Text

Annual Radiological Environmental Operating Report
	ML061390276
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/10/2006
From:	; Duke Energy Carolinas, Duke Power Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML061390276 (88)
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Units 1 and 2 2005

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 . . . . . . . . . . . . . . 3-9 3.5 Broadleaf Vegetation . . . . . . . . . . . 3-10 3.6 Food Products . . . . . . . . . . . . 3-11 3.7 Fish . . . . . . . . . . . . . . 3-12 3.8 Shoreline Sediment . . . . . . . . . . . 3-15 3.9 Direct Gamma Radiation . . . . . . . . . . 3-18 3.10 Land Use Census . . . . . . . . . . . 3-20 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 North Carolina Intercomparion Program . . . . 5-2 5.9 TLD Intercomparison Program . . . . . . . . . 5-2 5.9.1 Nuclear Technology Services Intercomparison Program . . . 5-2 5.9.2 State of North Carolina Intercomparison Program . . . . 5-3 5.9.3 Internal Crosscheck (Duke Power) . . . . . . . 5-3 6.0 References . . . . . . . . . . . . . 6-1 i

Appendices Appendix A: Environmental Sampling and Analysis Procedures . . . . A-1 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-4 A.4 Milk . . . . . . . . . . . . A-4 A.5 Broadleaf Vegetation . . . . . . . . . A-4 A.6 Food Products . . . . . . . . . . . A-4 A.7 Fish . . . . . . . . . . . . A-4 A.8 Shoreline Sediment . . . . . . . . . . A-5 A.9 Direct Gamma Radiation (TLD) . . . . . . . A-5 A.10 Annual Land Use Census . . . . . . . A-5 V. Global Positioning System (GPS) Analysis . . . . . . . A-6 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 Food Products . . . . . . . . . . . . B-8 Fish . . . . . . . . . . . . . . B-9 Shoreline Sediment . . . . . . . . . . . B-10 Direct Gamma Radiation (TLD) . . . . . . . . B-11 Appendix C: Sampling Deviations and Unavailable Analyses . . . . . C-1 C.1 Sampling Deviations . . . . . . . . . C-2 C.2 Unavailable Analyses . . . . . . . . . C-3 Appendix D: Analytical Deviations . . . . . . . . . . D-1 Appendix E: Radiological Environmental Monitoring Program Results . . . E-1 LIST OF FIGURES 2.1-1 Sampling Locations Map (0.5 Mile Radius) . . . . . . 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) . . . . . . 2-5 3.1 Concentration of Gross Beta in Air Particulate . . . . . . 3-3 3.2 Concentration of Tritium in Drinking Water . . . . . . 3-5 3.3 Concentration of Tritium in Surface Water . . . . . . . 3-7 3.7-1 Concentration of Cs-137 in Fish . . . . . . . . 3-13 3.7-2 Concentration of Co-60 in Fish . . . . . . . . . 3-13 3.8-1 Concentration of Cs-137 in Shoreline Sediment . . . . . . 3-15 3.8-2 Concentration of Co-60 in Shoreline Sediment . . . . . . 3-16 3.9 Direct Gamma Radiation (TLD) Results . . . . . . . 3-18 3.10 2005 Land Use Census Map . . . . . . . . . 3-21 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 ii

Environmental Samples . . . . . . . . . . 2-8 2.2-B REMP Analysis Frequency . . . . . . . . . 2-8 2.2-C Maximum Values for the Lower Limits of Detection . . . . . 2-9 3.1-A Mean Concentrations of Radionuclides in Air Particulate . . . . 3-3 3.1-B Mean Concentrations of Air Radioiodine (I-131) . . . . . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water . . . . 3-6 3.3 Mean Concentrations of Tritium in Surface Water . . . . . 3-8 3.4 Mean Concentrations of Cs-137 in Milk . . . . . . . 3-9 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation . . . . 3-10 3.6 Mean Concentrations of Cs-137 in Food Products . . . . . 3-11 3.7 Mean Concentrations of Radionuclides in Fish . . . . . . 3-14 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment . . . 3-16 3.9 Direct Gamma Radiation (TLD) Results . . . . . . . 3-19 3.10 Land Use Census Results . . . . . . . . . . 3-20 4.1-A 2005 Environmental and Effluent Dose Comparison . . . . . 4-3 4.1-B Maximum Individual Dose for 2005 based on Environmental Measurements for McGuire Nuclear Station . . . . . . 4-6 5.0-A 2005 Cross-Check Results for EnRad Laboratories . . . . . 5-4 5.0-B 2005 Environmental Dosimeter Cross-Check Results . . . . . 5-13 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 MNS McGuire Nuclear Station mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual 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 iii

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2005.

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, sampling deviations, unavailable samples, 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. Eleven-hundred seventy-two samples were analyzed comprising 1,660 test results in order to compile data for the 2005 report.

Based on the annual land use census, the current number of sampling sites for McGuire Nuclear Station is sufficient.

Concentrations observed in the environment in 2005 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and 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 7.72E-2 mrem for 2005.

It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

Vegetation Sampling Section 1 - Page 1

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station (MNS) is located geographically near the center of a highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land being used to support beef cattle and farming. The McGuire site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the north by 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Companys Cowans Ford Dam Hydroelectric Station. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site.

Lookout Shoals Hydroelectric Station is at the upper reaches of Lake Norman. Marshall Steam Station is located on the western shore of Lake Norman, approximately 16 miles upstream from the site (reference 6.3).

MNS consists of two pressurized water reactors. Each reactor unit is essentially a mirror image of the other joined by an auxiliary building housing both separate and common equipment. Each unit was designed to produce approximately 1200 gross Megawatts of electricity. Unit 1 achieved criticality August 8, 1981 and Unit 2 on May 8, 1983.

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 0.5 mile radius of MNS. Figure 2.1-2 comprises all sample locations within a ten mile radius of MNS.

2.2 SCOPE AND REQUIREMENTS OF THE REMP An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to operation of Unit 1 in 1981. 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 McGuire Nuclear Station. This program satisfies the Section 2 - Page 1

requirements of Section IV.B.2 of Appendix I to 10CFR50 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.

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 3.10.

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

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

N x

i =1 i

x =

N 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 2

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

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

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

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

2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station.

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

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

Therefore, how trends are identified will include some judgment by plant personnel.

Section 2 - Page 3

Figure 2.1-1 Section 2 - Page 4

Figure 2.1-2 Section 2 - Page 5

TABLE 2.1-A MCGUIRE 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 Air Rad. Surface Drinking Shoreline Food Fish Milk Broad Location Description* & Part. Water Water Sediment Products Leaf Veg.

101 North Mecklenburg Water Treatment Facility (3.31 mi E) M 119 Mt. Holly Municipal Water Supply ( 7.40 mi SSW ) M 120 Site Boundary ( 0.46 mi NNE ) W M(b) 121 Site Boundary ( 0.47 mi NE ) W 125 Site Boundary ( 0.38 mi SW ) W M(b) 128 Discharge Canal Bridge ( 0.45 mi NE ) M 129 Discharge Canal Entrance to Lake Norman ( 0.51 mi ENE) SA SA 130 Hwy 73 Bridge Downstream ( 0.52 mi SW ) SA 131 Cowans Ford Dam ( 0.64 mi WNW ) M 132 Charlotte Municipal Water Supply ( 11.1 mi SSE ) M 133 Cornelius ( 6.23 mi ENE ) W 134 C East Lincoln Jr.High School ( 8.77 mi WNW ) W M(b) 135 C Plant Marshall Intake Canal ( 11.9 mi N ) M 136 C Mooresville Municipal Water Supply ( 12.7 mi NNE ) M 137 C Pinnacle Access Area ( 12.0 mi N ) SA SA 139 William Cook Dairy ( 2.49 mi E ) SM 141 C Lynch Dairy-Cows ( 14.8 mi WNW ) SM 188 5 mile radius Gardens ( 2.79 mi NNE ) M (a )

192 Peninsula ( 2.84 mi NNE ) W 193 Site Boundary ( 0.19 mi N ) M(b) 194 East Lincoln County Water Supply ( 6.73 mi NNW ) M 195 Fishing Access Road ( 0.19 mi N ) W (a) During Harvest Season (b) When Available

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 6

TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location Distance* Sector Site Location Distance* Sector HAMBRIGHT &

143 SITE BOUNDARY 0.27 miles NW 164 BEATTIES FORD ROAD 4.64 miles SSE 144 SITE BOUNDARY 0.46 miles NNE 165 ARTHER AUTEN ROAD 4.57 miles S NECK ROAD 145 SITE BOUNDARY 0.47 miles NE 166 REFUGE BOUNDARY 4.44 miles SSW LUCIA RIVERBEND HWY/

146 SITE BOUNDARY 0.42 miles ENE 167 OLD FIREHOUSE 4.87 miles SW 147 SITE BOUNDARY 0.44 miles E 168 OLD PLANK ROAD BRIDGE 4.60 miles WSW 148 SITE BOUNDARY 0.46 miles ESE 169 GLOVER LANE 4.03 miles W 149 SITE BOUNDARY 0.50 miles SE 170 LITTLE EGYPT ROAD 4.32 miles WNW 151 SITE BOUNDARY 0.37 miles S 171 TRIANGLE ACE HARDWARE 3.95 miles NW LAKESHORE SOUTH RD &

152 SITE BOUNDARY 0.44 miles SSW 172 ISLAND VIEW COURT 4.69 miles NNW KEISTLER STORE /

153 SITE BOUNDARY 0.47 miles SW 173 SI GLENWOOD ROAD 8.39 miles NNW EAST LINCOLN JR. HIGH 154 SITE BOUNDARY 0.45 miles W 174 SI SCHOOL 8.77 miles WNW 156 SITE BOUNDARY 0.44 miles WNW 175 C BOGER CITY 15.5 miles WNW BELMARROW ROAD /

189 SITE BOUNDARY 0.43 miles SSE 177 SI COULWOOD COMMUNITY 8.77 miles S FLORIDA STEEL 190 SITE BOUNDARY 0.33 miles WSW 178 SI CORPORATION 9.32 miles SE MOORESVILLE WATER 157 THE POINTE/MOORESVILLE 4.69 miles N 180 SI TREATMENT FACILITY 12.7 miles NNE OLD DAVIDSON WATER 158 BETHEL CHURCH ROAD 4.33 miles NNE 181 SI TREATMENT FACILITY 7.02 miles NE HENDERSON ROAD &

159 WEST CATAWBA AVENUE 4.73 miles NE 182 SI CORNELIUS / AIR SITE # 133 6.23 miles ENE ANCHORAGE MARINE MCGUIRE FISHING ACCESS 160 SHOWROOM 4.89 miles ENE 186 SI ROAD ON PENINSULA 0.24 miles NNW SAM FURR ROAD ENERGY EXPLORIUM /

161 & HWY 21 4.70 miles E 187 SI AIR SITE # 195 0.19 miles N PENINSULA DEVELOPMENT /

162 RANSON ROAD 4.53 miles ESE 191 SI AIR SITE # 192 2.84 miles NNE 163 MCCOY ROAD 4.94 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 7

TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk BroadLeaf (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/m3) (pCi/kg-wet)

H-3 20,000(a),(b)

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 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) If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.

(b) H-3 Reporting level not applicable to surface water TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic I-131 Beta Air Radioiodine Weekly X Air Weekly X X Direct Radiation Quarterly X Surface Monthly Composite X Water Quarterly Composite X Drinking Monthly Composite X (a) X Water Quarterly Composite X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf Vegetation Monthly(b) X Food Products Monthly(b) X (a) Low-level I-131 analysis will be performed if the dose calculated for the consumption of drinking water is > 1 mrem per year. An LLD of 1 pCi/liter will be required for this analysis.

(b) When Available Section 2 - Page 8

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

(pCi/m3) (pCi/kg-wet)

Gross Beta 4 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1(b) 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) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

(b) If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

Section 2 - Page 9

3.0 INTERPRETATION OF RESULTS Review of 2005 REMP analysis results was performed to detect and identify changes in environmental levels as a result of station operation. The radionuclides with Selected Licensee Commitments reporting levels that indicate consistent detectable activity have been historically trended from preoperation to present. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year.

The highest annual mean concentration of applicable Selected Licensee Commitments radionuclides from the indicator locations for each media type was used for trending purposes.

Trending was performed by comparing annual mean concentrations to historical results. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the radionuclides 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 2005 was 4.48% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location 101).

Only Selected Licensee Commitments radionuclides were detected in 2005.

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. All negative values were replaced with a zero for calculational and graphical purposes to properly represent environmental conditions. 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 possible that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

This section includes tables and graphs containing the highest annual mean concentrations of any effluent related radionuclide detected since the change in analysis systems in 1987. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels. Only the specific radionuclides that represent the highest dose contributors or demonstrate consistent detectable activity are shown graphically.

Data presented in Sections 3.1 through 3.9 support the conclusion that there was no significant increase in radioactivity in the environment around McGuire Nuclear Station due to station operations in 2005. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2005 land use census data, shown in Section 3.10, indicates that no program changes are required as a result of the census.

Section 3 - Page 1

3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2005, 371 particulate and radioiodine samples were analyzed, 318 at six indicator locations and 53 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

Gross beta analyses indicated 1.68E-2 pCi/m3 at the location with the highest annual mean and 1.77E-2 pCi/m3 at the control location. Detectable gamma emitting particulate activity was last observed in environmental air particulate samples in 2004 and is described in PIP G-04-00134.

No detectable I-131 activity in any environmental air radioiodine samples was found in 2005. K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was detected on one cartridge in 2003 from the control location.

Cs-137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

Figure 3.1 shows gross beta highest annual mean indicator and control location concentrations since 1985. There is no reporting level for gross beta. Table 3.1-A shows indicator and control location highest annual means for Cs-137 and gross beta.

Table 3.1-B gives indicator location highest annual means and control means since 1979 for I-131. Preoperational and ten year averages are also shown. No I-131 activity has been detected since 1989. Since no activity was detected in 2005, no reporting levels were approached.

Section 3 - Page 2

Figure 3.1 pCi/m3 Concentration of Gross Beta in Air Particulate 1.00E-01 9.00E-02 8.00E-02 7.00E-02 6.00E-02 5.00E-02 4.00E-02 3.00E-02 2.00E-02 1.00E-02 0.00E+00 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Indicator Location Control Location There is no reporting level for Gross Beta in air particulate Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m3) (pCi/m3) (pCi/m3) (pCi/m3) 1979* 4.40E-3 1.47E-3 ** **

1980* 6.70E-3 4.53E-3 ** **

1981* 6.16E-3 5.32E-3 ** **

1982* 3.82E-3 2.29E-3 ** **

1983* 2.93E-3 3.21E-3 ** **

1984 1.74E-3 8.29E-4 ** **

1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 1986 4.98E-3 3.03E-3 2.64E-2 2.52E-2 1987 1.07E-2 7.91E-3 2.54E-2 2.59E-2 1988 0.00E0 0.00E0 7.49E-2 5.51E-2 1989 0.00E0 0.00E0 2.22E-2 2.14E-2 1990 0.00E0 0.00E0 2.58E-2 2.37E-2 1991 0.00E0 0.00E0 2.16E-2 2.15E-2 1992 0.00E0 0.00E0 1.92E-2 2.02E-2 1993 0.00E0 0.00E0 1.93E-2 2.04E-2 1994 0.00E0 0.00E0 2.28E-2 2.02E-2 1995 0.00E0 0.00E0 3.02E-2 5.17E-2 1996 0.00E0 0.00E0 3.11E-2 5.49E-2 1997 0.00E0 0.00E0 2.34E-2 3.62E-2 1998 0.00E0 0.00E0 1.86E-2 2.66E-2 1999 0.00E0 0.00E0 2.06E-2 3.47E-2 2000 0.00E0 0.00E0 2.00E-2 2.77E-2 2001 0.00E0 0.00E0 1.79E-2 1.91E-2 Section 3 - Page 3

Table 3.1-A continued YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m3) (pCi/m3) (pCi/m3) (pCi/m3) 2002 0.00E0 0.00E0 1.57E-2 1.72E-2 2003 0.00E0 0.00E0 1.50E-2 1.63E-2 2004 0.00E0 0.00E0 1.67E-2 1.71E-2 Average (1995 - 2004) NOT APPLICABLE NOT APPLICABLE 2.09E-2 3.02E-2 2005 0.00E0 0.00E0 1.68E-2 1.77E-2 0.00E0 = no detectable measurements

Radioiodines and Particulates analyzed together

- Gross Beta analysis not performed Table 3.1-B Mean Concentrations of Air Radioiodine (I-131)

Year Indicator Location (pCi/m3) Control Location (pCi/m3) 1979* 3.28E-3 1.04E-3 1980* 2.01E-3 1.10E-3 1981* 4.17E-3 6.27E-4 1982* 1.42E-3 2.48E-3 1983* 1.99E-3 2.01E-4 1984 3.17E-3 0.00E0 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.00E0 0.00E0 1989 2.18E-2 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 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 2005 0.00E0 0.00E0 0.00E0 = no detectable measurements

Radioiodines and Particulates analyzed together.

Section 3 - Page 4

3.2 DRINKING WATER In 2005, 65 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Fifty-two samples were from the four indicator locations and 13 from the control location. Tritium (H-3) analyses were performed on 20 composite samples, 16 at indicator locations and four at the control location.

No detectable gamma activity was found in drinking water samples in 2005 and has not been detected since 1987. Gross beta analyses indicated 1.74 pCi/l at the location with the highest annual mean and 1.30 pCi/l at the control location. Tritium was detected in 12 of the 16 indicator composite samples taken in 2005 with the highest annual mean resulting in only 3.68% of the reporting level. The dose for consumption of water was less than one mrem per year, historically and for 2005; therefore low-level iodine analysis is not required.

Figure 3.2 shows tritium highest annual mean indicator and control location concentrations with comparisons to 10% of the reporting level. Table 3.2 gives indicator location highest annual means and control means since 1979 for tritium and gross beta. There is no reporting level for gross beta.

Drinking water Location 101 was added to the sampling program in 1999. Figure 3.2 shows an increase beginning in that year. There was an increase in drinking water tritium in 2005.

This increase correlates with effluent releases from the plant.

Figure 3.2 pCi/liter Concentration of Tritium in Drinking Water 2500 2000 1500 1000 500 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 Indicator Location Control Location 10% Reporting Level Section 3 - Page 5

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

YEAR Indicator Control Indicator Control Location Location Location Location 1979 2.40E0 2.03E0 1.65E2 1.50E2 1980 2.34E0 1.87E0 1.63E2 2.05E2 1981 2.79E0 2.41E0 1.88E2 1.78E2 1982 2.62E0 2.43E0 2.43E2 1.45E2 1983 1.80E0 1.87E0 2.65E2 1.45E2 1984 2.78E0 1.81E0 5.77E2 2.45E2 1985 1.88E0 1.90E0 5.93E2 4.00E2 1986 2.13E0 2.15E0 1.14E3 4.37E2 1987 2.30E0 2.00E0 1.35E3 7.75E2 1988 2.00E0 2.00E0 9.92E2 7.11E2 1989 2.80E0 2.70E0 5.62E2 0.00E0 1990 3.70E0 4.30E0 7.32E2 6.11E2 1991 2.40E0 2.50E0 5.22E2 0.00E0 1992 2.00E0 1.70E0 6.73E2 0.00E0 1993 2.80E0 2.40E0 0.00E0 0.00E0 1994 2.47E0 2.90E0 0.00E0 0.00E0 1995 4.20E0 3.30E0 3.58E2 0.00E0 1996 2.75E0 2.11E0 3.60E2 0.00E0 1997 2.70E0 2.24E0 2.90E2 0.00E0 1998 2.75E0 2.33E0 2.68E2 0.00E0 1999 2.48E0 2.17E0 5.49E2 0.00E0 2000 2.66E0 1.99E0 5.04E2 0.00E0 2001 2.48E0 2.19E0 6.98E2 0.00E0 2002 2.47E0 2.08E0 5.64E2 0.00E0 2003 1.81E0 1.52E0 3.51E2 0.00E0 2004 1.68E0 1.29E0 4.61E2 0.00E0 2005 1.74E0 1.30E0 7.35E2 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 6

3.3 SURFACE WATER In 2005, 39 surface water samples were analyzed for gamma emitting radionuclides, 26 at the two indicator locations and 13 at the control location. Analyses for H-3 were performed on 12 samples, eight at indicator locations and four at the control location.

No detectable gamma activity was found in surface water samples in 2005 and has not been detected since 1988. Tritium was detected in all of the eight indicator composite samples taken in 2005.

Tritium was not detected in any of the control location composite samples in 2005.

Figure 3.3 shows tritium highest annual mean indicator and control location concentrations. Table 3.3 gives indicator and control location highest annual means since 1979 for tritium.

There was an increase in surface water tritium in 2005. This increase correlates with effluent releases from the plant.

Figure 3.3 pCi/liter Concentration of Tritium in Surface Water 4500 4000 3500 3000 2500 2000 1500 1000 500 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 Indicator Location Control Location There is no reporting level for tritium in surface water Section 3 - Page 7

Table 3.3 Mean Concentrations of Tritium in Surface Water YEAR H-3 Indicator (pCi/l) H-3 Control (pCi/l) 1979 1.85E2 1.66E2 1980 2.13E2 1.93E2 1981 1.75E2 1.70E2 1982 3.30E2 1.23E2 1983 5.75E2 3.67E2 1984 4.10E2 2.65E2 1985 7.33E2 0.00E0 1986 2.33E3 6.13E2 1987 9.20E2 7.70E2 1988 9.40E2 0.00E0 1989 8.22E2 0.00E0 1990 6.77E2 0.00E0 1991 7.53E2 0.00E0 1992 8.13E2 0.00E0 1993 6.85E2 0.00E0 1994 0.00E0 0.00E0 1995 3.15E2 0.00E0 1996 8.08E2 0.00E0 1997 4.85E2 0.00E0 1998 3.40E2 0.00E0 1999 5.60E2 0.00E0 2000 6.22E2 0.00E0 2001 6.98E2 0.00E0 2002 5.65E2 0.00E0 2003 3.91E2 0.00E0 2004 5.04E2 0.00E0 2005 8.74E2 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 8

3.4 MILK In 2005, 52 milk samples were analyzed for low level I-131 and other gamma emitting radionuclides, 26 at the indicator location and 26 at the control location.

No detectable activity was found in milk samples in 2005 other than naturally-occurring K-40. Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not been detected since 1987.

Table 3.4 gives indicator location highest annual means and control means since 1979 for Cs-137. Since no activity was detected in 2005, no reporting levels were approached.

Table 3.4 Mean Concentrations of Cs-137 in Milk YEAR Cs-137 Indicator (pCi/l) Cs-137 Control (pCi/l) 1979 2.48E1 6.04E0 1980 1.72E1 4.13E0 1981 2.04E1 4.15E0 1982 1.21E1 5.20E0 1983 2.01E1 2.82E0 1984 1.48E1 2.56E0 1985 1.42E1 2.72E0 1986 3.74E0 3.45E0 1987 5.20E0 8.60E0 1988 3.40E0 2.90E0 1989 6.00E0 5.60E0 1990 5.30E0 2.60E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 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 2005 0.00E0 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 9

3.5 BROADLEAF VEGETATION In 2005, 48 broadleaf vegetation samples were analyzed, 36 at the three indicator locations and twelve at the control location.

No detectable activity was detected in any of the vegetation samples taken in 2005.

Cs-137 was last detected in 1998 in one vegetation sample. No other detectable gamma activity was found in vegetation samples in 1998 and no other radionuclides have been detected in vegetation samples since 1987.

Table 3.5 gives indicator and control location highest annual means since 1979 for Cs-137.

Table 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg) 1979 2.19E1 1.93E1 1980 2.30E1 1.92E1 1981 3.04E1 2.02E1 1982 2.46E1 1.22E1 1983 9.07E0 7.85E0 1984 1.02E1 1.05E1 1985 8.05E0 2.37E-2 1986 4.03E1 1.27E1 1987 2.20E1 1.70E1 1988 3.90E1 3.40E1 1989 9.60E1 0.00E0 1990 4.00E1 0.00E0 1991 3.30E1 0.00E0 1992 4.90E1 0.00E0 1993 1.60E1 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 2.69E1 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 2005 0.00E0 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 10

3.6 FOOD PRODUCTS In 2005, 12 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media.

No detectable activity has been detected in this media since 1987. Table 3.6 shows Cs-137 indicator highest annual means with preoperational data and ten year averages. Since no activity was detected in 2005, no reporting levels were approached.

Table 3.6 Mean Concentrations of Cs-137 in Food Products YEAR Cs-137 Indicator (pCi/kg) 1979 2.19E1 1980 2.30E1 1981 3.04E1 1982 2.46E1 1983 9.07E0 1984 8.45E0 1985 7.99E0 1986 2.15E1 1987 2.90E1 1988 0.00E0 1989 0.00E0 1990 0.00E0 1991 0.00E0 1992 0.00E0 1993 0.00E0 1994 0.00E0 1995 0.00E0 1996 0.00E0 1997 0.00E0 1998 0.00E0 1999 0.00E0 2000 0.00E0 2001 0.00E0 2002 0.00E0 2003 0.00E0 2004 0.00E0 2005 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 11

3.7 FISH In 2005, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator location and six at the control location.

Figure 3.7-1 shows Cs-137 highest annual mean indicator and control location concentrations with comparisons to 5% of the reporting level. Figure 3.7-2 shows Co-60 highest annual mean indicator and control location concentrations also with comparisons to 5% of the reporting level.

Table 3.7 gives indicator location highest annual means since 1980 for all radionuclides detected since the analysis change in 1988. No indicator samples were analyzed in 1979. Co-58 activity was not detected in 2005 in any of the six indicator samples. Cs-137 activity was not detected in 2005 in any of the six indicator samples taken. Cs-137 was not detected in any of the six control location samples. All other radionuclides not shown in the table have demonstrated no detectable activity since 1986. Since no activity was detected in 2005, no reporting levels were approached.

Section 3 - Page 12

Figure 3.7-1 pCi/kg Concentration of Cs-137 in Fish 140 120 100 80 60 40 20 0

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location Control Location 5% of Reporting Level Figure 3.7-2 pCi/kg Concentration of Co-60 in Fish 600 500 400 300 200 100 0

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location Control Location 5% of Reporting Level Section 3 - Page 13

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

Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 1980 -1.97E1 8.36E0 -2.25E1 -2.70E1 -4.13E0 1981 -2.71E0 -2.98E0 -2.65E0 -1.99E0 1.80E1 1982 -3.83E0 8.16E0 -4.34E-1 -8.22E-1 2.69E1 1983 -2.60E0 2.60E1 1.11E1 -1.32E0 6.03E1 1984 3.61E0 1.45E2 2.82E1 3.11E1 4.38E1 1985 2.53E-1 7.19E0 1.72E1 -1.56E0 1.86E1 1986 1.03E0 3.17E1 2.96E1 1.67E1 3.49E1 1987 0.00E0 2.71E2 1.25E2 2.60E1 5.10E1 1988 1.20E1 7.70E1 0.00E0 2.70E1 3.60E1 1989 9.00E1 4.05E2 2.99E2 1.10E1 3.50E1 1990 0.00E0 5.60E1 4.10E1 0.00E0 3.30E1 1991 6.20E0 1.40E1 6.50E1 5.90E0 2.60E1 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90E1 1993 0.00E0 8.20E1 1.30E1 0.00E0 1.60E1 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10E1 1995 0.00E0 0.00E0 0.00E0 0.00E0 2.70E1 1996 0.00E0 0.00E0 0.00E0 0.00E0 2.78E1 1997 0.00E0 0.00E0 0.00E0 0.00E0 1.62E1 1998 0.00E0 0.00E0 0.00E0 0.00E0 3.21E1 1999 0.00E0 3.53E1 0.00E0 0.00E0 2.10E1 2000 0.00E0 4.28E1 0.00E0 0.00E0 2.34E1 2001 0.00E0 1.32E1 0.00E0 0.00E0 3.04E1 2002 0.00E0 0.00E0 0.00E0 0.00E0 2.33E1 2003 0.00E0 0.00E0 0.00E0 0.00E0 3.05E1 2004 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 2005 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 = no detectable measurements All negative values have been replaced with zeros for calculational purposes Section 3 - Page 14

3.8 SHORELINE SEDIMENT In 2005, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.

Figure 3.8-1 shows Cs-137 highest annual mean indicator and control location concentrations since 1979. Figure 3.8-2 shows Co-60 highest annual mean indicator and control location concentrations since 1979.

Table 3.8 gives indicator location highest annual means since 1979 for all radionuclides detected since the analysis change in 1988. There is no reporting level for shoreline sediment.

Figure 3.8-1 pCi/kg Concentration of Cs-137 in Shoreline Sediment 400 350 300 250 200 150 100 50 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 Indicator Location Control Location There is no reporting level for Cs-137 in shoreline sediment Section 3 - Page 15

Figure 3.8-2 pCi/kg Concentration of Co-60 in Shoreline Sediment 300 250 200 150 100 50 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 Indicator Location Control Location There is no reporting level for Co-60 in shoreline sediment Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)

Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 1979 -1.07E1 2.25E1 -6.50E0 0.00E0 1.20E1 1980 1.06E1 -8.74E0 2.36E1 -3.53E0 1.44E1 1981 2.13E1 1.20E1 8.21E0 3.97E1 3.36E1 1982 5.38E1 1.66E1 -1.69E0 7.67E1 4.40E1 1983 4.40E0 3.43E1 2.12E1 7.65E1 8.02E1 1984 1.19E1 7.11E1 3.04E1 3.34E1 9.13E1 1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 1986 1.37E1 1.02E1 1.16E1 6.35E1 1.53E2 1987 0.00E0 1.06E2 2.10E1 4.20E1 1.65E2 1988 6.50E0 9.20E1 1.20E1 9.10E0 2.66E2 1989 2.90E1 3.80E1 2.90E1 5.30E1 6.50E1 1990 3.80E1 2.70E1 1.68E2 0.00E0 6.10E1 1991 2.80E1 5.30E1 1.31E2 0.00E0 1.03E2 1992 9.40E0 0.00E0 5.10E1 9.20E0 8.60E1 1993 0.00E0 2.20E1 8.60E1 0.00E0 9.30E1 1994 4.10E1 0.00E0 0.00E0 0.00E0 8.00E1 1995 1.70E1 0.00E0 2.30E1 0.00E0 1.38E2 1996 2.90E1 1.78E1 3.50E1 0.00E0 1.47E2 1997 0.00E0 0.00E0 1.11E2 3.10E1 1.36E2 1998 0.00E0 0.00E0 5.21E1 0.00E0 9.97E1 1999 0.00E0 2.47E1 8.49E1 0.00E0 6.51E1 2000 0.00E0 3.04E1 0.00E0 0.00E0 1.08E2 Section 3 - Page 16

Table 3.8 continued Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 2001 0.00E0 0.00E0 0.00E0 0.00E0 2.77E1 2002 2.24E1 0.00E0 0.00E0 0.00E0 1.59E2 2003 0.00E0 0.00E0 0.00E0 0.00E0 1.11E2 2004 0.00E0 0.00E0 0.00E0 0.00E0 7.17E1 2005 0.00E0 0.00E0 0.00E0 0.00E0 8.08E1 Section 3 - Page 17

3.9 DIRECT GAMMA RADIATION In 2005, 164 TLDs were analyzed, 160 at indicator locations, four at the control location. TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 109.2 milliroentgen. The annual mean exposure for the control location was 94.4 milliroentgen.

Figure 3.9 and Table 3.9 show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year. Preoperational data and ten year rolling averages are also given. 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 the control average representing only one location.

The calculated total body dose from gaseous effluents for 2005 was 9.68E-1 millirem, which is 1.46% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact on the measured TLD values.

Figure 3.9 mR/yr Direct Gamma Radiation (TLD) Results 200 180 160 140 120 100 80 60 40 20 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 Inner Ring Outer Ring Control There is no reporting level for Direct Radiation (TLD)

Section 3 - Page 18

Table 3.9 Direct Gamma Radiation (TLD) Results YEAR Inner Ring Average Outer Ring Average Control (mR/yr) (mR/yr) (mR/yr) 1979 7.91E1 8.82E1 8.32E1 1980 7.54E1* 8.29E1* 1.05E2 1981 1.01E2 9.31E1 1.05E2 1982 8.95E1 8.97E1 1.10E2 1983 1.16E2 1.14E2 1.30E2 1984 7.85E1 7.83E1 9.02E1 1985 9.54E1 9.69E1 1.27E2 1986 8.91E1 9.35E1 1.10E2 1987 7.58E1 7.71E1 1.23E2 1988 6.03E1 6.42E1 5.48E1 1989 5.37E1 5.30E1 7.55E1 1990 4.34E1 4.78E1 6.25E1 1991 5.14E1 5.59E1 6.80E1 1992 5.65E1 5.55E1 7.60E1 1993 5.61E1 5.71E1 7.20E1 1994 6.40E1 6.93E1 9.55E1 1995 8.36E1 8.25E1 1.08E2 1996 7.18E1 7.02E1 9.88E1 1997 6.22E1 6.68E1 9.45E1 1998 6.59E1 6.32E1 8.69E1 1999 6.23E1 6.05E1 8.96E1 2000 6.50E1 6.08E1 8.97E1 2001 6.51E1 6.22E1 9.33E1 2002 6.57E1 6.43E1 9.48E1 2003 6.74E1 6.45E1 9.20E1 2004 6.46E1 6.33E1 9.16E1 Average (1995 - 2004) 6.74E1 6.58E1 9.39E1 2005 6.62E1 6.34E1 9.44E1

Values are based on two quarters due to change in TLD locations.

Section 3 - Page 19

3.10 LAND USE CENSUS The land use census was conducted May 31 and June 1, 2005 as required by SLC 16.11.14.

Table 3.10 summarizes census results. A map indicating identified locations is shown in Figure 3.10.

During the 2005 census, no new or closer irrigated gardens were identified. The nearest residence is located in the East sector at 0.48 miles. No program changes were required as a result of the 2005 land use census.

Table 3.10 McGuire 2005 Land Use Census Results Sector Distance Sector Distance (Miles) (Miles)

Nearest Residence 2.54 Nearest Residence 1.45 N Nearest Garden (irrigated) 2.79 S Nearest Garden 3.12 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 1.23 Nearest Residence 2.56 NNE Nearest Garden 2.35 SSW Nearest Garden 2.94 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 1.21 Nearest Residence 1.85 NE Nearest Garden 2.18 SW Nearest Garden 1.89 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 0.57 Nearest Residence 1.01 ENE Nearest Garden (irrigated) 2.54 WSW Nearest Garden 1.16 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 0.48 Nearest Residence 1.15 E Nearest Garden 0.48 W Nearest Garden 1.15 Nearest Milk Animal 2.48 Nearest Milk Animal -

Nearest Residence 0.65 Nearest Residence 0.88 ESE Nearest Garden 1.31 WNW Nearest Garden 2.14 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 0.67 Nearest Residence 0.95 SE Nearest Garden 1.18 NW Nearest Garden 1.68 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 1.06 Nearest Residence 1.48 SSE Nearest Garden 2.18 NNW Nearest Garden (irrigated) 1.69 Nearest Milk Animal - Nearest Milk Animal -

- indicates no occurrences within the 5 mile radius Section 3 - Page 20

Figure 3.10 Section 3 - Page 21

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 2005 MNS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program dose estimates.

Doses based on 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. Where applicable, average background concentration at the corresponding control location was subtracted.

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

Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, fish, and shoreline sediment sample results are reported in Table 4.1-A. The individual critical population and pathway dose calculations are reported in Table 4.1-B.

REMP-based dose estimates are not reported for airborne radioiodine, milk, or broadleaf vegetation sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates are not reported for surface water because sampled surface water is not considered to be a potable drinking water source. Exposure estimates based upon REMP TLD results are discussed in Section 3.9.

The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2005 was 7.61E-2 mrem to the maximum exposed child liver, total body, thyroid, kidney, lung, and GI-LLI from the consumption of drinking water.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2005 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. These doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates. Summaries of RETDAS dose calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

Section 4 - Page 1

The effluent-based liquid release doses are summations of the dose contributions from 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, inhalation, milk and vegetation pathways.

4.3 COMPARISON OF DOSES The environmental and effluent dose estimates 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 pathways, drinking water and fish consumption were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2005 environmental sample results was 7.722E-2 mrem to the child total body. The maximum total organ dose of 1.80E-1 mrem for liquid effluent-based estimates was to the child liver.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 9.69E-1 mrem to the childs lung and GI-LLI.

No environmental doses resulted from the gaseous pathway in 2005 because broadleaf vegetation, milk, and airborne radioiodine and particulates indicated no activity. The gaseous effluent dose is due to tritium in 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 MNS are being maintained well within regulatory limits.

Section 4 - Page 2

TABLE 4.1-A Page 1 of 3 MCGUIRE NUCLEAR STATION 2005 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose (3)

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

Skin Environmental Teen Shoreline Sediment 130 (0.52 mi SW) 1.10E-04 Skin Effluent Teen Shoreline Sediment 0.5 mi. NNE 1.72E-03 Bone Environmental - - - 0.00E+00 Bone Effluent Child Fish 0.5 mi. NNE 8.43E-03 Liver Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 Liver Effluent Child Drinking Water 0.5 mi. NNE 1.80E-01 T. Body Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 T. Body Effluent Child Drinking Water 0.5 mi. NNE 1.72E-01 Thyroid Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 Thyroid Effluent Child Drinking Water 0.5 mi. NNE 1.70E-01 Kidney Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 Kidney Effluent Child Drinking Water 0.5 mi. NNE 1.73E-01 Lung Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 Lung Effluent Child Drinking Water 0.5 mi. NNE 1.71E-01 GI-LLI Environmental Child Drinking Water 101 (3.31 mi E) 7.72E-02 GI-LLI Effluent Child Drinking Water 0.5 mi. NNE 1.73E-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 Environmental or Critical Critical Maximum Dose (3)

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

Skin Environmental - - - 0.00E+00 Skin Effluent All Ground Plane 0.5 mi. E 2.38E-05 Bone Environmental - - - 0.00E+00 Bone Effluent All Vegetation 0.5 mi. E 2.03E-05 Liver Environmental - - - 0.00E+00 Liver Effluent Child Vegetation 0.5 mi. E 9.68E-01 T. Body Environmental - - - 0.00E+00 T. Body Effluent Child Vegetation 0.5 mi. E 9.68E-01 Thyroid Environmental - - - 0.00E+00 Thyroid Effluent Child Vegetation 0.5 mi. E 9.68E-01 Kidney Environmental - - - 0.00E+00 Kidney Effluent Child Vegetation 0.5 mi. E 9.68E-01 Lung Environmental - - - 0.00E+00 Lung Effluent Child Vegetation 0.5 mi. E 9.69E-01 GI-LLI Environmental - - - 0.00E+00 GI-LLI Effluent Child Vegetation 0.5 mi. E 9.69E-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 ground/plane, inhalation, milk and vegetation pathways.

Section 4 - Page 4

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

Beta Environmental - - - Not Sampled Beta Effluent N/A Noble Gas 0.5 mi. NNE 2.23E-02 Gamma Environmental - - - Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 4.32E-02 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dose for 2005 based on Environmental Measurements (mrem) for McGuire 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 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-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 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-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 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-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 0.00E+00 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.97E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.29E-05 TOTAL 0.00E+00 7.72E-02 7.72E-02 7.72E-02 7.72E-02 7.72E-02 7.72E-02 2.29E-05 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 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-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 0.00E+00 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 9.41E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.10E-04 TOTAL 0.00E+00 4.10E-02 4.11E-02 4.10E-02 4.10E-02 4.10E-02 4.10E-02 1.10E-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 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-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 0.00E+00 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.69E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.97E-05 TOTAL 0.00E+00 5.80E-02 5.81E-02 5.80E-02 5.80E-02 5.80E-02 5.80E-02 1.97E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

McGuire Nuclear Station Dose from Drinking Water Pathway for 2005 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-07 101 735 0.00E+00 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 Dose Commitment (mrem) = 0.00E+00 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 Section 4 - Page 7

McGuire Nuclear Station Dose from Drinking Water Pathway for 2005 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-07 101 735 0.00E+00 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 Dose Commitment (mrem) = 0.00E+00 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 Section 4 - Page 8

McGuire Nuclear Station Dose from Fish Pathway for 2005 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 = 874 pCi/l x 0.9 = 787 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 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-07 128 787 0.00E+00 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 Dose Commitment (mrem) = 0.00E+00 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 1.10E-03 Section 4 - Page 9

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2005 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.3 (lake shore - location 129)

Shore Width Factor = 0.2 (river shoreline - location 130)

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 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 41.8 1.97E-05 2.29E-05 Dose Commitment (mrem) = 1.97E-05 2.29E-05 Section 4 - Page 10

McGuire Nuclear Station Dose from Drinking Water Pathway for 2005 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-07 101 735 0.00E+00 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 Dose Commitment (mrem)= 0.00E+00 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 Section 4 - Page 11

McGuire Nuclear Station Dose from Fish Pathway for 2005 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 = 874 pCi/l x 0.9 = 787 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 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-07 128 787 0.00E+00 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 Dose Commitment (mrem) = 0.00E+00 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 Section 4 - Page 12

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2005 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.3 (lake shore - location 129)

Shore Width Factor = 0.2 (river shoreline - location 130)

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 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 41.8 9.41E-05 1.10E-04 Dose Commitment (mrem) = 9.41E-05 1.10E-04 Section 4 - Page 13

McGuire Nuclear Station Dose from Drinking Water Pathway for 2005 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-07 101 735 0.00E+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 Dose Commitment (mrem) = 0.00E+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 Section 4 - Page 14

McGuire Nuclear Station Dose from Fish Pathway for 2005 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 = 874 pCi/l x 0.9 = 787 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 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-07 128 787 0.00E+00 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 Dose Commitment (mrem) = 0.00E+00 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 1.74E-03 Section 4 - Page 15

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2005 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.3 (lake shore - location 129)

Shore Width Factor = 0.2 (river shoreline - location 130)

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 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 41.8 1.69E-05 1.97E-05 Dose Commitment (mrem) = 1.69E-05 1.97E-05 Section 4 - Page 16

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 Duke Power Companys Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

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

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

5.4.3 BATCH PROCESSING Section 5 - Page 1

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 2005. 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 2005 is documented in Table 5.0-A.

5.6 DUKE POWER AUDITS The McGuire Radiation Protection Section was not audited by the Quality Assurance Group in 2005. The program was audited in 2004.

EnRad Laboratories was not audited by the Quality Assurance Group in 2005. The laboratory was audited in 2004.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2005 (Reference 6.12). There were no findings or issues identified by the audit.

5.8 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis.

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 Section 5 - Page 2

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 2005 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.

Section 5 - Page 3

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2005 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 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.39 E5 3 Pass Mn-54 2.26 - 4.01 E4 3.02 E4 3.04 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.85 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.62 E4 3 Pass Sr-85 5.11 - 9.07 E4 6.82 E4 6.52 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 7.05 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.66 E5 3 Pass Cs-137 1.64 - 2.91 E4 2.19 E4 2.05 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.49 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 - 6.94 E3 5.22 E3 5.40 E3 3 Pass Co-57 2.14 - 3.80 E2 2.86 E2 2.98 E2 3 Pass Co-60 1.22 - 2.16 E3 1.63 E3 1.62 E3 3 Pass Sr-85 1.08 - 1.91 E3 1.43 E3 1.39 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.53 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.81 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.27 E3 3 Pass Te-123M 2.50 - 4.43 E2 3.33 E2 3.26 E2 3 Pass Cs-137 0.99 - 1.75 E3 1.32 E3 1.27 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.16 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.16 E5 3 Pass Sr-85 0.80 - 1.41 E5 1.06 E5 1.04 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.89 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.82 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.27 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.25 E4 3 Pass Ce-139 1.88 - 3.34 E4 2.51 E4 2.60 E4 3 Pass (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 0.00E+00 3 Low (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 5.41 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 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.35 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.47 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.20 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.24 E3 3 Pass Cd-109 1.38 - 2.46 E4 1.85 E4 1.77 E4 3 Pass Sn-113 2.32 - 4.11 E3 3.09 E3 3.04 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.75 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 7.77 E2 3 Pass (2)

Hg-203 N/A N/A N/A N/A 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 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.25 E5 3 Pass Mn-54 2.26 - 4.01 E4 3.02 E4 3.03 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.85 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.55 E4 3 Pass Sr-85 5.11 - 9.07 E4 6.82 E4 6.48 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 6.94 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.64 E5 3 Pass Cs-137 1.64 - 2.91 E4 2.19 E4 2.04 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.43 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 - 6.94 E3 5.22 E3 5.31 E3 3 Pass Co-57 2.14 - 3.80 E2 2.86 E2 3.09 E2 3 Pass Co-60 1.22 - 2.16 E3 1.63 E3 1.61 E3 3 Pass Sr-85 1.08 - 1.91 E3 1.43 E3 1.35 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.50 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.12 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.28 E3 3 Pass Te-123M 2.50 - 4.43 E2 3.33 E2 3.29 E2 3 Pass Cs-137 0.99 - 1.75 E3 1.32 E3 1.26 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.12 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.15 E5 3 Pass Sr-85 0.80 - 1.41 E5 1.06 E5 1.01 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.88 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.86 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.05 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.05 E4 3 Pass Ce-139 1.88 - 3.34 E4 2.51 E4 2.54 E4 3 Pass (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 0.00E+00 3 Low (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 5.32 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 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.29 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.47 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.17 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.15 E3 3 Pass Cd-109 1.38 - 2.46 E4 1.85 E4 1.84 E4 3 Pass Sn-113 2.32 - 4.11 E3 3.09 E3 3.02 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.71 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 8.04 E2 3 Pass (2)

Hg-203 N/A N/A N/A N/A 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 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.54 E5 3 Pass Mn-54 2.26 - 4.01 E4 3.02 E4 3.04 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.81 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.70 E4 3 Pass Sr-85 5.11 - 9.07 E4 6.82 E4 6.51 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 6.96 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.59 E5 3 Pass Cs-137 1.64 - 2.91 E4 2.19 E4 2.03 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.46 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 - 6.94 E3 5.22 E3 5.44 E3 3 Pass Co-57 2.14 - 3.80 E2 2.86 E2 2.89 E2 3 Pass Co-60 1.22 - 2.16 E3 1.63 E3 1.62 E3 3 Pass Sr-85 1.08 - 1.91 E3 1.43 E3 1.35 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.60 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.24 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.34 E3 3 Pass Te-123M 2.50 - 4.43 E2 3.33 E2 3.63 E2 3 Pass Cs-137 0.99 - 1.75 E3 1.32 E3 1.28 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.09 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.16 E5 3 Pass Sr-85 0.80 - 1.41 E5 1.06 E5 1.00 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.87 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.87 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.00 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.10 E4 3 Pass Ce-139 1.88 - 3.34 E4 2.51 E4 2.53 E4 3 Pass (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 0.00E+00 3 Low (1)

Hg-203 4.02 - 7.13 E4 5.36 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 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.38 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.55 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.22 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.10 E3 3 Pass Cd-109 1.38 - 2.46 E4 1.85 E4 1.75 E4 3 Pass Sn-113 2.32 - 4.11 E3 3.09 E3 2.94 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.77 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 8.03 E2 3 Pass (2)

Hg-203 N/A N/A N/A N/A 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 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.45 E5 3 Pass Mn-54 2.26 - 4.01 E4 3.02 E4 3.12 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.86 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.69 E4 3 Pass Sr-85 5.11 - 9.07 E4 6.82 E4 6.57 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 7.05 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.72 E5 3 Pass Cs-137 1.64 - 2.91 E4 2.19 E4 2.08 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.51 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 - 6.94 E3 5.22 E3 5.34 E3 3 Pass Co-57 2.14 - 3.80 E2 2.86 E2 2.95 E2 3 Pass Co-60 1.22 - 2.16 E3 1.63 E3 1.58 E3 3 Pass Sr-85 1.08 - 1.91 E3 1.43 E3 1.34 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.61 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.74 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.28 E3 3 Pass Te-123M 2.50 - 4.43 E2 3.33 E2 3.43 E2 3 Pass Cs-137 0.99 - 1.75 E3 1.32 E3 1.23 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.16 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.17 E5 3 Pass Sr-85 0.80 - 1.41 E5 1.06 E5 1.03 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.88 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 6.19 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.16 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.23 E4 3 Pass Ce-139 1.88 - 3.34 E4 2.51 E4 2.54 E4 3 Pass (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 0.00E+00 3 Low (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 5.50 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 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.92 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.53 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.25 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.26 E3 3 Pass Cd-109 1.38 - 2.46 E4 1.85 E4 1.93 E4 3 Pass Sn-113 2.32 - 4.11 E3 3.09 E3 3.06 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.87 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 8.11 E2 3 Pass (2)

Hg-203 N/A N/A N/A N/A Gamma in Water 0.05 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.14 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.18 E5 3 Pass Sr-85 0.80 - 1.41 E5 1.06 E5 1.03 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.86 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.95 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.17 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.05 E4 3 Pass Ce-139 1.88 - 3.34 E4 2.51 E4 2.59 E4 3 Pass (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 0.00E+00 3 Low (1)

Hg-203 4.02 - 7.13 E4 5.36 E4 5.23 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 7/15/2005 1120-63-1 Co-57 3.48 - 6.17 E3 4.64 E3 4.74 E3 3 Pass Co-60 1.86 - 3.30 E4 2.48 E4 2.42 E4 3 Pass Sr-85 2.21 - 3.91 E4 2.94 E4 2.82 E4 3 Pass Y-88 3.54 - 6.27 E4 4.72 E4 4.69 E4 3 Pass Cd-109 0.97 - 1.72 E5 1.30 E5 1.26 E5 3 Pass Sn-113 1.70 - 3.02 E4 2.27 E4 2.24 E4 3 Pass Cs-137 1.51 - 2.68 E4 2.01 E4 1.91 E4 3 Pass Ce-109 4.51 - 8.00 E3 6.01 E3 5.96 E3 3 Pass Hg-203 0.99 - 1.76 E4 1.32 E4 1.38 E4 3 Pass 12/8/2005 E4806-37 Cr-51 1.02 - 2.15 E2 1.48 E2 1.49 E2 3 Pass Mn-54 0.88 - 1.56 E2 1.17 E2 1.24 E2 3 Pass Co-58 4.43 - 7.85 E1 5.90 E1 5.79 E1 3 Pass Fe-59 4.73 - 8.38 E1 6.30 E1 6.92 E1 3 Pass Co-60 6.38 - 11.31 E1 8.50 E1 8.51 E1 3 Pass Zn-65 0.89 - 1.57 E2 1.18 E2 1.16 E2 3 Pass Cs-134 5.03 - 8.91 E1 6.70 E1 6.47 E1 3 Pass Cs-137 1.09 - 1.93 E2 1.45 E2 1.37 E2 3 Pass Ce-141 1.29 - 2.29 E2 1.72 E2 1.70 E2 3 Pass Section 5 - Page 8

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 3/9/2005 Q051LIW1 I-131 N/A 0.00E+00 0.00E+00 3 Pass 3/9/2005 Q051LIW2 I-131 1.99 - 3.53 E2 2.65 E2 3.20 E2 3 Pass 3/9/2005 Q051LIW3 I-131 1.66 - 2.94 E3 2.21 E3 2.31 E3 3 Pass 8/8/2005 Q053LIW1 I-131 2.87 - 5.09 E2 3.82 E2 3.74 E2 3 Pass 8/8/2005 Q053LIW2 I-131 2.83 - 5.01 E1 3.77 E1 3.36 E1 3 Pass 8/8/2005 Q053LIW3 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 5/4/2005 Q052LIM1 I-131 5.67 - 10.05 E1 7.55 E1 6.95 E1 3 Pass 5/4/2005 Q052LIM2 I-131 6.76 - 11.98 E1 9.01 E1 8.85 E1 3 Pass 5/4/2005 Q052LIM3 I-131 N/A 0.00E+00 0.00E+00 3 Pass 11/21/2005 Q054LIM1 I-131 1.13 - 2.00 E2 1.50 E2 1.50 E2 3 Pass 11/21/2005 Q054LIM2 I-131 2.76 - 4.89 E1 3.68 E1 3.43 E1 3 Pass 11/21/2005 Q054LIM3 I-131 3.94 - 9.07 E0 5.96 E0 5.18 E0 3 Pass Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 5/1/2005 1103-74-4 I-131 3.16 - 5.60 E5 4.21 E5 3.89 E5 3 Pass (3)

Cs-137 N/A N/A 3.45 E1 N/A 8/15/2005 1120-63-2 I-131 2.30 - 4.09 E5 3.07 E5 3.38 E5 3 Pass 12/8/2005 E4807-37 I-131 5.55 - 9.84 E1 7.40 E1 8.23 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 3/17/2005 E4484-37 Beta 2.01 - 3.56 E2 2.68 E2 2.35 E2 3 Pass 6/23/2005 Q052ABW1 Beta 3.79 - 6.71 E2 5.05 E2 4.88 E2 3 Pass Section 5 - Page 9

Beta 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 6/23/2005 Q052ABW2 Beta 2.02 - 3.59 E2 2.70 E2 2.56 E2 3 Pass 6/23/2005 Q052ABW4 Beta 2.08 - 3.69 E2 2.77 E2 2.58 E2 3 Pass 6/23/2005 Q052ABW5 Beta 5.06 - 8.97 E1 6.75 E1 6.19 E1 3 Pass 9/15/2005 E4710-37 Beta 0.92 - 1.64 E2 1.23 E2 1.33 E2 3 Pass Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 8/19/2005 A19486-37 Cs-137 0.96 - 1.70 E4 1.28 E4 1.21 E4 3 Pass Beta Smear Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status dpm dpm dpm 2/25/2005 A18848-37 Beta 4.71 - 8.36 E3 6.28 E3 6.44 E3 3 Pass 2/25/2005 A18850-37 Beta 0.98 - 1.74 E4 1.31 E4 1.25 E4 3 Pass 8/19/2005 A19484-37 Cs-137 0.87 - 1.55 E4 1.17 E4 1.21 E4 3 Pass 11/11/2005 A19759-37 Beta 0.96 - 1.70 E4 1.28 E4 1.18 E4 3 Pass 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 4/19/2005 Q051TWSL1 H-3 1.44 - 2.55 E5 1.92 E5 1.80 E5 3 Pass 4/19/2005 Q051TWSL2 H-3 N/A 0.00E+00 0.00E+00 3 Pass 5/12/2005 Q052TWR1 H-3 1.86 - 3.30 E3 2.48 E3 2.33 E3 3 Pass 5/12/2005 Q052TWR2 H-3 N/A 0.00E+00 0.00E+00 3 Pass 5/12/2005 Q052TWR3 H-3 2.67 - 6.74 E2 4.24 E2 3.68 E2 3 Pass Section 5 - Page 10

Tritium 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 7/20/2005 Q053TWS1 H-3 N/A 0.00E+00 0.00E+00 3 Pass 7/20/2005 Q053TWS2 H-3 4.21 - 7.46 E4 5.61 E4 5.25 E4 3 Pass 7/20/2005 Q053TWS3 H-3 1.54 - 2.73 E5 2.05 E5 1.94 E5 3 Pass 11/21/2005 Q054TWR1 H-3 1.64 - 2.90 E3 2.18 E3 2.12 E3 3 Pass 11/21/2005 Q054TWR2 H-3 2.98 - 8.02 E2 4.89 E2 3.68 E2 3 Pass 11/21/2005 Q054TWR3 H-3 N/A 0.00E+00 0.00E+00 3 Pass Section 5 - Page 11

Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q053GWS, Reference Date 8/10/2005: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli, 0.05 L bottle Failure to identify Hg-203 [279.19 keV] during initial cross-check analysis.

Gamma spectroscopy library XENVIRON updated to include Hg-203 nuclide.

Cross-check reanalyzed, yielding acceptable data. PIP G-05-00331 written to record corrective actions taken.

(2) Gamma in Water, Sample ID Q054GWR, Reference Date 11/21/2005: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Cross-check analysis yielded low Hg-203 results for all geometries tested.

Investigation indicated Hg-203 volatility (plate out) despite cross-check preservation. PIP G-06-00038 written.

(3) Iodine on Cartridge, Sample 1103-74-4, Reference Date 5/1/2005 Cs-137 observed in all cross-check analyses. There was no reference value for Cs-137 in this cross-check. Cs-137 is a known contaminant of charcoal cartridges (Reference 6.13). Iodine-131 data were acceptable.

Section 5 - Page 12

TABLE 5.0-B 2005 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2005 2nd Quarter 2005 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 100260 95.4 104.1 9.12 <+/-15% Pass 100053 76.4 78.4 2.62 <+/-15% Pass 100225 95.4 96.4 1.05 <+/-15% Pass 100056 76.4 79.1 3.53 <+/-15% Pass 100266 95.4 101.9 6.81 <+/-15% Pass 100762 76.4 71.2 -6.81 <+/-15% Pass 100147 95.4 96.3 0.94 <+/-15% Pass 100870 76.4 78.6 2.88 <+/-15% Pass 100112 95.4 103.5 8.49 <+/-15% Pass 100873 76.4 76.4 0.00 <+/-15% Pass Average Bias (B) 5.28 Average Bias (B) 0.45 Standard Deviation (S) 4.00 Standard Deviation (S) 4.27 Measure Performance lBl+S 9.29 <15% Pass Measure Performance lBl+S 4.72 <15% Pass 3rd Quarter 2005 4th Quarter 2005 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 101124 92.0 96.8 5.22 <+/-15% Pass 102037 62.5 63.3 1.28 <+/-15% Pass 101136 92.0 98.0 6.52 <+/-15% Pass 102233 62.5 65.5 4.80 <+/-15% Pass 101249 92.0 94.8 3.04 <+/-15% Pass 102234 62.5 62.7 0.32 <+/-15% Pass 101366 92.0 97.5 5.98 <+/-15% Pass 102454 62.5 63.1 0.96 <+/-15% Pass 101241 92.0 95.2 3.48 <+/-15% Pass 102060 62.5 62.6 0.16 <+/-15% Pass Average Bias (B) 4.85 Average Bias (B) 1.50 Standard Deviation (S) 1.53 Standard Deviation (S) 1.90 Measure Performance lBl+S 6.38 <15% Pass Measure Performance lBl+S 3.40 <15% Pass State of North Carolina, Division of Radiation Protection Spring 2005 Fall 2005 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 100089 60.0 63.0 5.00 <+/-15% Pass 100076 30 29.6 -1.33 <+/-15% Pass 100215 60.0 59.8 -0.33 <+/-15% Pass 101309 30 30.7 2.33 <+/-15% Pass 100268 60.0 59.0 -1.67 <+/-15% Pass 101314 30 31.0 3.33 <+/-15% Pass 100110 60.0 58.9 -1.83 <+/-15% Pass 101306 30 29.7 -1.00 <+/-15% Pass 100814 60.0 58.5 -2.50 <+/-15% Pass 101209 30 29.3 -2.33 <+/-15% Pass 100411 60.0 61.7 2.83 <+/-15% Pass 101281 30 30.5 1.67 <+/-15% Pass 100154 60.0 55.9 -6.83 <+/-15% Pass 100631 30 28.8 -4.00 <+/-15% Pass 100174 60.0 59.7 -0.50 <+/-15% Pass 101188 30 31.4 4.67 <+/-15% Pass Average Bias (B) -0.73 Average Bias (B) 0.42 Standard Deviation (S) 3.55 Standard Deviation (S) 3.02 Measure Performance lBl+S 4.28 <15% Pass Measure Performance lBl+S 3.44 <15% Pass Section 5 - Page 13

Internal Crosscheck (Duke Power) 1st Quarter 2005 2nd Quarter 2005 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 101035 50.0 46.3 -7.33 <+/-15% Pass 102394 50.0 47.3 -5.49 <+/-15% Pass 100215 50.0 48.4 -3.29 <+/-15% Pass 102390 50.0 47.8 -4.45 <+/-15% Pass 100411 50.0 48.9 -2.13 <+/-15% Pass 102490 50.0 47.0 -5.94 <+/-15% Pass 100174 50.0 48.7 -2.52 <+/-15% Pass 102507 50.0 47.2 -5.66 <+/-15% Pass 100154 50.0 46.5 -6.92 <+/-15% Pass 102508 50.0 47.2 -5.53 <+/-15% Pass 100089 50.0 52.6 5.24 <+/-15% Pass 102509 50.0 48.3 -3.39 <+/-15% Pass 100814 50.0 47.8 -4.44 <+/-15% Pass 102510 50.0 47.5 -5.09 <+/-15% Pass 100786 50.0 47.9 -4.25 <+/-15% Pass 102521 50.0 47.5 -5.09 <+/-15% Pass 100455 50.0 55.0 9.92 <+/-15% Pass 102391 50.0 47.9 -4.22 <+/-15% Pass 100354 50.0 48.9 -2.19 <+/-15% Pass 102389 50.0 48.8 -2.39 <+/-15% Pass Average Bias (B) -1.79 Average Bias (B) -4.73 Standard Deviation (S) 5.37 Standard Deviation (S) 1.13 Measure Performance lBl+S 7.16 <15% Pass Measure Performance lBl+S 5.85 <15% Pass 3rd Quarter 2005 4th Quarter 2005 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 102402 50.0 48.8 -2.34 <+/-15% Pass 100308 62.0 61.1 -1.45 <+/-15% Pass 102367 50.0 47.9 -4.14 <+/-15% Pass 100312 62.0 63.5 2.42 <+/-15% Pass 102369 50.0 48.9 -2.13 <+/-15% Pass 100313 62.0 62.0 0.01 <+/-15% Pass 102361 50.0 47.9 -4.26 <+/-15% Pass 100316 62.0 60.1 -3.01 <+/-15% Pass 102346 50.0 47.7 -4.67 <+/-15% Pass 100317 62.0 59.2 -4.59 <+/-15% Pass 102343 50.0 49.7 -0.66 <+/-15% Pass 100318 62.0 61.0 -1.60 <+/-15% Pass 102399 50.0 48.9 -2.14 <+/-15% Pass 100319 62.0 60.4 -2.57 <+/-15% Pass 102398 50.0 48.7 -2.52 <+/-15% Pass 100321 62.0 60.9 -1.75 <+/-15% Pass 102400 50.0 48.8 -2.48 <+/-15% Pass 100322 62.0 59.2 -4.56 <+/-15% Pass 102401 50.0 49.1 -1.77 <+/-15% Pass 100327 62.0 63.1 1.71 <+/-15% Pass Average Bias (B) -2.71 Average Bias (B) -1.54 Standard Deviation (S) 1.26 Standard Deviation (S) 2.37 Measure Performance lBl+S 3.97 <15% Pass Measure Performance lBl+S 3.90 <15% Pass Section 5 - Page 14

6.0 REFERENCES

6.1 McGuire Selected License Commitments 6.2 McGuire Technical Specifications 6.3 McGuire Updated Final Safety Analysis Report 6.4 Duke Power Company McGuire Offsite Dose Calculation Manual 6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2004 6.6 McGuire Annual Radioactive Effluent Release Report 2005 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 (50-369/05-02, 50-370/05-02) 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was 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.

This appendix describes the environmental sampling frequencies and analysis procedures by media type.

I. CHANGE OF SAMPLING PROCEDURES Four outer ring TLDs were relocated within the 6 to 8 km range (3.73 miles to 4.97 miles) from the site as required by SLC Table 16.11.13-1. Relocation of the TLDs is described in PIP G-04-00139 and was a result of NPA assessment GO-04-007 (NPA)(RP)(ALL).

Location 159 was moved within the NE sector from 4.98 miles to 4.73 miles.

Location 165 was moved within the S sector from 5.11 miles to 4.57 miles.

Location 166 was moved within the SSW sector from 5.25 miles to 4.44 miles.

Location 172 was moved within the NNW sector from 5.70 miles to 4.69 miles.

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.

Appendix A - Page 2

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system or Perkin-Elmer 2900TR 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 Tennelec XLB Series 5 gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2005.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of seven 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 120 = Site Boundary (0.46 mi. NNE)

Location 121 = Site Boundary (0.47 mi. NE)

Location 125 = Site Boundary (0.38 mi. SW)

Location 133 = Cornelius (6.23 mi. ENE)

Location 134 = East Lincoln Jr. High School (8.77 mi. WNW)

Location 192 = Peninsula (2.84 mi. NNE)

Location 195 = Fishing Access Road (0.19 mi. N)

A.2 DRINKING WATER Monthly composite samples were collected. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected monthly from the locations listed below.

Location 101 = North Mecklenburg Water Treatment Facility (3.31 mi E)

Location 119 = Mt. Holly Municipal Water Supply (7.40 mi. SSW)

Location 132 = Charlotte Municipal Water Supply (11.1 mi. SSE)

Location 136 = Mooresville Municipal Water Supply (12.7 mi. NNE)

Location 194 = East Lincoln County Water Supply (6.73 mi. NNW)

Appendix A - Page 3

A.3 SURFACE WATER Monthly composite samples were collected. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites sample. The composites were collected monthly from the locations listed below.

Location 128 = Discharge Canal Bridge (0.45 mi. NE)

Location 131 = Cowans Ford Dam (0.64 mi. WNW)

Location 135 = Plant Marshall Intake Canal (11.9 mi. N)

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

Location 139 = William Cook Dairy (2.49 mi. E)

Location 141 = Lynch Dairy - Cows (14.8 mi. WNW)

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

Location 120 = Site Boundary (0.46 mi. NNE)

Location 125 = Site Boundary (0.38 mi. SW)

Location 134 = East Lincoln Junior High School (8.77 mi. WNW)

Location 193 = Site Boundary (0.19 mi. N)

A.6 FOOD PRODUCTS Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the location listed below.

Location 188 = 5 mile radius Gardens (2.79 mi NNE)

A.7 FISH Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.

Location 129 = Discharge Canal Entrance to Lake Norman (0.51 mi. ENE)

Location 137 = Pinnacle Access Area (12.0 mi. N)

Appendix A - Page 4

A.8 SHORELINE SEDIMENT Semiannual samples were collected and a gamma analysis was performed on each following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 129 = Discharge Canal Entrance to Lake Norman (0.51 mi. ENE)

Location 130 = Highway 73 Bridge Downstream (0.52 mi. SW)

Location 137 = Pinnacle Access Area (12.0 mi. N)

A.9 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations.

A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.

An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March, 1991.

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.

A.10 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 nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

The Nearest Residence

The Nearest Garden greater than 50 square meters or 500 square feet

The Nearest Milk-giving Animal (cow, goat, etc.)

The census was conducted during the growing season from 5/31 to 6/1/2005. Results are shown in Table 3.10. No changes were made to the sampling procedures during 2005 as a result of the 2005 census.

In the environmental program, the air deposition parameters (D/Q) are used to determine air, broadleaf vegetation and milk sampling locations. McGuires sectors with the three highest values did not change in 2005.

Appendix A - Page 5

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The McGuire site centerline used for GPS measurements was referenced from the McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1, Site Location. Waypoint coordinates used for MNS GPS measurements were latitude 35°-25'-59"N and longitude 80°-56'-55"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 A - Page 6

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2005 Appendix B - Page 1

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No.of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Air Particulate 134 (pCi/m3) (8.77 mi WNW)

BETA 371 1.00E-02 1.63E-2 (318/318) 121 1.68E-2 (53/53) 1.77E-2 (53/53) 0 3.37E 3.09E-2 (0.47 mi NE) 5.13E 2.82E-2 4.83E 3.07E-2 CS-134 371 5.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 371 6.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 371 7.00E-02 0.00 (0/312) 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 @ 5/1/2006 10:42 AM Appendix B - Page 2

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 Type and No. of Non-Medium or Lower Location with Highest Total All Indicator Control Routine Pathway Limit of Annual Mean Number Locations Location Report Sampled Detection Name, Distance, Direction of Meas.

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

(LLD)

Measurement Performed Range Code Range Range Air Radioiodine 134 (pCi/m3) (8.77 mi WNW)

CS-134 371 5.00E-02 0.00 (0/318) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 371 6.00E-02 0.00 (0/318) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 371 7.00E-02 0.00 (0/318) 0.00 (0/53) 0.00 (0/53) 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 @ 5/1/2006 10:42 AM Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Drinking Water 136 (pCi/liter) (12.7 mi NNE)

BALA-140 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 65 4 1.56 (47/52) 132 1.74 (11/13) 1.30 (13/13) 0 0.67 - 2.68 (11.1 mi SSE) 1.14 - 2.68 0.63 - 2.16 CO-58 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 65 18 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 20 2000 546 (12/16) 101 735 (4/4) 0.00 (0/4) 0 320 - 896 (3.31 mi E) 471 - 896 0.00 - 0.00 I-131 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 65 15 0.00 (0/52) 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 @ 5/1/2006 10:43 AM Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Surface Water 135 (pCi/liter) (11.9 mi N)

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 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 12 2000 654 (8/8) 128 874 (4/4) 0.00 (0/4) 0 349 - 1120 (0.45 mi NE) 715 - 1120 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 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 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 @ 5/1/2006 10:43 AM Appendix B - Page 5

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Milk 141 (pCi/liter) (14.8 mi WNW)

BALA-140 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 52 18 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 52 1 0.00 (0/26) 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 @ 5/1/2006 10:43 AM Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Broadleaf 134 Vegetation (8.77 mi WNW)

(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) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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 @ 5/1/2006 10:42 AM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet) LOCATION CS-134 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 80 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 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 @ 5/1/2006 10:43 AM Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Fish 137 (pCi/kg-wet) (12.0 mi N)

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 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 @ 5/1/2006 10:43 AM Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

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

(LLD)

Measurement Performed Range Code Range Range Shoreline 137 Sediment (12.0 mi N)

(pCi/kg-dry)

MN-54 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 6 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6 180 80.8 (1/4) 130 80.8 (1/2) 39.0 (1/2) 0 80.8 - 80.8 (0.52 mi SW) 80.8 - 80.8 39.0 - 39.0 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 5/1/2006 10:43 AM Appendix B - Page 10

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2005 to 31-DEC-2005 Type and No. of Non-Lower Location with Highest Medium or Total All Indicator Control Routine Limit of Annual Mean Pathway Sampled Number Locations Location Report Detection Name, Distance, Direction of Meas.

Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Unit of Measurement (LLD)

Performed Range Code Range Range Direct Radiation 175 TLD (15.5 mi WNW)

(mR/standard quarter) 164 0.00E+00 17.0 (160/160) 180 27.3 (4/4) 23.6 (4/4) 0 10.1 - 30.7 (12.7 mi NNE) 25.1 - 30.7 22.2 - 25.2 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 @ 5/1/2006 10:43 AM Appendix B - Page 11

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page 1

APPENDIX C MCGUIRE 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 CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power was interrupted to air sampling equipment at fuse box for undetermined reason. Power was restored and normal 133 1/5-1/12/2005 1/5-1/11/2005 PI sampling resumed.

Power outage to sample site occurred for undetermined reason. Samples were collected and new media was placed in air sampling equipment. Power was 134 6/22-6/29/2005 6/22-6/28/2005 PO restored and normal sampling resumed.

Drinking Water Scheduled Actual Reason Location Collection Collection Code Corrective Action Dates Dates Water treatment plant personnel isolated reservoir tank (turned off water supply) during composite period. It was discovered during the 10/26/2005 collection and sampler was returned to 136* 9/28-10/26/2005 9/28-10/26/2005 OT normal operation.

During composite period, water treatment plant personnel turned off water supply valve. Sampler was returned to normal 194* 9/28-10/26/2005 9/28-10/26/2005 OT operation 10/26/2005.

Signs have been placed on samplers and valves requesting EnRad be notified of any sampling interruptions.

Appendix C - Page 2

Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Work request 23618 written to restore sample flow to sample reservoir. Pump intake was clogged, impeding sample flow. Normal sampling resumed 128 4/13-5/11/2005 4/13-5/11/2005 PS 5/11/2005.

Plant Marshall maintenance personnel interrupted power to site on 10/31/2005 for planned power line rerouting. EnRad sample crew checked on equipment and discovered there was no water flow from sample reservoir. Work request 28524 written. Water flow was restored and normal sampling resumed 11/3/2005 135 10/26-11/23/2005 10/26-11/23/2005 PI 10:30.

C.2 UNAVAILABLE ANALYSES There were no unavailable samples for 2005.

Appendix C - Page 3

APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2005 Radiological Environmental Monitoring Program Appendix D - Page 1

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2005. 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.

Appendix E - Page 1

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