ML031330777

Annual Radiological Environmental Operating Report, Duke Power Company, Oconee Nuclear Station, Units 1, 2, & 3, Table of Contents Through Table 4.1-A

ML031330777
Person / Time
Site:	Oconee
Issue date:	12/31/2002
From:	Duke Power Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML031330777 (57)

Text

Duke rSPower.

A Duke Energy Company Oconee Nuclear Station Units 1, 2 and 3 Annual Radiological Environmental Operating Report 2002

A Duke Energy Company ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY OCONEE NUCLEAR STATION Units 1, 2, and 3 2002

TABLE OF CONTENTS 1.0 Executive Sunimarv . . . . . 1-1 2.0 Introdluction . . . . . . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . . . . . 2-1 2.2 Scope and Requirements of the REMP . . . . . . . 2-1 2.3 Statistical and Calculational Methodology . . . . . . . 2-2 2.3.1 Estimation of the Mean Value . . . . . . . . 2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity . . 2-3 2.3.3 Trend Identification . . . . . . . . . 2-3 3.0 Interpretationi of Results . . . . . . . . . . . 3-1 3.1 Airborne Radioiodine and Particulates . . . . . . . 3-2 3.2 Drinking Water. . . . . . . . . . . . 3-5 3.3 Surface Water . . . . . . . . . . . . 3-7 3.4 Milk. . . . . . . . . . . . . . 3-10 3.5 Broadleaf Vegetation . . . . . . . . . . 3-12 3.6 Fish . . . . . . . . . . . . . . 3-14 3.7 Shoreline Sediment . . . . . . . . . . . 3-17 3.8 Direct Gamma Radiation . . . . . . . . . . 3-20 3.9 Land Use Census . . . . . . . . . . . 3-22 4.0 Evaltuationi or Dose . . . . . . . . . . . . 4-1 4.1 Dose from Environmental Measurements . . . . . . . 4-1 4.2 Estimated Dose from Releases . . . . . . . . . 4-1 4.3 Comparison of Doses. . . . . . . . . . . 4-2 5.0 Quality Assturance . . . . . . . . . . . . 5-1 5.1 Sample Collection . . . . . . . . . . 5-1 5.2 Sample Analysis . . . . . . . . . . . 5-1 5.3 Dosimetry Analysis . . . . . . . . . . . 5-1 5.4 Laboratory Equipment Quality Assurance . . . . . . . 5-1 5.4.1 Daily Quality Control . . . . . . . . . 5-1 5.4.2 Calibration Verification . . . . . . . . . 5-1 5.4.3 Batch Processing . . . . . . . . . . 5-1 5.5 Duke Power Intercomparison Program . . . . . . . 5-2 5.6 Duke Power Audits . . . . . . . . . . . 5-2 5.7 U.S. Nuclear Regulatory Commission Inspections . . . . . 5-2 5.8 State of South Carolina Intercomparison Program . . . . . 5-2 5.9 TLD Intercomparison Program . . . . . . . . . 5-2 5.9.1 Nuclear Technology Services Intercomparison Program . . . 5-2 5.9.2 State of North Carolina Intercomparison Program . . . . 5-3 5.9.3 Internal Crosscheck (Duke Power) . . . . . . . 5-3 6.0 Rererences . . . . . . . . . . . . . 6-1 Appendices Appendix A: Environmental Sampling and Analysis Procedures . . . . A-1 i

I. Change of Sampling Procedures. A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A.l Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water. A-4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Fish A-4 A.7 Shoreline Sediment . A-5 A.8 Direct Gamma Radiation (TLD) A-5 A.9 Annual Land Use Census . A-5 Appendix B: Radiological Env. Monitoring Program - Summary of Results. B-1 Air Particulate B-2 Air Radioiodine. B-3 Drinking Water. B-4 Surface Water B-5 Milk . B-6 Broadleaf Vegetation B-7 Fish. B-8 Shoreline Sediment B-9 Direct Gamma Radiation (TLD) B-10 Appendix C: Sampling Deviations and Unavailable Analyses C-l C.1 Sampling Deviations C-2 C.2 Unavailable Analyses. C-4 Appendix D: Analytical Deviations D-1 D. 1 Analytical Deviations. D-2 Appendix E: Radiological Environmental Monitoring Program Results E-1 LISI' OF FIGURES 2.1-1 Sampling Locations Map (One Mile Radius) 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-4 3.2 Concentration of Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water . 3-8 3.5 Concentration of Cs-137 in Broadleaf Vegetation 3-12 3.6-1 Concentration of Cs-137 in Fish 3-15 3.6-2 Concentration of Cs-134 in Fish 3-15 3.7-1 Concentration of Cs-137 in Shoreline Sediment 3-18 3.7-2 Concentration of Co-60 in Shoreline Sediment 3-18 3.8 Direct Gamma Radiation (TLD) Results 3-20 3.9 Land Use Census Map 3-23 LISI' OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples . 2-8 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection . 2-9 3.1-A Mean Concentration of Air Radioiodine (1-131) . 3-3 ii

3.1-B Mean Concentration of Gross Beta in Air Particulate . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 3.3 Mean Concentrations of Radionuclides in Surface Water 3-9 3.4 Mean Concentrations of Radionuclides in Milk . 3-11 3.5 Mean Concentrations of Radionuclides in Vegetation . 3-13 3.6 Mean Concentrations of Radionuclides in Fish 3-16 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment 3-19 3.8 Direct Gamma Radiation (TLD) Results 3-21 3.9 Oconee 2002 Land Use Census Results 3-22 4.1-A 2002 Environmental and Effluent Dose Comparison 4-3 4.1-B Maximum Individual Dose for 2002 based on Environmental Measurements for Oconee Nuclear Station . 4-6 5.0-A Duke Power Company Interlaboratory Comparison Program 5-4 5.0-B 2002 Environmental Dosimeter Cross-Check Results 5-11 LIST OF ACRONY'NIS USED IN THIS TEXT (in alphabeticalorder)

BW BiWeekly C Control DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency GI-LLI Gastrointestinal - Lower Large Intestine LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual ONS Oconee Nuclear Station pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Process Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter ICi/mi microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Oconee Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2002.

Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLC's). Required analyses were performed and detection capabilities were met for all collected samples as required by SLC's. One-thousand forty-four samples were analyzed comprising 1,161 test results in order to compile data for the 2002 report. Based on the annual land use census, the current number of sampling sites for Oconee Nuclear Station is sufficient.

Concentrations observed in the environment in 2002 for station related radionuclides were within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. All positively identified measurements were within limits as specified in SLC's.

Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 5.41E-01 mrem for 2002. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

Air Samplin at Oconee Nuclear Station Section I - Page I

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant.

ONS consists of three pressurized water reactors. Each unit has an output of 866 megawatts net. Unit 1 began commercial operation 7/15/1973. Unit 2 began commercial operation 9/09/1974, and Unit 3 on 12/16/1974. An independent spent fuel storage installation is also located at the site.

Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within a one mile radius of ONS. Figure 2.1-2 comprises all sample locations within a ten mile radius of ONS.

2.2 SCOPE AND REQUIREMENTS OF THE REMP An environmental monitoring program has been in effect at Oconee Nuclear Station since 1969, four years prior to operation of Unit 1 in 1973. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.

The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency, and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from Oconee Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and 10CFR72.44(d)(2) and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the Section 2 - Page I

environment. Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B lists the REMP analysis and frequency schedule.

The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.9.

Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):

N Ixi X =i=l N

Where:

x = estimate of the mean, i individual sample, N = total number of samples with a net activity (or concentration),

Xi = net activity (or concentration) for sample i.

NOTE: "Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower C Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.

Section 2 -Page 2

2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program.

LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

MDA - The MDA may be thought of as an "actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.

2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Some factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident). Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include some judgment by plant personnel.

Section 2 - Page 3

Oconee Nuclear Station Figure 2.1-1 Sampling Locations Map (One Mile Radius)

• TLD Locations A AJI Other Locations Section 2 - Page 4

Oconee Nuclear Station Figure 2.1-2 Sampling Locations Map (Ten Mile Radius)

• TLD Locations A All Other Locations Section 2 - Page 5 c-Or

~~~~~~~~~~'

. l . ....

TABLE 2.1-A OCONEE RADIOLOGICAL MONITORING IROGRAM SAMPLING LOCATIONS Table 2.1 -A Codes W Weekly SM Semimonthl BW BiWeekly Q Quarterly M Monthly SA Semiannuall C Control Site L Location .

Description Air Rad. &

PacrtiCuatC Surfare Water Drinking Water Sbormilne Sediment Flsh Milk Bradler Vtgedatton 060

• Greenville Water Intake Road (2.6 mi NNE) W M SA M 062 C Lake Keowee Hydro Intake (0.8 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 (0.8 mi ESE) [000.7] M SA SA 063.1 Lake Hartwell Hwy 183 Bridge (0.78 mi E) M 064 C Seneca (6.7 mi SSW) [004.1] M 066 Anderson (19.0 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 (4.2 mi SSE) [005.2] SA SA 068 C High Falls County Park (2.0 mi W) SA 071 Clemson Dairy (10.3 mi SSE) [006.3] SM 081 C Clemson Operations Center (9.3 mi SE) W M 074 Keowee Key Resort (2.3 mi NNW) W 077 Skimmer Wall (1.0 mi SW) W M 078 Recreation Site (0.6 mi WSW) W . -

079 Keowee Dam (0.5 mi NE) W M 080 C Martin Dairy (17.2 mi SE) SM 082 Oakway Dairy (17.8 mi SSW) SM

• Control for Fish Only C = Control

[ ] Location Numbers prior to 1984 Section 2 - Page 6

TABLE 2.1-B OCONEE RADIOLOCICAL MONITORING PROGRAM SAMI'LING LOCATIONS (TLD SITES)

Site Location Description Distance Sector Site Location Description Distance Sector 020 SITE BOUNDARY 0.1 miles N 040 MICROWAVE TOWER. SIX MILE 4.5 miles E 021 SITE BOUNDARY 0.3 miles NNE 041 JCT HWY 101 & 133 4.0 miles ESE LAWRENCE CHAPEL CHURCH, 022 SITE BOUNDARY 0.5 miles NE 042 HWY 133 5.0 miles SE HWY 291 AT 023 SITE BOUNDARY 0.9 miles ENE 043 ISSAQUEENA PARK ENTRANCE 4.0 miles SSE 024 SITE BOUNDARY 0.8 miles E 044 HWY 130 AT LITTLE RIVER DAM 4.0 miles S TERMINUS OF HWY 588 025 SITE BOUNDARY 0.4 miles ESE 045 AT CROOKED CREEK 5.0 miles SSW HWY 188 AT 026 SITE BOUNDARY 0.3 miles SE 046 CROOKED CREEK BRIDGE 4.5 miles SW 027 SITE BOUNDARY 0.4 miles SSE 047 NEW HOPE CHURCH, HWY 188 4.0 miles WSW 028 SITE BOUNDARY 0.5 miles S 048 JCT HWY 175 & 188 4.0 miles W 029 SITE BOUNDARY 0.6 miles SSW 049 JCT HWY 201 &92 4.0 miles WNW STAMP CREEK LANDING -

030 SITE BOUNDARY 0.4 miles SW 050 END OF HWY 92 4.0 miles NW 031 SITE BOUNDARY 0.3 miles WSW 051 HWY 128, 1 MILE N OF HWY 130 4.5 miles NNW DPC BRANCH OFFICE SITE -

076 SITE BOUNDARY 0.2 miles W 052 SI PICKENS 12.0 miles ENE DPC BRANCH OFFICE SITE -

032 SITE BOUNDARY 0.2 miles WNW 053 S LIBERTY 11.0 miles E 033 SITE BOUNDARY 0.2 miles WNW 054 SI POST OFFICE - HWY 93 NORRIS 9.5 miles ESE 034 SITE BOUNDARY 0.2 miles NW 055 SI CLEMSON METEOROLOGY PLOT 9.5 miles SSE 035 SITE BOUNDARY 0.2 miles NNW 056 SI WATER TOWER - SENECA 8.4 miles SSW 036 MILE CREEK LANDING 4.0 miles N 057 SI OCONEE MEMORIAL HOSPITAL 9.0 miles SW BRANCH RD SUBSTATION 037 KEOWEE CHURCH, HWY 327 4.5 miles NNE 058 C WALHALLA. CONTROL 9.4 miles WSW DURHAM CONVENIENCE MART, 038 JCr HWY 183 &133 4.0 miles NE 059 SI TAMASSEE DAR SCHOOL 9.2 miles NW HWY 133, MILE EAST OF 039 JCT HWY 183 & 133 4.0 miles ENE F081 C CLEMSON OPERATIONS CENTER 9.3 miles SE C = Control SI = Special Interest Section 2 - Page 7

TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Broadleaf (pCi/liter) or Gases (pCi/kg-wet) (pCiAiter) Vegetation i_____________ (pCi/m 3 ) (pCi/kg-wet)

H-3 20,0003)

Mn-54 1,000 30.000 Fe-59 400 10.000 Co-58 1,000 30.000 Co-60 300 10,000 Zn-65 300 20.000 Zr-Nb-95 400 1-131 2 (b) 1 3 100 Cs-134 30 10 1,000 60 1.000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) For drinking water samples only. This is 40CFR Part 141 value.

(b) If low-level I-131 analyses are performed.

TABLE 2.2-B RENIP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic l-131 Beta ____

Air Radioiodine Weekly X l l_i___ ii Air Weekly X Particulate Quarterly Composite X l ______ li Direct Radiation Quarterly ________l X Surface Monthly X Water Quarterly Composite l _ _ X Drinking Monthly X _ _ l (a) X l Water Quarterly Composite l _ l X _ ______

Shoreline Sediment Semiannually X ____i_i_ii Milk Semimonthly l X X X

Fish Semiannualy X Broadleaf Vegetation Monthly X (a) Low level I-131 analysis will be performed if abnormal releases occur which could reasonably result in> 1 pCi/liter of I-131 in drinking water. An LLD of 1 pCiliter will be required for this analysis.

Section 2 - Page 8

TABLE 2.2-C MAXIMUM VALUES FOR TlIE LONER LIMITS OF DETECTION Analysis Water Air Fish Milk Broadleaf Sediment (pCiliter) Particulates (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry) or Gases (pCi/kg-wet) 3 (pCi/M ) I Gross Beta 4 0.01 _

H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58. 60 15 130 l Zn-65 30 260 l Zr-95 30 Nb-95 15 1-131 15(a) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) LLD for low-level 1-131 analyses is 1 pCi/liter if performed Section 2 - Page 9

3.0 INTERPRETATION OF RESULTS Review of 2002 REMP analysis results was performed to identify changes in environmental levels as a result of station operations. The review is summarized in this section. Data from 2002 was compared to preoperational and historical data. Sample data for some media is not directly comparable to preoperational and earlier operational sample results because of either significant changes in the analysis methods or changes in the reporting of the results.

Evaluation for significant trends was performed for the radionuclides that have required LLDs listed in Selected Licensee Commitment 16.11.6. These radionuclides are collectively referred to as "Selected Licensee Commitments radionuclides" and include H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140. Drinking water gross beta results are routinely trended. Trending of air particulate gross beta results was initiated in 1996 when the analysis was resumed. Trending is also performed for other radionuclides that are detected and could have been the result of station effluents. Only Selected Licensee Commitment radionuclides were detected in 2002.

Trending was performed by comparing annual mean concentrations of any effluent related detected radionuclide to historical results. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the radionuclide's SLC reporting level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level.

The highest value reached during 2002 was 5.5% for Cs-137 in a fish sample collected at Location 063.

Changes in sample location, analytical technique, and presentation of results must be considered when reviewing for trends. Calculation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net results (sample minus background), positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. A change in gamma spectroscopy analysis systems in 1987 ended a period when many measurements yielded detectable low-level activity for both indicator and control location samples. It is thought that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

Data presented in Sections 3.1 - 3.8 support the conclusion that there were no significant increases in radionuclides in the environment around ONS due to station operations in 2002.

Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas.

Section 3 - Page I

3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2002, 310 radioiodine and particulate samples were analyzed, 258 from five indicator locations and 52 from the control location. Radioiodine samples were analyzed by gamma spectroscopy. Particulate samples were analyzed for gross beta. Gamma analysis was performed on 24 composites of particulate samples, 20 at the five indicator locations and four at the control location.

There was no detectable I-131 in air samples in 2002. Table 3.1-A gives the highest indicator location annual mean and control location annual mean for 1-131 since the preoperational period.

The table shows similar concentrations for both the indicator and control locations and the activities decreasing from early in the operational history of the plant. No 1-131 has been detected since 1994.

Cs-137 was not detected in air radioiodine samples in 2002. Cs-137 has been detected in cartridges in previous years. A study performed in 1990 determined Cs-137 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion.

There were no detectable gamma emitting radionuclides detected in air particulate samples in 2002. No gamma emitting particulates have been detected in indicator location samples since the change in gamma spectroscopy analysis systems in 1987.

Beta analysis of particulate filters was initiated in March of 1996 and became required by Selected Licensee Commitments in 1998. Gross beta analysis was performed on particulate filters during the preoperational and early operational history of the plant but had not been required since 1984. Figure 3.1 summarizes gross beta results for the indicator location with the highest annual mean and the control location samples. Both the indicator and control location results are similar in concentration and are near the lower range of preoperational gross beta results.

K-40 and Be-7 are the naturally occurring radionuclides that were observed in air samples.

Oconee Air Monitoring Station Section 3 - Page 2

Table 3.1-A Mean Concentration of Air Radioiodine (-131)

Year Indicator Location (pCim 3 ) Control Location (pCi/m 3 )

Preoperational 1969-1972 O.OOE0 O.OOE0 Feb. 1973 - June 1973 O.OOE0 O.OOE0 July 1973 - Dec. 1973 O.00E0 O.OOE0 Jan. 1974 - June 1974 O.OOE0 O.OOE0 July 1974 - Dec. 1974 2.60E-2 8.OOE-3 Jan. 1975 - June 1975 8.65E-2 3.12E-2 July 1975 - Dec. 1975 1.13E-2 9.52E-3 1976 2.76E-2 2.18E-2 1977 3.60E-2 3.60E-2 1978 2.19E-1 1.15E-1 1979 7.54E-3 4.75E-4 1980 3.07E-3 9.67E-4 1981 6.31E-3 5.39E-4 1982 2.87E-3 8.1OE-4 1983 1.48E-3 3.05E-4 1984 8.1IE-4 -2.30E-5 1985 7.71E-4 4.54E-4 1986 5.02E-3 7.86E-3 1987 4.29E-3 5.19E-3 1988 O.OOEO O.OOEO 1989 4.99E-4 O.OOE0 1990 O.OOE0 O.OOEO 1991 O.OOEO O.OOEO 1992 O.OOEO O.OOEO 1993 O.OOE0 O.OOE0 1994 1.03E-2 O.OOEO 1995 O.OOEO O.OOEO 1996 O.OOEO O.OOEO 1997 O.OOEO O.OOEO 1998 O.OOEO O.OOEO 1999 O.0E0 0.00E0 2000 O.OOEO O.OOEO 2001 O.OOEO O.OOEO 2002 O.OOE0 O.OOE0 O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 -Page 3

Figure 3.1 3

pCrM Concentration of Gross Beta in Air Particulate 4.50E 4.00E-02 3.50E-02 3.00E-02 _

2.50E-02 __e_____

2.00E-02 _____1 _l 1.50E-02 _ _

1.OOE-02 5.00E-03 O.OOE+00 1996 1997 1998 1999 2000 2001 2002 Pre-operational sample results l  ; + Control Location Indicator ocation ranged from 0.04 to 1.46 pCrm C Tlhere is no reporting level for gross beta in airparticulate Table 3.1-B Mean Concentration of Gross Beta in Air Particulate Monitoring Period Indicator Location (pCi/m 3) Control Location (pCi/n 3 )

1996 3.87E-2 3.69E-2 1997 2.87E-2 2.92E-2 1998 2.47E-2 1.56E-2 1999 2.85E-2 2.23E-2 2000 2.38E-2 1.85E-2 2001 2.05E-2 1.94E-2 Average (1996 - 2001) 2.751E-2 2.371E-2 2002 2.01E-2 1.84E-2 Section 3 - Page 4 C_

3.2 DRINKING WATER Gross beta analysis and gamma spectroscopy were performed on 39 monthly drinking water samples. These samples were composited to form 15 quarterly period samples for Tritium analysis. Two indicator locations and a control location were sampled; however, only one of the indicator locations is downstream of the effluent release point.

Table 3.2 lists the highest indicator location annual mean and control location annual mean for gross beta results since the preoperational period. The indicator location had an average concentration of 1.61 pCi/liter in 2002, and the control location had a concentration of 1.21 pCi/liter. The 2001 indicator mean was 1.75 pCi/liter. The table shows that 2002 gross beta levels in drinking water are slightly lower than preopreational concentrations. The dose for consumption of water was less than one mrem per year, historically and for 2002; therefore low-level iodine analysis is not required.

Tritium was detected in five of the 15 composite samples during 2002. Tritium was detected in five of the 15 composite samples during 2001. The 2002 mean indicator location 066 concentration was 338 pCi/liter, which is 1.69% of the reporting level. Table 3.2 and Figure 3.2 show the highest indicator and control location annual means for Tritium since analysis was initiated early in the operational period. Tritium concentrations have decreased at both the indicator and control locations. The closure of the Clemson water plant in 1989 is one reason for the decrease shown in the table and graph. The Clemson site was typically the high mean location when the plant was in operation.

There were no gamma emitting radionuclides identified in drinking water samples in 2002.

Gamma spectroscopy analysis has not detected any activity in the water supplies since 1988.

K-40 is the naturally occurring radionuclide that was observed in drinking water samples.

Figure 3.2 Current reporting level implemented 1984 pCi/liter Concentration of Tritium in Drinking Water 5000 4500 4000_

3500 3000 ___

2500 l ___ _ _

1500 . =- _ = = = = =

1000 _ _ __vAf _

500 0

1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 l-- Control Location U Indicator Location - 20% Reporting Level Section 3 - Page 5

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCi/l) Tritium (pCi/1)

Year Indicator Control Indicator Control Location Location Location Location Preoperational ending Jan. 1971 3.03 5.90 Analysis not required Preoperational ending Jan. 1973 3.58 4.94 Analysis not required Feb. 1973 - June 1973 Qualitative results reported Analysis not required June 1973 - Dec. 1973 7.15 21.78 Analysis not required Jan. 1974 - June 1974 3.13 6.98 Analysis not required July 1974 - Dec. 1974 2.24 2.02 525 330 Jan. 1975 - June 1975 1.98 1.59 600 300 July 1975 - Dec. 1975 2.01 1.22 2990 505 1976 2.38 2.00 2196 224 1977 2.70 2.30 1200 290 1978 2.56 2.17 1050 333 1979 1.83 1.36 576 235 1980 1.86 1.63 660 200 1981 1.98 1.88 830 127 1982 2.04 1.45 643 153 1983 1.85 1.54 937 220 1984 1.87 1.08 765 145 1985 2.14 1.16 856 210 1986 1.91 1.04 1240 503 1987 2.00 1.20 815 680 1988 2.00 1.40 1570 0.00 1989 2.30 1.80 1350 559 1990 3.00 2.70 0.00 0.00 1991 1.80 1.40 558 0.00 1992 3.20 1.60 0.00 0.00 1993 2.10 1.90 0.00 0.00 1994 1.90 2.10 0.00 0.00 1995 5.10 2.90 248 0.00 1996 2.07 1.77 214 0.00 1997 2.52 2.23 194 0.00 1998 2.48 1.70 0.00 0.00 1999 1.73 1.49 185 0.00 2000 2.07 1.68 251 0.00 2001 1.75 1.29 390 0.00 2002 1.61 1.21 338 0.00 0.00 = no detectable measurements 1989 -Clemson water plant closes; nearest downstream plant is Anderson.

1979 - 1986 mean based on all net activity results Section 3 - Page 6

3.3 SURFACE WN'ATER Gamma spectroscopy was performed on 26 monthly surface water samples. These samples were composited to form 10 quarterly samples for Tritium analysis. One indicator and one control location were sampled. The indicator location is near the liquid effluent release point.

A new surface water site, 063.1 (0.78 miles E), was added to the REMP in the vicinity of the existing site 063 (0.8 miles ESE). The new site was added due to safety and equipment reliability concerns with the existing site 063 on the highway 183 bridge. The existing site 063 was removed from service effective 8/29/2002. The new site 063.1 began operation effective 7/12/2002.

Tritium was detected in the five indicator location samples. Three of the indicator samples were taken from site 063 and two indicator samples were taken from indicator site 063.1. The 2002 average concentration was 10,000 pCi/liter. The individual samples ranged from 5,060 pCi/liter to 13,700 pCi/liter. The 2001 mean concentration was 7,426 pCi/liter. Tritium was not detected in any control surface water samples.

There is a slight increasing trend in tritium surface water results since 1998. This increase correlates with tritium releases from the plant during this period. In addition, the region has experienced a severe drought over the past four years. Rainfall in the area has been substantially below normal (approximately 40 inches below normal) for the past four years. The increase in tritium surface water is considered to be the result of releases from the plant and reduced dilution because of the drought.

Figure 3.3 shows the indicator and control annual means for Tritium since the preoperational period. Table 3.3 lists the indicator annual means.

Gamma spectroscopy analysis did not detect any activities during 2002. In 1999, gamma spectroscopy analysis detected Co-58 in one indicator sample at 27.2 pCi/liter, which represents 2.73% of the reporting level. Gamma spectroscopy analysis has not detected any other activity in surface water samples since 1992. Table 3.3 summarizes the indicator annual means of radionuclides detected since the change in the gamma spectroscopy analysis system in 1987.

Visual inspection of the gamma spectroscopy tabular data covering the early operational period through 2002 did not reveal any increasing trends.

K-40 is the naturally occurring radionuclide observed in surface water samples in 2002.

Section 3 - Page 7

Figure 3.3 pCiIliter Concentration of Tritium in Surface Water 60000 50000 40000-30000 -__

20000 __

10000 t L___

1969 1972 1975 1977 1980 1983 1986 1989 1992 1995 1998 2001 0 Control Location - Indicator Location There is no reporting levelfor Tritiurn in surface water Section 3 - Page 8

Table 3.3 Mean Concentrations of Radionuclides in Surface Water Year Co-58 (pCi/l) Co-60 (pCi/1) Nb-95 (pCi/l) Cs-137 (pCi/l) H-3 pCi/l)

Preoperational 1969 Qualitative results reported 4.86E2 Preoperational 1970 5.94E2 Preoperational 1971 4.01E2 Preoperational 1972 3.62E2 1973 O.OOEO 1974 O.OOEO 1.32E1 O.OOEO 1.60E1 1.99E3 Jan. 1975 - June 1975 O.OOEO 0.00E0 0.OOEO O.OOEO 1.56E4 July 1975 - Dec. 1975 O.OOEO 1.34E1 O.OOEO O.OOEO 5.52E4 1976 1.08E2 3.30E1 O.OOEO 3.50E1 2.95E4 1977 2.60E1 1.80E1 O.OOEO 3.10EI 2.90E3 1978 2.96E2 O.OOEO O.OOEO 2.22E1 8.00E2 1979 1.33E0 2.60E0 1.78E0 2.82E0 4.37E3 1980 1.56E0 2.30E0 1.22E0 5.40E0 4.93E3 1981 1.1OEO 6.1OE-1 1.70E0 3.90E0 7.21E3 1982 6.14E-1 1.99E0 2.29E0 4.85E0 6.13E3 1983 6.99E-1 3.02E0 3.91E-1 6.83E-1 8.40E3 1984 9.40E-1 6.30E-1 7.90E-1 4.83E-1 9.90E3 1985 2.15E-1 6.27E- 1 4.95E-1 9.90E-1 1.05E4 1986 3.28E0 1.23E0 1.14E0 3.07E-1 1.26E4 1987 5.10EI 3.40E0 4.00EO O.OOEO 7.08E3 1988 6.20EO 5.OOEO 2.50E0 3.50EO 1.1OE4 1989 5.30E0 3.OOEO O.OOEO 3.40E0 1.02E4 1990 1.70E0 1.60EO O.OOEO O.OOEO 1.03E4 1991 5.40EO O.OOEO 0.OOEO O.OOEO 5.76E3 1992 2.50EO O.OOEO O.OOEO O.OOEO 6.22E3 1993 O.OOEO O.OOEO O.OOEO O.OOEO 8.62E3 1994 O.OOEO O.OOEO O.OOEO O.OOEO 5.75E3 1995 O.OOEO O.OOEO O.OOEO O.OOEO 6.65E3 1996 O.OOEO O.OOEO O.OOEO O.OOEO 4.54E3 1997 O.OOEO O.OOEO O.OOEO O.OOEO 5.50E3 1998 O.OOEO O.OOEO O.OOEO O.OOEO 3.35E3 1999 2.73E1 O.OOEO O.OOEO O.OOEO 1.13E4 2000 O.OOEO O.OOEO O.OOEO O.OOEO 1.48E4 2001 O.OOEO O.OOEO O.OOEO O.OOEO 7.43E3 2002 O.OOEO O.OOEO O.OOEO O.OOEO l.OOE4 O.OOEO = no detectable measurements 1979-1986 mean based on all net activity results Section 3 - Page 9

3.4 MILK Gamma spectroscopy and low level iodine analysis was performed on 78 milk samples collected in 2002. Two indicator locations and one control location were sampled.

There were no gamma emitting radionuclides

_l

/$ identified in indicator or control location samples in 2002. Cs-137 is the only radionuclide, other than naturally occurring, reported in milk samples since 1988. Cs-137 in milk is not unusual. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous years.

Table 3.4 lists the highest indicator location annual mean and control location annual mean for Cs-137 since the preoperational period. The table shows similar concentrations for both indicator and control locations.

K-40 is a naturally occurring radionuclide observed in milk samples in 2002.

Milk Samping Milk Sampling Section 3 - Page 10

Table 3.4 Mean Concentration of Radionuclides in Milk Year Cs-137 Indicator (pCill) Cs-137 Control (pCi/1)

Preoperational 1.57E1 1.46E1 Feb. 1973 -June 1973 Qualitative results reported Qualitative results reported July 1973 - Dec. 1973 5.80EO "

Jan. 1974 -June 1974 5.30EO O.OOEO July 1974 - Dec. 1974 l.lIE1 O.OOEO Jan. 1975 -June 1975 1.51EI 9.45EO July 1975 - Dec. 1975 O.OOEO O.OOEO 1976 1.80E1 7.47EO 1977 O.OOEO O.OOEO 1978 1.33E1 1.33E1 1979 7.25E0 2.52EO 1980 3.58E0 2.63EO 1981 5.52E0 5.51EO 1982 2.71E0 3.25EO 1983 5.04EO -4.27E-1 1984 2.30E0 2.58EO 1985 2.38E0 1.31EO 1986 2.92E0 2.97EO 1987 4.90E0 4.90EO 1988 3.90E0 3.20EO 1989 4.70E0 2.90EO 1990 6.40EO O.OOEO 1991 5.OOEO O.OOEO 1992 6.60EO 0.OOEO 1993 O.OOEO O.OOEO 1994 O.OOEO 1.80EO 1995 2.30E0 2.00EO 1996 O.OOEO 4.1 OEO 1997 O.OOEO O.OOEO 1998 O.OOEO O.OOEO 1999 O.OOEO O.OOEO 2000 O.OOEO O.OOEO 2001 O.OOEO O.OOEO 2002 0.00E0 0.00E0 O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page II

3.5 BROADLEAF VEGETATION Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2002. Three indicator locations and one control location were sampled. Cs-137 was reported in one indicator sample. Cs-137 was not detected in any control location samples. No other effluent related radionuclide was identified.

Sampling of control location 073 (which has historically had measurable Cs-137 concentrations greater than any indicator location) was discontinued early in 1999 due to construction. The new control location, 081, has had no measurable Cs-137 since this location was added to the program in 1998.

One of the thirty-six indicator location samples contained Cs-137 with a concentration of 84.4 pCi/kg (4.22% of the reporting level).

Cs-137 is the only radionuclide, other than naturally occurring, reported in indicator location vegetation samples since the change in gamma spectroscopy analysis systems in 1987.

It is not unusual for Cs-137 to be present in vegetation. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous years. Table 3.5 lists the highest indicator location annual mean and control location annual mean for Cs-137 since early in the station's operational history. Visual inspection of the tabular data did not reveal any increasing trends. There is no indication that the Cs-137 is due to ONS operations based on the low concentration observed and the absence of other radionuclides. No Cs-137 was released from Oconee in gaseous effluents in 2002.

K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf vegetation samples in 2002.

Figure 3.5 pCi/kg Concentration of Cs-137 in Broadleaf Vegetation 2500 1I I I I I I I I I I I I I 2000 1500 1000 IL 500 0

1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001

-l -- Indicator Location - Control Location - Reporting Level I Section 3 - Page 12 C u, L,

Table 3.5 Mean Concentration of Radionuclides in Vegetation Year Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg)

July 1974 - Dec. 1974 1.54E3 O.OOEO Jan. 1975 - June 1975 1.55E3 1.59E3 July 1975 - Dec. 1975 O.OOE0 O.OOE0 1976 O.OOE0 O.OOE0 1977 0.00E0 7.90E2 1978 I.19E2 8.19E1 1979 5.04E1 2.96E1 1980 2.80EI 1.55E1 1981 2.99E1 2.60E1 1982 2.42E1 2.62E1 1983 7.44E0 5.35E-1 1984 1.37E1 4.74E2 1985 1.62E1 2.20E2 1986 3.28E1 3.12E2 1987 2.70E1 4.20E1 1988 2.40E1 7.50E1 1989 O.OOE0 1.08E2 1990 2.73E2 1.74E2 1991 2.20E1 1.45E2 1992 O.OOE0 1.46E2 1993 O.OOE0 1.49E2 1994 O.OOEO 1.06E2 1995 4.30Ei 1.58E2 1996 3.79E1 1.83E2 1997 4.73E1 1.35E2 1998 7.28E1 1.61E2 1999 1.34E2 O.OOEO 2000 1.06E2 O.OOEO 2001 3.19E1 O.OOEO 2002 8.44E1 O.OOEO 0.OOEO = no detectable measurements Only qualitative results reported prior to 1974 Control location changed to 073 in 1984 Control location 081 added in 1998 Control location 073 was removed in 1999 1979 - 1986 mean based on all net activity results Section 3 - Page 13

3.6 FISH In 2002, gamma spectroscopy was performed on 12 fish samples. Two downstream indicator and one control location were sampled. Cs-137 was identified in all eight of the indicator location samples and in one of the four control location samples. No other effluent related radionuclide was identified.

The highest average concentration for Cs-137 was 93.7 pCi/kg (4.69% of reporting level).

The highest individual sample concentration for Cs-137 was 110 pCi/kg (5.5% of reporting level). The control Cs-137 average concentration was 21.0 pCi/kg. 2001 Cs-137 sample results for all locations were similar.

Figures 3.6-1 and 3.6-2 are graphs displaying the annual means for Cs-137 and Cs-134.

Historically, both are major contributors to the calculated dose from liquid effluents from ingestion of fish. Radioactivity concentrations in downstream fish samples are higher than those reported in preoperational fish samples, however, fluctuations in the graphed results are large and no trends are apparent. Based on these graphs, the levels at the two downstream locations do not appear to be increasing.

One factor affecting the trend analysis is a change in sampling locations. In 1984, a second downstream fish location was added. Location 063 is closer to the liquid effluent discharge point and has been the highest mean indicator since it was added.

K-40 was observed in fish samples in addition to the radionuclides discussed above.

Table 3.6 lists the highest indicator location annual means since the preoperational period for radionuclides detected in 2002. Also included in the table are radionuclides that

__ aEjl i  !!91have been identified in this Vtie . e : t _ media since the change in analysis systems in 1987.

r Comparison of data to previous years does not indicate any increases in concentrations.

Fish Sampling Section 3 - Page 14

Figure 3.6-1 pCVkg Concentration of Cs-137 in Fish 2500 Tr 2000 1500 1000 500 I o _ 1- w _- - I  :;

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 l-- Control Location - Indicator Location - Reporting Level I Figure 3.6-2 pCUkg Concentration of Cs-134 in Fish 700 __

600 500 400 __

300 _____ _ X 200 - _____

100 _ _ _ __r-'__ __ _

0 _

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002

- Control Location - Indicator Location - 50 % Reporting Level Current reporting levels implemented 1984 Section 3 - Page 15 Cd 9

Table 3.6 Mean Concentrations of Radionuclides in Fish Year Co-58 (pCilkg) Co-60 (pCi/kg) Cs-134 (pCi/kg) Cs-137 (pCi/kg)

Preop ending Jan.1971 O.OOEO O.OOEO O.OOEO 1.46E2 Preop ending Jan.1973 O.OOEO O.OOEO O.OOEO 1.66E2 Feb. 1973 - June 1973 Qualitative results reported-no significant measurements above background July 1973 - Dec. 1973 O.OOEO O.OOEO O.OOEO 1.89E2 Jan. 1974 - June 1974 O.OOEO O.OOEO O.OOEO 2.47EI July 1974 - Dec. 1974 O.OOEO O.OOEO O.OOEO 4.85EI Jan. 1975 - June 1975 O.OOEO O.OOEO 3.81EI 1.05E2 July 1975 - Dec. 1975 8.50EI O.OOEO 7.00E1 3.13E2 1976 5.70EI 1.14E2 7.73EI 1.66E2 1977 O.OOEO O.OOEO 1.80E2 3.60E2 1978 3.27E2 O.OOEO 3.3 1E2 O.OOEO 1979 1.91E0 1.56E1 9.26E1 3.88E2 1980 1.45E1 1.90EI l.IE2 3.99E2 1981 2.25E1 1.49E1 1.40E2 4.51E2 1982 9.83E-1 8.03E0 1.17E2 2.94E2 1983 3.35E1 4.53E0 1.24E2 3.32E2 1984 1.21E2 6.23E1 3.87E2 1.04E3 1985 1.62E1 1.10E1 7.93E1 2.85E2 1986 9.56E1 2.59E1 2.57E2 7.36E2 1987 1.63E2 6.30E1 9.80E1 3.93E2 1988 9.60E1 O.OOEO 7.20E1 2.60E2 1989 4.30EI 1.50E1 8.60E1 3.36E2 1990 1.50EI O.OOEO 4.80E1 1.19E2 1991 4.59E1 O.OOEO 1.25E2 1.94E2 1992 6.10EI O.OOEO 4.80E1 1.36E2 1993 O.OOEO O.OOEO 2.1OE I 1.1I OE2 1994 O.OOEO O.OOEO 2.80EI 1.05E2 1995 O.OOEO O.OOEO 3.10EI 9.20EI 1996 O.OOEO O.OOEO 4.49E1 1.25E2 1997 O.OOEO O.OOEO O.OOEO 1.1I8E2 1998 O.OOEO O.OOEO O.OOEO 5.79EI1 1999 O.OOEO O.OOEO O.OOEO 1.04E2 2000 O.OOEO O.OOEO O.OOEO 7.54E I 2001 1.72E1 O.OOEO O.OOEO 9.92EI 2002 O.OOEO O.OOEO O.OOEO 9.37EI O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page 16

3.7 SHORELINE SEDIMENT Gamma spectroscopy was performed on six sediment samples. Two downstream indicator locations and one control location were sampled.

Cs-137 was identified in all of the four indicator location samples. Cs-137 was not observed in any control location samples. The highest 2002 indicator location annual mean was 69.6 pCi/kg. 2001 Cs-137 sample results for all indicator locations were similar. Table 3.7 lists the highest indicator location annual means since shoreline sediment was initiated in 1984.

Included in the table are radionuclides that have been identified in this media since the change in analysis systems in 1987.

Visual inspection of the tabular data did not reveal any trends. Figure 3.7-1 is a graph of the Cs-137 annual means. Figure 3.7-2 is a graph of the Co-60 annual means. Historically, both are major contributors to the calculated dose from liquid effluents from shoreline sediment.

Fluctuations in the graphed results are large and no trends are apparent.

K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2002.

Section 3 - Page 17

Figure 3.7-1 pCUkg Concentration of Cs-137 in Shoreline Sediment 1000 a 1 900 _

800 _

700 *_ _

100 - ___ _

1984 1986 1988 1990 1992 1994 1996 1998 2000 2002

+ Control Location 068 -h-- Indicator Location 063 A - dicator Location 067 Figure 3.7-2 pCi/kg Concentration of Co-60 in Shoreline Sediment bUU 500 400 300 200 A ri_ _

100 A' 1 7 1/ ,,AIII \

1 1984 1986 1988 1990 1992 1994 1998 2000 2002 2

I 0 Control Location 068 U Indicator Location 063 --A--- Indicator Location 067l There are no reporting levels for shorelinesediment Section 3 - Page 18 C -

Table 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)

Year Mn-54 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ag-1Om Sb-125 1984 l.lOEI 1.09E1 1.19EI O.OOEO 7.77E1 5.16E1 O.OOEO O.OOEO 1985 9.39E0 1.27E0 4.79EO O.OOEO 7.63E1 9.47E1 O.OOEO O.OOEO 1986 2.24E1 1.62E1 2.50E1 O.OOEO 1.41E2 7.12E2 O.OOEO O.OOEO 1987 5.40E1 4.70E2 5.07E2 O.OOEO l.OlE2 6.22E2 3.46E2 O.OOEO 1988 3.30E1 1.20E2 1.87E2 6.70E1 6.60E1 7.59E2 1.62E2 3.67E2 1989 2.30E1 1.24E2 1.96E2 O.OOEO 5.40E1 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.OOE1 2.59E2 O.OOEO 4.50E1 5.36E2 1.71E2 9.OOE1 1991 3.26E1 5.60E1 8.57EI O.OOEO 6.91E1 1.24E2 1.1OE2 1.78E2 1992 8.79E1 1.79E2 1.12E2 O.OOEO 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50EI O.OOEO 3.20E1 1.36E2 5.63E1 1.1IE2 1994 5.30E1 7.OE1 1.49E2 O.OOEO 6.70E1 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 O.OOEO l.lOEl 5.20E1 O.OOEO O.OOEO 1996 O.OOEO 5.10EI O.OOEO O.OOEO 1.98E1 1.19E2 O.OOEO O.OOEO 1997 O.OOEO O.OOEO O.OOEO O.OOEO O.OOEO 1.06E2 O.OOEO O.OOEO 1998 O.OOEO O.OOEO O.OOEO O.OOEO O.OOEO 1.01E2 O.OOEO O.OOEO 1999 6.96E1 O.OOEO 0.00E0 O.OOEO O.OOEO 7.38E1 O.OOEO O.OOEO 2000 O.OOEO O.OOEO O.OOEO O.OOEO O.OOEO 8.54E1 O.OOEO O.OOEO 2001 O.OOEO 2.10E1 O.OOEO O.OOEO O.OOEO 1.20E2 O.OOEO O.OOEO 2002 O.OOEO O.OOEO O.OOEO O.OOEO O.OOEO 6.96EI O.OOEO O.OOEO O.OOEO = no detectable measurements 1984-1986 mean based on all net activity results Section 3 - Page 19

3.8 DIRECT GAMMA RADIATION In 2002, 166 Thermoluminescent Dosimeters (TLD) were analyzed, 158 at indicator locations, 8 at the two control locations. TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 104 milliroentgen. This TLD is located at indicator location 048, 4.0 miles from the station. The annual mean exposure for the control locations was 108 milliroentgen.

Figure 3.8 and Table 3.8 show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year. Data is provided from 1984 when TLD locations were added and arranged in an inner ring and outer ring configuration.

Preoperational data is also provided in the table. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise a number of data points with control averages representing only two locations.

The calculated total body dose (from gaseous effluents) for 2002 was 3.34E-02 mrem, which is 0.04% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.

The maximum measurement from TLDs at the Independent Spent Fuel Storage Installation (ISFSI) was 854.7 milliroentgen per standard quarter. This is higher than previous measurements but is expected due to Phase II operations of the ISFSI. TLD measurements in the inner ring (site boundary) have not shown an increase.

Figure 3.8 mRlyear Direct Gamma Radiation (TLD) Results 250-200 150 100 ____ ___ __

0-_

1984 1986 1988 1990 1992 1994 1996 1998 2000 2004

-l--Inner Ring -U- Outer Ring - Control There is no reporting levelfor Direct Radiation (TLD)

Section 3 - Page 20 (c~6-

Table 3.8 Direct Gamma Radiation (TLD) Results Year Inner Ring Average Outer Ring Average Control (mR/yr) (mRlyr) (nRJyr)

Preoperational 113.1 123.9 148.9 1984 79.4 83.8 110.3 1985 116.9 121.5 156.6 1986 104.2 106.0 150.9 1987 84.3 88.8 104.3 1988 72.3 78.6 112.6 1989 63.7 61.7 89.4 1990 52.2 50.7 70.1 1991 61.2 65.0 88.0 1992 76.2 73.2 92.0 1993 74.8 80.6 93.0 1994 86.8 94.7 112.0 1995 93.6 101.7 132.0 1996 68.5 78.3 101.0 1997 72.8 83.8 104.5 1998 71.7 80.8 118.0 1999 74.5 82.5 104 2000 76.2 84.5 105.6 2001 73.6 82.4 102.2 Average (1992 - 2001) 76.9 84.2 106.4 2002 76.6 85.3 108.0 Section 3 - Page 21

3.9 LAND USE CENSUS The Land Use Census was conducted during the growing season (7/16 - 7/18/02) as required by SLC 16.11.6. Table 3.9 summarizes census results. A map indicating identified locations is shown in Figure 3.9. The nearest residence is located in the NW sector at 1.04 miles. No program changes were required based on the results of the census.

Table 3.9 Oconee 2002 Land Use Census Results Sector Distance Sector Distance (Miles) (Mliles)

Nearest Residence 2.97 Nearest Residence 1.86 N Nearest Milk Animal - S Nearest Milk Animal -

Nearest Meat Animal - Nearest Meat Animal -

Nearest Residence 2.39 Nearest Residence 1.34 NNE Nearest Milk Animal - SSW Nearest Milk Animal -

Nearest Meat Animal (Cow) 3.32 Nearest Meat Animal -

Nearest Residence 1.22 Nearest Residence 1.38 NE Nearest Milk Animal - SW Nearest Milk Animal -

Nearest Meat Animal (Cow) 1.89 Nearest Meat Animal -

Nearest Residence 1.23 Nearest Residence 1.81 ENE Nearest Milk Animal - WSW Nearest Milk Animal -

Nearest Meat Animal - Nearest Meat Animal -

Nearest Residence 1.14 Nearest Residence 1.43 E Nearest Milk Animal - W Nearest Milk Animal -

Nearest Meat Animal (Cow) 2.52 Nearest Meat Animal -

Nearest Residence 1.90 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal -

Nearest Meat Animal (Cow) 2.60 Nearest Meat Animal -

Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal - NW Nearest Milk Animal -

Nearest Meat Animal - Nearest Meat Animal -

Nearest Residence 1.56 Nearest Residence 1.06 SSE Nearest Milk Animal - NNW Nearest Milk Animal -

Nearest Meat Animal - Nearest Meat Animal

"-" indicates no occurrences within the 5 mile radius Section 3 -Page 22

I I I Oconee Nuclear Station 2002 Land Use Census Map

• Milk cow 4 Beef cow

• /f; Residence Streams and Shorelines cl Roads CD County lines ft t'J 00 Railroads 2002 data in red SCALE: 1:95040 1 Projection N.C. State Plane July 2002 til OaA12

.1 cOq

4.0 EVALUATION OF DOSE 4.1 DOSE FROI ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2002 ONS REMP samples. The primary purpose of estimating doses based on sample results was to allow comparison to effluent program dose estimates. Doses based on sample results were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates.

Doses based on REMP sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location, and sample type, were used to calculate REMP-based doses, after subtracting the applicable average background concentration (as measured at the corresponding control location).

Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. A dose factor of zero was assumed when the guide listed "NO DATA" as the dose factor for a given radionuclide and organ.

Maximum dose estimates calculated using drinking water, broadleaf vegetation, fish and shoreline sediment results are reported in Table 4.1-A. The individual critical population and pathway dose calculations are contained in Table 4.1-B.

No radionuclides were detected in milk, airborne radioiodine or airborne particulate samples other than naturally-occurring K-40 and Be-7. Dose estimates were not calculated for surface water samples because surface water is not considered a potable drinking water source. REMP TLD exposure results are discussed in Section 3.8.

The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2002 was 7.18E-1 mrem to the child's bone from consuming broadleaf vegetation.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2002 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. The 2002 ONS Annual Radioactive Effluent Release Report (reference 6.6) included calendar year dose estimates for the location with the highest individual organ dose from liquid and gaseous effluent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

Section 4 -Page I

The effluent-based liquid release doses are summations of the dose contributions of the drinking water, fish and shoreline pathways. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas exposure there is no critical age group; as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, milk, inhalation and vegetation pathways.

4.3 COMPARISON OF DOSES The environmental and release data doses given in Table 4.1-A agree reasonably well.

The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways. This indicates that effluent program dose estimates are both valid and reasonably conservative.

There are some differences in how effluent and environmental doses are calculated that affect the comparison. Doses calculated from environmental data are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.

In calculations based on liquid release effluent pathways, fish and drinking water were the predominant dose pathways based on environmental and effluent samples. The maximum total organ dose based on 2002 environmental sample results was 2.12E-1 mrem to the adult liver. The maximum total organ dose of 4.64E-1 mrem for liquid effluent-based estimates was to the adult liver.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 3.36E-2 mrem to the child thyroid. Vegetation was the only gaseous release pathway media that contained detectable activity (See Section 3.5).

The maximum total organ dose for gaseous environmental estimates was 7.18E-1 mrem to the child bone.

Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.

The doses calculated do not exceed the 40CFR190 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of ONS are being maintained well within regulatory limits.

Section 4 - Page 2

TABLE 4.1-A Page 1 of 3 OCONEE NUCLEAR STATION 2002 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental Critical Critical Maximum Dose 3 Organ or Age (ca Patwa Location (mrem)

Effluent Data Pathway ()Lcto Skin Environmental Teen Shoreline Sediment 067 (4.2 mi SSE) 1.83E-04 Skin Effluent Teen Shoreline Sediment 0.7 mi. ENE 2.04E-03 Bone Environmental Child Fish 063 (0.8 mi ESE) 1.64E-01 Bone Effluent Child Fish 0.7 mi. ENE 4.37E-01 Liver Environmental Adult Fish 063 (0.8 mi ESE) 2.12E-01 Liver Effluent Teen Fish 0.7 mi. ENE 4.64E-01 T. Body Environmental Adult Fish 063 (0.8 mi ESE) 1.55E-01 T. Body Effluent Adult Fish 0.7 mi. ENE 2.91E-01 Thyroid Environmental Child Drinking Water 066 (19.0 mi SSE) 4.76E-02 Thyroid Effluent Teen Fish 0.7 mi. ENE 1.83E-03 Kidney Environmental Adult Fish 063 (0.8 mi ESE) 1.02E-01 Kidney Effluent Teen Fish 0.7 mi. ENE 1.59E-01 Lung Environmental Child Drinking Water 066 (19.0 mi SSE) 6.60E-02 Lung Effluent Teen Fish 0.7 mi. ENE 6.29E-02 GI-LLI Environmental Adult Drinking Water 066 (19.0 mi SSE) 4.90E-02 GI-LLI Effluent Teen Fish 0.7 mi. ENE 8.39E-03

".-. (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.

Section 4 - Page 3

Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, P'ARTICULATE, an( TRITIUM Environmental or Critical Critical Maximum Dose (3)

Organ Effluent Data Age () Pathway (2) Location (mrem)

Skin Environmental - 0.OOE+00 Skin Effluent All Ground Plane 1.0 mi. SW 9.08E-08 Bone Environmental Child Vegetation 077 (1.0 mi SW) 7.18E-01 Bone Effluent Child Vegetation 1.0 mi. SW 4.93E-07 Liver Environmental Child Vegetation 077 (1.0 mi SW) 6.87E-01 Liver Effluent Child Vegetation 1.0 mi. SW 3.34E-02 T. Body Environmental Adult Vegetation 077 (1.0 mi SW) 3.86E-01 T. Body Effluent Child Vegetation 1.0 mi. SW 3.34E-02 Thyroid Environmental - 0.OOE+00 Thyroid Effluent Child Vegetation 1.0 mi. SW 3.36E-02 Kidney Environmental Child Vegetation 077 (1.0 mi SW) 2.24E-01 Kidney Effluent Child Vegetation 1.0 mi. SW 3.34E-02 Lung Environmental Child Vegetation 077 (1.0 mi SW) 8.05E-02 Lung Effluent Child Vegetation 1.0 mi. SW 3.34E-02 GI-LLI Environmental Adult Vegetation 077 (1.0 mi SW) 1.14E-02 GI-LLI Effluent Child Vegetation 1.0 mi. SW 3.34E-02

~- (I) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.

Section 4 - Page 4

Page 3 of 3 NOBLE GAS Air Environmental or Critical Critical Maximum Dose Dose Effluent Data Age Pathway Location (mrad)

Beta Environmental - - - Not Sampled Beta Effluent N/A Noble Gas 1.0 mi. SW 4.50E-04 Gamma Environmental - - - Not Sampled Gamma Effluent N/A Noble Gas 1.0 mi. SW 1.61E-04 Section 4 - Page 5

r F F F F F F F F F F F F F F, F Ff F FF FF F F FF F F F F FF F r F F r F F f VF TABLE 4.1-B Maximin,n Idivi(liual Dose ftw 2002 based ont Enivironm,ental Mesvlreinents (ren,,) for Ocotee Niuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.0013+00 0.00E+00 0.0013+00 0.00E+00 Drinking Water 0.00E+00 3.44E-02 3.44E-02 3.44E-02 3.44E-02 3.44E-02 3.44E-02 0.00E+00 Milk 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.0013+00 3.44E-02 3.44E-02 3.44E-02 3.44E-02 3.44E-02 3.44E-02 0.OOE+00 Child Airborne 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Drinking Water 0.00E+00 3.5013-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 0.0013+00 Milk 0.0013+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 7.18E-01 6.87E-01 1.01E-01 0.00E+00 2.24E-01 8.05E-02 4.30E-03 0.00E+00 Fish 1.64E-01 1.70E-01 3.58E-02 1.26E-02 6.38E-02 3.101E-02 1.36E-02 0.00E+00 Shoreline Sediment 3.27E-05 3.27E-05 3.27E-05 3.27E-05 3.27E-05 3.27E-05 3.27E-05 3.82E-05 TOTAL 8.82E-01 8.92E-01 1.72E-01 4.76E-02 3.23E-01 1.47E-01 5.29E-02 3.82E-05 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.0013+00 0.00E+00 0.00E+00 0.00E+00 0.0013+00 Drinking Water 0.00E+00 1.83E-02 1.83E-02 1.83E-02 1.83E-02 1.83E-02 1.83E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 3.97E-01 5.28E-01 1.84E-01 0.00E+00 1.80E-01 6.9813-02 7.51E-03 0.00E+00 Fish 1.30E-01 1.89E-01 7.56E-02 1.53E-02 7.42E-02 3.8213-02 1.77E-02 0.0013+00 Shoreline Sediment 1.57E-04 1.57E-04 1.57E-04 1.57E-04 1.57E-04 1.57E-04 1.57E-04 1.83E-04 TOTAL 5.27E-01 7.35E-01 2.78E-01 3.38E-02 2.73E-01 1.26E-01 4.37E-02 1.83E-04 Adult Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 0.00E+00 Milk 0.00E+00 0.0013+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 4.311E-01 5.89E-01 3.86E-01 0.00E+00 2.00E-01 6.64E-02 1.14E-02 0.00E+00 Fish 1.22E-01 1.86E-01 1.29E-01 1.98E-02 7.63E-02 3.86E-02 2.311E-02 0.0013+00 Shoreline Sediment 2.811E-05 2.811E-05 2.811E-05 2.811E-05 2.811E-05 2.811E-05 2.81E-05 3.27E-05 TOTAL 5.53E-01 8.01 E-01 5.41 E-01 4.57E-02 3.02E-01 1.311E-01 6.04E-02 3.27E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

F FF F F F F F r F r r r F r r r (F r - V C C r r FC rC F (V C f F F F FF CF F Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2002 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/i)

Usage (intake in one year)= 330 1 Hlighest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung Gi-LLI Location (pCi/) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI IUn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALI 0.00 0.OOE+00 0.OOE+00 O.00E+00 0.001+00 0.00E+00 0.00E+00 0.OOE+00 Fe-59 3.08E4-5 5.38K-05 2.12E-05 NO DATA NO DATA 1.59E.05 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 O.OO0+00 0.00E+ 00 0.0 0.00E+00 0.00E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.O+00 0.00E+00 0.00E+00 0.OOE+00 Zn-65 1.84E-05 6.31E 05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Zr.95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+O0 0.OOE+00 O.OOE+00 0.OOE+00 Cs l.U 3.77E-04 7.03E-04 7.10K-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.OOE+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 O.00E+00 0.OOE+00 Cs-137 5.22E-04 6.1JE-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E 06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E06 NO DATA 4.06E4-8 1.05E-07 4.20E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 11.3 NO DATA 3.08E.07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 066 338.00 0.OOE+00 3.44E-02 3.44E-02 3.44E.02 3.44E-02 3.44E-02 3.44E-02 Dose Commitment (mrem) = 0.OOE+00 3.44E-02 3.44E-02 3.44EK02 3.44E-02 3.44E-02 3.44E-02 Section 4 -Page 7

r r vr r r r r C VC r C F V V F r r rr r r C C r Cr r CC r r V r V F r C VV r F Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2002 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCiA1)

Usage (intake In one year)= 510 1 Highest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Location (pCi/i) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Co-58 NO DATA 1.80E-06 551E-06 NO DATA NO DATA NO DATA l.OSE-OS ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Fe-59 1.65E-OS 2.67E-05 133E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 NO DATA 5.29E-06 1.56F-05 NO DATA NO DATA NO DATA 2.93E-OS ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-95 2.25E 08 8.76E-09 6.26E-09 NO DATA 8.23E49 NO DATA 1.62E-OS ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.0OE+00 Zr-95 1.16F-07 2.55E-08 2.27E-08 NO DATA 3.65F-08 NO DATA 2.66E-OS ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1-131 1.72E-05 1.73E-OS 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Cs-1.34 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 BaLa.140 8.31E-OS 7.28E-08 4.85E 06 NO DATA 2-37E-08 4-34E-08 4.21E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 11-3 NO DATA 2.03E4-7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 066 338.00 O.OOE+00 3.50E-02 3.50E-02 3.50E02 3.50E-02 3.50E-02 3.50E-02 Dose Commitment (mrem) = O.OOE+00 3.50E-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 3.50E-02 Section 4 -Page 8

r r f r r r f r r- r r r I r r rr r r rr r rr rr r Ir r r r r r r r r( r Cr r Oconee Nuclear Station Dose from BroadleafVegetation Pathwayfor 2002 Data Maximum Exposed Child Child Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake In one year)= 26 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCI/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-OS NO DATA 1.54E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-1.34 234E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-OS 2.07E-06 ALL 0.00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 077 84.40 7.18E-01 6.87E-01 I.OIE-01 0.OOE+00 2.24E-01 8.05E-02 4.30E-03 Dose Commitment (mrem) = 7.18E-01 6.87E-01 1.OIE-01 O.OOE+00 2.24E-01 8.05E-02 430E-03 Section 4 -Page 9

( r r( ( r( ( r( r rrr ( ( ( ( ( ( rr r rc( rr r( ( r( r r( ( r r( ( ( r(

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2002 Data Maximum Exposed Chlild Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCil = 10000 pCi/I x 0.9 = 9000 pCi/kg Usage (intake in one year)= 6.9 kg Ilighest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-.LLI Location (pCVkg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI NMn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E06 NO DATA 8.98E-06 ALL 0.00 O.OE+00 O.OOE+00 O.OE+00 O.OOE+00 O.OE+00 0.OOE+00 O.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.O0E+O0 O.OOE+00 O.O0E+0O Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 O.O0E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.O0E+O0 O.00E+O0 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+0O 0.OOE+00 O.O0E+00 Zn-65 1.37E-05 3.65E-05 2.27E.-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.G0EOO Cs-134 2.34E-04 3.84E-04 8.IOE-05 NO DATA 1.19E.04 4.27E.05 2.07E.06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0 O.O0E+00 Cs-137 3.27E-04 3.13E-04 4.62E05 NO DATA 1.02E-04 3.67E-05 1.96E-06 06.1 72.70 1.64E-01 1.57E-01 2.32E-02 O.O0E+00 5.12F.42 1.84E-02 9.83E-04 11-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 063 9000 0.00E+00 1.26E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 Dose Commitment (mrem) = 1.64E-01 1.70E-01 3.58E-02 1.26E02 6-38E02 3.1OE-O2 1.36E02 Section 4 -Page 10

t r f( ( ( I r ((r r r rrrrrrrrrr r r r r( r r r r c r r r r(rr ' ( (

Oconee Nuclear Station Dosefrom Shoreline Sediment Pathtwayfor2002 Data Maximum Exposed Child Shoreline Recreation = 14 hr (In one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m 2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCUm 2) x Shore Width Factor x Sediment Surface Mass (kg/mn) x Sediment Concentration (pCVkg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mremA/r per pCUm2) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Cs-134 1.20E-08 1.40E-08 ALL 0.00 O.OOE+OO O.OOE+00 Cs.137 4.20E-09 4.90E.09 067 69.60 3.27E-05 3.82E.05 Dose Commitment irem) = 3.27E-05 3.82E-05 Section 4 - Page 11

,r r r(-rC r rCr ( r rr FC Fc r Cr r r cr r CF F F' CF F( CF Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2002 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mremtpCi ingested) x Concentration (pCiA)

Usage (intake In one year)= 510 1 Ilighest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI.LLI Location (pC111) Bone Liver T. Body Thyroid Kidnty Lung GI.LLI Mtln-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALI. 0.00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 134E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Fe-59 5.87E-06 1-17E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66F-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 L22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Zr-95 4.12E-08 130E-08 L94E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05 ALL 0.00 0.OOE+00 0.OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1-131 5.85E-06 8.19E-06 4.40E-06 2-39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-1.4 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2-79E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E.05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2-34E-08 418E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 11-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 066 338.00 0.OOE+00 1.8.E-02 1.83E-02 1.83E-02 1.83E-02 1.83E-02 1.83E-02 Dose Commitment (mrem)= 0.OOE+00 1.8E-02 1.8E-02 1.83E-02 1.83E-02 1.8.E-02 I.LlE-02 Section 4 - Page 12

I r r r r r rr r ( rr r rr rr rr r r rr r r rr r r r rr r r r rr r r r r r Oconee Nuclear Station Dosefrom Broadleaf Vegetation Pathwayfor 2002 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake In one year) = 42 kg Ilighest Annual Net Mean In2estion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Location (pCikg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41EOS NO DATA 1.62E-06 ALL 0.00 O.OOE+O0 O.OOE+00 O.OOE+00 0.OOE+O0 0.OOE+0O O.OOE+00 O.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E05 NO DATA 6.26E.05 2.39E-05 2.45E06 ALI, 0.00 O.OOE+00 0.00E+00 0.OOE+O0 O.OOE +.0E+O0 0.OOE+00 O.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E05 1.97E.0S 2.12E-06 077 84.40 3.97E-01 5.28E-01 1.84E-01 O.OOE+00 1.80E-01 6.98E-02 7.51E-03 Dose Commitment (mrem) = 3.97E-01 5.28E.01 1.84E-01 O.OOE+00 1.80E-01 6.98E-02 7.51E03 Section 4 -Page 13

Oconee Nuclear Statiorn Dosefromn Fish Pathwayfor 2002 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mren/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 10000 pCi/I x 0.9 = 9000 pCi/kg Usage (intake in one year) = 16 kg Ilighest Annual In2estion Dose Factor Net Mean Dose (mrem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung Cl-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Min-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-0S ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA l.34E-05 ALL 0.00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 0.00E+00 O.OOE+00 Fe-59 5.87E06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-0S ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 5.76E-06 2.00E-OS 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 Cs-1.34 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Cs.137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 063 72.70 1.30E-01 1.73E-01 6.04E-02 O.OOE+00 5.90E-02 2.29E-02 2.47F-03 11-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063 9000 O.OOE+00 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E02 Dose Commitment (mrem) = 1.30E-01 1.89E-01 7.56E-02 1.53E-02 7.42E-02 3.82E-02 1.77F-02 Section 4-Page 14

F f- ( [-r ( r FCr (-F - !- ( [ ( ( ( ( ( ( (

C C-(F( FF - F F F-(- F- ( ( f ( F F F-Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2002 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/rm Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCVm 2) x Shore Width Factor x Sediment Surface Mass (kg/n?) x Sediment Concentration (pCVkg)

External Dose Factor Standing lighest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCV/n?) In dicator Sediment (mrem)

Radionuclide T. Body Skin Lc catlon (pCVkg) T. Body Skin Cs-.134 1.20E.08 1.40E-08 ALL 0.00 O.OOE+00 O.OOE+00 Cs-137 4.20E-09 4.90E-09 067 69.60 1.57E-04 1.83E-04 Dose Commitment (mrem) = 1.57E-04 1.83E-04 Section 4 - Page 15

r ( C (r-[-r ( r r- r( r r rr rr r r r (r r r r r r r ( r ( r ( ( ( (r c r(r Oconee Nuclear Station Dosefrom Drinking Water Pathtwayfor 2002 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCiA1)

Usage (intake in one year) = 730 1 Ilighest Annual Net Mean Inzestion Dose Factor Concentration Dose (mrem)

Indicator Waler Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/i) Bone Liver T. Body Thyroid Kidney Lung GI.LLI Mn.54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E.05 ALL 0.00 01OE+00 O.OOE+00 O.OOE+00 0.00E+0O O.OOE+00 O.OOE+00 0.0EOO0 Co-58 NO DATA 7.45E-07 1.67E.06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00O0 O.E+00 O.OOE+00 0.00E+O0 Fe-59 4.34E.06 1.02E-S05 3.91E-06 NO DATA NO DATA 2.SSE-06 3.40E-05 ALL 0.00 0.OOE+00 O.OOE+00 0.OOE+O0 O.OOE+O0 0.OOE+O0 O.OOE+00 0.OOE+O0 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.W0E+00 Zn-65 4.84E-06 1.54E-05 6.96E.06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+O0 Nb-95 6.22E.09 3.46E-09 1.86E.09 NO DATA 3.42E-09 NO DATA 2.10E-OS ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+O0 0.WOE+00 Zr-95 3.04E-08 9.75E.09 6.60F,09 NO DATA 1.53E-08 NO DATA 3.09E-O5 ALL 0.00 O.OOE+00 0.WOE+00 O.OOE+00 0.OOE+00 0.WOE+00 O.OOE+00 O.W0E+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E.03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 O.OOE+OO 0.00E+00 0.OOE+00 O.OOE+OO .OOE+W0 O.OOE+OO O.OE+O0 Cs-134 6.22E-05 1.48E.04 1.21E-04 NO DATA 4.79E-OS 1.59E-OS 2.59E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.W0E+00 O.OOE+00 O.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.I1E-06 ALL 0.00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OEE+00 O.OOE+00 0.WE+0 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E.09 1.46E.08 4.18E-05 ALL 0.00 O.OOE+00 O.OOE+O0 O.OOE+00 0.WOE+0 O.OOE+00 O.OOE+O0 0.00E+00 11.3 NO DATA I.05E.07 I.05E-07 1.05E-07 1.05E-07 1.OSE-07 1.05E.07 066 338.00 O.OOE+00 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 Dose Commitment (mrem) = O.OOE+00 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 Section 4 -Page 16

r r r r r r r r r- r r r r r r r r r r r r r r r r (- (- r r r - r r ( r rrrrrr Oconee Nuclear Stationt Dosefront BroadleafVegetation Pathwayfor 2002 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) = 64 kg lighest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung Cl-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI 1.131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.00E+00 0.OOE+00 O.OOE+00 Cs-l.U 6.22E-O5 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-0S 2.59E-06 ALL 0.00 0.OOE+00 O.OOE+00O.OOE+00 .OOE+0 O.OE+O0 O.OOE+00 0O.OOE+00 Cs-137 7.97E-05 1.09E-0-i 7.14E-05 NO DATA 3.70E-OS 1.23FO5 2.11E-06 077 8.40 4.31E-01 5.89E-01 3.86E-01 O.00E+00 2.0OE-01 6.64E-02 1.14E-02 Dose Commitment (mrem) = 4.3IE-01 5.89E-01 3.86E-01 O.OOE+00 2.00E-01 6.64E-02 1.14E-02 Section 4 -Page 17

F( ( F F F( F F F F F r Fr F F F F F F F F F F F ( F F F F F F F F F FF F F F F ( (

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2002 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/i x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 10000 pCi/l x 0.9 = 9000 pCi/kg Usage (intake In one year)= 21 kg Ilighest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCilkg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn.54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+O0 O.OOE+00 0.00tE+00 0.OOE+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E400 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 4.34E.06 1.02E-05 3.91E06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E 0.00EE00 0.00E+0 E0 0. 0.0E+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 O.OOE+00 0.00E+00 0.OOE+00 0.OO1E+O0 .OOE+00 0.00E+00 0.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+O0 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE.00 0.OOE+00 0.00E 000 0.00Er00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E.05 NO DATA 3.70E-05 1.23E-05 2.IIE-06 063 72.70 1.22E-01 1.66E-01 1.09E-01 0.00E+00 5.65E-02 I.88E-02 3.22E-03 11-3 NO DATA 1.05E-07 1.OSE-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063 9000 0.00E+00 1.98E-02 1.98E.02 1.98E-02 L.02 1.98E-02 198E-02 Dose Commitment (mre m) = 1.22E-01 1.86E-01 1.29E-01 1.98E-02 7.63E-02 3.86E-02 2.31E-02 Section 4 -Page 18

F F F F F' F F' r F F r F F F F F c F ( ( F F F F F F F F F F ( F f Fr F r f rrrrrr Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor2002 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremhlr per pCI/mr2) x Shore Width Factor x Sediment Surface Mass (kg/ni) x Sediment Concentration (pCiVkg)

External Dose Factor Standing Higlest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)

(mrem/hr per pC/m 2) Indicator Sediment Radionuclide T. Body Skin Location (pCiVkg) T. Body Skin Cs-134 1.20E.08 1.40E-08 ALL 0.00 O.OOE+00 O.OOE+00 Cs-137 4.20E-09 4.90E-09 067 69.60 2.81E-05 3.27E-05 Dose Commitment (mrem) = 2.81E-05 3.27E-05 Section 4 - Page 19