ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 110

Document Title:

Fernald Environmental Management 

Project – Occupational Environmental 

Dose

Document Number: ORAUT-TKBS-0017-4 

Revision: 01 

Effective Date: 02/07/2006

Type of Document: TBD

Supersedes: Revision 00 

Subject Expert: Samuel L. T. Chu

Approval: Signature on File Approval Date: 02/02/2006

Melton H. Chew, Document Owner

Approval: Signature on File Approval Date: 02/03/2006

Judson L. Kenoyer, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 02/06/2006

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 02/07/2006

Larry Elliott, Director, OCAS

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 2 of 110

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

04/06/2004 00 New Technical Basis Document for the Fernald Environmental 

Management Project – Occupational Environmental Dose. First 

approved issue. Initiated by Samuel L.T. Chu.

02/07/2006 01 Approved issue of Revision 01 to add NIOSH “boilerplate” language. 

Added totals to tables 4.2a and b,, revised tables 4.9a and b to 

include Radon-222, table 4-10a to include intakes uranium and non 

uranium radionuclides and table 4-10b to include site wide intakes of 

Radon-222, added radon-222 concentrations in Table 4A in 

Appendix A. Constitutes a total rewrite of the document. Training 

required: As determined by the Task Manager. Initiated by Melton 

H. Chew.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 3 of 110

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

6

4.0 Occupational Environmental Dose ...........................................................................................7

4.1 Introduction ......................................................................................................................8

4.2 Site Background and History............................................................................................8

4.3 Internal Doses from Atmospheric Radionuclide Concentrations .......................................9

4.3.1 Airborne Radioactive Materials Emissions (1951–1988) ........................................ 9

4.3.2 Onsite Environmental Radioactive Material Air Concentrations 

 and Intake (1951–2002) ....................................................................................... 10

 4.3.2.1 Exposure Site Locations ......................................................................... 10

 4.3.2.2 Airborne Radionuclide Concentration Derivation..................................... 16

 4.3.2.3 Radionuclide Concentrations and Intake from Routine Emissions

 (1951-1988)............................................................................................ 20

4.3.3 Onsite Air Monitored Average Concentrations (1989–2002)................................. 23

 4.3.3.1 Onsite Radionuclide Concentrations and Intakes (1989–1996).............. 25

 4.3.3.2 Onsite Radionuclide Concentrations and Intakes (1997–2002).............. 25

4.3.4 Site-Wide Average Intake Summary by Isotopes (1951–2002) ............................ 25

4.4 OnSite external Doses from Ambient Radiation ..............................................................28

4.4.1 K-65 and Production Plants External Dose Contribution ...................................... 28

4.4.2 External Dose Contribution from Waste Pits ........................................................ 34

4.4.3 Onsite Ambient Dose Rate Estimate .................................................................... 35

References ........................................................................................................................................38

Glossary ............................................................................................................................................41

Attachment A, Airborne Radionuclide Concentration and Intake Summary..........................................42

Attachment B, External Occupational Environmental Dose Rates Summary.................................55

Attachment C, FEMP Radionuclide Concentration and Intake Results by Exposure Area and 

Year..........................................................................................................61

Attachment D, Annual Average Radon Background Concentrations and Concentration at Selected 

Radon Locations, 1989-2002........................................................................110 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 4 of 110

LIST OF TABLES

TABLE TITLE

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

PAGE

11

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

and 3......................................................................................................................................12

4-3 Fugitive uranium and thorium emissions from wind erosion of Waste Pits 4, 5, 

and 6......................................................................................................................................13

4-4 Thorium emission estimates by year (kg)............................................................................... 14

4-5 222Rn and 222Rn daughter product releases for drummed K-65 material stored 

on Plant 1 Pad .......................................................................................................................14

4-6 Facilities and buildings in each Exposure Area ...................................................................... 15

4-7 (χ/Q) values versus distances from emission source.............................................................. 19

4-8 Receptor downwind estimated distances from contributing emission sources ........................ 20

4-9 Percentage of time that wind blew in direction of Exposure Areas.......................................... 21

4-10 Inputs and results of application of equation 4-5 .................................................................... 22

4-11 Site-wide intakes of each uranium and nonuranium radionuclide (Bq/yr) for 

1951 through 2002................................................................................................................. 26

4-12 Site-wide intakes of radon in WLM for 1951 through 2002 ..................................................... 27

4-13 Radiation dose rates at site boundary .................................................................................... 29

4-14 TLD measurement summary.................................................................................................. 31

4-15 Average onsite background dose rates .................................................................................. 33

4-16 Waste pit dose rate data ........................................................................................................ 34

4-17 Comparison of estimated dose rates in EAs and aerial survey results.................................... 36

4-18 Site-wide average dose rates comparison.............................................................................. 36

A-1 Radionuclide concentration and intake summary for 1951 to 1988......................................... 42

A-3 Radionuclide concentration and intake from 1989 to 1996 ..................................................... 51

A-4 Radionuclide concentration and intake from 1997 to 2002 ..................................................... 53

A-2 Conversion factors and isotopic content for values in Table A-1 ............................................ 54

A-5 External occupational environmental dose rates summary..................................................... 55

B-1 FEMP radionuclide concentration and intake results by exposure area and 

year........................................................................................................................................61
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 5 of 110

LIST OF FIGURES 

FIGURE TITLE

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

PAGE

14

4-2 Exposure Areas .....................................................................................................................15

4-3 Horizontal diffusion, σy, versus downwind distance from point source for 

Pasquill’s stability categories.................................................................................................. 18

4-4 Horizontal diffusion, σz, versus downwind distance from continuously emitting 

point source for Pasquill’s stability categories ........................................................................ 19

4-5 Wind rose for 10-m height for 2000 ........................................................................................ 21

4-6 Air monitoring station locations .............................................................................................. 24

4-7 Average onsite uranium concentrations (1989 to 1996) ......................................................... 24

4-8 Average onsite thorium concentrations (1989 to 1996) .......................................................... 25

4-9 FEMP fenceline TLD locations (1976 to 1995) ....................................................................... 30

4-10 TLD monitoring locations (1996 to 2002)................................................................................ 30

4-11 1976 exposure rate contour map of FEMP survey area ......................................................... 31

4-12 1985 exposure rate contour map of FEMP survey area ......................................................... 32

4-13 Beta-gamma dose rate contours in waste pit area ................................................................. 33

4-14 Waste pit dose rate profiles.................................................................................................... 34

4-15 Projected site-wide direct radiation dose rates based on metal production rate ...................... 37

C-1 Annual average radon background concentrations and concentration at 

selected radon locations, 1989-2002.................................................................................... 110
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 6 of 110

ACRONYMS AND ABBREVIATIONS

AMS air monitoring station

Bq Becquerel

Ci curie 

DOE U.S. Department of Energy

EA Exposure Area

EEOICPA Energy Employees Occupational Illness Compensation Program Act

FEMP Fernald Environmental Management Project

FMPC Feed Material Production Center

ft foot

g gram

GM Geometric Mean

GSD Geometric Standard Deviation

keV kilovolt-electron

kg kilogram

L liter

m meter

mg milligram

mR milliroentgen

mrad millirad

mrem millirem

MTU metric ton of uranium

NIOSH National Institute for Occupational Safety and Health

pCi picocurie

ppb part per billion

s second

TBD technical basis document

TLD thermoluminescent dosimeter

U.S.C. United States Code

WL unit of measurement for radon daughter exposure rate, 1 WL ≈ 100 pCi/L of radon in 

100%.

WLM exposure of an individual to 1 WL for 170 hr (working month).

yr year

μCi microcurie

μm micrometer
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 7 of 110

4.0 OCCUPATIONAL ENVIRONMENTAL DOSE

This technical basis document (TBD) provides the technical basis for estimation of historic radiological 

doses to workers from the U.S. Department of Energy (DOE) Fernald Environmental Management 

Project (FEMP; previously known as the Feed Material Production Center, or FMPC) based on

exposure to occupational environmental radiation sources.

TBDs 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 the National Institute for Occupational Safety and Health (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 Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the [probability of causation] guidelines established under subsection 

(c) ....” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation guidelines (nor the 

dose reconstruction regulation) define “performance of duty” for DOE employees with a covered 

cancer or restrict the “duty” to nuclear weapons work.

As noted above, the statute includes a definition of a DOE facility that excludes “buildings, structures, 

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 

(42 U.S.C. 7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. 

While this definition contains an exclusion with respect to the Naval Nuclear Propulsion Program, the 

section of EEOICPA that deals with the compensation decision for covered employees with cancer 

[i.e., 42 U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all radiation exposures in its dose 

reconstructions for employees at DOE facilities, including radiation exposures related to the Naval 

Nuclear Propulsion Program. As a result, all internal and external dosimetry results are considered 

valid for use in dose reconstruction. No efforts are made to determine the eligibility of any fraction of 

total measured exposure for inclusion in dose reconstruction.

For the NIOSH Dose Reconstruction Program and this TBD, the following criteria are applicable:
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 8 of 110

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

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

reconstruction.

• The information gathered for the TBDs takes into consideration that EEOICPA (pursuant to 

Executive Order 13179) requires HHS to consider 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)(3)(C)].

• The purpose of TBDs is to support dose reconstruction efforts that involve determining or

assuming specific characteristics of the monitoring procedures, identifying unmonitored events 

or processes, identifying the types and quantities of radioactive materials, evaluating 

production processes and safety procedures, identifying locations and activities of exposed 

persons, and identifying comparable exposure circumstances for which data are available to 

make assumptions regarding exposures.

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

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 on 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 gases or from airborne contamination.

• Radiation exposures from offsite sources are not occupational exposures.

• The compilation of data for this TBD did not consider accidents. Dose reconstructors will 

handle accidents as special cases. Decisions on how to handle accidents will be on a caseby-case basis.

• The establishment of dose values did not consider the contribution of food chain vectors.

• This TBD does not consider fallout a contributing factor in dose reconstruction.

4.1 INTRODUCTION 

Records review showed that personnel likely to receive an 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 and exposure to direct radiation 

from emission plumes, radioactive materials in the process plants, and radioactive substances 

deposited on the ground or surfaces. Dose reconstructors can determine the internal dose from 

inhalation of radioactive materials from radionuclide air concentrations, and the external dose from 

exposure to radioactive materials outside the body from historical data of external dosimetry 

monitoring. 

This TBD discusses the derivation of radionuclide air concentrations and subsequent radionuclide 

intakes by an individual on the site and presents historical external dose area radiation monitoring 

data for 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. Its primary 

function 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 standard 

isotopic assays. These products were for use as production reactor fuel cores and target fuel element 

fabrication. In addition, the FEMP processed small amounts of thorium. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 9 of 110

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, 

DOE predecessor agencies considered 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 employment 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 are limited to site remediation and restoration. 

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 (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 

undergoing remediation, and some of the plants and buildings that existed 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 are in various phases of dismantlement.

4.3 INTERNAL DOSES FROM ATMOSPHERIC RADIONUCLIDE CONCENTRATIONS

History of FEMP Radionuclide Discharges (Boback et al. 1987) and The Fernald Dosimetry 

Reconstruction Project, Tasks 2 and 3, Radionuclide Source Terms and Uncertainties (RAC 1995)

evaluated radioactive emissions from the FEMP operating years (from 1951 through 1988). The 

values for uranium and thorium discharges from routine operations during the operating years are 

from Dolan and Dolan (1988), which is an 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 in the general Plant areas for each 

production year for the unmonitored worker dose reconstruction effort using Plant emission data. 

Emission quantities from remediation and decommissioning activities are not readily available for 

1989 and after; however, there are information and data relevant to environmental dose in the annual 

environmental reports. Therefore, this TBD reports occupational environmental dose information 

available in FEMP environmental reports for this period (e.g., WEMCO 1990 to 1992; FERMCO 1993 

to 1996; Fluor 1997 to 2001).

4.3.1

During FEMP production operations, 175,130 kg of uranium and 8,769 kg of thorium were released to 

the atmosphere from various emission sources due to routine operations. Table 4-1 lists annual 

airborne uranium emissions due to FEMP operations throughout the operating history (1951 through 

1988) from each production plant and processing facility. The values in Table 4-1 include:

Airborne Radioactive Materials Emissions (1951–1988)

• Monitored source emissions as reported in Boback et al. (1987)

• Emissions from Plant 2/3 UO3 gulping

• Emissions from processes

• Building exhaust emissions due to normal operating conditions

• Emission approximations for laboratory hoods
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 10 of 110

Tables 4-2 and 4-3 summarize annual fugitive uranium and thorium emissions from wind erosion of 

the waste storage area. In addition, the tables list estimated radon fluxes at the waste pits. 

Table 4-4 lists annual airborne 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, actual thorium emissions should not 

exceed those listed in Table 4-4. 

Appendix J of Radionuclide Source Terms and Uncertainties (RAC 1995) estimated emissions of

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

Figure 4-1 shows 222Rn emission quantity estimates. Table 4-5 lists emissions of radon and its 

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

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

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

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

gas (220Rn). The average thoron activity concentration in outside air is comparable to the 

environmental background concentration of radon; therefore, it can be assumed that FEMP thoron 

environmental concentrations vary with fluctuations in radon concentrations (Tomes 1997). Most

thorium materials are stored in Buildings 64, 65, 67, 68, and 69. Because thoron has a half-life of 

55.6 s, significant accumulation occurs only in areas near buildings in which thorium is stored. 

Therefore, for 1972 and subsequent years, an activity concentration equal to that of the radon 

background concentration is assigned to areas close to buildings where thorium was stored.

4.3.2

This section presents the derivation of onsite radioactivity concentrations at FEMP locations based on 

discharges from routine operations during Plant operating years.

Onsite Environmental Radioactive Material Air Concentrations and Intake (1951–

2002)

4.3.2.1

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

significantly from facility to facility. This TBD analysis assumed that the radioactive aerosol 

concentration varies significantly in various sections of the Plant. The dose received by a worker is 

highly dependent on the amount of time spent in specific work areas. To provide 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 radiological 

conditions where employees might have worked. Figure 4-2 shows the FEMP site plan with the grid. 

This TBD presents airborne radionuclide concentrations from routine operations for 11 EAs. 

Table 4-6 lists major facilities in each EA. 

Exposure Site Locations

 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 11 of 110

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 1,483.88 13,272 47,164.67 2,686.75 3,131 68.9 596 2,490.5 39.4 110.2 173,675.16
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 12 of 110

Table 4-2. 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 813,860 29.2 -- 342,288 892.45 0.282 2,902,837 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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 13 of 110

Table 4-3. Fugitive uranium and thorium emissions from wind erosion of Waste Pits 4, 5, and 6. 

Year

Pit 4a Pit 5a Pit 6a

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 1,998,096 394.9 79.8 949,596 15.1 5.1 72,900 186 --

a. Radon Flux – less than 0.1 pCi/m3/sec
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 14 of 110

Table 4-4. 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 4-5. 222Rn and 222Rn daughter product releases (Ci) for 

drummed K-65 material stored on 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 listed for Rn-222 daughters are comprised of quantities of each shortlived daughter: Po-218, Pb-214, Bi-214, and Po-214. 

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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 15 of 110

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 4-6. 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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 16 of 110

4.3.2.2

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

obtained by:

Airborne Radionuclide Concentration Derivation

∑  ( ) 

 



 = 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 EA are the sum of the contributions of all emission 

sources to the most probable occupied area in the EA.

Radionuclide Emission Rates (Ri) × (RF) 

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

through 4-4 and Figure 4-1 by 3.154 × 107

 second 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 3 months in 

one case and 6 months in another (Table 4-5). However, their release rates were annualized as if the 

total emission quantities were released over a 1-year period. The radon daughter releases in 

Table 4-5 represent an equilibrium factor ranging from 1% to 27% for 1951 through 1953. Dose 

reconstructors should use the U.S. Environmental Protection Agency default equilibrium factor of 70% 

for outdoors in the intake calculation. This equilibrium factor is claimant-favorable. Therefore, the 

radon daughter releases in Table 4-5 were not used in the radon intake calculations.

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

respirable and sufficiently small to remain airborne during transport. Appendix E of Fernald 

DosimetryReconstruction Project (RAC 1988) states that the size distribution of emissions released 

from 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 RAC (1988) 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 in equation 4-1, 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) can be calculated 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 centerline (m)
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 17 of 110

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 centerline (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), the ground-level concentration 

would be approximately half that in equation 4-3.

Table 4-7 lists χ/Q values with respect to receptor distances downwind on the plume centerline 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 uranium and thorium 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 uranium and thorium fugitive 

emissions from the waste pits. Radon-222 is treated as an elevated gaseous release primarily from 

the head space of the K-65 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 4-8 lists the EA receptor downwind distance estimation from each contributing emission source

used for radioactivity concentration calculations. The estimated distances were based on emission 

sources to the most likely occupied location in each EA. Distances slightly higher (approaching the 

500-m maximum concentration distance) than those scaled from plot plan reproductions were 

assigned to ensure they were claimant-favorable.

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 for 2000. The prevailing winds were from the west through 

south-southwest about 40% of the time.

Table 4-9 lists the fraction of time that the wind blew toward the EAs from a contributing emission 

source, as determined using Figures 4-2 and 4-5. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 18 of 110

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

point source for Pasquill’s stability categories. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 19 of 110

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

from continuously emitting point source for Pasquill’s stability 

categories. 

Table 4-7. χ/Q values versus distances from emission 

source. 

Distance (m)

(χ/Q) (s/m3)

a

Ground release 10-m release height

100 0.02 5.12E-11

150 8.29E-3 3.37E-8

200 4.14E-3 1.60E-5

250 2.48E-3 1.09E-4

300 1.69E-3 2.11E-4

350 1.21E-3 2.31E-4

400 8.85E-4 2.71E-4

450 7.68E-4 2.77E-4

500 6.98E-4 2.87E-4

550 5.92E-4 2.71E-4

600 4.61E-4 2.48E-4

650 4.19E-4 2.41E-4

700 3.51E-4 2.23E-4

750 2.84E-4 2.02E-4

1,000 1.75E-4 1.40E-4

2,000 6.46E-5 5.83E-5

5,000 1.63E-5 1.56E-5

a. For uranium and thorium particulate aerosol, 0.5 × the values in 

the table.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 20 of 110

Table 4-8. 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

4.3.2.3

Table A-1 in Attachment A lists estimates of radionuclide concentrations and the amount of 

radionuclide intake for a claimant who spent a year in an EA between 1951 and 1988. The 95thpercentile radon release values in Figure 4-1 and Table 4-4 were used for the estimates. Attachment

C lists the detailed results. Table A-1 also lists concentration values that include background radon 

concentrations. The concentrations used were the average background concentrations of 0.47 pCi/L 

measured from 1989 to 2000 (Fluor 2001). Attachment D shows background concentration 

measurements. 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 A-1 are in 

milligrams per cubic meter and milligrams respectively. Table A-4 lists 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 (WLM). For 222Rn, 1 WL= 100 pCi/L and the derivation of 

WLM is based on an individual who continuously breathed air at the FEMP for 2,000 hr 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 NCRP (1984)]. For 220Rn, 1 WL=7.47 pCi/L and the equilibrium factor 

have been documented to range between 0.02 and 0.1 at several locations (Tomes 1997).

Radionuclide Concentrations and Intake from Routine Emissions (1951-1988)

Therefore,

Radon-222 WLM = L

pCi × Concentration

×

×

170100

7.0 2000 = 8.24 × 10-2 × (radon concentration in pCi/L),

and

Radon-220 WLM = 

L

pCi × Concentration

×

×

17047.7

20001.0 = 1.58 × 10-1 × (thoron concentration in pCi/L). 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 21 of 110

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

Table 4-9. Percentage of time that wind blew in direction of 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

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 emission source (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 consequence of emission from source i,

where i can be Plant 1, 2/3, 4, etc.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 22 of 110

Ri = uranium emission rate of source i. Table 4-1, 4-2, and 4-3 values for uranium

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

Figure 4-1 was used. 

 = atmospheric dilution factor at distance d, where d is the distance from EA-8 to 

emission source i using Table 4-7 values based on distance values in 

Table 4-8. 

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

Section 4.3.2.2.

fi = fraction of time the wind blew in EA-8 direction from emission source i using 

Table 4-9 percentages.

The data in Table 4-10 list inputs and results of application of equation 4-5. The resulting 

CEA8i appear in Attachment C for 1955 Row EA-8 and Columns 3 through 10 for uranium

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

release.

Table 4-10. Inputs and results of application of equation 4-5. 

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-05b 11 4.26E-10

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

a. Plant 1 release included solid and liquid waste incineration and oil and graphite releases

(46.2 kg + 118 kg). 

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 radionuclide emission sources and obtain total radionuclide intake for the 

year by multiplying the concentration by 2,400 m3

: 

5 3

8 * CC .1 1053 / mg

i

EA EA i

− ∑ ×== or 1.53 × 10-2 mg/ m3

 

and

U intake = (1.53 × 10-2 mg/m3

)(2,400 m3) = 36.7 mg

The uranium concentration and intake results are in Attachment C for 1955, columns 13 

and 14, respectively.

Q di





 



 χ
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 23 of 110

Step 3. Transfer the total uranium concentration and annual intake in EA-8 forward to Table A-1 in 

Attachment A. Calculate the radon intake in WLM by adding the average background 

concentration and using the conversion factor in Table A-4 as shown in the following:

Rn intake (WLM) = ((5.0 × 10-9 Ci/m3

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

WLM/(pCi/m3

) 

= 0.450 WLM

Column 10 of Table A-1 lists this radon WLM result for EA-8 for 1955.

4.3.3

Onsite average radionuclide concentrations for 1989 to 1996 were obtained from continuous, highvolume air monitoring stations (AMSs) as part of FEMP sampling programs to monitor releases to the 

environment. The annual site environmental reports for the years covered in this TBD contain the air 

monitoring results. 

Onsite Air Monitored Average Concentrations (1989–2002)

Figure 4-6 shows AMS locations. Onsite 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 show the 

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

concentrations are from the average monitoring results from six fenceline AMS locations along 

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

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 

compliance to National Emission Standards for Hazardous Air Pollutants, Subpart H. 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 

fugitive emissions generated by remediation activities. 

The annual environmental reports presented 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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 24 of 110

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. 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 to 

1996). 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 25 of 110 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 to 1996). 

4.3.3.1

The values in Figure 4-5 were used to estimate radionuclide concentrations at each EA. By using 

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

concentrations obtained from AMS 8 and 9, which are approximately 750 m and 500 m, respectively,

from the center of the Production Area (Plant 4), downwind of the prevailing wind direction (40% of the 

time). The radionuclide release rates used to estimate EA concentrations were the average of those 

release rates calculated for AMS 8 and 9, using ground release (χ/Q)s. The source of release was 

assumed to be at the center of the Production Area (Plant 4). EA concentrations and intakes were 

calculated using these input data. The average radon concentrations measured from the AMS 

locations discussed in the Environmental Reports are used as the average EA radon concentrations 

in accordance with the following. These radon concentrations included the ambient concentration.

Onsite Radionuclide Concentrations and Intakes (1989–1996)

• 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 A-2 in Attachment A lists the results; Attachment C contains more detail.

4.3.3.2

Onsite radionuclide concentrates discussed in the Integrated Site Environmental Reports (Fluor 1997, 

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

Table A-3 in Attachment A lists maximum concentration values from 1997 to 2002.

Onsite Radionuclide Concentrations and Intakes (1997–2002)

4.3.4

The conversion factors listed in Table A-4 in Attachment A were used to develop FEMP site-wide 

intakes (averaging over the EAs) of each uranium and nonuranium radionuclide, and are listed in 

Table 4-11. The site-wide intakes for radon (222Rn) are represented by the 95th-percentile values from 

a lognormal distribution and are listed in Table 4-12, which includes the Geometric Mean (GM) and 

Geometric Standard Deviation (GSD) of the lognormal distribution. 

Site-Wide Average Intake Summary by Isotopes (1951–2002)
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 26 of 110

Table 4-11. Site-wide intakes of each uranium and nonuranium 

radionuclide (Bq/yr) for 1951 through 2002. 

Year Tc-99a Th-232 U-234a Np-237a Pu-239a

1951 3.82E-01 0 5.66E+00 9.48E-04 2.23E-02

1952 1.54E+00 0 2.28E+01 3.83E-03 9.01E-02

1953 5.80E+00 0 8.60E+01 1.44E-02 3.39E-01

1954 4.19E+01 2.86E+00 6.20E+02 1.04E-01 2.45E+00

1955 9.12E+01 3.26E+00 1.35E+03 2.26E-01 5.33E+00

1956 4.39E+01 0 6.50E+02 1.09E-01 2.56E+00

1957 3.31E+01 2.56E-04 4.91E+02 8.22E-02 1.94E+00

1958 2.93E+01 5.85E-04 4.34E+02 7.27E-02 1.71E+00

1959 2.98E+01 5.85E-04 4.41E+02 7.39E-02 1.74E+00

1960 7.86E+00 7.55E-03 1.02E+01 1.95E-02 4.60E-01

1961 2.59E+01 2.05E-02 3.84E+02 6.43E-02 1.51E+00

1962 2.38E+01 2.87E-02 3.53E+02 5.91E-02 1.39E+00

1963 2.09E+01 3.22E-02 3.09E+02 5.18E-02 1.22E+00

1964 1.95E+01 1.44E+00 2.89E+02 4.83E-02 1.14E+00

1965 2.53E+01 1.44E+00 3.75E+02 6.28E-02 1.48E+00

1966 8.54E+00 1.96E+00 1.27E+02 2.12E-02 4.99E-01

1967 1.17E+01 1.44E+00 1.74E+02 2.91E-02 6.85E-01

1968 1.91E+01 1.44E+00 2.83E+02 4.74E-02 1.12E+00

1969 1.56E+01 6.23E+00 2.31E+02 3.86E-02 9.09E-01

1970 6.30E+00 5.16E+00 9.33E+01 1.56E-02 3.68E-01

1971 3.86E+00 2.19E+00 5.73E+01 9.59E-03 2.26E-01

1972 5.43E+00 6.21E-01 8.05E+01 1.35E-02 3.17E-01

1973 5.84E+00 2.49E-01 8.66E+01 1.45E-02 3.41E-01

1974 8.99E+00 4.55E-01 1.33E+02 2.23E-02 5.26E-01

1975 1.05E+01 6.58E-02 1.56E+02 2.61E-02 6.14E-01

1976 1.19E+01 6.67E-02 1.77E+02 2.96E-02 6.97E-01

1977 3.82E+00 1.72E+00 5.66E+01 9.48E-03 2.23E-01

1978 1.11E+00 1.73E+00 1.64E+01 2.75E-03 6.48E-02

1979 1.14E+00 1.74E+00 1.70E+01 2.84E-03 6.69E-02

1980 1.47E+00 3.02E-01 2.18E+01 3.66E-03 8.61E-02

1981 2.55E+00 7.56E-02 3.78E+01 6.34E-03 1.49E-01

1982 1.87E+00 7.55E-02 2.77E+01 4.65E-03 1.09E-01

1983 1.86E+00 7.55E-02 2.75E+01 4.61E-03 1.09E-01

1984 3.72E+00 7.55E-02 5.51E+01 9.23E-03 2.17E-01

1985 1.31E+00 7.55E-02 1.95E+01 3.26E-03 7.68E-02

1986 8.89E-01 7.55E-02 1.32E+01 2.21E-03 5.20E-02

1987 1.55E+00 7.90E-02 2.30E+01 3.86E-03 9.08E-02

1988 1.19E+00 8.16E-02 1.77E+01 2.96E-03 6.97E-02

1989 6.57E-04 3.28E-04 9.81E-03 1.64E-06 3.86E-05

1990 3.53E-04 1.46E-04 5.27E-03 8.83E-07 2.08E-05

1991 5.09E-04 4.88E-05 7.61E-03 1.27E-06 2.99E-05

1992 4.56E-04 1.37E-04 6.81E-03 1.14E-06 2.68E-05

1993 5.47E-04 1.31E-04 8.18E-03 1.37E-06 3.22E-05

1994 1.44E-04 1.00E-04 2.15E-03 3.60E-07 8.46E-06

1995 9.38E-05 3.86E-05 1.40E-03 2.35E-07 5.52E-06

1996 9.48E-05 0 1.42E-03 2.37E-07 5.57E-06

1997 3.64E-03 0 5.44E-02 9.10E-06 2.14E-04

1998 2.29E-03 0 3.42E-02 5.73E-06 1.35E-04

1999 3.32E-03 2.23E-03 4.96E-02 8.30E-06 1.95E-04

2000 2.99E-03 1.69E-02 4.47E-02 7.48E-06 1.76E-04

2001 2.99E-03 6.59E-02 4.47E-02 7.48E-06 1.76E-04

2002 5.75E-03 5.15E-02 8.59E-02 1.44E-05 3.38E-04

a. Based on 2% enriched recycled uranium. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 27 of 110

Table 4-12. Site-wide intakes of radon in WLM for 

1951 through 2002. 

Year

Rn-222a

GM GSD 95th Rn-220

1951 1.13E-01 2.30E+00 4.46E-01 --

1952 1.40E+00 2.87E+00 7.90E+00 --

1953 4.55E-01 2.25E+00 1.72E+00 --

1954 5.78E-01 1.59E+00 1.24E+00 --

1955 5.78E-01 1.59E+00 1.24E+00 --

1956 5.78E-01 1.59E+00 1.24E+00 --

1957 5.78E-01 1.59E+00 1.24E+00 --

1958 5.78E-01 1.59E+00 1.24E+00 --

1959 6.86E-01 1.60E+00 1.48E+00 --

1960 6.86E-01 1.60E+00 1.48E+00 --

1961 6.86E-01 1.60E+00 1.48E+00 --

1962 6.86E-01 1.60E+00 1.48E+00 --

1963 6.86E-01 1.60E+00 1.48E+00 --

1964 6.86E-01 1.60E+00 1.48E+00 --

1965 6.86E-01 1.60E+00 1.48E+00 --

1966 6.86E-01 1.60E+00 1.48E+00 --

1967 6.86E-01 1.60E+00 1.48E+00 --

1968 6.86E-01 1.60E+00 1.48E+00 --

1969 6.86E-01 1.60E+00 1.48E+00 --

1970 6.86E-01 1.60E+00 1.48E+00 --

1971 6.86E-01 1.60E+00 1.48E+00 --

1972 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1973 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1974 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1975 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1976 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1977 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1978 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1979 6.86E-01 1.60E+00 1.48E+00 2.03E-02

1980 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1981 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1982 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1983 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1984 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1985 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1986 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1987 1.71E-01 1.47E+00 3.23E-01 2.03E-02

1988 1.50E-01 1.45E+00 2.75E-01 2.03E-02

1989 7.03E-02 1.73E+00 1.73E-01 2.15E-02

1990 6.09E-02 1.80E+00 1.60E-01 2.15E-02

1991 6.54E-02 1.78E+00 1.68E-01 2.50E-02

1992 5.33E-02 1.74E+00 1.33E-01 1.72E-02

1993 6.03E-02 1.97E+00 1.84E-01 4.09E-02

1994 5.58E-02 1.80E-01 1.47E-01 4.31E-02

1995 7.55E-02 1.73E+00 1.86E-01 3.44E-02

1996 1.53E-01 1.68E+00 3.61E-01 3.03E-02

1997b 1.86E-01b -- -- 8.61E-03

1998b 2.48E-01b -- -- 1.29E-02

1999b 2.58E-01b -- -- 1.29E-02

2000b 1.05E-01b -- -- 8.61E-03

2001b 8.70E-02b -- -- 8.61E-03

2002b 2.90E-02b -- -- 8.61E-03

a. Background included.

b. See Section 4.3.3 for the description of these values. The 1997 

to 2002 values are to be used as maximum constant values, 

applied site-wide. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 28 of 110

4.4 ONSITE 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 was the waste stored in the K-65 Silos and 

the radionuclides in the Production Plants and facilities. To a lesser extent, the radioactive waste pit 

area is another direct radiation source for unmonitored personnel who worked in that area.

4.4.1

There were three significant external radiation sources at the FEMP, but by far the largest was the 

wastes stored in the K-65 Silos. The ambient dose rates started to increase to measurable levels in 

1955 with the relocation of wastes from Niagara Falls, New York, to the silos. This elevation in 

ambient dose was due to the radium content of these wastes. Direct radiation occurred not only from 

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 DOE found it necessary to construct reinforcement beams and coat the exterior 

surfaces in an attempt to strengthen the structures and reduce the radiation. While these actions 

provided some benefit, the radon-thoron dose contribution continued to increase as 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 to the surface of the 

stored material in an attempt to contain the radioactive gases (Fluor 2001). This was effective, as 

indicated 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 increased again, and in 2002 monitoring showed an 

increase of about a factor of four in external radiation. 

K-65 and Production Plants External Dose Contribution

The reference materials reviewed for external radiation information has yielded useful data back to 

1975 (NLO 1975, 1976, 1977, 1978, 1979, 1980, 1981, 1982, 1983, 1984, 1985; WEMCO 1990, 

1991, 1992; FERMCO 1993, 1994, 1995, 1996; Fluor 1997, 1998, 1999, 2000, 2001). The data 

collection, consisting of thermoluminescent dosimeter (TLD) measurements, became possible with 

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 3 months. Table 4-13 is a summary of the maximum dose 

rates measured at the monitoring stations for 1976 through 1995. Figure 4-9 shows the locations of 

the monitoring stations. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 29 of 110

Table 4-13. Radiation dose rates at site boundary. 

Year

Maximum measured dose at TLD stations (mR/hr or mrem/hr)

BS1 BS2 BS3 BS4 BS5 BS6 BS7 BS8 BS9 Onsite Background

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

1995a 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

 

Since 1996, the FEMP expanded its direct radiation monitoring system to continuously measure at 32 

locations, including a number of onsite monitoring locations. Figure 4-10 shows the locations of the 

TLD stations. Table 4-14 provides summary level information pertaining to direct radiation 

measurements for 1996 through 2002.

These measurement data were used to estimate the dose rate distribution to each EA.

In 1985, EG&G, Inc. conducted an on- and offsite aerial survey of the FEMP and surrounding areas 

for radiation due to gamma emission. The survey (EG&G 1985) resulted in dose rate contour maps of 

the site for 1976 and 1985 (Figures 4-11 and 4-12, respectively). The aerial survey data were used to 

correlate dose rates estimated for the EAs using site TLD measurements. The aerial survey data are 

particularly important because the 1976 data represent a low annual production rate of approximately 

1,230 MTU while those for 1985 represent a modest annual production rate of about 3,700 MTU. The 

peak FEMP production rate of was 10,000 MTU in 1960.

Other relevant direct radiation exposure measurements are those called “onsite-background” 

measurements, which were conducted using TLDs starting in 1988 and extending through the first 

quarter of 2003 and covering as many as 15 locations1

. All locations were not monitored throughout 

this period; some locations were added and others were deleted such that there were approximately 

eight monitored 

 

1 From the ORAU O: Drive, O:\DOE Site Images\FEMP\07-28-03-Data Capture\010001026 through 010001036.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 30 of 110

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 fenceline TLD locations (1976 to 1995). 

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 to 2002). 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 31 of 110

Table 4-14. TLD measurement summary. 

Year

TLD monitoring results (mrem/hr)

Fenceline Onsite Offsite

Background

Min. Max. average

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

Figure 4-11. 1976 exposure rate contour map of FEMP survey area. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 32 of 110

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

sites at all times, which provided adequate coverage for the site. The individual locations for each 

year were averaged because the data did not identify specific locations and instead used general 

identifiers such as “men’s locker,” “Health and Safety Laboratory,” etc. Table 4-15 lists average 

values in mrem/month. These onsite-background dose rate measurements were compared with EA 

dose rate estimates derived from onsite and fenceline TLD measurement to validate the EA dose rate 

estimates.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 33 of 110

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

Table 4-15. Average onsite 

background dose rates. 

Year

Average dose rates 

(mrem/month)

1988 12.4

1989 11.33

1990 NA

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

NA – Data Not Available
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 34 of 110

4.4.2

The Waste Pit Area is in EA-5. Figure 4-13 shows the beta gamma dose rate contours in the Waste 

Pit area (FEMP 1994). Table 4-16 lists operational periods and the direct dose rate for each pit

(FEMP 1994). Figure 4-14 shows the radiation profile of the Waste Pit Area, taking into account the 

development of each pit (i.e., increasing dose rates as the pits filled with wastes). 

External Dose Contribution from Waste Pits

Table 4-16. Waste pit 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 pit dose rate profiles. 

The beta and gamma radiation at the Waste Pit area is emitted from radionuclides buried in the 

ground. Gamma radiation is emitted at ground level toward the atmosphere, and scattered from the 

atmosphere to reach receptor locations some distance from the waste pits; this is known as the 

“skyshine” phenomenon. Radiation from skyshine typically is about 1% of the dose rate at the 

receptor location.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 35 of 110

4.4.3

The dose rate at each EA is estimated by summing the dose rates from the major direct dose 

contributors (i.e., K-65 Silos, production facilities, and waste pits) and the background radiation, and

can be represented by equation 4-5: 

Onsite 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.

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 fenceline 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 4-13 and 4-14 and Figure 4-14 were used for equation 4-5. 

Table B-1 in Attachment B summarizes Equation 4-5 results. Equation 4-5 results were correlated to 

the direct dose rate contour maps (Figures 4-11 and 4-12) resulting from the EG&G aerial surveys in 

1976 and 1985. The correlations have resulted in closely matched dose rates in each EA, as listed in 

Table 4-17. 

Starting in 1988, equation 4-5 results were compared to the measured “onsite-background” dose rate 

in Table 4-15. This comparison assumed that the “onsite-background” TLDs were inside buildings. 

One-half of the background dose rate was added to the values in Table 4-15 to correct for building 

shielding. Background radiation from building-penetrating cosmic rays accounts for half the 

background dose rate that is not added to the “onsite-background” dose rate. Equation 4-5 results for 

comparison are dose rate values averaging over all EAs but EA-6, which contains the K-65 silos. 

Because EA-6 has the highest dose rate, excluding its dose rate from site-wide averaging ensures a 

truer equivalent comparison. Table 4-18 lists the results of the comparison. 

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.

Because no usable direct radiation measurements were identified in the available reference materials 

for the 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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 36 of 110

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 back 

to the 1970s, 1960s, and part of the 1950s. The onsite ambient direct radiation dose rates for those 

years were estimated by the ratio of the annual plant production rates, a factor of 1.35 increase of the 

highest average ambient dose rates in the 1980s. Using the same methodology resulted in the 

following ambient dose rate projections:

1951 to 1953 0.015 mrem/hr,

1954 and 1955 1.8 mrem/hr, and 

1956 to 1970 0.3 mrem/hr

Table B-1 in Attachment B summarizes onsite ambient dose rates (mrem/hour) by EAs and years. In 

addition, it lists site-wide average ambient dose rate. EA-6, which includes the K-65 Silos, was 

excluded from the site average because that area has the highest dose rate and is infrequently 

occupied. 

Table 4-17. Comparison of estimated dose rates in EAs and 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)

Table 4-18. 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

1990 0.042 NA

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

NA – Data Not Available
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 37 of 110

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. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 38 of 110

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, 1988, History of FEMP Radionuclide Discharges, Addendum to FEMP2082, Special UC-11, Feed Materials Production Center, Fernald, Ohio, December. 

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, 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, 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, Fernald, Ohio.

FERMCO (Fernald Environment Restoration Management Company), 1996, 1995 Fernald Site 

Environmental Report, Site Restoration Services Department, Fluor-Daniel Fernald, Fernald, 

Ohio.

Fluor (Fluor-Daniel Fernald), 1997, 1996 Fernald Site Environmental Report, The Environmental 

Monitoring Project, 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.

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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 39 of 110

NCRP (National Council on Radiation Protection and Measurements), 1984, Evaluation of 

Occupational and Environmental Exposures to Radon and Radon Daughters in the United 

States, Report 78, Washington, D.C.

NLO (National Lead of Ohio, Inc.), 1975, FEMP Environmental Report for 1975, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1976, FEMP Environmental Report for 1976, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1977, FEMP Environmental Report for 1977, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1978, FEMP Environmental Report for 1978, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1979, FEMP Environmental Report for 1978, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1980, FEMP Environmental Report for 1980, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1981, FEMP Environmental Report for 1981, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1982, FEMP Environmental Report for 1982, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1983, FEMP Environmental Report for 1983, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1984, FEMP Environmental Report for 1984, Fernald 

Environmental Management Project, Fernald, Ohio.

NLO (National Lead of Ohio, Inc.), 1985, FEMP Environmental Report for 1985, Fernald 

Environmental Management Project, 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, 

Neeses, South Carolina. 

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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 40 of 110

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.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 41 of 110

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 dosimeters as 

well as interpretation and documentation of results.

exposure

As used in the technical sense, 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 kg of dry 

air (Standard Temperature and Pressure). An exposure of 1 roentgen is approximately

equivalent to an absorbed dose of 1 rad in soft tissue for higher (more than about 100 keV) 

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. 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 42 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 1 of 13

Table A-1. Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4). 

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) 1.61E+01 1.36E+00 7.14E-01 2.37E+00 1.64E+00 4.91E-01 4.91E-01 7.14E-01 1.70E-01 1.67E+00 9.43E-02

Conc.+ backgrd 1.66E+01 1.83E+00 1.18E+00 2.84E+00 2.11E+00 9.61E-01 9.61E-01 1.18E+00 6.40E-01 2.14E+00 5.64E-01

Intake (WLM) 1.36E+00 1.50E-01 9.76E-02 2.34E-01 1.74E-01 7.92E-02 7.92E-02 9.76E-02 5.27E-02 1.76E-01 4.65E-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) 2.72E+02 2.59E+01 1.50E+01 4.78E+01 3.50E+01 1.07E+01 1.21E+01 1.44E+01 4.13E+00 3.16E+01 4.38E+00

Conc.+ backgrd 2.73E+02 2.63E+01 1.55E+01 4.83E+01 3.55E+01 1.12E+01 1.25E+01 1.49E+01 4.60E+00 3.21E+01 4.85E+00

Intake (WLM) 2.25E+01 2.17E+00 1.27E+00 3.98E+00 2.92E+00 9.19E-01 1.03E+00 1.23E+00 3.79E-01 2.64E+00 3.99E-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) 4.78E+01 6.26E+00 4.29E+00 1.28E+01 1.04E+01 3.26E+00 4.29E+00 3.89E+00 1.45E+00 7.48E+00 2.36E+00

Conc.+ backgrd 4.82E+01 6.73E+00 4.76E+00 1.33E+01 1.08E+01 3.73E+00 4.76E+00 4.36E+00 1.92E+00 7.95E+00 2.83E+00

Intake (WLM) 3.98E+00 5.54E-01 3.92E-01 1.10E+00 8.92E-01 3.07E-01 3.93E-01 3.59E-01 1.58E-01 6.55E-01 2.34E-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) 1.29E+01 6.66E+00 5.99E+00 1.65E+01 1.50E+01 4.92E+00 7.50E+00 5.00E+00 2.49E+00 7.65E+00 5.27E+00

Conc.+ backgrd 1.34E+01 7.13E+00 6.46E+00 1.70E+01 1.55E+01 5.39E+00 7.97E+00 5.47E+00 2.96E+00 8.12E+00 5.74E+00

Intake (WLM) 1.10E+00 5.88E-01 5.32E-01 1.40E+00 1.27E+00 4.44E-01 6.57E-01 4.50E-01 2.44E-01 6.69E-01 4.73E-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) 1.29E+01 6.66E+00 5.99E+00 1.65E+01 1.50E+01 4.92E+00 7.50E+00 5.00E+00 2.49E+00 7.65E+00 5.27E+00

Conc.+ backgrd 1.34E+01 7.13E+00 6.46E+00 1.70E+01 1.55E+01 5.39E+00 7.97E+00 5.47E+00 2.96E+00 8.12E+00 5.74E+00

Intake (WLM) 1.10E+00 5.88E-01 5.32E-01 1.40E+00 1.27E+00 4.44E-01 6.57E-01 4.50E-01 2.44E-01 6.69E-01 4.73E-01
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 43 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 2 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.29E+01 6.66E+00 5.99E+00 1.65E+01 1.50E+01 4.92E+00 7.50E+00 5.00E+00 2.49E+00 7.65E+00 5.27E+00

Conc.+ backgrd 1.34E+01 7.13E+00 6.46E+00 1.70E+01 1.55E+01 5.39E+00 7.97E+00 5.47E+00 2.96E+00 8.12E+00 5.74E+00

Intake (WLM) 1.10E+00 5.88E-01 5.32E-01 1.40E+00 1.27E+00 4.44E-01 6.57E-01 4.50E-01 2.44E-01 6.69E-01 4.73E-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) 1.29E+01 6.66E+00 5.99E+00 1.65E+01 1.50E+01 4.92E+00 7.50E+00 5.00E+00 2.49E+00 7.65E+00 5.27E+00

Conc.+ backgrd 1.34E+01 7.13E+00 6.46E+00 1.70E+01 1.55E+01 5.39E+00 7.97E+00 5.47E+00 2.96E+00 8.12E+00 5.74E+00

Intake (WLM) 1.10E+00 5.88E-01 5.32E-01 1.40E+00 1.27E+00 4.44E-01 6.57E-01 4.50E-01 2.44E-01 6.69E-01 4.73E-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) 1.29E+01 6.66E+00 5.99E+00 1.65E+01 1.50E+01 4.92E+00 7.50E+00 5.00E+00 2.49E+00 7.65E+00 5.27E+00

Conc.+ backgrd 1.34E+01 7.13E+00 6.46E+00 1.70E+01 1.55E+01 5.39E+00 7.97E+00 5.47E+00 2.96E+00 8.12E+00 5.74E+00

Intake (WLM) 1.10E+00 5.88E-01 5.32E-01 1.40E+00 1.27E+00 4.44E-01 6.57E-01 4.50E-01 2.44E-01 6.69E-01 4.73E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.06E+01 1.94E+01 1.63E+01 1.13E+00 9.89E+00 6.42E+00 9.98E+00 9.03E-00 3.45E-00 1.84E+01 3.44E+00

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-01
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 44 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 3 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-01
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 45 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 4 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-01
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 46 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 5 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 47 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 6 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 48 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 7 of 13 

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 1.55E+01 8.00E+00 7.19E+00 1.98E+01 1.80E+01 5.91E+00 9.02E+00 5.99E+00 3.00E+00 9.20E+00 6.33E+00

Conc.+ backgrd 1.59E+01 8.47E+00 7.66E+00 2.03E+01 1.85E+01 6.38E+00 9.49E+00 6.46E+00 3.47E+00 9.67E+00 6.80E+00

Intake (WLM) 1.31E+00 6.98E-01 6.31E-01 1.67E+00 1.52E+00 5.26E-01 7.82E-01 5.32E-01 2.86E-01 7.96E-01 5.60E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 49 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 8 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ Backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 50 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 9 of 13

Table A-1 (Cont’d). Radionuclide concentration and intake summary for 1951 to 1988 (g to Bq conversion factors are in Table A-4).

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) 3.09E+00 1.61E+00 1.44E+00 3.95E+00 3.62E+00 1.18E+00 1.80E+00 1.20E+00 5.99E-01 1.85E+00 1.26E+00

Conc.+ Backgrd 3.56E+00 2.08E+00 1.91E+00 4.42E+00 4.09E+00 1.65E+00 2.27E+00 1.67E+00 1.07E+00 2.32E+00 1.73E+00

Intake (WLM) 2.93E-01 1.71E-01 1.57E-01 3.64E-01 3.37E-01 1.36E-01 1.87E-01 1.37E-01 8.80E-02 1.91E-01 1.43E-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) 2.58E+00 1.33E+00 1.20E+00 3.30E+00 3.00E+00 9.84E-01 1.50E+00 9.99E-01 4.98E-01 1.53E+00 1.05E+00

Conc.+ Backgrd 3.05E+00 1.80E+00 1.67E+00 3.77E+00 3.47E+00 1.45E+00 1.97E+00 1.47E+00 9.68E-01 2.00E+00 1.52E+00

Intake (WLM) 2.51E-01 1.48E-01 1.37E-01 3.11E-01 2.86E-01 1.20E-01 1.62E-01 1.21E-01 7.98E-02 1.65E-01 1.25E-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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 51 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 10 of 13

Table A-2. Radionuclide concentration (Bq/m3

, pCi/L for radon) and intake (Bq, WLM for Rn) from 1989 to 1996. (Breakdown of 

transuranic components of recycled uranium listed in Table A-4.)

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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 52 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 11 of 13

Table A-2 (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 listed in Table A-4.)

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

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

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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 53 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 12 of 13

Table A-3. 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 in Table A-4.)

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

2000

Uranium Conc. (Bq/m3

) 3.66E-05

Intake (Bq) 8.80E-02

Thorium-230 Conc. (Bq/m3

) 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/m3

) 3.66E-05

Intake (Bq) 8.80E-02

Thorium Conc. (Bq/m3

) 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/m3

) 7.03E-05

Intake (Bq) 1.69E-01

Thorium-230 Conc. (Bq/m3

) 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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 54 of 110

ATTACHMENT A

AIRBORNE RADIONUCLIDE CONCENTRATION AND INTAKE SUMMARY

Page 13 of 13

Table A-4. Conversion factors and isotopic content for values in Attachment A. 

Specific activities for recycled uranium:

Uranium 

enrichment

U + cont.

(Bq/mg)

U Pu – 80 ppb Np - 300 ppb Tc- 5,000 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

Use 2% enriched recycled uranium that is claimant-favorable as the default value for mass to activities 

conversion.

From Table A-1 and year 1955, an intake of 24.3 mg for an individual in EA-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 uranium. 

Using the fractions in Column 4 for uranium, Column 6 for plutonium, Column 8 for neptunium, and Column 

10 for technetium, the individual would have inhaled:

1,466 Bq 2% enriched uranium, or 1,129 Bq U-234 (for further breakdown of uranium isotopes, see below) 

4.44 Bq plutonium

0.189 Bq neptunium

75.5 Bq technetium

Specific activities for enriched uranium:

Uranium enrichment Isotope 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 Th-232 and daughters is 

1.11E-07 Ci/g or 4.11 Bq/mg.

WL conversion factor for radon daughters:

1 WL = 100 pCi/L for 100% radon daughter equilibrium

1 WLM (100% equilibrium) = 1.70E+04 pCi/L/hr

No. of RnConcentration

WLM

FactormEquilibriu Exposure Time

WLM × × =

100

0.1

, L

pCi × Concentration × = 17000

7.0 2000 , 

WLM = 8.24E-02 × Rn-222 concentration in pCi/L for 70% equilibrium and 2,000 hr exposure time.

WL conversion factor for thoron daughters:

1 WL = 7.47 pCi/L for 100% Rn-220 daughter equilibrium

1 WLM (100% equilibrium) = 7.47 pCi/L × 170 hr = 1.27E+03 pCi/L/hr

No. of ThoronConcentration

WLM

FactionmEquilibriu Exposure Time

WLM × × =

100 0.1 , L

pCi × Concentration × = 1270

1.0 2000 , 

WLM = 1.57E-01 × Rn-220 concentration in pCi/L for 10% equilibrium and 2,000 hrs exposure time.
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 55 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 1 of 6 

Table B-1. 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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 56 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 2 of 6 

Table B-1 (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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 57 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 3 of 6 

Table B-1 (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

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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 58 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 4 of 6 

Table B-1 (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

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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 59 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 5 of 6 

Table B-1 (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

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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 60 of 110

ATTACHMENT B 

EXTERNAL OCCUPATIONAL ENVIRONMENTAL DOSE RATES SUMMARY 

Page 6 of 6 

Table B-1 (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

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 61 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 1 of 49

Table C-1. 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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 62 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 2 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1951/Radon 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 1.61E-08 1.61E+01

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 1.36E-09 1.36E+00

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 7.14E-10 7.14E-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 2.37E-09 2.37E+00

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 1.64E-09 1.64E+00

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 4.91E-10 4.91E-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 4.91E-10 4.91E-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 7.14E-10 7.14E-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 1.70E-10 1.70E-01

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 1.67E-09 1.67E+00

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 9.43E-11 9.43E-02

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 63 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 3 of 49

Table C-1 (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 6.88E-09 6.88E+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 3.56E-09 3.56E+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 3.20E-09 3.20E+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 8.78E-09 8.78E+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 8.02E-09 8.02E+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 2.62E-09 2.62E+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 4.00E-09 4.00E+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 2.66E-09 2.66E+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 1.33E-09 1.33E+00

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 4.08E-09 4.08E+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 2.82E-09 2.82E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 64 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 4 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1952/Radon 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 2.65E-07 2.65E+02

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 2.23E-08 2.23E+01

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 1.18E-08 1.18E+01

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 3.90E-08 3.90E+01

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 2.70E-08 2.70E+01

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 8.07E-09 8.07E+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 8.07E-09 8.07E+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 1.18E-08 1.18E+01

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 2.80E-09 2.80E+00

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 2.75E-08 2.75E+01

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 1.56E-09 1.56E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 65 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 5 of 49

Table C-1 (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 5.16E-09 5.16E+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 2.67E-09 2.67E+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 2.40E-09 2.40E+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 6.59E-09 6.59E+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 6.02E-09 6.02E+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 1.97E-09 1.97E+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 3.00E-09 3.00E+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 2.00E-09 2.00E+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 9.98E-10 9.98E-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 3.06E-09 3.06E+00

Thorium 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 2.12E-09 2.12E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 66 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 6 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

1953/Radon 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 4.26E-08 4.26E+01

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 3.59E-09 3.59E+00

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 1.89E-09 1.89E+00

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 6.26E-09 6.26E+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 4.34E-09 4.34E+00

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 1.29E-09 1.29E+00

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 1.29E-09 1.29E+00

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 1.89E-09 1.89E+00

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 4.50E-10 4.50E-01

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 4.42E-09 4.42E+00

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 2.50E-10 2.50E-01

Thorium 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 67 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 7 of 49

Table C-1 (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 1.29E-08 1.29E+01

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 6.66E-09 6.66E+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 5.99E-09 5.99E+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 1.65E-08 1.65E+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 1.50E-08 1.50E+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 4.92E-09 4.92E+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 7.50E-09 7.50E+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 5.00E-09 5.00E+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 2.49E-09 2.49E+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 7.65E-09 7.65E+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 5.27E-09 5.27E+00

Thorium 0 0 0 0 0 0 0 6.79E-08 0 0 6.79E-08 1.63E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 68 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 8 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.29E-08 1.29E+01

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 6.66E-09 6.66E+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 5.99E-09 5.99E+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 1.65E-08 1.65E+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 1.50E-08 1.50E+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 4.92E-09 4.92E+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 7.50E-09 7.50E+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 5.00E-09 5.00E+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 2.49E-09 2.49E+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 7.65E-09 7.65E+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 5.27E-09 5.27E+00

Thorium 0 0 0 0 0 0 0 7.77E-08 0 0 7.77E-08 1.87E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 69 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 9 of 49

Table C-1 (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 1.29E-08 1.29E+01

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 6.66E-09 6.66E+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 5.99E-09 5.99E+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 1.65E-08 1.65E+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 1.50E-08 1.50E+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 4.92E-09 4.92E+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 7.50E-09 7.50E+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 5.00E-09 5.00E+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 2.49E-09 2.49E+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 7.65E-09 7.65E+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 5.27E-09 5.27E+00

Thorium 0 0 0 0 0 0 0 0 0 0 0 0 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 70 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 10 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.29E-08 1.29E+01

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 6.66E-09 6.66E+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 5.99E-09 5.99E+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 1.65E-08 1.65E+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 1.50E-08 1.50E+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 4.92E-09 4.92E+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 7.50E-09 7.50E+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 5.00E-09 5.00E+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 2.49E-09 2.49E+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 7.65E-09 7.65E+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 5.27E-09 5.27E+00

Thorium 0 0 0 0 0 0 0 0 0 6.58E-12 6.58E-12 1.58E-05 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 71 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 11 of 49

Table C-1 (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 1.29E-08 1.29E+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 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 6.66E-09 6.66E+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 5.99E-09 5.99E+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 1.65E-08 1.65E+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 1.50E-08 1.50E+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 4.92E-09 4.92E+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 7.50E-09 7.50E+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 5.00E-09 5.00E+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 2.49E-09 2.49E+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 7.65E-09 7.65E+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 5.27E-09 5.27E+00

Thorium 0 0 0 0 0 0 0 0 0 1.50E-11 1.50E-11 3.61E-05 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 72 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 12 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.50E-11 1.50E-11 3.61E-05 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 73 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 13 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-10 1.94E-10 4.65E-04 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 74 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 14 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 5.27E-10 5.27E-10 1.26E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 75 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 15 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 7.38E-10 7.38E-10 1.77E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 76 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 16 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 8.28E-10 8.28E-10 1.99E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 77 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 17 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.22E-10 8.79E-08 2.11E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 78 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 18 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.12E-10 8.79E-08 2.11E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 79 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 19 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 80 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 20 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 9.87E-10 8.79E-08 2.11E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 81 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 21 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 8.70E-08 1.08E-09 8.80E-08 2.11E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 82 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 22 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 83 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 23 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+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 
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 84 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 24 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 85 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 25 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 3.56E-08 1.18E-09 3.68E-08 8.84E-02 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 86 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 26 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 1.26E-08 1.17E-09 1.38E-08 3.31E-02 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 87 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 27 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 2.53E-08 1.22E-09 2.65E-08 6.36E-02 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 88 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 28 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 7.58E-10 1.38E-09 2.14E-09 5.13E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 89 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 29 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 0 1.71E-09 1.71E-09 4.11E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 90 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 30 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.58E-09 1.05E-07 2.51E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 91 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 31 of 49

Table C-1 (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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.85E-09 1.05E-07 2.52E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 92 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 32 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 1.55E-08 1.55E+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 8.00E-09 8.00E+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 7.19E-09 7.19E+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 1.98E-08 1.98E+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 1.80E-08 1.80E+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 5.91E-09 5.91E+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 9.02E-09 9.02E+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 5.99E-09 5.99E+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 3.00E-09 3.00E+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 9.20E-09 9.20E+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 6.33E-09 6.33E+00

Thorium 0 0 0 0 0 0 0 0 1.03E-07 1.94E-09 1.05E-07 2.52E-01 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 93 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 33 of 49

Table C-1 (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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 7.76E-09 7.76E-09 1.86E-02 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 94 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 34 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.66E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 95 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 35 of 49

Table C-1 (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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 96 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 36 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 97 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 37 of 49

Table C-1 (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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 98 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 38 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 99 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 39 of 49

Table C-1 (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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 1.94E-09 1.94E-09 4.65E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 100 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 40 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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 3.09E-09 3.09E+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 1.61E-09 1.61E+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 1.44E-09 1.44E+00

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 3.95E-09 3.95E+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 3.62E-09 3.62E+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 1.18E-09 1.18E+00

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 1.80E-09 1.80E+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 1.20E-09 1.20E+00

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 5.99E-10 5.99E-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 1.85E-09 1.85E+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 1.26E-09 1.26E+00

Thorium 0 0 0 0 0 0 0 0 0 0 2.03E-09 2.03E-09 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 101 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 41 of 49

Table C-1 (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 2.58E-09 2.58E+00

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 1.33E-09 1.33E+00

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 1.20E-09 1.20E+00

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 3.30E-09 3.30E+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 3.00E-09 3.00E+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 9.84E-10 9.84E-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 1.50E-09 1.50E+00

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 9.99E-10 9.99E-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 4.98E-10 4.98E-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 1.53E-09 1.53E+00

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 1.05E-09 1.05E+00

Thorium 0 0 0 0 0 0 0 0 0 2.10E-09 2.10E-09 5.04E-03 0 0
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 102 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 42 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 103 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 43 of 49

Table C-1 (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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 104 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 44 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 105 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 45 of 49

Table C-1 (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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 106 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 46 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 107 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 47 of 49

Table C-1 (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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 108 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 48 of 49

Table C-1 (Cont’d). FEMP radionuclide concentration and intake results by exposure area and year.

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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 109 of 110

ATTACHMENT C 

FEMP RADIONUCLIDE CONCENTRATION AND INTAKE RESULTS BY EXPOSURE AREA AND YEAR

Page 49 of 49

Table C-1 (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
Document No. ORAUT-TKBS-0017-4 Revision No. 01 Effective Date: 02/07/2006 Page 110 of 110

ATTACHMENT D 

ANNUAL AVERAGE RADON BACKGROUND CONCENTRATIONS AND 

CONCENTRATION AT SELECTED RADON LOCATIONS, 1989-2002

Figure D-1. Annual average radon background concentrations and concentration at selected radon 

locations, 1989-2002 (Fluor 2003).