ML051370581
| ML051370581 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/31/2004 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051370581 (88) | |
Text
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY OCONEE NUCLEAR STATION Units 1, 2, and 3 2004
i 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 Nuclear Technology Services Intercomparison Program 5-3 5.9.2 State of North Carolina Intercomparison Program.
5-3 5.9.3 Internal Crosscheck (Duke Power) 5-3 6.0 References 6-1 Appendices Appendix A: Environmental Sampling and Analysis Procedures.
A-1
ii I.
Change of Sampling Procedures.
A-2 II.
Description of Analysis Procedures.
A-2 III.
Change of Analysis Procedures.
A-3 IV.
Sampling and Analysis Procedures A-3 A.1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water.
A-3 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Fish A-4 A.7 Shoreline Sediment.
A-4 A.8 Direct Gamma Radiation (TLD).
A-5 A.9 Annual Land Use Census.
A-5 V.
Global Positioning System (GPS) Analysis.
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 2004 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
iii 2.2-C Maximum Values for the Lower Limits of Detection
.2-9 3.1-A Mean Concentration of Air Radioiodine (I-131).
3-3 3.1-B Mean Concentra tion of Gross Beta in Air Particulate.
3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water.
3-6 3.3 Mean Concentrations of Radionuclides in Surface Water 3-9 3.4 Mean Concentrations of Radionuclides in Milk.
3-11 3.5 Mean Concentrations of Radionuclides in Vegetation.
3-13 3.6 Mean Concentrations of Radionuclides in Fish.
3-16 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment 3-19 3.8 Direct Gamma Radiation (TLD) Results 3-21 3.9 Oconee 2004 Land Use Census Results 3-22 4.1-A 2004 Environmental and Effluent Dose Comparison 4-3 4.1-B Maximum Individual Dose for 2004 based on Environmental Measurements for Oconee Nuclear Station.
4-6 5.0-A 2004 Cross-Check Results for EnRad Laboratories 5-4 5.0-B 2004 Environmental Dosimeter Cross-Check Results 5-12 LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order)
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 GPS Global Positioning System LLD Lower Limit of Detection M
Monthly MDA Minimum Detectable Activity mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual ONS Oconee Nuclear Station pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Process Q
Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter
µCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W
Weekly
Section 1 - Page 1 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 2004.
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 (SLCs).
Required analyses were performed and detection capabilities were met for all collected samples as required by SLCs. One-thousand fifty-three samples were analyzed comprising 1,508 test results in order to compile data for the 2004 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 2004 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 SLCs.
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 1.04E-01 mrem for 2004. 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 2 - 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 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.
Section 2 - Page 2 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):
x
=
N N
i ix
=1 Where:
x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration),
i = 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 3 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program.
LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.
MDA - The MDA may be thought of as an "actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.
2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station.
Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.
Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Some factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident). Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include some judgment by plant personnel.
Section 2 - Page 4 Figure 2.1-1
Section 2 - Page 5 Figure 2.1-2
Section 2 - Page 6 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 Location Description*
Air Rad. &
Particulate Surface Water Drinking Water Shoreline Sediment Fish Milk Broadleaf Vegetation 060 Greenville Water Intake Road (2.58 mi NNE)
W M
060 Greenville Water Intake Road (3.23 NE)
M 060 C **
Greenville Water Intake Road (2.28 NE)
SA 062 C Lake Keowee Hydro Intake (0.85 mi ENE)
M 063 Lake Hartwell Hwy 183 Bridge (0.80 mi ESE) [000.7]
SA SA 063.1 Lake Hartwell Hwy 183 (0.79 mi E)
M 064 C Seneca (6.67 mi SSW) [004.1]
M 066 Anderson (18.9 mi SSE) [012]
M 067 Lawrence Ramsey Bridge Hwy 27 (4.34 mi SSE) [005.2]
SA SA 068 C High Falls County Park (1.82 mi W)
SA 071 Clemson Dairy (10.2 mi SSE) [006.3]
SM 074 Keowee Key Resort (2.36 mi NNW)
W 077 Skimmer Wall (1.00 mi SW)
W M
078 Recreation Site (0.58 mi WSW)
W 079 Keowee Dam (0.56 mi NE)
W M
080 C Martin's Dairy (17.2 mi SE)
SM 081 C Clemson Operations Center (9.33 mi SE)
W M
082 Oakway Dairy (17.8 mi SSW)
SM 083 Oconee Belle Farm Dairy (7.10 mi W)
- GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
- Control for Fish Only
[ ] Location Numbers prior to 1984
Section 2 - Page 7 TABLE 2.1-B OCONEE RADIOLOCICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
Site Location*
Distance Sector Site Location*
Distance Sector 020 SITE BOUNDARY 0.16 miles N
040 MICROWAVE TOWER, SIX MILE 4.74 miles E
021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 4.25 miles ESE 022 SITE BOUNDARY 0.53 miles NE 042 LAWRENCE CHAPEL CHURCH, HWY 133 4.93 miles SE 023 SITE BOUNDARY 0.93 miles ENE 043 HWY 291 AT ISSAQUEENA PARK 4.09 miles SSE 024 SITE BOUNDARY 0.81 miles E
044 HWY 130 AT LITTLE RIVER DAM 3.96 miles S
025 SITE BOUNDARY 0.42 miles ESE 045 TERMINUS OF HWY 588 AT CROOKED CREEK 4.78 miles SSW 026 SITE BOUNDARY 0.34 miles SE 046 HWY 188 AT CROOKED CREEK 4.61 miles SW 027 SITE BOUNDARY 0.49 miles SSE 047 NEW HOPE CHURCH, HWY 188 3.58 miles WSW 028 SITE BOUNDARY 0.46 miles S
048 JCT HWY 175 & 188 3.64 miles W
029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.60 miles WNW 030 SITE BOUNDARY 0.42 miles SW 050 STAMP CREEK LANDING, END OF HWY 92 3.53 miles NW 031 SITE BOUNDARY 0.27 miles WSW 051 HWY 128, 1 MILE N OF HWY 130 4.64 miles NNW 076 SITE BOUNDARY 0.19 miles W
052 DPC BRANCH OFFICE SITE - PICKENS 12.4 miles ENE 032 SITE BOUNDARY 0.19 miles WNW 053 DPC BRANCH OFFICE SITE - LIBERTY 11.7 miles E
033 SITE BOUNDARY 0.21 miles WNW 054 POST OFFICE - HWY 93 NORRIS 8.60 miles ESE 034 SITE BOUNDARY 0.22 miles NW 055 CLEMSON METEOROLOGY PLOT 9.27 miles SSE 035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER -
SENECA 7.30 miles SSW 036 MILE CREEK LANDING 4.32 miles N
057 OCONEE MEMORIAL HOSPITAL 8.42 miles SW 037 KEOWEE CHURCH, HWY 327 4.85 miles NNE 058 C BRANCH RD SUBSTATION, WALHALLA 9.39 miles WSW 038 CONVENIENCE MART, JCT HWY 183 & 133 4.24 miles NE 059 TAMASSEE DAR SCHOOL 9.20 miles NW 039 HWY 133, 1 MILE EAST OF JCT HWY 183 & 133 4.02 miles ENE 081 C CLEMSON OPERATIONS CENTER 9.33 miles SE C = Control SI = Special Interest
- GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 2 - Page 8 TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water (pCi/liter)
Air Particulates or Gases (pCi/m3)
Fish (pCi/kg-wet)
Milk (pCi/liter)
Broadleaf Vegetation (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 I-131 2(b) 1 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) For drinking water samples only. This is 40CFR Part 141 value.
(b) If low-level I-131 analyses are performed.
TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Medium Analysis Schedule Gamma Isotopic Tritium Low Level I-131 Gross Beta TLD Air Radioiodine Weekly X
Air Particulate Weekly X
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 Semiannually X
Broadleaf Vegetation Monthly X
(a) Low level I-131 analysis will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of I-131 in drinking water. An LLD of 1 pCi/liter will be required for this analysis.
Section 2 - Page 9 TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION Analysis Water (pCi/liter)
Air Particulates or Gases (pCi/m3)
Fish (pCi/kg-wet)
Milk (pCi/liter)
Broadleaf Vegetation (pCi/kg-wet)
Sediment (pCi/kg-dry)
Gross Beta 4
0.01 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 I-131 15(a) 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) LLD for low-level I-131 analyses is 1 pCi/liter if performed
Section 3 - Page 1 3.0 INTERPRETATION OF RESULTS Review of 2004 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 2004 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, I-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 2004.
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 2004 was 2.65% 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 2004. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas.
Section 3 - Page 2 3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2004, 312 radioiodine and particulate samples were analyzed, 260 from five indicator locations and 52 from the control location. Particulate samples were analyzed weekly for gamma and gross beta.
Radioiodine samples received a weekly gamma analysis.
There was no detectable I-131 in air samples in 2004. Table 3.1-A gives the highest indicator location annual mean and control location annual mean for I-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 I-131 has been detected since 1994.
Cs-137 was not detected in air radioiodine samples in 2004. 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 2004. No gamma emitting particulates have been detected in indicator location samples since the change in gamma spectroscopy analysis systems in 1987.
Beta analysis of particulate filters was initiated in March of 1996 and became required by Selected Licensee Commitments in 1998. Gross beta analysis was performed on particulate filters during the preoperational and early operational history of the plant but had not been required since 1984. Figure 3.1 summarizes gross beta results for the indicator location with the highest annual mean and the control location samples. Both the indicator and control location results are similar in concentration and are near the lower range of preoperational gross beta results.
K-40 and Be-7 are the naturally occurring radionuclides that were observed in air samples.
Section 3 - Page 3 Table 3.1-A Mean Concentration of Air Radioiodine (I-131)
Year Indicator Location (pCi/m3)
Control Location (pCi/m3)
Preoperational 1969-1972 0.00E0 0.00E0 Feb. 1973 - June 1973 0.00E0 0.00E0 July 1973 - Dec. 1973 0.00E0 0.00E0 Jan. 1974 - June 1974 0.00E0 0.00E0 July 1974 - Dec. 1974 2.60E-2 8.00E-3 Jan. 1975 - June 1975 8.65E-2 3.12E-2 July 1975 - Dec. 1975 1.13E-2 9.52E-3 1976 2.76E-2 2.18E-2 1977 3.60E-2 3.60E-2 1978 2.19E-1 1.15E-1 1979 7.54E-3 4.75E-4 1980 3.07E-3 9.67E-4 1981 6.31E-3 5.39E-4 1982 2.87E-3 8.10E-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 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 1.03E-2 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results
Section 3 - Page 4 Figure 3.1 There is no reporting level for gross beta in air particulate Table 3.1-B Mean Concentration of Gross Beta in Air Particulate Monitoring Period Indicator Location (pCi/m3)
Control Location (pCi/m3) 1996 3.87E-2 3.69E-2 1997 2.87E-2 2.92E-2 1998 2.47E-2 1.56E-2 1999 2.85E-2 2.23E-2 2000 2.38E-2 1.85E-2 2001 2.05E-2 1.94E-2 2002 2.01E-2 1.84E-2 2003 1.86E-2 1.82E-2 Average (1996 - 2003) 2.55E-2 2.23E-2 2004 1.92E-2 1.90E-2 Concentration of Gross Beta in Air Particulate 0.00E+00 5.00E-03 1.00E-02 1.50E-02 2.00E-02 2.50E-02 3.00E-02 3.50E-02 4.00E-02 4.50E-02 1996 1997 1998 1999 2000 2001 2002 2003 2004 pCi/m 3
Control Location Indicator Location Pre-operational sample results ranged from 0.04 to 1.46 pCi/m3
Section 3 - Page 5 3.2 DRINKING WATER Gross beta analysis and gamma spectroscopy were performed on 39 monthly drinking water samples.
These samples were composited to form 15 quarterly period samples for Tritium analysis. Two indicator locations and a control location were sampled; however, only one of the indicator locations is downstream of the effluent release point.
Table 3.2 lists the highest indicator location annual mean and control location annual mean for gross beta results since the preoperational period. The indicator location had an average concentration of 1.58 pCi/liter in 2004, and the control location had a concentration of 1.25 pCi/liter. The 2003 indicator mean was 1.51 pCi/liter. The table shows that 2004 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 2004; therefore low-level iodine analysis is not required.
Tritium was detected in four of the 15 composite samples during 2004. Tritium was detected in four of the 15 composite samples during 2003. The 2004 mean indicator location 066 concentration was 225 pCi/liter, which is 1.13% 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 2004. Gamma spectroscopy analysis has not detected any activity in the water supplies since 1988. K-40 is the naturally occurring radionuclide that was observed in drinking water samples.
Figure 3.2 Current reporting level implemented 1984 Concentration of Tritium in Drinking Water 0
500 1000 1500 2000 2500 3000 3500 4000 4500 5000 1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 pCi/liter Control Location Indicator Location 20 % Reporting Level
Section 3 - Page 6 Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCi/l)
Tritium (pCi/l)
Year Indicator Location Control Location Indicator Location Control Location Preoperational ending Jan. 1971 3.03 5.90 Analysis not required Preoperational ending Jan. 1973 3.58 4.94 Analysis not required Feb. 1973 - June 1973 Qualitative results reported Analysis not required June 1973 - Dec. 1973 7.15 21.78 Analysis not required Jan. 1974 - June 1974 3.13 6.98 Analysis not required July 1974 - Dec. 1974 2.24 2.02 525 330 Jan. 1975 - June 1975 1.98 1.59 600 300 July 1975 - Dec. 1975 2.01 1.22 2990 505 1976 2.38 2.00 2196 224 1977 2.70 2.30 1200 290 1978 2.56 2.17 1050 333 1979 1.83 1.36 576 235 1980 1.86 1.63 660 200 1981 1.98 1.88 830 127 1982 2.04 1.45 643 153 1983 1.85 1.54 937 220 1984 1.87 1.08 765 145 1985 2.14 1.16 856 210 1986 1.91 1.04 1240 503 1987 2.00 1.20 815 680 1988 2.00 1.40 1570 0.00 1989 2.30 1.80 1350 559 1990 3.00 2.70 0.00 0.00 1991 1.80 1.40 558 0.00 1992 3.20 1.60 0.00 0.00 1993 2.10 1.90 0.00 0.00 1994 1.90 2.10 0.00 0.00 1995 5.10 2.90 248 0.00 1996 2.07 1.77 214 0.00 1997 2.52 2.23 194 0.00 1998 2.48 1.70 0.00 0.00 1999 1.73 1.49 185 0.00 2000 2.07 1.68 251 0.00 2001 1.75 1.29 390 0.00 2002 1.61 1.21 338 0.00 2003 1.51 1.05 266 0.00 2004 1.58 1.25 225 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 7 3.3 SURFACE WATER Gamma spectroscopy was performed on 26 monthly surface water samples. These samples were composited to form 10 quarterly samples for Tritium analysis. One indicator and one control location were sampled. The indicator location is near the liquid effluent release point.
Tritium was detected in the five indicator location samples. The 2004 average concentration was 3,858 pCi/liter. The individual samples ranged from 1,150 pCi/liter to 6,209 pCi/liter. The 2003 mean concentration was 4,768 pCi/liter. Tritium was not detected in any control surface water samples.
Figure 3.3 shows the indicator and control annual means for Tritium since the preoperational period.
Table 3.3 lists the indicator annual means. Tritium in the indicator location was elevated during an extended drought from 1998 through 2002. The average tritium concentration decreased in 2003 with increased rainfall.
Gamma spectroscopy analysis did not detect any station related activity during 2004. In 1999, gamma spectroscopy analysis detected Co-58 in one indicator sample at 27.2 pCi/liter. 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 2004 did not reveal any increasing trends.
K-40 is the naturally occurring radionuclide observed in surface water samples in 2004.
Section 3 - Page 8 Concentration of Tritium in Surface Water 0
10000 20000 30000 40000 50000 60000 1969 1972 1975 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 pCi/liter Control Location Indicator Location Figure 3.3 There is no reporting level for Tritium in surface water
Section 3 - Page 9 Table 3.3 Mean Concentrations of Radionuclides in Surface Water Year Co-58 (pCi/l)
Co-60 (pCi/l)
Nb-95 (pCi/l)
Cs-137 (pCi/l)
H-3 pCi/l)
Preoperational 1969 Qualitative results reported 4.86E2 Preoperational 1970 5.94E2 Preoperational 1971 4.01E2 Preoperational 1972 3.62E2 1973 0.00E0 1974 0.00E0 1.32E1 0.00E0 1.60E1 1.99E3 Jan. 1975 - June 1975 0.00E0 0.00E0 0.00E0 0.00E0 1.56E4 July 1975 - Dec. 1975 0.00E0 1.34E1 0.00E0 0.00E0 5.52E4 1976 1.08E2 3.30E1 0.00E0 3.50E1 2.95E4 1977 2.60E1 1.80E1 0.00E0 3.10E1 2.90E3 1978 2.96E2 0.00E0 0.00E0 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 1.10E0 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 1.14E0 3.07E-1 1.26E4 1987 5.10E1 3.40E0 4.00E0 0.00E0 7.08E3 1988 6.20E0 5.00E0 2.50E0 3.50E0 1.10E4 1989 5.30E0 3.00E0 0.00E0 3.40E0 1.02E4 1990 1.70E0 1.60E0 0.00E0 0.00E0 1.03E4 1991 5.40E0 0.00E0 0.00E0 0.00E0 5.76E3 1992 2.50E0 0.00E0 0.00E0 0.00E0 6.22E3 1993 0.00E0 0.00E0 0.00E0 0.00E0 8.62E3 1994 0.00E0 0.00E0 0.00E0 0.00E0 5.75E3 1995 0.00E0 0.00E0 0.00E0 0.00E0 6.65E3 1996 0.00E0 0.00E0 0.00E0 0.00E0 4.54E3 1997 0.00E0 0.00E0 0.00E0 0.00E0 5.50E3 1998 0.00E0 0.00E0 0.00E0 0.00E0 3.35E3 1999 2.73E1 0.00E0 0.00E0 0.00E0 1.13E4 2000 0.00E0 0.00E0 0.00E0 0.00E0 1.48E4 2001 0.00E0 0.00E0 0.00E0 0.00E0 7.43E3 2002 0.00E0 0.00E0 0.00E0 0.00E0 1.00E4 2003 0.00E0 0.00E0 0.00E0 0.00E0 4.77E3 2004 0.00E0 0.00E0 0.00E0 0.00E0 3.86E3 0.00E0 = no detectable measurements 1979-1986 mean based on all net activity results
Section 3 - Page 10 3.4 MILK Gamma spectroscopy and low level iodine analysis was performed on 104 milk samples collected in 2004. Three indicator locations and one control location were sampled.
There were no gamma emitting radionuclides identified in indicator or control location samples in 2004. 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 2004.
Section 3 - Page 11 Table 3.4 Mean Concentration of Radionuclides in Milk Year Cs-137 Indicator (pCi/l)
Cs-137 Control (pCi/l)
Preoperational 1.57E1 1.46E1 Feb. 1973 - June 1973 Qualitative results reported Qualitative results reported July 1973 - Dec. 1973 5.80E0 Jan. 1974 - June 1974 5.30E0 0.00E0 July 1974 - Dec. 1974 1.11E1 0.00E0 Jan. 1975 - June 1975 1.51E1 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 0.00E0 1991 5.00E0 0.00E0 1992 6.60E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 1.80E0 1995 2.30E0 2.00E0 1996 0.00E0 4.10E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results
Section 3 - Page 12 3.5 BROADLEAF VEGETATION Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2004. Three indicator locations and one control location were sampled. There were no gamma emitting radionuclides identified in indicator location samples in 2004. Cs-137 was reported in one control location sample in 2004 at a concentration of 59.6 pCi/kg.
Sampling of control location 073 (which has historically had measurable Cs-137 concentrations greater than any indicator location) was discontinued early in 1999 due to construction. The new control location, 081, was added to the program in 1998.
Cs-137 is the only radionuclide, other than naturally occurring, reported in indicator location vegetation samples since the change in gamma spectroscopy analysis systems in 1987.
It is not unusual for Cs-137 to be present in vegetation. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous years.
Table 3.5 lists the highest indicator location annual mean and control location annual mean for Cs-137 since early in the stations operational history. Visual inspection of the tabular data did not reveal any increasing trends. There is no indication that the Cs-137 is due to ONS operations based on the low concentration observed and the absence of other radionuclides.
K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf vegetation samples in 2004.
Figure 3.5 Concentration of Cs-137 in Broadleaf Vegetation 0
500 1000 1500 2000 2500 1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 pCi/kg Indicator Location Control Location Reporting Level
Section 3 - Page 13 Table 3.5 Mean Concentration of Radionuclides in Vegetation Year Cs-137 Indicator (pCi/kg)
Cs-137 Control (pCi/kg)
July 1974 - Dec. 1974 1.54E3 0.00E0 Jan. 1975 - June 1975 1.55E3 1.59E3 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 0.00E0 0.00E0 1977 0.00E0 7.90E2 1978 1.19E2 8.19E1 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 0.00E0 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 1997 4.73E1 1.35E2 1998 7.28E1 1.61E2 1999 1.34E2 0.00E0 2000 1.06E2 0.00E0 2001 3.19E1 0.00E0 2002 8.44E1 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 5.96E1 0.00E0 = 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 14 3.6 FISH In 2004, 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. Cs-137 was not detected in any of the four control location samples.
The highest average concentration for Cs-137 was 52.9 pCi/kg (2.65% of reporting level). The highest individual sample concentration for Cs-137 was 82.8 pCi/kg (4.14% of reporting level).
Figures 3.6-1 and 3.6-2 are graphs displaying the annual means for Cs-137 and Cs-134.
Historically, both are major contributors to the calculated dose from liquid effluents from ingestion of fish. Radioactivity concentrations in downstream fish samples are higher than those reported in preoperational fish samples, however, concentrations in fish have decreased over time with decreases in radioactive material releases from the plant.
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 2004. 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.
Section 3 - Page 15 Figure 3.6-1 Figure 3.6-2 Current reporting levels implemented 1984 Concentration of Cs-137 in Fish 0
500 1000 1500 2000 2500 1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 pCi/kg Control Location Indicator Location Reporting Level Concentration of Cs-134 in Fish 0
100 200 300 400 500 600 700 1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 pCi/kg Control Location Indicator Location 50 % Reporting Level
Section 3 - Page 16 Table 3.6 Mean Concentrations of Radionuclides in Fish Year Co-58 (pCi/kg)
Co-60 (pCi/kg)
Cs-134 (pCi/kg)
Cs-137 (pCi/kg)
Preop ending Jan.1971 0.00E0 0.00E0 0.00E0 1.46E2 Preop ending Jan.1973 0.00E0 0.00E0 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 0.00E0 7.00E1 3.13E2 1976 5.70E1 1.14E2 7.73E1 1.66E2 1977 0.00E0 0.00E0 1.80E2 3.60E2 1978 3.27E2 0.00E0 3.31E2 0.00E0 1979 1.91E0 1.56E1 9.26E1 3.88E2 1980 1.45E1 1.90E1 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 0.00E0 7.20E1 2.60E2 1989 4.30E1 1.50E1 8.60E1 3.36E2 1990 1.50E1 0.00E0 4.80E1 1.19E2 1991 4.59E1 0.00E0 1.25E2 1.94E2 1992 6.10E1 0.00E0 4.80E1 1.36E2 1993 0.00E0 0.00E0 2.10E1 1.10E2 1994 0.00E0 0.00E0 2.80E1 1.05E2 1995 0.00E0 0.00E0 3.10E1 9.20E1 1996 0.00E0 0.00E0 4.49E1 1.25E2 1997 0.00E0 0.00E0 0.00E0 1.18E2 1998 0.00E0 0.00E0 0.00E0 5.79E1 1999 0.00E0 0.00E0 0.00E0 1.04E2 2000 0.00E0 0.00E0 0.00E0 7.54E1 2001 1.72E1 0.00E0 0.00E0 9.92E1 2002 0.00E0 0.00E0 0.00E0 9.37E1 2003 5.02E1 0.00E0 0.00E0 6.04E1 2004 0.00E0 0.00E0 0.00E0 5.29E1 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results
Section 3 - Page 17 3.7 SHORELINE SEDIMENT Gamma spectroscopy was performed on eight sediment samples. Two downstream indicator locations and one control location were sampled. Six samples were taken from indicator locations and two from the control location. A second set of samples was taken from the indicator locations for the October 2004 sampling for verification of Mn-54 activity.
Mn-54 was identified in three of the six indicator location samples. The highest 2004 Mn-54 indicator location annual mean was 85.4 pCi/kg. Mn-54 was last detected in shoreline sediment in 1999.
Cs-137 was identified in three of the six indicator location samples. Cs-137 was not observed in any control location samples. The highest 2004 indicator location annual mean was 95.6 pCi/kg.
Releases of Cs-137 in liquid effluents in 2004 were less than releases in 2003. Releases of Cs-137 in liquid effluents for 2003 were slightly higher than 2002. Table 3.7 lists the highest indicator location annual means since shoreline sediment was initiated in 1984. Included in the table are radionuclides that have been identified in this media since the change in analysis systems in 1987.
Visual inspection of the tabular data did not reveal any trends. Figure 3.7-1 is a graph of the Cs-137 annual means. Figure 3.7-2 is a graph of the Co-60 annual means. Historically, both are major contributors to the calculated dose from liquid effluents from shoreline sediment. No trends are apparent.
K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2004.
Section 3 - Page 18 Figure 3.7-1 Figure 3.7-2 There are no reporting levels for shoreline sediment Concentration of Cs-137 in Shoreline Sediment 0
100 200 300 400 500 600 700 800 900 1000 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 pCi/kg Control Location 068 Indicator Location 063 Indicator Location 067 Concentration of Co-60 in Shoreline Sediment 0
100 200 300 400 500 600 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 pCi/kg Control Location 068 Indicator Location 063 Indicator Location 067
Section 3 - Page 19 Table 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)
Year Mn-54 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ag-110m Sb-125 1984 1.10E1 1.09E1 1.19E1 0.00E0 7.77E1 5.16E1 0.00E0 0.00E0 1985 9.39E0 1.27E0 4.79E0 0.00E0 7.63E1 9.47E1 0.00E0 0.00E0 1986 2.24E1 1.62E1 2.50E1 0.00E0 1.41E2 7.12E2 0.00E0 0.00E0 1987 5.40E1 4.70E2 5.07E2 0.00E0 1.01E2 6.22E2 3.46E2 0.00E0 1988 3.30E1 1.20E2 1.87E2 6.70E1 6.60E1 7.59E2 1.62E2 3.67E2 1989 2.30E1 1.24E2 1.96E2 0.00E0 5.40E1 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.00E1 2.59E2 0.00E0 4.50E1 5.36E2 1.71E2 9.00E1 1991 3.26E1 5.60E1 8.57E1 0.00E0 6.91E1 1.24E2 1.10E2 1.78E2 1992 8.79E1 1.79E2 1.12E2 0.00E0 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50E1 0.00E0 3.20E1 1.36E2 5.63E1 1.11E2 1994 5.30E1 7.00E1 1.49E2 0.00E0 6.70E1 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 0.00E0 1.10E1 5.20E1 0.00E0 0.00E0 1996 0.00E0 5.10E1 0.00E0 0.00E0 1.98E1 1.19E2 0.00E0 0.00E0 1997 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.06E2 0.00E0 0.00E0 1998 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.01E2 0.00E0 0.00E0 1999 6.96E1 0.00E0 0.00E0 0.00E0 0.00E0 7.38E1 0.00E0 0.00E0 2000 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 8.54E1 0.00E0 0.00E0 2001 0.00E0 2.10E1 0.00E0 0.00E0 0.00E0 1.20E2 0.00E0 0.00E0 2002 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 6.96E1 0.00E0 0.00E0 2003 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.93E2 0.00E0 0.00E0 2004 8.54E1 0.00E0 0.00E0 0.00E0 0.00E0 9.56E1 0.00E0 0.00E0 0.00E0 = no detectable measurements 1984-1986 mean based on all net activity results
Section 3 - Page 20 Direct Gamma Radiation (TLD) Results 0
50 100 150 200 250 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 mR/year Inner Ring Outer Ring Control 3.8 DIRECT GAMMA RADIATION In 2004, 167 Thermoluminescent 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 115 milliroentgen. This TLD is located at indicator location 036, 4.32 miles from the station. The annual mean exposure for the control locations was 110 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 2004 was 2.69E-2 mrem, which is 0.03% 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 909 milliroentgen per standard quarter. This is consistent with previous measurements. TLD measurements in the inner ring (site boundary) have remained relatively constant.
Figure 3.8 There is no reporting level for Direct Radiation (TLD)
Section 3 - Page 21 Table 3.8 Direct Gamma Radiation (TLD) Results Year Inner Ring Average (mR/yr)
Outer Ring Average (mR/yr)
Control (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 2001 73.6 82.4 102.2 2002 76.6 85.3 108.0 2003 77.4 86.6 108.8 Average (1994 - 2003) 77.2 86.1 109.6 2004 80.1 87.5 110.4
Section 3 - Page 22 3.9 LAND USE CENSUS The Land Use Census was conducted during the growing season (6/21 - 6/22/2004) 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 1.00 miles. No program changes were required based on the results of the census.
Table 3.9 Oconee 2004 Land Use Census Results Sector Distance (Miles)*
Sector Distance (Miles)*
N Nearest Residence Nearest Milk Animal 2.98 S
Nearest Residence Nearest Milk Animal 1.86 NNE Nearest Residence Nearest Milk Animal 2.38 SSW Nearest Residence Nearest Milk Animal 1.36 NE Nearest Residence Nearest Milk Animal 1.20 SW Nearest Residence Nearest Milk Animal 1.39 ENE Nearest Residence Nearest Milk Animal 1.34 WSW Nearest Residence Nearest Milk Animal 1.81 E
Nearest Residence Nearest Milk Animal 1.14 W
Nearest Residence Nearest Milk Animal 1.76 ESE Nearest Residence Nearest Milk Animal 1.57 WNW Nearest Residence Nearest Milk Animal 1.35 SE Nearest Residence Nearest Milk Animal 1.46 NW Nearest Residence Nearest Milk Animal 1.00 SSE Nearest Residence Nearest Milk Animal 1.54 NNW Nearest Residence Nearest Milk Animal 1.06
- indicates no occurrences within the 5 mile radius
- GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 3 - Page 23 Figure 3.9
Section 4 - Page 1 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 2004 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, 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, airborne particulate, or broadleaf vegetation 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 2004 was 1.32E-1 mrem to the teen's liver from consuming fish.
4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2004 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 2004 ONS Annual Radioactive Effluent Release Report (reference 6.6) included calendar year dose estimates for the location with the highest
Section 4 - Page 2 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.
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 2004 environmental sample results was 1.46E-1 mrem to the adult liver. The maximum total organ dose of 5.71E-1 mrem for liquid effluent-based estimates was to the teen liver.
No environmental doses resulted from the gaseous pathway in 2004 because broadleaf vegetation, milk, and airborne radioiodines and particulates indicated no activity. The gaseous effluent dose is due to tritium on broadleaf vegetation.
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.
TABLE 4.1-A Page 1 of 3 OCONEE NUCLEAR STATION 2004 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Organ Environmental or Effluent Data Critical Age (1)
Critical Pathway (2)
Location Maximum Dose (3)
(mrem)
Skin Environmental Teen Shoreline Sediment 067 (4.34 mi SSE) 5.62E-04 Skin Effluent Teen Shoreline Sediment 1.0 mi. SW 7.64E-03 Bone Environmental Child Fish 063 (0.80 mi ESE) 1.19E-01 Bone Effluent Child Fish 1.0 mi. SW 4.87E-01 Liver Environmental Adult Fish 063 (0.80 mi ESE) 1.46E-01 Liver Effluent Teen Fish 1.0 mi. SW 5.71E-01 T. Body Environmental Adult Fish 063 (0.80 mi ESE) 1.04E-01 T. Body Effluent Adult Fish 1.0 mi. SW 3.88E-01 Thyroid Environmental Child Drinking Water 066 (18.9 mi SSE) 2.82E-02 Thyroid Effluent Child Drinking Water 1.0 mi. SW 5.07E-02 Kidney Environmental Adult Fish 063 (0.80 mi ESE) 6.60E-02 Kidney Effluent Adult/Teen Fish 1.0 mi. SW 2.20E-01 Lung Environmental Child Drinking Water 066 (18.9 mi SSE) 4.16E-02 Lung Effluent Teen Fish 1.0 mi. SW 1.11E-01 GI-LLI Environmental Child Drinking Water 066 (18.9 mi SSE) 2.89E-02 GI-LLI Effluent Adult Fish 1.0 mi. SW 1.08E-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 Organ Environmental or Effluent Data Critical Age (1)
Critical Pathway (2)
Location Maximum Dose (3)
(mrem)
Skin Environmental 0.00E+00 Skin Effluent All Ground Plane 1.0 mi. SW 4.41E-05 Bone Environmental 0.00E+00 Bone Effluent Child Vegetation 1.0 mi. SW 8.57E-05 Liver Environmental 0.00E+00 Liver Effluent Child Vegetation 1.0 mi. SW 2.69E-02 T. Body Environmental 0.00E+00 T. Body Effluent Child Vegetation 1.0 mi. SW 2.69E-02 Thyroid Environmental 0.00E+00 Thyroid Effluent Child Vegetation 1.0 mi. SW 2.69E-02 Kidney Environmental 0.00E+00 Kidney Effluent Child Vegetation 1.0 mi. SW 2.69E-02 Lung Environmental 0.00E+00 Lung Effluent Child Vegetation 1.0 mi. SW 2.69E-02 GI-LLI Environmental 0.00E+00 GI-LLI Effluent Child Vegetation 1.0 mi. SW 2.69E-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 Dose Environmental or Effluent Data Critical Age Critical Pathway Location Maximum Dose (mrad)
Beta Environmental Not Sampled Beta Effluent N/A Noble Gas 1.0 mi. SW 5.66E-04 Gamma Environmental Not Sampled Gamma Effluent N/A Noble Gas 1.0 mi. SW 2.79E-04 Section 4 - Page 5
TABLE 4.1-B Maximum Individual Dose for 2004 based on Environmental Measurements (mrem) for Oconee Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 0.00E+00 Child Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 1.19E-01 1.19E-01 2.17E-02 4.86E-03 4.21E-02 1.83E-02 5.58E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.00E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-04 TOTAL 1.19E-01 1.42E-01 4.51E-02 2.82E-02 6.54E-02 4.16E-02 2.89E-02 1.18E-04 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 9.48E-02 1.32E-01 4.98E-02 5.89E-03 4.88E-02 2.26E-02 7.68E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 4.81E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.62E-04 TOTAL 9.48E-02 1.44E-01 6.25E-02 1.81E-02 6.10E-02 3.48E-02 1.99E-02 5.62E-04 Adult Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 8.85E-02 1.29E-01 8.70E-02 7.66E-03 4.88E-02 2.13E-02 1.00E-02 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 8.61E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-04 TOTAL 8.85E-02 1.46E-01 1.04E-01 2.49E-02 6.60E-02 3.85E-02 2.72E-02 1.00E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.
Section 4 - Page 6
Oconee Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
330 l 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 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-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 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 066 225 0.00E+00 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 Dose Commitment (mrem) =
0.00E+00 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 2.29E-02 Section 4 - Page 7
Oconee Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
510 l 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-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 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+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 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 066 225 0.00E+00 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 Dose Commitment (mrem) =
0.00E+00 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 2.33E-02 Section 4 - Page 8
Oconee Nuclear Station Dose from Fish Pathway for 2004 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 = 3858 pCi/l x 0.9 = 3472 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 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-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 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+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 52.9 1.19E-01 1.14E-01 1.69E-02 0.00E+00 3.72E-02 1.34E-02 7.15E-04 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 063.1 3472 0.00E+00 4.86E-03 4.86E-03 4.86E-03 4.86E-03 4.86E-03 4.86E-03 Dose Commitment (mrem) =
1.19E-01 1.19E-01 2.17E-02 4.86E-03 4.21E-02 1.83E-02 5.58E-03 Section 4 - Page 9
Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Child Shoreline Recreation =
14 hr (in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2)
Indicator Sediment (mrem)
Radionuclide T. Body Skin Location (pCi/kg)
T. Body Skin Mn-54 5.8E-09 6.8E-09 067 85.4 5.55E-05 6.50E-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 95.6 4.50E-05 5.25E-05 Dose Commitment (mrem) =
1.00E-04 1.18E-04 Section 4 - Page 10
Oconee Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
510 l 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 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-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 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-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 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+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 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 066 225 0.00E+00 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 Dose Commitment (mrem)=
0.00E+00 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 Section 4 - Page 11
Oconee Nuclear Station Dose from Fish Pathway for 2004 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 = 3858 pCi/l x 0.9 = 3472 pCi/kg Usage (intake in one year) =
16 kg Highest Annual Ingestion Dose Factor Net Mean Dose (mrem)
Concentration 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 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-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 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+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 52.9 9.48E-02 1.26E-01 4.39E-02 0.00E+00 4.29E-02 1.67E-02 1.79E-03 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063.1 3472 0.00E+00 5.89E-03 5.89E-03 5.89E-03 5.89E-03 5.89E-03 5.89E-03 Dose Commitment (mrem) =
9.48E-02 1.32E-01 4.98E-02 5.89E-03 4.88E-02 2.26E-02 7.68E-03 Section 4 - Page 12
Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Teen Shoreline Recreation =
67 hr (in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2)
Indicator Sediment (mrem)
Radionuclide T. Body Skin Location (pCi/kg)
T. Body Skin Mn-54 5.8E-09 6.8E-09 067 85.4 2.65E-04 3.11E-04 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 95.6 2.15E-04 2.51E-04 Dose Commitment (mrem) =
4.81E-04 5.62E-04 Section 4 - Page 13
Oconee Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
730 l 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 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-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 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 066 225 0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 Dose Commitment (mrem) =
0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 Section 4 - Page 14
Oconee Nuclear Station Dose from Fish Pathway for 2004 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 = 3858 pCi/l x 0.9 = 3472 pCi/kg Usage (intake in one year) =
21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)
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 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-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 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 063 52.9 8.85E-02 1.21E-01 7.93E-02 0.00E+00 4.11E-02 1.37E-02 2.34E-03 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063.1 3472 0.00E+00 7.66E-03 7.66E-03 7.66E-03 7.66E-03 7.66E-03 7.66E-03 Dose Commitment (mrem) =
8.85E-02 1.29E-01 8.70E-02 7.66E-03 4.88E-02 2.13E-02 1.00E-02 Section 4 - Page 15
Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Adult Shoreline Recreation =
12 hr (in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)
(mrem/hr per pCi/m2)
Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg)
T. Body Skin Mn-54 5.8E-09 6.8E-09 067 85.4 4.76E-05 5.57E-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 95.6 3.85E-05 4.50E-05 Dose Commitment (mrem) =
8.61E-05 1.01E-04 Section 4 - Page 16
Section 5 - Page 1 Duke Power Companys Environmental Center 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 Companys Environmental Center.
5.3 DOSIMETRY ANALYSIS 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 2 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 2004. 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 2004 is documented in Table 5.0-A.
5.6 DUKE POWER AUDITS The Oconee Radiation Protection Section was audited by the Quality Assurance Group in March 2004. There were no findings as a result of this 2004 audit.
EnRad Laboratories was audited by the Quality Assurance Group in March, 2004. Laboratory practices and procedures were reviewed. One example of insufficient documentation for a cross-check which yielded data outside of acceptance limits was identified and is described in PIP G-04-00140. Several areas for improvement were identified and are described in PIP G-04-00142.
There were no significant findings as a result of this audit.
5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Oconee Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in September, 2004 (reference 6.12). The 2003 AREOR was reviewed. No findings were noted in the report.
EnRad Laboratories was not audited by the NRC in 2004.
5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the States 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 3 5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 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.
5.9.2 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 2004 is documented in Table 5.0-B.
5.9.3 INTERNAL CROSSCHECK (DUKE POWER)
Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Power)
Result is documented in Table 5.0-B.
TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2004 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 "1 Pass" 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/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.41 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.73 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.00 E3 3 Pass(1)
Co-58 7.07 - 12.53 E3 9.42 E3 9.40 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.80 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.85 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.21 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.22 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.80 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 6.10 E2 3 Pass(1)
Ce-141 0.76 - 1.35 E3 1.01E+03 1.01 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.56 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 1.86 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.06 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.64 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.76 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 5.43 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.78 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.36 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.96 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.96 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.39 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.45 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.10 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.30 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.51 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.31 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.68 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.25 E4 3 Pass Section 5 - Page 4
Gamma in Water 3.5 liters, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.27 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.18 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.52 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 2.01 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.07 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.95 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.47 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.83 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.24 E4 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/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.55 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.73 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.02 E3 3 Pass(1)
Co-58 7.07 - 12.53 E3 9.42 E3 9.37 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.85 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.86 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.30 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.07 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.77 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.81 E2 3 Pass(1)
Ce-141 0.76 - 1.35 E3 1.01E+03 1.00 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.52 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 2.00 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.06 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.23 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.73 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 5.04 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.15 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.39 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.89 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.94 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.39 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.56 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 7.93 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.31 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.43 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.25 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.67 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.19 E4 3 Pass Section 5 - Page 5
Gamma in Water 1.0 liter, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.25 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.07 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.54 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.97 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.06 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.72 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.43 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.77 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 E4 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/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.58 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.77 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.01 E3 3 Pass(1)
Co-58 7.07 - 12.53 E3 9.42 E3 9.35 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.83 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.89 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.45 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 4.87 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.78 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.89 E2 3 Pass(1)
Ce-141 0.76 - 1.35 E3 1.01E+03 1.05 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.53 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 1.91 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.08 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.42 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.76 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 4.83 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.36 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.51 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.92 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.95 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.38 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.63 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.08 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.32 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.48 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.25 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.66 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.32 E4 3 Pass Section 5 - Page 6
Gamma in Water 0.5 liter, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.22 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.09 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.53 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.98 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.01 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.55 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.42 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.79 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 E4 3 Pass Gamma in Water 0.25 liter Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.52 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.84 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.02 E3 3 Pass(1)
Co-58 7.07 - 12.53 E3 9.42 E3 9.54 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.97 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 7.04 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.54 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.00 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.87 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.85 E2 3 Pass(1)
Ce-141 0.76 - 1.35 E3 1.01E+03 1.05 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.45 E3 3 Pass Co-57 1.34 - 2.81 E2 1.94 E2 1.73 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.07 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.15 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.67 E3 3 Pass Cd-109 3.58 - 7.30 E3 5.11 E3 4.85 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.40 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.40 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.72 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 5.03 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.40 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.74 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.18 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.33 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.55 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.41 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.71 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.39 E4 3 Pass Section 5 - Page 7
Gamma in Water 0.25 liter, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.25 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.18 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.55 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.97 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.05 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.88 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.45 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.83 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 E4 3 Pass Gamma in Filter Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/15/2004 1066324 Cr-51 0.97 - 1.94 E2 1.37 E2 1.52 E2 3 Pass Co-57 2.55 - 7.09 E0 4.25 E0 5.32 E0 3 Pass Co-60 1.66 - 3.20 E1 2.30 E1 2.32 E1 3 Pass Sr-85 1.82 - 3.22 E1 2.42 E1 2.54 E1 3 Pass Y-88 3.07 - 5.45 E1 4.10 E1 4.23 E1 3 Pass Cd-109 0.68 - 1.78 E2 1.10 E2 1.32 E2 3 Pass Sn-113 1.40 - 2.85 E1 1.99 E1 1.89 E1 3 Pass Te-123m 4.08 - 7.23 E0 5.44 E0 5.72 E0 3 Pass Cs-137 1.23 - 2.52 E1 1.76 E1 1.72 E1 3 Pass 12/9/2004 E4348-37 Cr-51 1.82 - 3.23 E2 2.43 E2 2.38 E2 3 Pass Mn-54 6.53 - 11.57 E1 8.70 E1 9.11 E1 3 Pass Co-57 0.00 - 0.00 E0 0.00E+00 4.06 E0 3 Pass(2)
Co-58 7.05 - 12.50 E1 9.40 E1 9.11 E1 3 Pass Fe-59 5.85 - 10.37 E1 7.80 E1 8.25 E1 3 Pass Co-60 0.84 - 1.49 E2 1.12 E2 1.09 E2 3 Pass Zn-65 0.95 - 1.68 E2 1.26 E2 1.23 E2 3 Pass Cs-134 0.82 - 1.45 E2 1.09 E2 0.98 E2 3 Pass Cs-137 6.08 - 10.77 E1 8.10 E1 7.80 E1 3 Pass Ce-141 0.77 - 1.37 E2 1.03 E2 1.00 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 1/2/2004 Q041LIW1 I-131 6.00 - 10.64 E2 8.00 E2 7.94 E2 3 Pass 1/2/2004 Q041LIW2 I-131 6.38 - 11.32 E1 8.51 E1 9.12 E1 3 Pass 1/2/2004 Q041LIW3 I-131 N/A 0.00E+00 0.00E+00 3 Pass Section 5 - Page 8
Iodine in Water, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 7/14/2004 Q043LIW1 I-131 7.16 - 12.69 E2 9.54 E2 6.91 E2 3/3 Low(3) 7/14/2004 Q043LIW2 I-131 2.56 - 4.54 E2 3.41 E2 2.53 E2 2/3 Low(4) 7/14/2004 Q043LIW3 I-131 1.61 - 10.04 E0 4.02 E0 2.61 E0 3 Pass 12/2/2004 Q044LIW1 I-131 2.36 - 4.18 E1 3.15 E1 3.02 E1 3 Pass 12/2/2004 Q044LIW2 I-131 0.92 - 1.62 E2 1.22 E2 1.15 E2 3 Pass 12/2/2004 Q044LIW3 I-131 N/A 0.00E+00 0.00E+00 3 Pass Iodine in Milk Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 6/22/2004 Q042LIM1 Co-58 0.00 - 0.00 E0 0.00E+00 3.47 E0 3/3 High(5)
I-131 N/A 0.00E+00 0.00E+00 3 Pass 6/22/2004 Q042LIM2 I-131 0.82 - 1.45 E3 1.09 E3 0.91 E3 3 Pass 6/22/2004 Q042LIM3 I-131 1.87 - 3.31 E1 2.49 E1 2.09 E1 3 Pass Iodine on Cartridge Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/15/2004 1066-32-3 I-131 4.13 - 7.33 E6 5.51 E6 4.91 E6 3 Pass 12/9/2004 E4349-37 I-131 6.64 - 11.77 E1 8.85 E1 10.63 E1 3 Pass Beta in Water Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/25/2004 E4056-37 Cs-137 2.07 - 3.67 E2 2.76 E2 2.60 E2 3 Pass 9/16/2004 E4233-37 Cs-137 1.69 - 2.99 E2 2.25 E2 2.34 E2 3 Pass Beta Smear Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status dpm dpm dpm 5/14/2004 A18024-37 Am-241 N/A Interference 4.71 E3 3 Pass Cs-137 1.01 - 1.80 E4 1.35 E4 1.35 E4 3 Pass Section 5 - Page 9
Tritium in Water Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041TWSL1 H-3 2.70 - 4.79 E4 3.60 E4 3.17 E4 3 Pass 3/17/2004 Q041TWSL2 H-3 N/A 0.00E+00 0.00E+00 3 Pass 6/28/2004 Q042TWR1 H-3 5.24 - 9.29 E2 6.99 E2 7.33 E2 3 Pass 6/28/2004 Q042TWR2 H-3 2.29 - 5.59 E2 3.58 E2 4.12 E2 3 Pass 6/28/2004 Q042TWR3 H-3 N/A 0.00E+00 0.00E+00 3 Pass 9/8/2004 Q043TWSL1 H-3 N/A 0.00E+00 0.00E+00 3 Pass 9/8/2004 Q043TWSL2 H-3 6.18 - 10.96 E4 8.24 E4 7.94 E4 3 Pass 12/3/2004 Q044TWR1 H-3 N/A 0.00E+00 0.00E+00 3 Pass 12/3/2004 Q044TWR2 H-3 4.43 - 8.07 E2 5.98 E2 5.77 E2 3 Pass 12/3/2004 Q044TWR3 H-3 1.52 - 2.70 E3 2.03 E3 2.04 E3 3 Pass Section 5 - Page 10
Section 5 - Page 11 Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q041GWSL, Reference Date 3/17/2004: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Co-57 and Ce-139 were observed in cross-checks and attributed to a contaminant 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 E4348-37, Reference Date 12/9/2004 Co-57 was observed in cross-check and attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.
(3) Iodine in Water, Sample ID Q043LIW1, Reference Date 7/14/2004 Three results for low-level I-131 [364.48 keV] analysis were reported, with all three being below acceptance limit. General Office PIP G-04-00280 was written to record investigative actions.
(4) Iodine in Water, Sample ID Q043LIW2, Reference Date 7/14/2004 Three results for low-level I-131 [364.48 keV] analysis were reported, with two of the three being below acceptance limit. General Office PIP G-04-00280 was written to record investigative actions.
(5) Iodine in Milk, Sample ID Q042LIM1, Reference Date 6/22/2004 Three results for low-level I-131 [364.48 keV] analysis were reported and were within acceptance limits. Co-58 was observed in all three analyses and was attributed to an unintended contaminant. General Office PIP G-04-00248 was written to record investigative actions.
TABLE 5.0-B 2004 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2004 2nd Quarter 2004 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 101150 90.5 98.5 8.84
<+/-15%
Pass 100380 65.5 66.6 1.68
<+/-15%
Pass 101147 90.5 96.6 6.74
<+/-15%
Pass 100215 65.5 66.1 0.92
<+/-15%
Pass 101175 90.5 95.4 5.41
<+/-15%
Pass 100240 65.5 66.9 2.14
<+/-15%
Pass 101173 90.5 96.0 6.08
<+/-15%
Pass 100045 65.5 66.9 2.14
<+/-15%
Pass 101374 90.5 95.3 5.30
<+/-15%
Pass 100040 65.5 63.0
-3.82
<+/-15%
Pass Average Bias (B) 6.48 Average Bias (B) 0.61 Standard Deviation (S) 1.44 Standard Deviation (S) 2.52 Measure Performance lBl+S 7.92
<15%
Pass Measure Performance lBl+S 3.14
<15%
Pass 3rd Quarter 2004 4th Quarter 2004 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100178 94.0 100.2 6.60
<+/-15%
Pass 101290 71.7 67.8
-5.44
<+/-15%
Pass 100700 94.0 97.8 4.04
<+/-15%
Pass 101322 71.7 69.9
-2.51
<+/-15%
Pass 100821 94.0 99.3 5.64
<+/-15%
Pass 101370 71.7 70.7
-1.39
<+/-15%
Pass 101179 94.0 101.3 7.77
<+/-15%
Pass 101373 71.7 69.5
-3.07
<+/-15%
Pass 101376 94.0 97.5 3.72
<+/-15%
Pass 101418 71.7 70.1
-2.23
<+/-15%
Pass Average Bias (B) 5.55 Average Bias (B)
-2.93 Standard Deviation (S) 1.70 Standard Deviation (S) 1.53 Measure Performance lBl+S 7.26
<15%
Pass Measure Performance lBl+S 4.46
<15%
Pass State of North Carolina, Division of Radiation Protection Spring 2004 Fall 2004 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 101213 54.0 59.9 10.93
<+/-15%
Pass 100958 46.5 51.7 11.15
<+/-15%
Pass 101145 54.0 57.4 6.30
<+/-15%
Pass 100526 46.5 49.9 7.33
<+/-15%
Pass 101370 54.0 58.9 9.07
<+/-15%
Pass 100121 46.5 52.6 13.12
<+/-15%
Pass 101322 54.0 58.7 8.70
<+/-15%
Pass 100109 46.5 49.9 7.25
<+/-15%
Pass 101290 54.0 56.7 5.00
<+/-15%
Pass 100723 46.5 48.3 3.94
<+/-15%
Pass 101339 54.0 57.8 7.04
<+/-15%
Pass 100267 46.5 51.4 10.63
<+/-15%
Pass 101265 54.0 56.7 5.00
<+/-15%
Pass 100660 46.5 50.2 8.03
<+/-15%
Pass 101418 54.0 57.8 7.04
<+/-15%
Pass 100921 46.5 50.9 9.51
<+/-15%
Pass Average Bias (B) 7.38 Average Bias (B) 8.87 Standard Deviation (S) 2.07 Standard Deviation (S) 2.85 Measure Performance lBl+S 9.45
<15%
Pass Measure Performance lBl+S 11.71
<15%
Pass Section 5 - Page 12
Internal Crosscheck (Duke Power) 1st Quarter 2004 2nd Quarter 2004 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100103 26.0 24.1
-7.31
<+/-15%
Pass 100080 19.0 19.0 0.19
<+/-15%
Pass 100794 26.0 24.6
-5.38
<+/-15%
Pass 100727 19.0 19.4 1.94
<+/-15%
Pass 100964 26.0 24.4
-6.15
<+/-15%
Pass 100964 19.0 19.1 0.44
<+/-15%
Pass 100940 26.0 25.4
-2.31
<+/-15%
Pass 101020 19.0 18.6
-1.93
<+/-15%
Pass 100747 26.0 24.6
-5.38
<+/-15%
Pass 100103 19.0 18.8
-0.99
<+/-15%
Pass 101020 26.0 24.3
-6.54
<+/-15%
Pass 100794 19.0 18.7
-1.46
<+/-15%
Pass 100080 26.0 24.5
-5.77
<+/-15%
Pass 101036 19.0 19.6 2.98
<+/-15%
Pass 100818 26.0 24.8
-4.62
<+/-15%
Pass 100176 19.0 19.7 3.62
<+/-15%
Pass 101122 26.0 24.1
-7.31
<+/-15%
Pass 100770 19.0 18.5
-2.42
<+/-15%
Pass 100727 26.0 25.5
-1.92
<+/-15%
Pass 101035 19.0 18.3
-3.44
<+/-15%
Pass Average Bias (B)
-5.27 Average Bias (B)
-0.11 Standard Deviation (S) 1.87 Standard Deviation (S) 2.37 Measure Performance lBl+S 7.14
<15%
Pass Measure Performance lBl+S 2.47
<15%
Pass 3rd Quarter 2004 4th Quarter 2004 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100813 38.0 36.7
-3.43
<+/-15%
Pass 100079 63.0 61.0
-3.16
<+/-15%
Pass 100068 38.0 40.2 5.78
<+/-15%
Pass 100106 63.0 62.5
-0.72
<+/-15%
Pass 100940 38.0 39.4 3.74
<+/-15%
Pass 100148 63.0 62.0
-1.55
<+/-15%
Pass 100953 38.0 38.4 1.18
<+/-15%
Pass 100268 63.0 60.2
-4.46
<+/-15%
Pass 100251 38.0 39.4 3.80
<+/-15%
Pass 100110 63.0 61.8
-1.96
<+/-15%
Pass 100506 38.0 39.8 4.73
<+/-15%
Pass 100830 63.0 60.8
-3.54
<+/-15%
Pass 100654 38.0 40.6 6.74
<+/-15%
Pass 100801 63.0 61.9
-1.72
<+/-15%
Pass 101017 38.0 38.4 1.11
<+/-15%
Pass 100826 63.0 62.9
-0.19
<+/-15%
Pass 100252 38.0 38.5 1.42
<+/-15%
Pass 100439 63.0 64.5 2.34
<+/-15%
Pass 100150 38.0 39.2 3.22
<+/-15%
Pass 100953 63.0 61.3
-2.75
<+/-15%
Pass Average Bias (B) 2.83 Average Bias (B)
-1.77 Standard Deviation (S) 2.91 Standard Deviation (S) 1.94 Measure Performance lBl+S 5.74
<15%
Pass Measure Performance lBl+S 3.71
<15%
Pass Section 5 - Page 13
Section 6 - Page 1
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 1969-2003 6.6 Oconee Annual Radioactive Effluent Release Report 2004 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, Canberra Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report 50-269/04-04, 50-270/04-04, 50-287/04-04 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001
Appendix A - Page 1 APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES
Appendix A - Page 2 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, and Fisheries and Aquatic Ecology.
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 procedure during 2004.
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.
Low-level iodine analyses are performed by passing a designated sample aliquot through a pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being 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.
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.
Appendix A - Page 3 III.
CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2004.
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 separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.
Location 060
=
Greenville Water Intake Rd. (2.58 mi. NNE)
Location 074
=
Keowee Key Resort (2.36 mi. NNW)
Location 077
=
Skimmer Wall (1.00 mi. SW)
Location 078
=
Recreation Site (0.58 mi. WSW)
Location 079
=
Keowee Dam (0.56 mi. NE)
Location 081
=
Clemson Operations Center (9.33 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 =
Greenville Water Intake Rd. (3.23 mi. NE)
Location 064 =
Seneca (6.67 mi. SSW)
Location 066
=
Anderson (18.9 mi SSE)
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.
Appendix A - Page 4 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 (0.85 mi. ENE)
Location 063.1
=
Lake Hartwell Hwy 183 Bridge (0.79 mi. E)
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 (10.2 mi. SSE)
Location 080
=
Martins Dairy (17.2 mi. SE)
Location 082
=
Oakway Dairy (17.8 mi. SSW)
Location 083
=
Oconee Belle Farm Dairy (7.10 mi. W)
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
=
Greenville Water Intake Rd. (2.58 mi. NNE)
Location 077
=
Skimmer Wall (1.00 mi. SW)
Location 079
=
Keowee Dam (0.56 mi. NE)
Location 081
=
Clemson Operations Center (9.33 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
=
Greenville Water Intake Rd. (2.28 mi. NE)
Location 063
=
Lake Hartwell Hwy 183 Bridge (0.80 mi. ESE)
Location 067
=
Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE)
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 (0.80 mi. ESE)
Appendix A - Page 5 Location 067
=
Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE)
Location 068
=
High Falls County Park (1.82 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 Milk-giving Animal (cow, goat, etc.) where milk is used for human consumption The census was conducted during the growing season from 6/21 to 6/22/2004. Results are shown in Table 3.9. No changes were made to the sampling procedures during 2004 as a result of the 2004 census.
V.
GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The Oconee site centerline used for GPS measurements was referenced from the Oconee Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location.
Waypoint coordinates used for ONS GPS measurements were latitude 34°-47'-38.2"N and longitude 82°-53'-55.4"W. Maps and tables were generated using North American Datum (NAD)
- 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement. GPS field measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.
Appendix B - Page 1 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 2004
Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Air Particulate (pCi/m3) 081 (9.33 mi SE)
BETA 312 1.00E-02 1.89E-2 (260/260) 074 1.92E-2 (52/52) 1.90E-2 (52/52) 0 6.41E 3.34E-2 (2.36 mi NNW) 8.39E 2.82E-2 8.97E 3.37E-2 CS-134 312 5.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 312 6.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 312 7.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Air Radioiodine (pCi/m3) 081 (9.33 mi SE)
CS-134 312 5.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 312 6.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 312 7.00E-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Drinking Water 064 (pCi/liter)
(6.67 mi SSW)
BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 39 4
1.32 (22/26) 066 1.58 (12/13) 1.25 (10/13) 0 0.70 - 2.27 (18.9 mi SSE) 0.77 - 2.27 0.78 - 1.67 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 15 2000 225 (4/10) 066 225 (4/5) 0.00 (0/5) 0 184 - 255 (18.9 mi SSE) 184 - 255 0.00 - 0.00 I-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Surface Water 062 (pCi/liter)
(0.85 mi ENE)
BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 10 2000 3858 (5/5) 063.1 3858 (5/5) 0.00 (0/5) 0 1150 - 6209 (0.79 mi E) 1150 - 6209 0.00 - 0.00 I-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Milk 080 (pCi/liter)
(17.2 mi SE)
BALA-140 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 104 18 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 104 1
0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Broadleaf Vegetation 081 (9.33 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 0.00 (0/36) 0.00 (0/12) 59.6 (1/12) 0 0.00 - 0.00 0.00 - 0.00 59.6 - 59.6 I-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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Fish 060 (pCi/kg-wet)
(2.28mi NE)
CO-58 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 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 49.8 (8/8) 063 52.9 (4/4) 0.00 (0/4) 0 36.9 - 82.8 (0.80 mi ESE) 36.9 - 82.8 0.00 - 0.00 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Shoreline 068 Sediment (1.82 mi W)
(pCi/kg-dry)
MN-54 8
67.3 (3/6) 067 85.4 (2/3) 0.00 (0/2) 31.1 - 125 (4.34 SSE) 45.9 - 125 0.00 - 0.00 CS-134 8
150 0.00 (0/6) 0.00 (0/3) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 8
180 78.4 (3/6) 063 95.6 (2/3) 0.00 (0/2) 0 31.9 - 159 (0.80 mi ESE) 31.9 - 159 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 @ 4/19/2005 8:13 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-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.
Unit of Measurement Analyses Performed (LLD)
Mean (Fraction)
Range Location Code Mean (Fraction)
Range Mean (Fraction)
Range Direct Radiation TLD 058 (9.39 mi WSW)
(mR/standard quarter) 081 (9.33 mi SE) 167 0.00E+00 21.1 (159/159) 036 28.7 (3/3) 27.6 (8/8) 0 12.2 - 33.3 (4.32 mi N) 25.8 - 32.1 21.3 - 35.9 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 @ 4/19/2005 8:13 AM Appendix B - Page 10
Appendix C - Page 1 APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES
Appendix C - Page 2 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 IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 060 9/13-9/20/2004 9/13-9/20/2004 PI Power to sampling equipment was interrupted during composite period.
Both samplers were operative at time of collection, but run clock indicated power interruption of about 40.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Drinking Water Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 060 1/19-2/16/2004 1/19-1/31/2004 PI Power interruption to sampling equipment occurred on 1/31/2004. Water treatment plant employees inadvertently tripped power breaker during routine cleaning. Sample composite period was estimated based on available sample in collection reservoir.
060 3/15-4/12/2004 4/12-4/12/2004 PI Power to sampling equipment was turned off, possibly by water treatment plant employee. A grab sample was collected.
066 9/27-10/25/2004 10/25-10/25/2004 OT Water supply valve turned off by water treatment plant employee. A sign was generated and placed on the water supply valve requesting contact with Duke personnel be attempted prior to shutting off the water supply valve.
Appendix C - Page 3 Surface Water Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 063.1 2/16-3/15/2004 2/16-3/15/2004 PO Sampling equipment malfunctioned during composite period due to tripped breaker. Collection barrel volume allowed for an estimate of collection time to be derived which was 2/16/2004 15:00 to about 2/27/2004 13:30. A grab sample was collected on 3/15/2004. Breaker was reset and normal sampling resumed.
063.1*
8/30-9/27/2004 9/9-9/27/2004 OT Sampler started 8/30/2004 17:00.
Sampling equipment destroyed by flood events associated with Hurricane Frances. Remnants of Hurricanes Ivan and Jeanne further disrupted the scheduled composite period.
PIP O-04 05861 written. Synopsis of events follows deviation table.
063.1 9/27-10/25/2004 9/28-10/25/2004 OT Sample deviation occurred due to flooding-related events during the previous scheduled composite period of 8/30/2004 - 9/7/2004 which damaged sampling site and equipment. Oconee PIP O-04-05861 was written. A grab sample was taken on 9/28/2004 13:00.
Sampling equipment was restored and returned to operation on 9/28/2004 13:05.
- Location 063.1 sampling chronology for collection period 8/30-9/27/2004.
Event Description 1
Sampler started 8/30/04 at 17:00 2
ISCO sampler destroyed by hydro flood gates opened due to excessive rains on 9/8/2004 PIP O-05861 written. ISCO 01042 damaged. Sample from 8/30 to 9/8/04 lost (remnants of Hurricane Frances) 3 Grabs collected 9/9/2004 14:00, 9/10/2004 9:45, 9/11/2004 11:30, 9/12/2004 10:45, 9/13/2004 9:25 4
ISCO 00282 calibrated and sampling started on 9/13/04 10:53 ISCO sampled from 9/13/04 10:53 to 9/15/04 13:12 5
ISCO removed from service 9/15/04 13:12 due to expected heavy rains from Hurricane Ivan 6
Grabs collected 9/15/2004 13:15, 9/16/2004 8:30, 9/17/2004 8:00, 9/18/2004 10:20, 9/19/2004 10:45, 9/20/2004 11:30 7
ISCO returned to service 9/20/2004 16:55 8
Sample from period 9/21/2004 to 9/26/2004 unavailable due to insufficient volume collected by sampling equipment.
9 Power to sampler cut & sampler removed due to expected flooding from remnants of Hurricane Jeanne.
10 Grab sample collected 9/27/2004 10:30 11 Sampling equipment restored to operation on 9/28/2004 13:05.
Appendix C - Page 4 C.2 UNAVAILABLE ANALYSES TLD Location Scheduled Collection Dates Reason Code Corrective Action 036 6/14-9/13/2004 VN TLD missing. 4th quarter 2004 TLD placed in field.
Appendix D - Page 1 APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2004 Radiological Environmental Monitoring Program
Appendix E - Page 1 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2004. Appendix E is located separately from this report and is permanently archived at Duke Power Companys Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.