0 0 2.19E-07 4.04E-09 1.92E-10 7.42E-10 0 2.27E-10 1.66E-10 0 2.05E-08 2.45E-07 1.07E-09 1.07E+00

Thorium 0 0 0 0 0 0 0 0 0 0 1.40E-09 1.40E-09 0 0

EA-3 Uranium 0 0 1.40E-07 8.14E-11 3.38E-14 1.88E-10 0 3.72E-10 1.37E-10 0 1.71E-08 1.58E-07 9.59E-10 9.59E-01

Thorium 0 0 0 0 0 0 0 0 0 0 1.17E-09 1.17E-09 0 0

EA-4 Uranium 0 0 1.81E-11 5.54E-10 6.92E-11 9.27E-10 0 4.37E-14 1.17E-10 0 2.40E-08 2.57E-08 2.63E-09 2.63E+00

Thorium 0 0 0 0 0 0 0 0 0 0 1.64E-09 1.64E-09 0 0

EA-5 Uranium 0 0 5.03E-08 7.57E-10 9.73E-12 1.13E-10 0 7.66E-11 3.46E-11 0 8.09E-07 8.61E-07 2.41E-09 2.41E+00

Thorium 0 0 0 0 0 0 0 0 0 0 5.52E-08 5.52E-08 0 0

EA-6 Uranium 0 0 6.15E-08 1.19E-09 1.51E-11 7.53E-11 0 8.27E-11 2.81E-11 0 1.43E-07 2.06E-07 7.88E-10 7.88E-01

Thorium 0 0 0 0 0 0 0 0 0 0 9.76E-09 9.76E-09 0 0

EA-7 Uranium 0 0 7.26E-08 9.39E-10 3.52E-11 6.80E-10 0 2.53E-10 1.31E-10 0 2.51E-08 9.98E-08 1.20E-09 1.20E+00

Thorium 0 0 0 0 0 0 0 0 0 0 1.71E-09 1.71E-09 0 0

EA-8 Uranium 0 0 1.09E-07 1.65E-09 1.02E-10 6.36E-10 0 8.45E-11 1.28E-10 0 1.25E-08 1.24E-07 7.99E-10 7.99E-01

Thorium 0 0 0 0 0 0 0 0 0 0 8.55E-10 8.55E-10 0 0

EA-9 Uranium 0 0 2.16E-08 1.75E-09 9.25E-11 8.18E-10 0 4.67E-11 1.92E-10 0 7.57E-09 3.21E-08 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 0 5.16E-10 5.16E-10 0 0

EA-10 Uranium 0 0 1.95E-07 9.73E-10 5.52E-11 3.63E-10 0 3.41E-10 5.14E-11 0 1.09E-07 3.06E-07 1.23E-09 1.23E+00

Thorium 0 0 0 0 0 0 0 0 0 0 7.44E-09 7.44E-09 0 0

EA-11 Uranium 0 0 1.68E-08 3.36E-10 1.41E-11 1.63E-10 0 9.35E-11 2.38E-11 0 2.97E-08 4.72E-08 8.43E-10 8.43E-01

Thorium 0 0 0 0 0 0 0 0 0 0 2.03E-09 2.03E-09 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 78 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1988 Concentration contribution from emission sources (g/m3) Total 

conc. 

(g/m3)

Total 

intake 

(mg)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 3.44E-08 2.61E-10 3.90E-11 2.25E-10 0 5.86E-11 6.39E-11 0 9.19E-08 1.27E-07 3.05E-01 8.59E-10 8.59E-01

Thorium 0 0 0 0 0 0 0 0 0 6.43E-09 6.43E-09 1.54E-02 0 0

EA-2 Uranium 0 9.86E-08 1.34E-09 1.28E-10 2.84E-10 0 5.52E-11 8.29E-11 0 2.07E-08 1.21E-07 2.91E-01 4.44E-10 4.44E-01

Thorium 0 0 0 0 0 0 0 0 0 1.45E-09 1.45E-09 3.48E-03 0 0

EA-3 Uranium 0 6.29E-08 2.70E-11 2.25E-14 7.19E-11 0 9.05E-11 6.86E-11 0 1.73E-08 8.04E-08 1.93E-01 3.99E-10 3.99E-01

Thorium 0 0 0 0 0 0 0 0 0 1.21E-09 1.21E-09 2.90E-03 0 0

EA-4 Uranium 0 8.13E-12 1.84E-10 4.61E-11 3.55E-10 0 1.06E-14 5.86E-11 0 2.43E-08 2.49E-08 5.99E-02 1.10E-09 1.10E+00

Thorium 0 0 0 0 0 0 0 0 0 1.70E-09 1.70E-09 4.08E-03 0 0

EA-5 Uranium 0 2.26E-08 2.51E-10 6.49E-12 4.33E-11 0 1.86E-11 1.73E-11 0 8.19E-07 8.42E-07 2.02E+00 1.00E-09 1.00E+00

Thorium 0 0 0 0 0 0 0 0 0 5.73E-08 5.73E-08 1.37E-01 0 0

EA-6 Uranium 0 2.77E-08 3.96E-10 1.01E-11 2.88E-11 0 2.01E-11 1.41E-11 0 1.45E-07 1.73E-07 4.15E-01 3.28E-10 3.28E-01

Thorium 0 0 0 0 0 0 0 0 0 1.01E-08 1.01E-08 2.43E-02 0 0

EA-7 Uranium 0 3.27E-08 3.11E-10 2.35E-11 2.60E-10 0 6.17E-11 6.53E-11 0 2.54E-08 5.89E-08 1.41E-01 5.00E-10 5.00E-01

Thorium 0 0 0 0 0 0 0 0 0 1.78E-09 1.78E-09 4.27E-03 0 0

EA-8 Uranium 0 4.89E-08 5.45E-10 6.78E-11 2.44E-10 0 2.06E-11 6.39E-11 0 1.27E-08 6.25E-08 1.50E-01 3.33E-10 3.33E-01

Thorium 0 0 0 0 0 0 0 0 0 8.87E-10 8.87E-10 2.13E-03 0 0

EA-9 Uranium 0 9.74E-09 5.80E-10 6.17E-11 3.13E-10 0 1.14E-11 9.58E-11 0 7.66E-09 1.85E-08 4.43E-02 1.66E-10 1.66E-01

Thorium 0 0 0 0 0 0 0 0 0 5.36E-10 5.36E-10 1.29E-03 0 0

EA-10 Uranium 0 8.79E-08 3.22E-10 3.68E-11 1.39E-10 0 8.29E-11 2.57E-11 0 1.10E-07 1.99E-07 4.77E-01 5.10E-10 5.10E-01

Thorium 0 0 0 0 0 0 0 0 0 7.72E-09 7.72E-09 1.85E-02 0 0

EA-11 Uranium 0 7.58E-09 1.11E-10 9.37E-12 6.25E-11 0 2.27E-11 1.19E-11 0 3.00E-08 3.78E-08 9.08E-02 3.51E-10 3.51E-01

Thorium 0 0 0 0 0 0 0 0 0 2.10E-09 2.10E-09 5.04E-03 0 0

1989 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 1.44E-16 0 0 0 0 0 0 0 1.44E-16 3.46E-10 0 0

Thorium 0 0 2.36E-18 0 0 0 0 0 0 0 2.36E-18 5.66E-12 0 0

EA-2 Uranium 0 0 7.41E-16 0 0 0 0 0 0 0 7.41E-16 1.78E-09 0 0

Thorium 0 0 1.21E-17 0 0 0 0 0 0 0 1.21E-17 2.91E-11 0 0

EA-3 Uranium 0 0 1.49E-17 0 0 0 0 0 0 0 1.49E-17 3.58E-11 0 0

Thorium 0 0 1.66E-18 0 0 0 0 0 0 0 1.66E-18 3.98E-12 0 0

EA-4 Uranium 0 0 1.02E-16 0 0 0 0 0 0 0 1.02E-16 2.44E-10 0 0

Thorium 0 0 1.66E-18 0 0 0 0 0 0 0 1.66E-18 3.98E-12 0 0

EA-5 Uranium 0 0 1.39E-16 0 0 0 0 0 0 0 1.39E-16 3.33E-10 0 0

Thorium 0 0 2.27E-18 0 0 0 0 0 0 0 2.27E-18 5.44E-12 0 0

EA-6 Uranium 0 0 2.19E-16 0 0 0 0 0 0 0 2.19E-16 5.25E-10 0 0

Thorium 0 0 3.58E-18 0 0 0 0 0 0 0 3.58E-18 8.59E-12 0 0

EA-7 Uranium 0 0 1.72E-16 0 0 0 0 0 0 0 1.72E-16 4.13E-10 0 0

Thorium 0 0 2.81E-18 0 0 0 0 0 0 0 2.81E-18 6.75E-12 0 0

EA-8 Uranium 0 0 3.01E-16 0 0 0 0 0 0 0 3.01E-16 7.23E-10 0 0

Thorium 0 0 4.93E-18 0 0 0 0 0 0 0 4.93E-18 1.18E-11 0 0

EA-9 Uranium 0 0 3.21E-16 0 0 0 0 0 0 0 3.21E-16 7.70E-10 0 0

Thorium 0 0 5.25E-18 0 0 0 0 0 0 0 5.25E-18 1.26E-11 0 0

EA-10 Uranium 0 0 1.78E-16 0 0 0 0 0 0 0 1.78E-16 4.28E-10 0 0

Thorium 0 0 2.91E-18 0 0 0 0 0 0 0 2.91E-18 6.99E-12 0 0

EA-11 Uranium 0 0 6.16E-17 0 0 0 0 0 0 0 6.16E-17 1.48E-10 0 0

Thorium 0 0 1.01E-18 0 0 0 0 0 0 0 1.01E-18 2.42E-12 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 79 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1990 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 7.75E-17 0 0 0 0 0 0 0 7.75E-17 1.86E-10 0 0

Thorium 0 0 1.05E-18 0 0 0 0 0 0 0 1.05E-18 2.53E-12 0 0

EA-2 Uranium 0 0 3.98E-16 0 0 0 0 0 0 0 3.98E-16 9.55E-10 0 0

Thorium 0 0 5.42E-18 0 0 0 0 0 0 0 5.42E-18 1.30E-11 0 0

EA-3 Uranium 0 0 8.01E-18 0 0 0 0 0 0 0 8.01E-18 1.92E-11 0 0

Thorium 0 0 7.43E-19 0 0 0 0 0 0 0 7.43E-19 1.78E-12 0 0

EA-4 Uranium 0 0 5.46E-17 0 0 0 0 0 0 0 5.46E-17 1.31E-10 0 0

Thorium 0 0 7.43E-19 0 0 0 0 0 0 0 7.43E-19 1.78E-12 0 0

EA-5 Uranium 0 0 7.45E-17 0 0 0 0 0 0 0 7.45E-17 1.79E-10 0 0

Thorium 0 0 1.01E-18 0 0 0 0 0 0 0 1.01E-18 2.43E-12 0 0

EA-6 Uranium 0 0 1.18E-16 0 0 0 0 0 0 0 1.18E-16 2.82E-10 0 0

Thorium 0 0 1.60E-18 0 0 0 0 0 0 0 1.60E-18 3.84E-12 0 0

EA-7 Uranium 0 0 9.25E-17 0 0 0 0 0 0 0 9.25E-17 2.22E-10 0 0

Thorium 0 0 1.26E-18 0 0 0 0 0 0 0 1.26E-18 3.02E-12 0 0

EA-8 Uranium 0 0 1.62E-16 0 0 0 0 0 0 0 1.62E-16 3.89E-10 0 0

Thorium 0 0 2.21E-18 0 0 0 0 0 0 0 2.21E-18 5.29E-12 0 0

EA-9 Uranium 0 0 1.72E-16 0 0 0 0 0 0 0 1.72E-16 4.14E-10 0 0

Thorium 0 0 2.35E-18 0 0 0 0 0 0 0 2.35E-18 5.63E-12 0 0

EA-10 Uranium 0 0 9.58E-17 0 0 0 0 0 0 0 9.58E-17 2.30E-10 0 0

Thorium 0 0 1.30E-18 0 0 0 0 0 0 0 1.30E-18 3.13E-12 0 0

EA-11 Uranium 0 0 3.31E-17 0 0 0 0 0 0 0 3.31E-17 7.94E-11 0 0

Thorium 0 0 4.50E-19 0 0 0 0 0 0 0 4.50E-19 1.08E-12 0 0

1991 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 1.12E-16 0 0 0 0 0 0 0 1.12E-16 2.68E-10 0 0

Thorium 0 0 3.52E-19 0 0 0 0 0 0 0 3.52E-19 8.44E-13 0 0

EA-2 Uranium 0 0 5.74E-16 0 0 0 0 0 0 0 5.74E-16 1.38E-09 0 0

Thorium 0 0 1.81E-18 0 0 0 0 0 0 0 1.81E-18 4.33E-12 0 0

EA-3 Uranium 0 0 1.15E-17 0 0 0 0 0 0 0 1.15E-17 2.77E-11 0 0

Thorium 0 0 2.48E-19 0 0 0 0 0 0 0 2.48E-19 5.94E-13 0 0

EA-4 Uranium 0 0 7.87E-17 0 0 0 0 0 0 0 7.87E-17 1.89E-10 0 0

Thorium 0 0 2.48E-19 0 0 0 0 0 0 0 2.48E-19 5.94E-13 0 0

EA-5 Uranium 0 0 1.07E-16 0 0 0 0 0 0 0 1.07E-16 2.58E-10 0 0

Thorium 0 0 3.38E-19 0 0 0 0 0 0 0 3.38E-19 8.11E-13 0 0

EA-6 Uranium 0 0 1.70E-16 0 0 0 0 0 0 0 1.70E-16 4.07E-10 0 0

Thorium 0 0 5.34E-19 0 0 0 0 0 0 0 5.34E-19 1.28E-12 0 0

EA-7 Uranium 0 0 1.33E-16 0 0 0 0 0 0 0 1.33E-16 3.20E-10 0 0

Thorium 0 0 4.20E-19 0 0 0 0 0 0 0 4.20E-19 1.01E-12 0 0

EA-8 Uranium 0 0 2.34E-16 0 0 0 0 0 0 0 2.34E-16 5.60E-10 0 0

Thorium 0 0 7.35E-19 0 0 0 0 0 0 0 7.35E-19 1.76E-12 0 0

EA-9 Uranium 0 0 2.49E-16 0 0 0 0 0 0 0 2.49E-16 5.97E-10 0 0

Thorium 0 0 7.83E-19 0 0 0 0 0 0 0 7.83E-19 1.88E-12 0 0

EA-10 Uranium 0 0 1.38E-16 0 0 0 0 0 0 0 1.38E-16 3.31E-10 0 0

Thorium 0 0 4.35E-19 0 0 0 0 0 0 0 4.35E-19 1.04E-12 0 0

EA-11 Uranium 0 0 4.77E-17 0 0 0 0 0 0 0 4.77E-17 1.14E-10 0 0

Thorium 0 0 1.50E-19 0 0 0 0 0 0 0 1.50E-19 3.60E-13 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 80 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1992 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 1.00E-16 0 0 0 0 0 0 0 1.00E-16 2.40E-10 0 0

Thorium 0 0 9.85E-19 0 0 0 0 0 0 0 9.85E-19 2.36E-12 0 0

EA-2 Uranium 0 0 5.14E-16 0 0 0 0 0 0 0 5.14E-16 1.23E-09 0 0

Thorium 0 0 5.06E-18 0 0 0 0 0 0 0 5.06E-18 1.21E-11 0 0

EA-3 Uranium 0 0 1.03E-17 0 0 0 0 0 0 0 1.03E-17 2.48E-11 0 0

Thorium 0 0 6.94E-19 0 0 0 0 0 0 0 6.94E-19 1.67E-12 0 0

EA-4 Uranium 0 0 7.04E-17 0 0 0 0 0 0 0 7.04E-17 1.69E-10 0 0

Thorium 0 0 6.94E-19 0 0 0 0 0 0 0 6.94E-19 1.67E-12 0 0

EA-5 Uranium 0 0 9.61E-17 0 0 0 0 0 0 0 9.61E-17 2.31E-10 0 0

Thorium 0 0 9.48E-19 0 0 0 0 0 0 0 9.48E-19 2.27E-12 0 0

EA-6 Uranium 0 0 1.52E-16 0 0 0 0 0 0 0 1.52E-16 3.64E-10 0 0

Thorium 0 0 1.50E-18 0 0 0 0 0 0 0 1.50E-18 3.59E-12 0 0

EA-7 Uranium 0 0 1.19E-16 0 0 0 0 0 0 0 1.19E-16 2.86E-10 0 0

Thorium 0 0 1.18E-18 0 0 0 0 0 0 0 1.18E-18 2.82E-12 0 0

EA-8 Uranium 0 0 2.09E-16 0 0 0 0 0 0 0 2.09E-16 5.02E-10 0 0

Thorium 0 0 2.06E-18 0 0 0 0 0 0 0 2.06E-18 4.94E-12 0 0

EA-9 Uranium 0 0 2.23E-16 0 0 0 0 0 0 0 2.23E-16 5.34E-10 0 0

Thorium 0 0 2.19E-18 0 0 0 0 0 0 0 2.19E-18 5.26E-12 0 0

EA-10 Uranium 0 0 1.24E-16 0 0 0 0 0 0 0 1.24E-16 2.97E-10 0 0

Thorium 0 0 1.22E-18 0 0 0 0 0 0 0 1.22E-18 2.92E-12 0 0

EA-11 Uranium 0 0 4.27E-17 0 0 0 0 0 0 0 4.27E-17 1.02E-10 0 0

Thorium 0 0 4.21E-19 0 0 0 0 0 0 0 4.21E-19 1.01E-12 0 0

1993 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 1.20E-16 0 0 0 0 0 0 0 1.20E-16 2.88E-10 0 0

Thorium 0 0 9.45E-19 0 0 0 0 0 0 0 9.45E-19 2.27E-12 0 0

EA-2 Uranium 0 0 6.17E-16 0 0 0 0 0 0 0 6.17E-16 1.48E-09 0 0

Thorium 0 0 4.85E-18 0 0 0 0 0 0 0 4.85E-18 1.16E-11 0 0

EA-3 Uranium 0 0 1.24E-17 0 0 0 0 0 0 0 1.24E-17 2.98E-11 0 0

Thorium 0 0 6.65E-19 0 0 0 0 0 0 0 6.65E-19 1.60E-12 0 0

EA-4 Uranium 0 0 8.46E-17 0 0 0 0 0 0 0 8.46E-17 2.03E-10 0 0

Thorium 0 0 6.65E-19 0 0 0 0 0 0 0 6.65E-19 1.60E-12 0 0

EA-5 Uranium 0 0 1.15E-16 0 0 0 0 0 0 0 1.15E-16 2.77E-10 0 0

Thorium 0 0 9.08E-19 0 0 0 0 0 0 0 9.08E-19 2.18E-12 0 0

EA-6 Uranium 0 0 1.82E-16 0 0 0 0 0 0 0 1.82E-16 4.37E-10 0 0

Thorium 0 0 1.43E-18 0 0 0 0 0 0 0 1.43E-18 3.44E-12 0 0

EA-7 Uranium 0 0 1.43E-16 0 0 0 0 0 0 0 1.43E-16 3.44E-10 0 0

Thorium 0 0 1.13E-18 0 0 0 0 0 0 0 1.13E-18 2.71E-12 0 0

EA-8 Uranium 0 0 2.51E-16 0 0 0 0 0 0 0 2.51E-16 6.02E-10 0 0

Thorium 0 0 1.98E-18 0 0 0 0 0 0 0 1.98E-18 4.74E-12 0 0

EA-9 Uranium 0 0 2.67E-16 0 0 0 0 0 0 0 2.67E-16 6.41E-10 0 0

Thorium 0 0 2.10E-18 0 0 0 0 0 0 0 2.10E-18 5.05E-12 0 0

EA-10 Uranium 0 0 1.48E-16 0 0 0 0 0 0 0 1.48E-16 3.56E-10 0 0

Thorium 0 0 1.17E-18 0 0 0 0 0 0 0 1.17E-18 2.80E-12 0 0

EA-11 Uranium 0 0 5.13E-17 0 0 0 0 0 0 0 5.13E-17 1.23E-10 0 0

Thorium 0 0 4.03E-19 0 0 0 0 0 0 0 4.03E-19 9.68E-13 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 81 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1994 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 3.16E-17 0 0 0 0 0 0 0 3.16E-17 7.58E-11 0 0

Thorium 0 0 7.22E-19 0 0 0 0 0 0 0 7.22E-19 1.73E-12 0 0

EA-2 Uranium 0 0 1.62E-16 0 0 0 0 0 0 0 1.62E-16 3.89E-10 0 0

Thorium 0 0 3.71E-18 0 0 0 0 0 0 0 3.71E-18 8.91E-12 0 0

EA-3 Uranium 0 0 3.26E-18 0 0 0 0 0 0 0 3.26E-18 7.83E-12 0 0

Thorium 0 0 5.09E-19 0 0 0 0 0 0 0 5.09E-19 1.22E-12 0 0

EA-4 Uranium 0 0 2.22E-17 0 0 0 0 0 0 0 2.22E-17 5.34E-11 0 0

Thorium 0 0 5.09E-19 0 0 0 0 0 0 0 5.09E-19 1.22E-12 0 0

EA-5 Uranium 0 0 3.04E-17 0 0 0 0 0 0 0 3.04E-17 7.29E-11 0 0

Thorium 0 0 6.95E-19 0 0 0 0 0 0 0 6.95E-19 1.67E-12 0 0

EA-6 Uranium 0 0 4.79E-17 0 0 0 0 0 0 0 4.79E-17 1.15E-10 0 0

Thorium 0 0 1.10E-18 0 0 0 0 0 0 0 1.10E-18 2.63E-12 0 0

EA-7 Uranium 0 0 3.77E-17 0 0 0 0 0 0 0 3.77E-17 9.04E-11 0 0

Thorium 0 0 8.62E-19 0 0 0 0 0 0 0 8.62E-19 2.07E-12 0 0

EA-8 Uranium 0 0 6.60E-17 0 0 0 0 0 0 0 6.60E-17 1.58E-10 0 0

Thorium 0 0 1.51E-18 0 0 0 0 0 0 0 1.51E-18 3.62E-12 0 0

EA-9 Uranium 0 0 7.03E-17 0 0 0 0 0 0 0 7.03E-17 1.69E-10 0 0

Thorium 0 0 1.61E-18 0 0 0 0 0 0 0 1.61E-18 3.86E-12 0 0

EA-10 Uranium 0 0 3.90E-17 0 0 0 0 0 0 0 3.90E-17 9.37E-11 0 0

Thorium 0 0 8.93E-19 0 0 0 0 0 0 0 8.93E-19 2.14E-12 0 0

EA-11 Uranium 0 0 1.35E-17 0 0 0 0 0 0 0 1.35E-17 3.24E-11 0 0

Thorium 0 0 3.08E-19 0 0 0 0 0 0 0 3.08E-19 7.40E-13 0 0

1995 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 2.06E-17 0 0 0 0 0 0 0 2.06E-17 4.94E-11 0 0

Thorium 0 0 2.77E-19 0 0 0 0 0 0 0 2.77E-19 6.66E-13 0 0

EA-2 Uranium 0 0 1.06E-16 0 0 0 0 0 0 0 1.06E-16 2.54E-10 0 0

Thorium 0 0 1.43E-18 0 0 0 0 0 0 0 1.43E-18 3.42E-12 0 0

EA-3 Uranium 0 0 2.13E-18 0 0 0 0 0 0 0 2.13E-18 5.11E-12 0 0

Thorium 0 0 1.95E-19 0 0 0 0 0 0 0 1.95E-19 4.69E-13 0 0

EA-4 Uranium 0 0 1.45E-17 0 0 0 0 0 0 0 1.45E-17 3.48E-11 0 0

Thorium 0 0 1.95E-19 0 0 0 0 0 0 0 1.95E-19 4.69E-13 0 0

EA-5 Uranium 0 0 1.98E-17 0 0 0 0 0 0 0 1.98E-17 4.75E-11 0 0

Thorium 0 0 2.67E-19 0 0 0 0 0 0 0 2.67E-19 6.40E-13 0 0

EA-6 Uranium 0 0 3.13E-17 0 0 0 0 0 0 0 3.13E-17 7.50E-11 0 0

Thorium 0 0 4.21E-19 0 0 0 0 0 0 0 4.21E-19 1.01E-12 0 0

EA-7 Uranium 0 0 2.46E-17 0 0 0 0 0 0 0 2.46E-17 5.90E-11 0 0

Thorium 0 0 3.31E-19 0 0 0 0 0 0 0 3.31E-19 7.95E-13 0 0

EA-8 Uranium 0 0 4.31E-17 0 0 0 0 0 0 0 4.31E-17 1.03E-10 0 0

Thorium 0 0 5.80E-19 0 0 0 0 0 0 0 5.80E-19 1.39E-12 0 0

EA-9 Uranium 0 0 4.58E-17 0 0 0 0 0 0 0 4.58E-17 1.10E-10 0 0

Thorium 0 0 6.17E-19 0 0 0 0 0 0 0 6.17E-19 1.48E-12 0 0

EA-10 Uranium 0 0 2.55E-17 0 0 0 0 0 0 0 2.55E-17 6.11E-11 0 0

Thorium 0 0 3.43E-19 0 0 0 0 0 0 0 3.43E-19 8.23E-13 0 0

EA-11 Uranium 0 0 8.79E-18 0 0 0 0 0 0 0 8.79E-18 2.11E-11 0 0

Thorium 0 0 1.18E-19 0 0 0 0 0 0 0 1.18E-19 2.84E-13 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 82 of 83

Appendix 4A (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1996 Concentration contribution from emission sources (Ci/m3) Total 

conc. 

(Ci/m3)

Total 

intake 

(mCi)

Rn-222

Silos

(Ci/m3)

Rn-222 

Conc. 

Area Source Plant 1 Plant 2/3 Plant 4 Plant 5 Plant 6 Plant 7 Plant 8 Plant 9 (pCi/L)

Pilot 

Plant

Waste 

Pit

EA-1 Uranium 0 0 2.08E-17 0 0 0 0 0 0 0 2.08E-17 4.99E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-2 Uranium 0 0 1.07E-16 0 0 0 0 0 0 0 1.07E-16 2.57E-10 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-3 Uranium 0 0 2.15E-18 0 0 0 0 0 0 0 2.15E-18 5.16E-12 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-4 Uranium 0 0 1.47E-17 0 0 0 0 0 0 0 1.47E-17 3.52E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-5 Uranium 0 0 2.00E-17 0 0 0 0 0 0 0 2.00E-17 4.80E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-6 Uranium 0 0 3.16E-17 0 0 0 0 0 0 0 3.16E-17 7.58E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-7 Uranium 0 0 2.48E-17 0 0 0 0 0 0 0 2.48E-17 5.96E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-8 Uranium 0 0 4.35E-17 0 0 0 0 0 0 0 4.35E-17 1.04E-10 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-9 Uranium 0 0 4.63E-17 0 0 0 0 0 0 0 4.63E-17 1.11E-10 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-10 Uranium 0 0 2.57E-17 0 0 0 0 0 0 0 2.57E-17 6.17E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0

EA-11 Uranium 0 0 8.89E-18 0 0 0 0 0 0 0 8.89E-18 2.13E-11 0 0

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0
Effective Date: 04/06/2004 Revision No. 00 Document No. ORAUT-TKBS-0017-4 Page 83 of 83

 

Appendix 4B. Annual average radon background concentrations and concentration at selected radon 

locations, 1989-2002. (Fluor, 2003).