ML021400059

Annual Radiological Environmental Operating Report

ML021400059
Person / Time
Site:	Oconee
Issue date:	05/08/2002
From:	Mccollum W Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021400059 (93)

Text

Duke Energy SkDuke Oconee Nuclear Station WEnergy 7800 Rochester Highway Seneca, SC 29672 (864) 885-3107 OFFICE W. R. McCollum, Jr. (864) 885-3564 FAX Vice President May 8, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Oconee Nuclear Site Docket Nos. 50-269, 50-270 and 50-287 Annual Radiological Environmental Operating Report

Dear Sir:

Pursuant to Oconee Nuclear Station Technical Specification 5.6.2, please find enclosed the Oconee Nuclear Site Annual Radiological Environmental Operating Report for 2001.

Very truly yours, W. R. McCollum, J~~

Site Vice Presi ent Oconee Nuclear Station Attachment 7, <7

Document Control Desk May 8, 2002 Page 2 xc: Mr. L. A. Reyes Regional Administrator, Region II Mr. L. N. Olshan Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector, ONS American Nuclear Insurers ANI Library Town Center, Suite 300S 29 South Main Street West Hartford, CT 06107-2445

Document Control Desk May 8, 2002 Page 3 bxc: J.A. Twiggs ON01R2 E.H. Wehrman ON01R2 B.L. Norris ONO11C L.E. Nicholson ON03RC D.V. Baysinger CN03RP Mike Cash EC050 NSRB EC12A ELL EC050 ONS Document Control

Duke EPower A Duke Energy Company Oconee Nuclear Station Units 1 , 2, and 3 F' km

- -L muI rý1

"Duke

~Powerw A Duke Energy Company ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY OCONEE NUCLEAR STATION Units 1, 2, and 3 2001

TABLE OF CONTENTS 1.0 Executive Summary 1-1 2.0 Introduction 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 Interpretation 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 Evaluation of 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 Assurance 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 5-2 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 . 5-3 5.9.1 State of North Carolina Intercomparison Program 5-3 5.9.2 Nuclear Technology Services Intercomparison Program 5-3 6.0 References 6-1 Appendices Appendix A: Environmental Sampling and Analysis Procedures A-1 I. Change of Sampling Procedures. A-2 i

II. Description of Analysis Procedures A-2 M. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A.1 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-1 C. 1 Sampling Deviations. C-2 C.2 Unavailable Analyses C-4 Appendix D: Analytical Deviations D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 LIST 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 LIST 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 (1-13 1) . 3-3 3.1-B Mean Concentration of Gross Beta in Air Particulate . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 ii

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 2001 Land Use Census Results 3-22 4.1-A 2001 Environmental and Effluent Dose Comparison 4-3 4.1--B Maximum Individual Dose for 2001 based on Environmental Measurements for Oconee Nuclear Station. 4-6 5.0-A Duke Power Company Interlaboratory Comparison Program 5-4 5.0-B 2001 Environmental Dosimeter Cross-Check Results . 5-11 LIST OF ACRONYMS 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/i picocurie per liter pCi/m3 picocurie per cubic meter Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter

ýtCi/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 2001.

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 eighty-one samples were analyzed comprising 1204 test results in order to compile data for the 2001 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 2001 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 3.03E-01 mrem for 2001. 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 Sampling at Oconee Nuclear Station Section 1 - Page 1

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 1

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 Yxi

-- i-1 X =

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 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 Chemobyl 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 AU! Other Locations iN Section 2 - Page 4 Col

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

. TLD Locations N

A Alt Other Locations S.d 2- Npge 5 C0*-2

TABLE 2.1-A OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-A Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly M Monthly SA Semiannually C Control Site SL tAir Location Description Red. & Surface Drinking Shoreline Fish Milk Broadleaf Particulate Water Water Sediment Vegetation 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 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 I M 080 C Martin Dairy (17.2 mi SE) SM 082 Oakway Dairy (17.8 mi SSW) SM

• Control for Fish Only C = Control

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

TABLE 2.1-B OCONEE RADIOLOCICAL MONITORING PROGRAM SAMPLING 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 OFHWY 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 SI 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 JCT HWY 183 & 133 4.0 miles NE 059 SI TAMASSEE DAR SCHOOL 9.2 miles NW HWY 133, 1 MILEEASTOF 039 JCT HWY 183 & 133 4.0 miles ENE 081 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) (pCi/liter) Vegetation (pCi/m )

3 (pCi/kg-wet)

H-3 20,000(a)

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 2c°) 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 1-131 analyses are performed.

TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta Air Radioiodine Weekly X Air Weekly X Particulate Quarterly Composite X _

Direct Radiation Quarterly X Surface Monthly X Water Quarterly Composite X Drinking Monthly X (a) X Water Quarterly Composite X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannualy X Broadleaf Vegetation Monthly X

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

Section 2 - Page 8

TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION Analysis Water Air Fish Milk Broadleaf Sediment (pCi/liter) Particulates (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry) or Gases (pCi/kg-wet)

(pCi/m 3)

Gross Beta 4 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 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 1 1 (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 2001 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 2001 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 2001.

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 2001 was 8.25% 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 2000.

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

Section 3 - Page 1

3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2001, 324 radioiodine and particulate samples were analyzed, 270 from five indicator locations and 54 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 1-131 in air samples in 2001. 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 2001. 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 2001. 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 shows the 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 (1-131) 3 3 Year Indicator Location (pCi/m ) Control Location (pCi/m )

Preoperational 1969-1972 0.00E0 0.OOEO Feb. 1973 - June 1973 0.00E0 O.00E0 July 1973 - Dec. 1973 0.00E0 0.00E0 Jan. 1974 - June 1974 O.00E0 0.00E0 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 6.3 1E-3 5.39E-4 1982 2.87E-3 8.10E-4 1983 1.48E-3 3.05E-4 1984 8.11E-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 0.00E0 0.00E0 1989 4.99E-4 O.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 O.00E0 1993 0.OOEO 0.00E0 1994 1.03E-2 0.OOEO 1995 O.00E0 0.OOEO 1996 0.00E0 0.OOEO 1997 O.OOEO 0.00E0 1998 0.OOEO 0.OOEO 1999 0.00E0 0.00E0 2000 0.00E0 0.OOEO 2001 O.OOEO O.OOEO O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page 3

Figure 3.1 pCVm 3 Concentration of Gross Beta in Air Particulate (Quarterly Data) 4.500E-2 3.500E2 3.0005-2 - -

2Ž500E,2 2.000152 - -

1.500E2--------

5.0005-3 0.O00E+0 3/26- 9/16- 3/31 - 9/29- 3/30- 9/28- 3/29- 9/27- 3S27- 9/25- 3/26- 9/24 6/25/96 12/30/96 6/30/97 12/29/97 6/29/98 12/28/98 6/28/99 12/27/99 6/26/00 12/27/00 6/25/01 12/31/01 Pre-operational sample results rangedp from 0.N04t 1.46 PCt/r 3 1 -ý Cntrol Location - Indicator LocaDon There is no reporting levelfor 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/m) 3/26 - 6/25/96 3.28E-2 3.05E-2 6/25 - 9116/96 4.15E-2 4.22B-2 9/16- 12/30/96 4.16E-2 3.80F,2 12/30 - 3/31/97 3.22E-2 3.18E-2 3/31 - 6/30/97 3.19E-2 3.14E-2 6/30 - 9/29/97 3.59E-2 3.72E-2 9/29 - 12/29/97 1.48E-2 1.65E-2 12/29 - 3/30/98 1.94E-2 1.OOE-2 3/30 - 6/29t98 2.21E-2 9.89E-3 6/29 - 9128/98 3.09E-2 1.95E-2 9/28 - 12/28/98 2.63E-2 2.28E-2 12/28 - 3/29/99 2.57E-2 2.37E-2 3/29 - 6128/99 3.02E-2 2.62E-2 6/28 - 9/27/99 3.08E-2 2.65E-2 9/27 - 12/27/99 2.74E-2 1.27E-2 12/27 - 3/27/00 2.88E-2 1.19E-2 3/27 - 6/26/00 1.93E-2 1.51E-2 6/26 - 9125/00 2.18E-2 1.73E-2 9125 - 12/27/00 3.08E-2 2.95E-2 12/17 - 3/26/01 1.88E-2 1.82E-2 3/26 - 6/25/01 1.87E-2 1.89E-2 6/25 - 9/24/01 2.18-2 1.92E-2 9/24- 12/31/01 2.22E-2 2.10E-2 Average (2001) 2.05E 2 1.94E-2 Section 3 - Page 4

3.2 DRINKING WATER Gross beta analysis and gamma spectroscopy were performed on 42 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 1.75 pCi/liter in 2001, and the control location had a concentration of 1.29 pCi/liter. The 2000 indicator mean was 2.07 pCi/liter. The table shows that 2001 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 2001; therefore low level iodine analysis is not required.

Tritium was detected in five of the 15 composite samples during 2001. Tritium was detected in five of the 15 composite samples during 2000. The 2001 mean indicator location 066 concentration was 390 pCi/liter, which is 1.95% 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 2001.

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 reportinglevel implemented 1984 pCLiiter Concentration of Tritium in Drinkring Water 5000 4500 _ _

4000 __ __

3500 _

3000 _

2500 ___

2000 ___ ___

1500 1000 500 1974 1976 1979 1982 1985 1988 1991 1994 1997 2000

-- Control [ocatmoj -i- idicator ýLocan ý-20% .Reportmg Level Secioj 3 - Page 5 cQ0tLI

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCi/1) 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 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 WATER Gamma spectroscopy was performed on 28 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.

Tritium was detected in the five indicator location samples. The 2001 average concentration was 7,426 pCi/liter. The individual samples ranged from 4,040 pCi/liter to 11,800 pCi/liter. The 2000 mean concentration was 14,802 pCi/liter. Tritium was not detected in any control surface water samples.

The concentration of Tritium at the 063 sample location was higher in 1999 and 2000 than in previous years. Lower than normal lake levels (and therefore lower flow in the discharge canal) and sampler operation problems during 2000 are possible reasons for the change. The chronically low water level of Lake Hartwell continues to cause sampling equipment difficulties (see Appendix C) during 2001.

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 2001. 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 2001 did not reveal any increasing trends.

K-40 is the naturally occurring radionuclide observed in surface water samples in 2001.

Section 3 - Page 7

Figure 3.3 pOl'Uter Concentration of Tritium in Surface Water 600D0 50000 400DO 30D000 20000 10000 0 -a-19%9 1973 1976 12M0 19M4 1988 1992 1996 2000 I Control Location - Indicator Locaton There is no reporting levelfor Tritium in surface water Sedion 3 - Page 8

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

Preoperational 1969 Quialitative results reported 4.86E2 Preoperational 1970 5.94E2 Preoperational 1971 4.0 1E2 Preoperational 1972 3.62E2 1973 0.OOEO 1974 0.00E0 1.32E1 0.OOEO 1.60E1 1.99E3 Jan. 1975 - June 1975 0.00E0 0.00E0 0.OOEO 0.00E0 1.56E4 July 1975 - Dec. 1975 O.OOEO 1.34E1 0.00E0 0.OOEO 5.52E4 1976 1.08E2 3.30E1 0.OOEO 3.50E1 2.95E4 1977 2.60E1 1.80E1 O.OOEO 3.LOEI 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 6.10E-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. 14EO 3.07E-1 1.26E4 1987 5.10EL 3.40E0 4.OOE0 O.00E0 7.08E3 1988 6.20E0 5.OOEO 2.50E0 3.50E0 1.10E4 1989 5.30E0 3.OOEO O.00E0 3.40E0 1.02E4 1990 1.70E0 1.60E0 0.OOEO O.OOEO 1.03E4 1991 5.40E0 0.00E0 0.00E0 O.OOEO 5.76E3 1992 2.50E0 O.00E0 0.OOEO 0.OOEO 6.22E3 1993 0.OOEO O.00E0 0.OOEO 0.00E0 8.62E3 1994 0.OOEO O.OOEO 0.00E0 0.OOEO 5.75E3 1995 O.OOEO O.00E0 0.00E0 0.00E0 6.65E3 1996 0.00E0 0.00E0 0.OOEO 0.00E0 4.54E3 1997 0.00E0 0.00E0 0.OOEO 0.OOEO 5.50E3 1998 0.OOEO 0.00E0 0.OOEO 0.00E0 3.35E3 1999 2.73E1 0.OOEO 0.00E0 0.00E0 1.13E4 2000 0.00E0 0.OOEO 0.00E0 0.OOEO 1.48E4 2001 0.OOEO 0.OOEO 0.00E0 0.OOEO 7.43E3 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 81 milk samples collected in 2001. Two indicator and one control location were sampled.

There were no gamma emitting radionuclides identified in indicator or control location samples in 2001. 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 2001.

Milk Sampling Section 3 - Page 10

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

Preoperational 1.57E11 1.46E1 Feb. 1973 - June 1973 Qualitative results reported Qualitative results reported 5.80E0 "

July 1973 - Dec. 1973 Jan. 1974- June 1974 5.30E0 0.00E0 July 1974 - Dec. 1974 1.11E1 0.00E0 Jan. 1975 - June 1975 1.51El 9.45E0 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 1.80E1 7.47E0 1977 0.00E0 0.00E0 1978 1.33E1 1.33E1 1979 7.25E0 2.52E0 1980 3.58E0 2.63E0 1981 5.52E0 5.51E0 1982 2.71E0 3.25E0 1983 5.04E0 -4.27E-1 1984 2.30E0 2.58E0 1985 2.38E0 1.31E0 1986 2.92E0 2.97E0 1987 4.90E0 4.90E0 1988 3.90E0 3.20E0 1989 4.70E0 2.90E0 1990 6.40E0 0.OOEO 1991 5.OOEO 0.OOEO 1992 6.60E0 0.OOEO 1993 O.OOEO 0.OOEO 1994 0.OOEO 1.80E0 1995 2.30E0 2.OOEO 1996 O.00E0 4.1OEO 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 O.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.OOEO 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page 11

S S

U U 3.5 BROADLEAF VEGETATION U

Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2001. Three S indicator locations and one control location were sampled. Cs-137 was reported in one S indicator sample. Cs-137 was not detected in any control location samples. No other effluent S related radionuclide was identified.

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

S One of the thirty-six indicator location samples contained Cs-137. The highest concentration S was 31.9 pCi/kg (1.60% of the reporting level). This result is less than those reported in S 2000.

S Cs-137 is the only radionuclide, other than naturally occurring, reported in indicator location 0 vegetation samples since the change in gamma spectroscopy analysis systems in 1987.

S S It is not unusual for Cs-137 to be present in vegetation. It is a constituent of nuclear weapons S 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 S mean for Cs-137 since early in the station's operational history. Visual inspection of the U tabular data did not reveal any increasing trends. There is no indication that the Cs-137 is S due to ONS operations based on the low concentration observed and the absence of other radionuclides.

S S K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf S vegetation samples in 2001.

S Figure 3.5 S pC0/kg Concentration of Cs-137 in Broadleaf Vegetation S 2500 S

S 2000 S 1500 S

S 1000 S

500 S

S 0

S 1974 1976 1979 1982 1985 1988 1991 1994 1997 2000 S - indicator Location - Control Lccation - Reporting Level I

S Seotion 3 - Page 12 S

S co9 S

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

July 1974 - D= 1974 1.54E3 0.00E0 Jan. 1975 - June 1975 1.55E3 1.59133 July 1975 - Dec. 1975 0.00130 0.00130 1976 0.00E0 0.00130 1977 0.00110 7.90E2 1978 1.19132 8.19E13 1979 5.04E1 2.96E1 1980 2.80E1 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.00E0 1.08E2 1990 2.73E2 1.74E2 1991 2.20E1 1.45E2 1992 0.00E0 1.46E2 1993 0.00E0 1.49E2 1994 0.00E0 1.06E2 1995 4.30E1 1.58E2 1996 3.79E1 1.83E2 1947 4.73E1 1.35E2 1998 7.28E1 1.61E2 1999 1.34E2 0.00E0 2000 1.06E2 0.00E0 2001 3.19E1 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 2001, 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 two of the four control location samples. Co-58 was identified in two of the eight indicator location samples. Co-58 was not identified in any control location samples. No other effluent related radionuclide was identified.

The highest average concentration for Co-58 was 17.2 pCi/kg. The highest individual sample concentration for Co-58 was 19.1 pCi/kg (0.06% of reporting level). Co-58 was last identified in a fish sample in 1992.

The highest average concentration for Cs-137 was 99.2 pCi/kg (4.96% of reporting level).

The highest individual sample concentration for Cs-137 was 165 pCi/kg (8.25% of reporting level). The control Cs-137 average concentration was 24.9 pCi/kg. 2000 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 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 2001. Also included in the table are radionuclides that have been identified in this media since the change in analysis systems in 1987.

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

Fish Sampling Section 3 - Page 14

Figure 3.6-1 peltkg Concentration of Cs-137 in Fish 2500 2000-1500 1000 +

500 1970 1975 1977 1981 1985 1989 1993 1997 2001

--- Control Location - Indicator I-- Location - Reporting Level Figure 3.6-2 pCi/kg Concentration of Cs-134 In Fist 700 500 400 - __

300 ___

200 __

100 __

1970 1975 1977 1981 1985 1989 1993 1997 2001

--- Control Location --- Indicator Location -50% Reporting Level Current reportinglevels implemented 1984 Sec.o6 3 - Page 15 COl

Table 3.6 Mean Concentrations of Radionuclides in Fish Year Co-58 (paCi/kg) Co-60 (pCi/kg) Cs-134 (p3Ci/kg) Cs-137 (pCi/kg)

Preop ending Jan. 19714.00E0 0.00E0 0.00E0 1.46E2 Preop ending Jan. 1973 O.OOEO O.OOEO 0.00E0 1.66E2 Feb. 1973 - June 1973 Qualitative results reported-no significant measurements above background July 1973 - Dec. 1973 0.00E0 0.00E0 0.00E0 1.89E2 Jan. 1974 - June 1974 0.00E0 0.00E0 0.00E0 2.47E1 July 1974 - Dec. 1974 0.00E0 0.00E0 0.00E0 4.85E1 Jan. 1975 - June 1975 0.00E0 0.00E0 3.81E1 1.05E2 July 1975 - Dec. 1975 8.50E1 0.OOEO 7.OOE1 3.13E2 1976 5.70E1 1.14E2 7.73E1 1.66E2 1977 0.OOEO O.OOEO 1.80E2 3.60E2 1978 3.27E2 0.OOEO 3.31E2 0.OOEO 1979 1.91E0 1.56E1 9.26E1 3.88E2 1980 1.45E1 1.90El 1.10E2 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 0.OOEO 7.20E1 2.60E2 1989 4.30E1 1.50E1 8.60E1 3.36E2 1990 1.50E1 0.OOEO 4.80E1 1.19E2 1991 4.59E1 O.OOEO 1.25E2 1.94E2 1992 6.10EL O.OOEO 4.80E1 1.36E2 1993 0.OOEO O.OOEO 2.10E1 1.10E2 1994 O.OOEO 0.OOEO 2.80E1 1.05E2 1995 0.OOEO 0.OOEO 3.1ME1 9.20E1 1996 O.OOEO O.OOEO 4.49E1 1.25E2 1997 O.OOEO 0.OOEO 0.OOEO 1.18E2 1998 0.OOEO 0.OOEO 0.OOEO 5.79E1 1999 O.OOEO O.OOEO 0.00E0 1.04E2 2000 0.OOEO 0.00E0 0.00E0 7.54E1 2001 1.72E1 0.OOEO 0.OOEO 9.92E1 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 2001 indicator location annual mean was 120 pCi/kg. 2000 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.

Co-58 was identified in one of the indicator location samples at a concentration of 21 pCi/kg.

Co-58 was last identified in shoreline sediment in 1996.

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

Previous environmental reports (reference 6.5) have addressed the fluctuations in shoreline sediment sample results. Some of these are attributed to differences in the actual point of sampling due to periods of drought. Samples are collected at the edge of the water. Reduced lake levels caused some samples to be taken at points that are normally submerged and where sediment deposition is expected to be greater.

K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2001.

Section 3 - Page 17

Figure 3.7-1 pCgkg Concentration of CS137 in Shoreline Sediment 1000------------------------

900 - - - _

800 __

700--K 600 500 300 200 1 00 1984 1986 1988 1990 1992 1994 1996 1998 200

-. onfroI Location 068 - Indicator Location 063 - Indicator Location 067 Figure 3.7-2 pC/kg Concentration of Co-SO in Shoreline Sediment 60 500 4 --

200 _

100 __

984 1986 1988 1990 1992 1994 1996 1998 2000 Control Locan ----- Indicator Location 063 Indicator Location W7 There are no reporting levels for shoreline sediment Sed.on 3 -Page 18 colý

Table 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment (pCilk2)

Year Mn-54 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ag-110m Sb-125 1984 1.10E1 1.09E1 1.19E1 0.OOEO 7.77E1 5.16E1 0.OOEO 0.OOEO 1985 9.39E0 1.27E0 4.79E0 0.OOEO 7.63E1 9.47E1 0.OOEO 0.OOEO 1986 2.24E1 1.62E1 2.50E1 0.OOEO 1.41E2 7.12E2 0.OOEO 0.OOEO 1987 5.40E1 4.70E2 5.07E2 0.OOEO 1.01E2 6.22E2 3.46E2 0.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 0.OOEO 5.40E1 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.MOE1 2.59E2 0.OOEO 4.50E1 5.36E2 1.71E2 9.OOEl 1991 3.26E1 5.60EI 8.57E1 0.OOEO 6.91E1 1.24E2 1.10E2 1.78E2 1992 8.79E1 1.79E2 1.12E2 O.OOEO 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50E1 0.OOEO 3.20E1 1.36E2 5.63E1 1.11E2 1994 5.30E1 7.00El 1.49E2 O.OOEO 6.70E1 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 0.OOEO 1.1El 5.20E1 O.OOEO O.OOEO 1996 0.OOEO 5.10El 0.OOEO 0.OOEO 1.98E1 1.19E2 0.OOEO 0.OOEO 1997 0.OOEO O.OOEO 0.OOEO 0.OOEO 0.OOEO 1.06E2 0.OOEO 0.OOEO 1998 O.OOEO 0.OOEO O.OOEO O.OOEO 0.OOEO 1.01E2 0.OOEO 0.OOEO 1999 6.96E1 0.OOEO O.00E0 O.OOEO O.00E0 7.38E1 0.OOEO 0.OOEO 2000 0.OOEO O.OOEO 0.00E0 0.OOEO O.00E0 8.54E1 0.00E0 0.OOEO 2001 0.OOEO 2.10E1 0.OOEO 0.OOEO O.OOEO 1.20E2 0.OOEO 0.00E0 O.OOEO = no detectable measurements 1984-1986 mean based on all net activity results Section 3 - Page 19

3.8 DIRECT GAMMA RADIATION In 2001, 167 Thenmoluminescent Dosimeters (TLD) were analyzed, 159 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 101 milliroentgen. This TLD is located at indicator location 048, 4.0 miles from the station. The annual mean exposure for the control locations was 102.4 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 2001 was 2.92E-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 824.5 milliroentgen per standard quarter. This is higher than previous measurements but is expected due to Phase 11 operations of the ISFSI. TLD measurements in the inner ring (site boundary) have not shown an increase.

Figure 3.8 mR'ynr Direct Gamma Radiation (TLD) Results 250- _

200 100 _

50 0

1984 1986 1988 1990 1992 1994 1996 1998 2000 1 A- Wner Ring -.--- Outer Ring ---- CntroI There is no reporting level for DirectRadiation (TLD)

Section 3 - Page 20 cog

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

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 Average (1991 - 2000) 75.6 82.5 105.0 2001 73.6 82.4 102.2 Section 3 - Page 21

3.9 LAND USE CENSUS The Land Use Census was conducted during the growing season (7/16 - 7/18/01 & 8/13/01) 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 2001 Land Use Census Results Sector Distance Sector Distance (Miles) (Miles)

Nearest Residence 2.97 Nearest Residence 1.98 N Nearest Milk Animal - S Nearest Milk Animal Nearest Meat Animal (Cow) - Nearest Meat Animal (Cow)

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 (Cow) 3.64 Nearest Meat Animal (Cow) 3.81 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 (Cow) 3.28 Nearest Residence 1.90 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal (Cow)

Nearest Meat Animal (Cow) 2.60 Nearest Meat Animal (Cow)

Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal - NW Nearest Milk Animal Nearest Meat Animal (Cow) - Nearest Meat Animal (Cow)

Nearest Residence 1.56 Nearest Residence 1.06 SSE Nearest Milk Animal - NNW Nearest Milk Animal Nearest Meat Animal 4.63 Nearest Meat Animal "indicatesno occurrences within the 5 mile radius Section 3 - Page 22

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4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2001 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 2001 was 2.71E-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 2001 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 2001 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 1

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 2001 environmental sample results was 2.15E-1 mrem to the adult liver. The maximum total organ dose of 6.13E-1 mrem for liquid effluent-based estimates was to the adult GI-LLI.

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 3.52E-2 mrem to the child thyroid. Vegetation was the only gaseous release pathway media that contained detectable activity. The maximum total organ dose for gaseous environmental estimates was 2.7 1E-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 2001 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental Critical Critical Maximum Dose (3)

Effluent Data Age (1) Pathway (2) (mrem)

Skin Environmental Teen Shoreline Sediment 063 (0.8 mi ESE) 4.07E-04 Skin Effluent Teen Shoreline Sediment 0.8 mi ESE 9.25E-03 Bone Environmental Child Fish 063 (0.8 mi ESE) 1.68E-01 Bone Effluent Child Fish 0.8 mi ESE 4.83E-01 Liver Environmental Adult Fish 063 (0.8 mi ESE) 2.15E-01 Liver Effluent Teen Fish 0.8 mi ESE 5.50E-01 T. Body Environmental Adult Fish 063 (0.8 mi ESE) 1.57E-01 T. Body Effluent Adult Fish 0.8 mi ESE 3.63E-01 Thyroid Environmental Child Drinking Water 063 (0.8 mi ESE) 4.98E-02 Thyroid Effluent Adult Fish 0.8 mi ESE 3.21E-02 Kidney Environmental Adult Fish 063 (0.8 mi ESE) 1.03E-01 Kidney Effluent Teen Fish 0.8 mi ESE 2.06E-01 Lung Environmental Child Drinking Water 063 (0.8 mi ESE) 6.87E-02 Lung Effluent Teen Fish 0.8 mi ESE 9.87E-02 GI-LLI Environmental Adult Drinking Water 063 (0.8 mi ESE) 5.35E-02 GI-LLI Effluent Adult Fish 0.8 mi ESE 6.13E-01 (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, PARTICULATE, and TRITIUM Critical Maximum Dose (3)

Organ Environmental or Critical Effluent Data Age (1) Pathway 2) Location (mrem)

Skin Environmental - 0.OOE+00 Skin Effluent All Ground/Plane 1.0 mi SW 4.07E-05 Bone Environmental Child Vegetation 077 (1.0 mi SW) 2.71E-01 Bone Effluent Child Vegetation 1.0 mi SW 1.42E-05 Liver Environmental Child Vegetation 077 (1.0 mi SW) 2.60E-01 Liver Effluent Child Vegetation 1.0 mi SW 2.30E-02 T. Body Environmental Adult Vegetation 077 (1.0 mi SW) 1.46E-01 T. Body Effluent Child Vegetation 1.0 mi SW 2.92E-02 Thyroid Environmental - 0.OOE+00 Thyroid Effluent Child Vegetation 1.0 mi SW 3.52E-02 Kidney Environmental Child Vegetation 077 (1.0 mi SW) 8.46E-02 Kidney Effluent Child Vegetation 1.0 mi SW 2.29E-02 Lung Environmental Child Vegetation 077 (1.0 mi SW) 3.04E-02 Lung Effluent Child Vegetation 1.0 mi SW 2.29E-02 GI-LLI Environmental Adult Vegetation 077 (1.0 mi SW) 4.31E-03 GI-LLI Effluent Child Vegetation 1.0 mi SW 2.29E-02 (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 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 7.62E-04 Gamma Environmental N/A Not Sampled Gamma Effluent N/A Noble Gas 1.0 mi SW 2.75E-04 Section4 - Page 5

F I I F F F F F F. F F I I I I F I F I F F I I F f I F I f F TABLE 4.1-B Maximum Individual Dose for 2001 based on EnvironmentalMeasurements (morem) for Oconee Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 O.OOE+00 Milk 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL O.OOE-O00 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 O.OOE+00 Child Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 2.71E-01 2.60E-01 3.83E-02 O.OOE+00 8.46E-02 3.04E-02 1.63E-03 O.OOE+00 Fish 1.68E-01 1.70E-01 3.37E-02 9.36E-03 6.17E-02 2.82E-02 1.16E-02 O.OOE+00 Shoreline Sediment 7.29E-05 7.29E-05 7.29E-05 7.29E-05 7.29E-05 7.29E-05 7.29E-05 8.51E-05 TOTAL 4.39E-01 4.70E-01 1.12E-01 4.98E-02 1.87E-01 9.91E-02 5.37E-02 8.51E-05 Teen Airborne O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 2.1lE-02 2.11E-02 2.11E-02 2.11E-02 2.1 1E-02 2.11E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.50E-01 2.OOE-01 6.95E-02 O.OOE+00 6.79E-02 2.64E-02 2.84E-03 O.OOE+00 Fish 1.33E-01 1.89E-01 7.36E-02 1.13E-02 7.16E-02 3.48E-02 1.75E-02 O.OOE+00 Shoreline Sediment 3.49E-04 3.49E-04 3.49E-04 3.49E-04 3.49E-04 3.49E-04 3.49E-04 4.07E-04 TOTAL 2.83E-01 4.10E-01 1.65E-01 3.27E-02 1.61E-01 8.26E-02 4.18E-02 4.07E-04 Adult Airborne O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.63E-01 2.23E-01 1.46E-01 O.OOE+00 7.55E-02 2.51E-02 4.31E-03 O.OOE+00 Fish 1.24E-01 1.85E-01 1.27E-01 1.47E-02 7.25E-02 3.39E-02 2.35E-02 O.OOE+00 Shoreline Sediment 6.25E-05 6.25E-05 6.25E-05 6.25E-05 6.25E-05 6.25E-05 6.25E-05 7.30E-05 TOTAL 2.87E-01 4.38E-01 3.03E-01 4.47E-02 1.78E-01 8.90E-02 5.78E-02 7.30E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

[ f " It I I I f" i i fl " I f I f I li I If I I Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2001 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (1) x.Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water 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 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Zn-65 1.84E-05 6.31F-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 O.00E+00 O.00E+00 Nb-95 4.20E-08 1.73E-08 1.00F-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+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.OOE+00 0.OOE+00 0.OOE+00 0.00OE+00 1-131 3.59E-05 4.23E-05 1.86E-05 1.39F-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+00 0.00E+00 0.OOE+00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+0O 0.OOE+00 Cs-137 5.22E-04 6.11E-04 4.33K-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06K-08 1.05K-07 4.20K-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 066 390.00 0.00E+00 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96F-02 Dose Commitment (mrem) = 0.OOE+00 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 3.96E-02 Section 4 - Page 7

II 1 F I I I[ F l I F I¸ F I  ! F* F I¸ i I FI t I !I I 1 t I

• I I IF F IF Oconee NuclearStation Dose from Drinking Water Pathwayfor 2001 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (1)x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) Bone Liver T. Body Thyroid Kidney Lung GI-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 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0,00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 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.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 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.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.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 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.O0E+00 O.OOE+00 O.OOE+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.OOE+00 O.00E+00 O.00E+00 0.OOE+00 O.O0E+00 O.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.00E+00 0.OOE+00 O.OOE+00 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.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 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 O.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 066 390.00 0.OOE+00 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 Dose Commitment (mrem) = O.OOE+00 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 Section 4 - Page 8

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Oconee NuclearStation Dosefrom BroadleafVegetation Pathwayfor 2001 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-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

+000.00E+0 0.OOE+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.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 31.90 2.71E-01 2.60E-01 3.83E-02 0.00E+00 8.46E-02 3.04E-02 1.63E-03 Dose Commitment (mrem) = 2.71E-01 2.60E-01 3.83E-02 0.OOE+00 8.46E-02 3.04E-02 1.63E-03 Section 4 - Page 9

SF F t ¸ Ii i F I F ! F l I I I¸ F I I 'F F F F Oconee Nuclear Station Dosefrom Fish Pathwayfor 2001 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 7426 pCi/l x 0.9 = 6683 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 O.OE+00 0.00E+00 0.OOE+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 063 17.20 0.OOE+00 2.14E-04 6.54E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.25E-03 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.O0E+00 0.OOE+00 0.OOE+00 0.00E+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.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 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 063 74.30 1.68E-01 1.60E-01 2.37E-02 0.OOE+00 5.23E-02 1.88E-02 1.00E-03 R-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 063 6683 0.OOE+00 9.36E-03 9.36E-03 9.36E-03 9.36E-03 9.36E-03 9.36E-03 Dose Commitment (mrem) = 1.68E-01 1.70E-01 3.37E-02 9.36E-03 6.17E-02 2.82E-02 1.16E-02 Section 4 -Page 10

Sf F F F t F i F I F* FF ( F I F I " F* FF I *F F F F Fl F Oconee NuclearStation Dosefrom Shoreline Sediment Pathwayfor 2001 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/mr Child Dose from Shorline Sediment Pathway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mz) x Shore Width Factor x Sediment Surface Mass (kglm7) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/mr) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Co-58 7.OOE-09 8.20E-09 063 21.00 1.65E-05 1.93E-05 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 063 120.00 5.64E-05 6.59E-05 Dose Commitment irem) = 7.29E-05 8.51E-05 Section 4 - Page 11

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Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2001 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (1)x Dose Factor (mrem/pCi ingested) x Concentration (pCi/1)

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

Indicator Water 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 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 O.00E+00 0.OOE+00 0.OOE+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ALL 0.00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 O.OOE+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 O.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 066 390.00 0.OOE+00 2.IIE-02 2.11E-02 2.11E-02 2.11E-02 2.11E-02 2.11E-02 Dose Commitment (mrem)= 0.OOE+00 2.11E-02 2.11E-02 2.11E-02 2.11E-02 2.11E-02 2.11E-02 Section 4- Page 12

Oconee Nuclear Station Dosefrom BroadleafVegetation Pathwayfor 2001 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 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 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2A5E-06 ALL 0.00 O.O0E+00 0.OOE+00 O.OOE+00 O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 077 31.90 1.50E-01 2.OOE-01 6.95E-02 0.OOE+00 6.79E-02 2.64E-02 2.84E-03 Dose Commitment (mrem) = 1.50E-01 2.OOE-01 6.95E-02 0.OOE+00 6.79E-02 2.64E-02 2.84E-03 Section4 - Page 13

Oconee NuclearStation Dosefrom Fish Pathwayfor 2001 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 7426 pCi/l x 0.9 = 6683 pCi/kg Usage (intake in one year) = 16 kg Highest Annual In2estion Dose Factor Net Mean Dose (mrem)

Concentration 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 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 063 17.20 0.00E+00 2.67E-04 6.16E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.69E-03 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+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 3.66E-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 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.00E+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 74.30 1.33E-01 1.77E-01 6.17E-02 0.OOE+00 6.03E-02 2.34E-02 2.52E-03 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063 6683 0.OOE+00 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E-02 Dose Commitment (mrem) = 1.33E-01 1.89E-01 7.36E-02 1.13E-02 7.16E-02 3.48E-02 1.75E-02 Section 4 - Page 14

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• IF f Oconee NuclearStation Dosefrom ShorelineSediment Pathwayfor 2001 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/rn Teen Dose from Shorline Sediment Pathway (mrem) = Shorline Recreation (hr) x External 2 2 Dose Factor (mrem/hr per pCi/m ) x Shore Width Factor x Sediment Surface Mass (kg/m ) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/rn) InCdicator Sediment (mrem)

Radionuclide T. Body Skin Lo cation (pCi/kg) T. Body Skin Co-58 7.OOE-09 8.20E-09 063 21.00 7.88E-05 9.23E-05 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 063 120.00 2.70E-04 3.15E-04 Dose Commitment (mrem) = 3.49E-04 4.07E-04 Section 4 - Page 15

Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2001 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (1)x Dose Factor (mrem/pCi ingested) x Concentration (pCi/i)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) 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.O0E+00 0.OOE+00 0.OOE+00 O.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Fe-59 4.34E-06 1.02F-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+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 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70F-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 O.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1-131 4.16E-06 5.95E-06 3.41F-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.ODE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79K-05 1.59F-05 2.59E-06 ALL 0.00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.00E4+00 0.OOE+00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70K-05 1.23E-05 2.11E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 2.03E-05 2.55E-08 1.33F-06 NO DATA 8.67E-09 1.46F-08 4.18E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 H-3 NO DATA 1.05&-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 066 390.00 0.OOE+00 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 Dose Commitment (mrem) = 0.OOE+00 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 2.99E-02 Section 4 - Page 16

Fii I I / ( (F i I F

• f I I F F Ii , , F ( F F Oconee Nuclear Station Dosefrom Broadleaf Vegetation Pathwayfor 2001 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mrenm/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) = 64 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 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 O0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 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 O.OOE+00 0.OO00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E00 0.001E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NODATA 3.70E-05 1.23E-05 2.11E-06 077 31.90 1.63E-01 2.23E-01 1.46E-01 0.00E+00 7.55F-02 2.51E-02 4.31E-03 Dose Commitment (mrem) = 1.63E-01 2.23E-01 1.46E-01 0.00E+00 7.55E-02 2.51E-02 4.31E-03 Section 4 - Page 17

Oconee Nuclear Station Dose from Fish Pathwayfor 2001 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 7426 pCi/1 x 0.9 = 6683 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Radionuclide Bone Liver NO DATA 4.57F-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Mn-54 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 063 17.20 0.OOE+00 2.69E-04 6.03E-04 0.00E+00 0.00E+00 0.00E+00 5.45E-03 Co-58 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85F-06 3.40E-05 ALL 0.00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Fe-59 Co-60 NO DATA 2.14E-06 4.72F-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96F-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 6.22F-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 063 74.30 1.24E-01 1.70E-01 1.11E-01 0.OOE+00 5.77E-02 1.92E-02 3.29E-03 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063 6683 0.00E+00 1.47E-02 1.47E-02 1.47E-02 1.47E-02 1.47E-02 1.47E-02 H-3 Dose Commitment (mrem) = 1.24E-01 1.85E-01 1.27E-01 1.47E-02 7.25E-02 3.39F-02 2.35E-02 Section 4 - Page 18

Oconee Nuclear Station Dosefrom ShorelineSediment Pathwayfor 2001 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/mZ Adult Dose from Shorline Sediment Pathway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mi) x Shore Width Factor x Sediment Surface Mass (kg/ms) x Sediment Concentration (pCi/kg)

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

(mrem/hr per pCi/mr) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Co-58 7.OOE-09 8.20E-09 063 21.00 1.41E-05 1.65E-05 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 063 120.00 4.84E-05 5.64E-05 Dose Commitment (mrem) = 6.25E-05 7.30E-05 Section 4 - Page 19

5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad Laboratories is located in Huntersville, North Carolina, at Duke Power Company's Environmental Center.

Duke Power Company's 5.3 DOSIMETRY ANALYSIS Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.

Section 5 - Page 1

5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 DUKE POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2001. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2001 is documented in Table 5.0-A.

5.6 DUKE POWER AUDITS The Oconee Radiation Protection Section was not audited by the Quality Assurance Group in 2001. A Quality Assurance audit was performed February 15 and February 16, 2000. There were no findings as a result of this 2000 audit.

EnRad Laboratories was not audited by the Quality Assurance Group in 2001. A Quality Assurance audit was performed January 26, January 27, and February 1, 2000.

Laboratory practices and procedures were reviewed. No significant problems were identified as a result of this 2000 audit.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Oconee Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in March of 2001 (reference 6.13). Air and water sampling sites were inspected and no concerns or recommendations were noted in the report. EnRad Laboratories was not audited by the NRC in 2001.

5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. Water, milk, vegetation, sediment, and fish samples collected by EnRad Laboratories are routinely split with DHEC for intercomparison analysis. DHEC collects air samples near two of the locations sampled for air by ONS. Results of the analyses performed on split and duplicate samples are sent to DHEC.

Section 5 - Page 2

5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2001 is documented in Table 5.0-B.

5.9.2 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

of Roswell, GA. Nuclear Technology Services irradiates environmental dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.

Section 5 - Page 3

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2001 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "1Pass" indicates that one analysis of the cross-check was performed.

Footnote explanations are included following this data table.

Gamma in Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/l pci 3/15/2001 Q0l1GWSL Cr-51 6.11- 10.84 E4 8.15 E4 8.19 E4 3 Pass Mn-54 2.17-3.86 E4 2.90 E4 3.01 E4 3 Pass Co-57 0.00- 0.00 EQ 0.00 EQ 1.42 E2 3 Pass "I Co-58 1.09- 1.93 E4 1.45 E4 1.47 E4 3 Pass Fe-59 2.00- 3.54 E4 2.66 E4 2.78 E4 3 Pass Co-60 3.13-5.55 E4 4.17 E4 4.17 E4 3 Pass Zn-65 4.03- 7.15 E4 5.37 E4 5.56 E4 3 Pass Cs-134 2.76-4.90 E4 3.68 E4 3.36 EN 3 Pass Cs-137 2.16-3.82 E4 2.88 E4 2.64 E4 3 Pass Ce-139 0.00-0.00 EQ 0.00 EQ 2.72 E2 3 Pass "I Ce-141 2.31-4.10 E4 3.08 E4 3.11 E4 3 Pass 6/4/2001 Q012GWR Cr-51 1.79-3.17 E2 2.39 E2 2.40 E2 3 Pass Mn-54 4.04-7.16 E2 5.39 E2 5.60 E2 3 Pass Co-58 1.09- 1.94 E2 1.46 E2 1.46 E2 3 Pass Fe-59 1.26-2.24 E2 1.68 E2 1.76 E2 3 Pass Co-60 6.75- 11.97 E2 9.00 E2 8.94 E2 3 Pass Zn-65 7.12- 12.62 E2 9.49 E2 9.67 E2 3 Pass Cs-134 5.70-10.10 E2 7.59 E2 6.71 E2 3 Pass Cs-137 4.77- 8.46 E2 6.36 E2 5.71 E2 3 Pass Ce-141 0.91- 1.62 E2 1.22 E2 1.21 E2 3 Pass 8/20/2001 Q013GWSL Cr-51 2.63-4.66 N4 3.50 E4 3.42 E4 3 Pass Mn-54 7.19 - 12.75 E3 9.58 E3 9.70 E3 3 Pass Co-58 0.79- 1.40 N4 1.05 N4 1.04 E4 3 Pass Fe-59 4.57-8.11 E3 6.10 E3 6.36 E3 3 Pass Co-60 0.88- 1.56 E4 1.17 E4 1.18 N4 3 Pass Zn-65 0.91- 1.61 N 1.21 N 1.25 E4 3 Pass Cs-134 5.37-9.52 E3 7.16 E3 6.48 E3 3 Pass Cs-137 1.04- 1.85 E4 1.39 E4 1.29 E4 3 Pass Ce-141 0.77- 1.37 EN 1.03 N4 1.04 N4 3 Pass Section 5 - Page 4

Gamma in Water 3.5 liters continued 12/4/2001 Q014GWR Cr-51 0.44-2.36 E2 1.01 E2 1.00 E2 3 Pass Mn-54 2.33-4.14 E2 3.11 E2 3.20 E2 3 Pass Co-58 1.14-2.03 E2 1.53 E2 1.55 E2 3 Pass Fe-59 3.38-6.90 El 4.83 El 5.66 El 3 Pass Co-60 3.47-6.16 E2 4.63 E2 4.76 E2 3 Pass Zn-65 2.76-4.90 E2 3.69 E2 3.84 E2 3 Pass Cs-134 2.00-3.55 E2 2.67 E2 2.46 E2 3 Pass Cs-137 4.25-7.53 E2 5.66 E2 5.38 E2 3 Pass Ce-141 3.17-6.13 El 4.41 El 4.82 El 3 Pass Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

_pCi/I pCi/I pCi/I 3/15/2001 Q011GWSL Cr-51 6.11- 10.84 E4 8.15 E4 8.10 E4 3 Pass Mn-54 2.17- 3.86 E4 2.90 E4 3.04 E4 3 Pass Co-57 0.00- 0.00 EO 0.00 EO 1.47 E2 3 Pass (

Co-58 1.09- 1.93 E4 1.45 E4 1.45 E4 3 Pass Fe-59 2.00- 3.54 E4 2.66 E4 2.81 E4 3 Pass Co-60 3.13-5.55 E4 4.17 E4 4.17 E4 3 Pass Zn-65 4.03-7.15 E4 5.37 E4 5.63 E4 3 Pass Cs-134 2.76-4.90 E4 3.68 E4 3.27 E4 3 Pass Cs-137 2.16-3.82 E4 2.88 E4 2.61 E4 3 Pass Ce-139 0.00-0.00 EO 0.00 EO 2.65 E2 3 Pass `

Ce-141 2.31-4.10 E4 3.08 E4 3.13 E4 3 Pass 6/4/2001 Q012GWR Cr-51 1.19-4.77 E2 2.39 E2 2.06 E2 3 Pass Mn-54 4.04-7.16 E2 5.39 E2 5.57 E2 3 Pass Co-58 1.09- 1.94 E2 1.46 E2 1.48 E2 3 Pass Fe-59 1.26-2.24 E2 1.68 E2 1.86 E2 3 Pass Co-60 6.75- 11.97 E2 9.00 E2 8.86 E2 3 Pass Zn-65 7.12 - 12.62 E2 9.49 E2 9.74 E2 3 Pass Cs-134 5.70- 10.10 E2 7.59 E2 6.67 E2 3 Pass Cs-137 4.77- 8.46 E2 6.36 E2 5.54 E2 3 Pass Ce-141 0.91- 1.62 E2 1.22 E2 1.14 E2 3 Pass 8/20/2001 Q013GWSL Cr-51 2.63-4.66 E4 3.50 E4 3.39 E4 3 Pass Mn-54 7.19- 12.75 E3 9.58 E3 9.86 E3 3 Pass Co-58 0.79- 1.40 E4 1.05 E4 1.04 E4 3 Pass Fe-59 4.57-8.11 E3 6.10 E3 6.46 E3 3 Pass Co-60 0.88- 1.56 E4 1.17 E4 1.17 E4 3 Pass Zn-65 0.91 - 1.61 E4 1.21 E4 1.26 E4 3 Pass Cs-134 5.37-9.52 E3 7.16 E3 6.26 E3 3 Pass Cs-137 1.04- 1.85 E4 1.39 E4 1.31 E4 3 Pass Ce-141 0.77- 1.37 E4 1.03 E4 1.02 E4 3 Pass Section 5 - Page 5

Gamma in Water 1.0 liter continued 12/4/2001 Q014GWR Cr-51 0.47-2.20 E2 1.01 E2 1.28 E2 3 Pass Mn-54 2.33-4.14 E2 3.11 E2 3.31 E2 3 Pass Co-58 1.14-2.03 E2 1.53 E2 1.56 E2 3 Pass Fe-59 2.99-7.77 El 4.83 El 5.66 El 3 Pass Co-60 3.47-6.16 E2 4.63 E2 4.83 E2 3 Pass Zn-65 2.76-4.90 E2 3.69 E2 3.97 E2 3 Pass Cs-134 2.00-3.55 E2 2.67 E2 2.40 E2 3 Pass Cs-137 4.25- 7.53 E2 5.66 E2 5.49 E2 3 Pass I Ce-141 3.09-6.30 El 4.41 El 4.59 El 3 Pass Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/I 3/15/2001 Q011GWSL Cr-51 6.11- 10.84 E4 8.15 E4 8.06 E4 3 Pass Mn-54 2.17-3.86 E4 2.90 E4 2.99 E4 3 Pass Co-57 0.00-0.00 E0 0.00 EQ 1.75 E2 3 Pass ()

Co-58 1.09- 1.93 E4 1.45 E4 1.45 E4 3 Pass Fe-59 2.00- 3.54 E4 2.66 E4 2.75 E4 3 Pass Co-60 3.13-5.55 E4 4.17 E4 4.12 E4 3 Pass Zn-65 4.03-7.15 E4 5.37 E4 5.50 E4 3 Pass Cs- 134 2.76-4.90 E4 3.68 E4 3.22 E4 3 Pass Cs-137 2.16- 3.82 E4 2.88 E4 2.57 E4 3 Pass Ce-139 0.00-0.00 EQ 0.00 EQ 2.52 E2 3 Pass ("

Ce-141 2.31-4.10 E4 3.08 E4 3.01 E4 3 Pass 6/4/2001 Q012GWR Cr-51 1.19- 4.77 E2 2.39 E2 2.51 E2 3 Pass Mn-54 4.04- 7.16 E2 5.39 E2 5.53 E2 3 Pass Co-58 1.09- 1.94 E2 1.46 E2 1.51 E2 3 Pass Fe-59 1.26-2.24 E2 1.68 E2 1.94 E2 3 Pass Co-60 6.75- 11.97 E2 9.00 E2 8.83 E2 3 Pass Zn-65 7.12- 12.62 E2 9.49 E2 9.98 E2 3 Pass Cs-134 5.70- 10.10 E2 7.59 E2 6.44 E2 3 Pass Cs-137 4.77- 8.46 E2 6.36 E2 5.73 E2 3 Pass Ce-141 0.91- 1.62 E2 1.22 E2 1.13 E2 3 Pass 8/20/2001 Q013GWSL Cr-51 2.63- 4.66 E4 3.50 E4 3.29 E4 3 Pass Mn-54 7.19 - 12.75 E3 9.58 E3 9.70 E3 3 Pass Co-58 0.79- 1.40 E4 1.05 E4 1.03 E4 3 Pass Fe-59 4.57-8.11 E3 6.10 E3 6.31 E3 3 Pass Co-60 0.88- 1.56 E4 1.17 E4 1.17 E4 3 Pass Zn-65 0.91- 1.61 E4 1.21 E4 1.25 E4 3 Pass Cs-134 5.37-9.52 E3 7.16 E3 6.06 E3 3 Pass Cs-137 1.04- 1.85 E4 1.39 E4 1.29 E4 3 Pass Ce-141 0.77- 1.37 E4 1.03 E4 1.01 E4 3 Pass Section 5 - Page 6

Gamma in Water 0.5 liter continued 12/4/2001 Q014GWR Cr-51 0.16- 6.34 E2 1.01 E2 0.82 E2 2 Pass Mn-54 2.33-4.14 E2 3.11 E2 3.22 E2 2 Pass Co-58 1.14-2.03 E2 1.53 E2 1.56 E2 2 Pass Fe-59 2.94-7.92 El 4.83 El 6.15 El 2 Pass Co-60 3.47-6.16 E2 4.63 E2 4.74 E2 2 Pass Zn-65 2.76-4.90 E2 3.69 E2 3.89 E2 2 Pass Cs-134 2.00- 3.55 E2 2.67 E2 2.30 E2 2 Pass Cs-137 4.25-7.53 E2 5.66 E2 5.31 E2 2 Pass Ce-141 3.04-6.39 E1 4.41 E1 4.08 E1 2 Pass Gamma in Water 50 ml Bottle Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pci/I pCi/I 3/15/2001 QO1IGWSL Cr-51 6.11 - 10.84 E4 8.15 E4 8.42 E4 3 Pass Mn-54 2.17-3.86 E4 2.90 E4 3.02 E4 3 Pass Co-57 0.00-0.00 EQ 0.00 EQ 1.90 E2 3 Pass "'

Co-58 1.09- 1.93 E4 1.45 E4 1.48 E4 3 Pass Fe-59 2.00- 3.54 E4 2.66 E4 2.85 E4 3 Pass Co-60 3.13- 5.55 E4 4.17 E4 4.20 E4 3 Pass Zn-65 4.03- 7.15 E4 5.37 E4 5.76 N4 3 Pass Cs-134 2.76-4.90 N4 3.68 E4 3.09 E4 3 Pass Cs-137 2.16-3.82 N4 2.88 E4 2.57 E4 3 Pass Ce-139 0.00-0.00 EQ 0.00 EQ 2.76 E2 3 Pass "

Ce-141 2.31-4.10 4 3.08 E4 3.10 E4 3 Pass Gamma In Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status p__ pa Li 6/14/2001 E2671-37 Cr-51 1.73-3.07 E2 2.31 E2 2.68 E2 3 Pass Mn-54 1.16-2.06 E2 1.55 E2 1.86 E2 3 Pass Co-58 0.75- 1.33 E2 1.00 E2 1.07 E2 3 Pass Fe-59 6.75- 11.97 El 9.00 El 12.17 El 2/3 High (2)

Co-60 1.04- 1.85 E2 1.39 E2 1.56 E2 3 Pass Zn-65 1.40-2.49 E2 1.87 E2 2.40 E2 1/3 High Cs-134 1.04- 1.84 E2 1.38 E2 1.16 E2 3 Pass Cs-137 0.94- 1.66 E2 1.25 E2 1.30 E2 3 Pass Ce-141 1.26- 2.23 E2 1.68 E2 1.80 E2 3 Pass 8/10/2001 A14773-04 Cr-51 0.77- 1.36 E5 1.02 E5 1.04 E5 3 Pass Mn-54 1.67-2.95 N4 2.22 N4 2.21 N4 3 Pass Co-57 0.00-0.00 EQ 0.00 EQ 1.54 E2 3 Pass ()

Co-58 1.97 - 3.48 E4 2.62 N4 2.62 N4 3 Pass Fe-59 1.21-2.14 E4 1.61 N4 1.65 N4 3 Pass Co-60 2.00- 3.55 E4 2.67 E4 2.70 N4 3 Pass Zn-65 2.12-3.76 N4 2.83 N4 2.84 E4 3 Pass Cs-134 1.23-2.18 N4 1.64 N4 1.53 N4 3 Pass Cs-137 2.37-4.20 N4 3.16 N4 2.94 N4 3 Pass Ce-139 0.00- 0.00 EQ 0.00 EQ 3.58 E2 3 Pass()

Ce-141 2.18-3.86 N4 2.90 N4 2.91 E4 3 Pass Section 5 - Page 7

Gamma In Filtercontinued 12/6/2001 E2899-37 Cr-51 0.92-9.01 E2 2.88 E2 3.22 E2 3 Pass Mn-54 6.45- 11.44 El 8.60 El 8.75 El 3 Pass Co-58 3.48- 7.75 El 5.20 El 5.35 El 3 Pass Fe-59 2.66- 13.10 El 5.90 El 7.96 El 3 Pass Co-60 1.54- 2.73 E2 2.05 E2 2.07 E2 3 Pass Zn-65 0.84- 1.72 E2 1.20 E2 1.32 E2 3 Pass Cs-134 0.86-1.53 E2 1.15 E2 1.11 E2 3 Pass Cs-137 1.38-2.45 E2 1.84 E2 1.69 E2 3 Pass Ce-141 1.65-2.93 E2 2.20 E2 2.19 E2 3 Pass Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 4/18/2001 Q012LIWl 1-131 1.25-2.22 E2 1.67 E2 1.81 E2 3 Pass 4/18/2001 Q012LIW2 1-131 2.51-4.44 El 3.34 El 4.17 El 3 Pass 4/18/2001 QO12LIW3 1-131 0.00- 0.00 EQ 0.00 EQ 0.00 EQ 3 Pass 8/13/2001 QO13LIW1 1-131 0.00-0.00 EQ 0.00 EO 0.00 EQ 3 Pass 8/13/2001 Q013LIW2 1-131 1.13-2.00 El 1.50 El 1.83 El 3 Pass 8/13/2001 Q013LIW3 1-131 0.75- 1.33 E2 1.00 E2 0.98 E2 3 Pass Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/i pCi/l pxi/1 11/8/2001 Q014LIM1 1-131 0.75- 1.34 El 1.01 El 0.95 El 3 Pass 11/8/2001 Q014LIM2 1-131 5.22- 9.26 El 6.97 El 6.97 El 3 Pass 11/8/2001 Q014LIM3 1-131 0.00- 0.00 EQ 0.00 EQ 0.00 EQ 3 Pass Iodine Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 1Ki pci pCi 2/16/2001 A14175-04 1-131 2.99 - 5.29 E5 3.98 E5 3.94 E5 3 Pass 6/14/2001 E2672-37 1-131 6.00 - 10.64 E1 8.00 El 8.81 El 3 Pass 8/10/2001 A14774-04 1-131 3.68 - 6.53 E5 4.91 E5 5.00 E5 3 Pass 12/6/2001 E2900-37 1-131 6.90 - 12.24 El 9.20 El 9.79 El 3 Pass Section 5 - Page 8

Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/l 3/22/2001 E2561-37 Beta 2.01-3.56 E2 2.68 E2 2.88 E2 3 Pass 9/20/2001 E2804-37 Beta 1.54-2.73 E2 2.05 E2 1.96 E2 3 Pass Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 5/11/2001 A14318-37 Beta 5.33-9.44 E3 7.10 E3 6.11 E3 3 Pass 5/11/2001 A14340-04 Beta 2.81-4.97 E3 3.74 E3 3.92 E3 3 Pass 11/9/2001 A14998-37 Beta 5.01- 8.88 E3 6.68 E3 5.92 E3 3 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/l pCi/I 3/5/2001 Q011TWSL1 H-3 0.00-0.00 E0 0.00 E0 0.00 E0 3 Pass 3/5/2001 QO11TWSL2 H-3 1.11- 1.97 E4 1.48 E4 1.29 E4 3 Pass 6/4/2001 Q012TWRI H-3 0.00 - 0.00 EQ 0.00 EQ 0.00 EQ 3 Pass 6/4/2001 Q012TWR2 H-3 1.34- 2.37 E2 1.78 E2 0.00 E2 3 Fail"'

6/4/2001 Q012TWR3 H-3 1.73-3.08 E3 2.31 E3 2.05 E3 3 Pass 8/20/2001 Q013TWS1 H-3 1 0.00-0.00 E0 0.00 EQ 0.00 E0 3 Pass 8/20/2001 Q013TWS2 H-3 2.15- 3.82 E4 2.87 E4 2.49 E4 3 Pass 12/4/2001 Q014TWR1 H-3 3.63-6.44 E2 4.84 E2 5.24 E2 3 Pass 12/4/2001 QO14TWR2 H-3 2.71-4.81 E3 3.62 E3 3.51 E3 3 Pass 12/4/2001 Q014TWR3 H-3 0.00- 0.00 EQ 0.00 EQ 0.00 EQ 3 Pass Section 5 - Page 9

Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q01 1GWSL, Reference Date 3/15/2001: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 50 ml Bottle Gamma in Filter, Sample ID A 14773-04, Reference Date 8/10/2001 Co-57 and Ce-139 were observed in cross-checks and were attributed to contaminants arriving with the source. The nuclides were determined to be present, but there was no reference activity applicable to the results.

(2) Gamma in Filter, Sample ID E2671-37, Reference Date 6/14/2001 Three results for Fe-59 [1099.2 keV] were reported, with two being above acceptance limits. Three results for Zn-65 [1115.5 keV]were reported, with one being above acceptance limits. Coincidence loss from calibration on detector face was determined to be the cause. Sample geometry was recalibrated at 3 centimeter distance from detector face. Reanalysis of cross-check yielded acceptable data. Corrective action 2001-43386 was written to record corrective actions.

(3) Tritium in Water, Sample ID Q012TWR2, Reference Date 6/4/2001 Three results were reported as blank, all indicating absence of tritium in the cross check. The reference activity value for this cross-check was 178 pCi/l. The calculated detection limit for this cross-check was 152 pCi/l. The reference value for this cross-check was below the lower limit of an expected value for a cross check. The counting error at this activity level near the LLD made accurate measurement of the cross-check virtually unattainable.

Section 5 - Page 10

TABLE 5.0-B 2001 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES State of Acceptance Cross-Check North Carolina Radiation Dosimetry & Records Criteria Date Delivered Value Reported Value (mR) (mR) +1- 15%

Spring 2001 1.00 E2 9.29 E1 -7.10 Fall 2001 5.00 El 4.92 E1 -1.68 NUCLEAR TECHNOLOGY SERVICES, INCORPORATED Acceptance Cross-Check NTS Radiation Dosimetry & Records Criteria Date Delivered Value Reported Value (mR) (mR) +1- 15%

lst Quarter 2001 8.30 E1 8.19 E1 -1.20 2nd Quarter 2001 8.20 El 8.14 El -0.76 3rd Quarter 2001 6.70 E1 6.64 El -0.96 4th Quarter 2001 7.80 El 7.76 El -0.46 Section 5 - Page 11

6.0 REFERENCES

6.1 Oconee Selected License Commitments 6.2 Oconee Technical Specifications 6.3 Oconee Updated Final Safety Analysis Report 6.4 Duke Power Company Offsite Dose Calculation Manual 6.5 Oconee Annual Radiological Environmental Operating Report 1969-2000 6.6 Oconee Annual Radioactive Effluent Release Report 2001 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Vertechs Version 3.5.0, Duke Power Revision # 3.0 6.12 Oconee Environmental Chemistry Operating Procedures 6.13 NRC Integrated Inspection Report 50-269/00-08, 50-270/00-08, 50-287/00-08 6.14 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Oconee Nuclear Station is required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.

Environmental sampling and analyses were performed by EnRad Laboratories, Dosimetry and Records, Fisheries and Aquatic Ecology, and ONS Environmental Chemistry.

Section IV of this appendix describes the environmental sampling frequencies and analysis procedures by media type.

I. CHANGE OF SAMPLING PROCEDURES No changes were made to the sampling procedures during 2001.

II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy.

Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.

Low-level iodine analyses are performed by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable.

Appendix A - Page 2

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2001.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of six locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A weekly gamma analysis was performed on each charcoal cartridge and a weekly gross beta analysis was performed on each filter. Filters were segregated by location and a quarterly gamma analysis was performed on the filter composite. The continuous composite samples were collected from the locations listed below.

Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)

Location 074 = Keowee Key Resort (2.3 mi. NNW)

Location 077 = Skimmer Wall (1.0 mi. SW)

Location 078 = Recreation Site (0.6 mi. WSW)

Location 079 = Keowee Dam (0.5 mi. NE)

Location 081 = Clemson Operations Center (9.3 mi. SE)

A.2 DRINKING WATER Monthly composite samplers were operated to collect an aliquot at least every two hours. Gross beta and gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected monthly from the locations listed below.

Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)

Location 064 = Seneca (6.7 mi. SSW)

Location 066 = Anderson (19.0 mi SSE)

Appendix A - Page 3

A.3 SURFACE WATER Monthly composite samplers were operated to collect an aliquot at least every two hours. Gamma analysis was performed on the monthly composites.

Tritium analysis was performed on the quarterly composites sample. The composites were collected monthly from the locations listed below.

Location 062 Lake Keowee/Hydro Intake (0.8 mi. ENE)

Location 063 Lake Hartwell - Hwy 183 Bridge (0.8 mi. ESE)

A.4 MILK Semimonthly grab samples were collected at each dairy. A gamma and low level Iodine-131 analysis was performed on each sample. The semimonthly grab samples were collected from the locations listed below.

Location 071 = Clemson Dairy - (10.3 mi. SSE)

Location 080 = Martin's Dairy - (17.2 mi. SE)

Location 082 = Oakway Dairy (17.8 mi SSW)

A.5 BROADLEAF VEGETATION Monthly samples were collected and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.

Location 060 New Greenville Water Intake Rd. (2.6 mi. NNE)

Location 077 Skimmer Wall (1.0 mi. SW)

Location 079 Keowee Dam (0.5 mi. NE)

Location 081 Clemson Operations Center (9.3 mi. SE)

A.6 FISH Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. The samples were collected from the locations listed below.

Location 060 New Greenville Water Intake Rd. (2.6 mi. NNE)

Location 063 Lake Hartwell - Hwy 183 Bridge (0.8 mi. ESE)

Location 067 Lawrence Ramsey Bridge, Hwy 27 (4.2 mi. SSE)

Appendix A - Page 4

A.7 SHORELINE SEDIMENT Semiannual samples were collected and a gamma analysis was performed on each sample following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 063 = Lake Hartwell - Hwy 183 Bridge (0.8 mi. ESE)

Location 067 = Lawrence Ramsey Bridge, Hwy 27 (4.2 mi. SSE)

Location 068 = High Falls County Park (2.0 mi. W)

A.8 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-two locations. A gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.

An inner ring of 17 TLDs, one in each meteorological sector in the general area of the site boundary.

An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.

The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and control locations.

TLD Locations are listed in Table 2.1-B.

A.9 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the following locations in each of the sixteen meteorological sectors:

• The Nearest Residence

• The Nearest Meat Animal

• The Nearest Milk-giving Animal (cow, goat, etc.) where milk is used for human consumption The census was conducted during the growing season from 7/16 to 7/18/2001 and completed on 8/13/2001. Results are shown in Table 3.9.

Appendix A - Page 5

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2001 Appendix B - Page 1

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 Location with Highest No. of Non Routine Medium or Type and LocationrTowithLHighestitControl Annual Mean Location Report Pathway Total Lower Limit All Indicator Locations Name, Distance, Direction Measr Sampled Number of Detection Of Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Air Particulate (pCi/m3) 081 (9.3 mi SE)

BETA 324 1.00E-02 2.OOE-2 (270/270) 060 2.05E-2 (54/54) 1.94E-2 (54/54) 0 7.26E 4.66E-2 (2.6 mi NNE) 8.86E 4.66E-2 6.42E 3.83E-2 CS-134 24 5.OOE-02 0.00(0/20) 0.00(0/4) 0.00(0/4) 0 0.00- 0.00 0.00 - 0.00 0.00 -0.00 CS-137 24 6.00E-02 0.00 (0/20) 0.00(0/4) 0.00(0/4) 0 0.00-0.00 0.00 - 0.00 0.00- 0.00 1-131 24 7.OOE-02 0.00(0/20) 0.00(0/4) 0.00(0/4) 0 0.00-0.00 0.00-0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 2

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Lepor Meas.

Unit of Analyses (LD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Air Radioiodine (pCi/m3) 081 (9.3 mi SE)

CS-134 324 5.OOE-02 0.00 (0/270) 0.00(0/54) 0.00(0/54) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 CS-137 324 6.OOE-02 0.00 (0/270) 0.00 (0/54) 0.00(0/54) 0 0.00-0.00 0.00 - 0.00 0.00 - 0.00 1-131 324 7.00E-02 0.00 (0/270) 0.00(0/54) 0.00(0/54) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Lower Location with Highest ControlNone Medium or Type and Total Limit of Annual Mean Pathway Number Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Drinking Water 064 (pCi/liter) (6.7 mi SSW)

BALA-140 42 15 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 42 4 1.63 (25/28) 066 1.75 (14/14) 1.29 (12/14) 0 0.80- 3.04 (19.0 mi SSE) 0.99 -2.45 0.83 - 1.89 CO-58 42 15 0.00(0/28) 0.00(0/14) 0.00(0/14) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 42 15 0.00 (0/28) 0.00(0/14) 0.00(0/14) 0 0.00- 0.00 0.00-0.00 0.00 -0.00 CS-134 42 15 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00 -0.00 0.00-0.00 0.00-0.00 CS-137 42 18 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 FE-59 42 30 0.00(0/28) 0.00 (0/14) 0.00(0/14) 0 0.00 -0.00 0.00-0.00 0.00-0.00 H-3 15 2000 390 (5/10) 066 390 (5/5) 0.00 (0/5) 0 306- 487 (19.0 mi SSE) 306-487 0.00-0.00 1-131 42 15 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 MN-54 42 15 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 NB-95 42 15 0.00 (0/28) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00- 0.00 ZN-65 42 30 0.00 (0/28) 0.00 (0/14) 0.00(0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 ZR-95 42 30 0.00(0/28) 0.00(0/14) 0.00(0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Medium or Type and Total Lower Al Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Surface Water 062 (pCi/liter) (0.8 mi ENE)

BALA-140 28 15 0.00 (0/14) 0.00 (0/14) 0.00(0/14) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 28 15 0.00 (0/14) 0.00(0/14) 0.00 (0/14) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 CO-60 28 15 0.00 (0/14) 0.00(0/14) 0.00 (0/14) 0 0.00 - 0.00 0.00-0.00 0.00 - 0.00 CS-134 28 15 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00 - 0.00 0.00-0.00 CS-137 28 18 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00 - 0.00 0.00-0.00 FE-59 28 30 0.00(0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00 - 0.00 0.00-0.00 H-3 10 2000 7426 (5/5) 063 7426 (5/5) 0.00 (0/5) 0 4040- 11800 (0.8 mi ESE) 4040- 11800 0.00- 0.00 1-131 28 15 0.00(0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 MN-54 28 15 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 NB-95 28 15 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00- 0.00 0.00-0.00 ZN-65 28 30 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00-0.00 0.00-0.00 0.00-0.00 ZR-95 28 30 0.00 (0/14) 0.00 (0/14) 0.00 (0/14) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @4/13/2002 8:51 AM Appendix B - Page 5

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269, 270, 287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Lower Location with Highest ControlNone Medium or Type and Total Limit of Annual Mean Pathway Number Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Milk 080 (pCi/liter) (17.2 mi SSE)

BALA-140 81 15 0.00 (0/54) 0.00 (0/27) 0.00 (0/27) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 81 15 0.00 (0/54) 0.00(0/27) 0.00(0/27) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 81 18 0.00 (0/54) 0.00(0/27) 0.00(0/27) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 1-131 81 15 0.00 (0/54) 0.00 (0/27) 0.00 (0/27) 0 0.00 - 0.00 0.00-0.00 0.00-0.00 LLI-131 81 1 0.00 (0/54) 0.00 (0/27) 0.00 (0/27) 0 0.00 - 0.00 0.00-0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 9:08 AM Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Lower Location with Highest ControlNone Medium or Type and Total Limit of Annual Mean Pathway Number Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Broadleaf Vegetation 081 (9.3 mi SE)

(pCi/kg-wet)

CS-134 48 60 0.00 (0/36) 0.00(0/12) 0.00(0/12) 0 0.00 - 0.00 0.00 -0.00 0.00 - 0.00 CS-137 48 80 31.9(1/36) 077 31.9(1/12) 0.00(0/12) 0 31.9-31.9 (1.0 mi SW) 31.9-31.9 0.00-0.00 1-131 48 60 0.00(0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 -0.00 0.00 - 0.00 0.00-0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4113/2002 9:08 AM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN.2001 to 31-DEC-2001 No. of Non-!

Lower Location with Highest ControlNone Medium or Type and Total Limit of Annual Mean Pathway Number Name, Distance, Direction Location Report Sampled of Detection Locations Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Fish 060 (pCi/kg-wet) (2.6 mi NNE)

CO-58 12 130 17.2 (2/8) 063 17.2(2/4) 0.00 (0/4) 0 15.2- 19.1 (0.8 mi ESE) 15.2 - 19.1 0.00- 0.00 CO-60 12 130 0.00 (0/8) 0.00(0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00(0/8) 0.00 (0/4) 0.00(0/4) 0 0.00-0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 83.2 (8/8) 063 99.2 (4/4) 24.9 (2/4) 0 43.9 - 165 (0.8 mi ESE) 46.6 - 165 15.5 - 34.4 FE-59 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00-0.00 0.00 - 0.00 0.00-0.00 MN-54 12 130 0.00 (0/8) 0.00 (0/4) 0.00(0/4) 0 0.00-0.00 0.00 - 0.00 0.00-0.00 ZN-65 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00-0.00 0.00-0.00 0.00-0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Shoreline 068 Sediment (2.0 mi W)

(pCi/kg-dry)

CO-58 6 0 21.0 (1/4) 063 21.0 (1/2) 0.00(0/2) 0 21.0-21.0 (0.8 mi ESE) 21.0-21.0 0.00- 0.00 CS-134 6 150 0.00(0/4) 0.00(0/2) 0.00(0/2) 0 0.00 - 0.00 0.00-0.00 0.00 - 0.00 CS-137 6 180 97.5 (4/4) 067 120(2/2) 0.00(0/2) 0 70.6- 162 (4.2 mi SSE) 77.1 - 162 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2001 to 31-DEC-2001 No. of Non Type and Total Lower LimiD Location with Highest Mean Control Location Routine Report PathwaTmyd Mediump orNumeof Number of Detection All Indicator Locations Name, Annual Distance, Direction Meas.

Unit of Measurement Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Performed Range Code Range Range Direct Radiation TLD 058 (9.4 mi WSW)

(mR/standard quarter) 081 (9.3 mi SE) 167 0.00E+00 19.6 (159/159) 048 25.3 (4/4) 25.3 (8/8) 0 12.6 -29.5 (4.0 mi W) 22.9_-27.2 19.2- 32.4 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/13/2002 8:51 AM Appendix B - Page 10

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page 1

APPENDIX C OCONEE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Tom Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action A planned power outage due to construction occurred to sampling equipment on 8/14/01 between 8:00 and 9:00 am as part of the Keowee underground cable replacement project.

Power was restored to sampling 079 8/13 - 8/20/01 8/13 - 8/20/01 PO equipment on 8/14/01 at 16:13.

Drinking Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was turned off to perform plant maintenance. Power was restored on 10/17/01 and sampling 060 10/15 - 11/12/01 10/17 - 11/12/01 PO was resumed.

Power to sampling equipment was turned off to perform plant maintenance. Power was restored on 10/17/01 and sampling 064 10/15 - 11/12/01 10/17 - 11/12/01 PO was resumed.

Appendix C - Page 2

Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Faulty power supply cord to sampling equipment caused loss of power during composite period. Power was available to the site and it was determined the cord 062 12/11/00 - 1/8/01 1/8/01 - 1/8/01 PO was causing power loss problem.

Site was checked during composite period and was inoperable. The power cord for sampling equipment was replaced on 1/15/01. Sampling equipment operating normally for the remainder of the 062 1/8 - 2/5/01 1/15 - 2/5/01 PO composite period.

Construction work on a power panel supplying power to the sampling equipment caused sampling equipment to malfunction. Power was restored and equipment was reset and sampling 062 5/29 - 6/25/01 6/20 - 6/25/01 PO resumed on 6/20/01.

Power to sampling equipment was cut during composite period due to 6/25 - 7/23/01 7/23 - 7/23/01 construction associated with the Keowee underground cable replacement project.

Sampling equipment monitored to resume 062 7/23 - 8/20/01 7/23 - 8/20/01 PO normal sampling when possible.

Sampling equipment malfunctioned and was discovered on 9/10/01. A new sampler was calibrated and placed into operation on 9/11/01. Normal sampling continued for the remainder of the 062 8/20 - 9/17/01 9/11 - 9/17/01 PS composite period.

Pump out of service due to cracked intake 12/11/00 - 1/8/01 12/11/00 - 1/8/01 line and low lake level. Work request 98168575 was written for equipment 1/8 - 2/5/01 1/8 - 2/5/01 repair. Daily 500 ml grab samples were collected when normal sampling was not 063 2/5 - 3/5/01 2/5 - 3/5/01 PS possible due to equipment failure.

Pump remains out of service. No intake flow to reservoir pump was available at time of collection. Work request 98172647 was written for repair of this site. Grab samples were taken 3/6 and 3/7/01. Water flow was restored to the 063 3/5 - 4/2/01 3/6 - 4/2/01 PS reservoir pump on 3/7/01.

Appendix C - Page 3

C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action TLD missing at time of collection. 3rd quarter TLD placed in a more secluded section at this site away 056 3/19 - 6/18/01 VN from the adjacent parking lot.

Appendix C - Page 4

APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 2001 Radiological Environmental Monitoring Program Appendix D - Page 1

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2001. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

Appendix E - Page 1