Text

Annual Radiological Environmental Operating Report for 2009
	ML101440041
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/11/2010
From:	Repko R; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101440041 (89)
	v • d • e

REGIS T. REPKO PDuke Vice President EEnergy McGuire Nuclear Station Duke Energy MGQIVP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko@duke-energy.corn May 11, 2010 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report Pursuant to the requirements of Technical Specification 5.6.2, attached is the Annual Radiological Environmental Operating Report for the 2009 calendar year.

Questions regarding this report should be directed to Kay Crane, McGuire Regulatory Compliance at (980) 875-4306.

Regis T. Repko www. duke-energy. corn

U. S. Nuclear Regulatory Commission May 11, 2010 Page 2 Mr. Jon Thompson NRC Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 8-H4A Washington, D.C. 20555 Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Division of Radiation Protection State of North Carolina 3825 Barrett Drive Raleigh, N.C. 27609-7221 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Site

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TABLE OF CONTENTS 1.0 Executive Summary 1-1 0

2.0 Introduction 2-1 0 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 0 2.3 Statistical and Calculational Methodology . 2-2 2.3.1 Estimation of the Mean Value . 2-2 S 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2.3.3 Trend Identification.

2-3 2-3 S 3.0 Interpretation of Results . 3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water.

0 3.3 Surface Water .

3-5 3-7 S 3.4 Milk. 3-9 0 3.5 Broadleaf Vegetation. 3-10 3.6 Food Products . 3-11 S 3.7 Fish. 3-12 3.8 Shoreline Sediment 3-15 S 3.9 Direct Gamma Radiation 3-18 3.10 Land Use Census 3-20 S 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 0 4.2 Estimated Dose from Releases 4.3 Comparison of Doses.

4-1 4-2 0 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 0 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis . 5-1 0 5.4 Laboratory Equipment Quality Assurance 5-1 5.4.1 Daily Quality Control 0 5.4.2 Calibration Verification 5-1 5-1 5.4.3 Batch Processing 5-2 0 5.5 Duke Energy Intercomparison Program 5-2 S 5.6 5.7 ERAProficiency Testing Duke Energy Audits .

5-2 5-2 5.8 U.S. Nuclear Regulatory Commission Inspections 5-2 5.9 State of North Carolina Intercomparion Program 5-2 S 5.10 TLD Intercomparison Program . 5-3 5.10.1 Nuclear Technology Services Intercomparison Program 5-3 5.10.2 Internal Crosscheck (Duke Energy). 5-3 6.0 References 6-1 i

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Appendices Appendix A: Environmental Sampling and Analysis Procedures A-1 0

I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 0 IV. Sampling and Analysis Procedures A-3 A. 1 Airborne Particulate and Radioiodine A-3 0 A.2 Drinking Water A-3 0 A.3 Surface Water. A-4 A.4 Milk A-4 S A.5 Broadleaf Vegetation A-4 0 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 0 A.10 Annual Land Use Census A-5 V. Global Positioning System (GPS) Analysis A-6 0

Appendix B: Radiological Env. Monitoring Program - Summary of Results B-1 0 Air Particulate . B-2 Air Radioiodine. B-3 Drinking Water. B-4 Surface Water . B-5 0 Milk. B-6 Broadleaf Vegetation B-7 Food Products . B-8 0 Fish. B-9 Shoreline Sediment . B-10 0 Direct Gamma Radiation (TLD) B-11 Appendix C: Sampling Deviations and Unavailable Analyses C-1 0 C. 1 Sampling Deviations C-2 0 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations Appendix E: Radiological Environmental Monitoring Program Results D-1 E-1 0

LIST OF FIGURES 0 2.1-1 Sampling Locations Map (0.5 Mile Radius) 2-4 0 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-3 S 3.2 Concentration of Tritium in Drinking Water 3-5 0 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-i37 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 2009 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 ii

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2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-8 2.2-B REMP Analysis Frequency 2-8 0 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 0 3.1-B Mean Concentrations of Air Radioiodine (1-131) 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 0 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 S 3.7 Mean Concentrations of Radionuclides in Fish 3-14 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment 3-16 0 3.9 Direct Gamma Radiation (TLD) Results 3-19 3.10 Land Use Census Results . 3-20 0 4.1-A 2009 Environmental and Effluent Dose Comparison 4-3 0 4.1-B Maximum Individual Dose for 2009 based on Environmental Measurements for McGuire Nuclear Station 4-6 5.0-A 2009 Cross-Check Results for EnRad Laboratories 5-4 5.0-B 2009 Environmental Resource Associates QuikTM Response Program 5-9 5.0-C 2009 Environmental Dosimeter Cross-Check Results . 5-11 0 LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder) 0 BW C

BiWeekly Control 0 DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control 0 EPA Environmental Protection Agency ERA Environmental Resource Associates 0 GI-LLI GPS Gastrointestinal - Lower Large Intestine Global Positioning System LLD Lower Limit of Detection 0 M Monthly MDA Minimum Detectable Activity MNS McGuire Nuclear Station 0 mrem millirem 0 NIST NRC National Institute of Standards and Technology Nuclear Regulatory Commission 0 ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picocurie per liter 0 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 1tCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

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0 1.0 EXECUTIVE

SUMMARY

0 0This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Monitoring Program (REMP), and the 0program results for the calendar year 2009.

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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 0measurements 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.

0Sampling activities were conducted as prescribed by Selected Licensee Commitments

(SLC's). Required analyses were performed and detection capabilities were met for all collected samples as required by SLC's. Eleven-hundred twenty-eight samples were analyzed comprising 1,582 test results in order to compile data for the 2009 report. Based on the annual land use census, the current number of sampling sites for McGuire Nuclear

Station is sufficient.

0 Concentrations observed in the environment in 2009 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 0operation of the station. Measured concentrations were not higher than expected, and all

positively identified measurements were within limits as specified in SLC's.

Additionally, environmental radiological monitoring data is consistent with effluents

introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data,

excluding TLD results, was 8.86E-2 mrem for 2009. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

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2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS 0McGuire 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 0i amount of land being used for 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 Energy Corporation's 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 SAn 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 0which is necessary to evaluate the significance, if any, of the contributions to the existing Senvironmental radioactivity levels that result from station operation.

0 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, 0and analytical sensitivity requirements. Indicator and control locations were established for 5comparison 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 0

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from releases of radionuclides from McGuire Nuclear Station. This program satisfies the 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.

0 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE 0 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. "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. The following equation was used to estimate the mean (reference 6.8):

X - =

N Where:

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

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

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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 0between sample collection and counting. The "required" LLD's for each sample medium 0and selected radionuclides are given in the Selected Licensee Commitments and are listed

in Table 2.2-C.

MDA - The MDA is the net counting rate (sample after subtraction of background) that Smust be surpassed before a sample is considered to contain a scientifically measurable amount of a radioactive material exceeding background amounts. The MDA is calculated using a sample background and may be thought of as an "actual" LLD for a particular sample measurement.

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 0influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release 0from the nuclear plant will greatly affect the resulting environmental levels; therefore, a 0knowledge 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.

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Figure 2.1-1 Section 2 - Page 4

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Figure 2.1-2 Section 2 - Page 5

TABLE 2.1-A MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 0

Table 2.1-A Codes 0 W Weekly SM Semimonthly BW BiWeekly Q Quarterly 0 M

C Monthly Control SA Semiannually 0 0

SiteSescription Location D t

Air Rad.

& Part. Surface Water Drinking Water Shoreline Sediment Food Products Fish Milk Broad Leaf Veg.

101 North Mecklenburg Water Treatment Facility (3.31 mi E) M 102 C Amity Church Road (9.89 mi WNW) W M(b) 10 3P) Cottonwood Substation (4.20 mi NE) W 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 SA SA ENE) 130 Hwy 73 Bridge Downstream (0.52 mi SW) SA 131 Cowans Ford Dam (0.64 mi WNW) M 0 132 133 Charlotte Municipal Water Supply ( 11.1 mi SSE)

Cornelius ( 6.23 mi ENE ) W M

0 135 C 136 C Plant Marshall Intake Canal ( 11.9 mi N)

Mooresville Municipal Water Supply (12.7 mi NNE)

M M

0 137 C Pinnacle Access Area ( 12.0 mi N ) SA SA 0 141 C Lynch Dairy-Cows ( 14.8 mi WNW) SM 188 5 mile radius Gardens ( 2.79 mi NNE) M (a) 0 19 2(t) 193 Peninsula (2.84 mi NNE)

Site Boundary ( 0.19 mi N )

W

_ M(b) 0 0

194 195 East Lincoln County Water Supply ( 6.73 mi NNW)

Fishing Access Road ( 0.19 mi N ) W (1) Location 103 (Air Radioiodine, Air Particulate) was added as a replacement for location 192 (Air Radioiodine, M

4 Air Particulate), which was removed from the progratm. Movetnent of the air radioiodine and air particulate location is described reference 6.14. 0 0

(a) During Harvest Season 0 (b) When Available 0

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

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TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 0

0 (TLD SITES) 0 Site Location Distance* Sector Site Location Distance* Sector 0 143 SITE BOUNDARY 0.27 miles NW 164 HAMBRIGHT &

BEATTIES FORD ROAD 4.64 miles SSE 144 SITE BOUNDARY 0.46 miles NNE 165 ARTHER AUTEN ROAD 4.57 miles S 0 145 SITE BOUNDARY 0.47 miles NE 166 NECK ROAD REFUGE BOUNDARY 4.44 miles SSW 0 LUCIA RIVERBEND HWY/

146 SITE BOUNDARY 0.42 miles ENE 167 OLD FIREHOUSE 4.87 miles SW 0

147 SITE BOUNDARY 0.44 miles E 168 OLD PLANK ROAD BRIDGE 4.60 miles WSW 0 148 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 0 151 SITE BOUNDARY 0.37 miles S 171 TRIANGLE ACE HARDWARE 3.95 miles NW 0 LAKESHORE SOUTH RD &

152 SITE BOUNDARY 0.44 miles SSW 172 ISLAND VIEW COURT 4.69 miles NNW 0 KEISTLER STORE /

0 153 SITE BOUNDARY 0.47 miles SW 173 S1 GLENWOOD ROAD EAST LINCOLN JR. HIGH 8.39 miles NNW 154 SITE BOUNDARY 0.45 miles W 174 SI SCHOOL 8.77 miles WNW S 156 SITE BOUNDARY 0.44 miles WNW 175 C BOGER CITY 15.5 miles WNW 0 BELMARROW ROAD /

189 SITE BOUNDARY 0.43 miles SSE 177 SI COULWOOD COMMUNITY 8.77 miles S FLORIDA STEEL 0 190 SITE BOUNDARY 0.33 miles WSW 178 SI CORPORATION MOORESVILLE WATER 9.32 miles SE 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 &

0 159 WEST CATAWBA AVENUE 4.73 miles NE 182SI 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 0 SAM FURR ROAD ENERGY EXPLORIUM /

0 161 & HWY 21 4.70 miles E 187 SI AIR SITE # 195 PENINSULA DEVELOPMENT /

0.19 miles N 0 162 RANSON ROAD 4.53 miles ESE 191 SI AIR SITE # 192 2.84 miles NNE 0 163 MCCOY ROAD 4.94 miles SE 0 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

S TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY S CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0

Analysis Water Air Particulates Fish Milk BroadLeaf (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/m 3) (pCi/kg-wet)

H-3 20,000(a)')

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 S Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 S 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 S

S Sample Analysis Gamma Tritium Low Level Gross TLD S Medium Air Radioiodine Schedule Weekly Isotopic X

1-131 Beta S Air Weekly X X S Direct Radiation Quarterly X S Surface Monthly Composite X Water Quarterly Composite X S

Drinking Monthly Composite X (a) X S Water Shoreline Sediment Quarterly Composite Semiannually X X

S Milk Semimonthly X X S Fish Semiannually X S Broadleaf Vegetation Monthly(b) X Food Products Monthly(b) X S

S (a) Low-level 1-131 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 S Section 2 - Page 8

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TABLE 2.2-C S

0 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 0 Analysis Water Air Particulates Fish Milk BroadLeaf Sediment (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry) 0 (pCi/M 3) (pCi/kg-wet) 0 Gross Beta 4 2000 (a) 0.01 H-3 S Mn-54 15 130 0 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (b) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 0 Ba-La-140 15 15 0 (a) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

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

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3.0 INTERPRETATION OF RESULTS Review of 2009 REMP analysis results was performed to detect and identify changes in 0environmental 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 0analyses 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 0radionuclides from the indicator locations for each media type was used for trending purposes.

0Trending 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

radionuclide's SLC reporting level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level. The highest value reached during 2009 was

5.15% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location

101). Only Selected Licensee Commitments radionuclides were detected in 2009.

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 0control 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 2009. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2009 land use census data, shown in Section 3.10, indicates that no program changes are required as a result of the census.

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0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES S 0

In 2009, 363 particulate and radioiodine samples were analyzed, 311 at six indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma -

analysis.

0 Gross beta analyses indicated 1.79E-2 pCi/m 3 at the location with the highest annual mean and 1.76E-2 pCi/m 3 at the control location. The control location was relocated during 2008 (reference 6.14). Detectable gamma emitting particulate activity was last observed in environmental air particulate samples in 2004 (reference 6.15).

No detectable 1-131 activity in any environmental air radioiodine samples was found in 2009.

K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was not detected on any cartridges in 2009. 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.

0 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.

0 Table 3.1-B gives indicator location highest annual means and control means since 1979 for 1-131. Preoperational and ten year averages are also shown. No 1-131 activity has been detected since 1989. Since no activity was detected in 2009, no reporting levels were approached.

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S Figure 3.1 S pCi/m 3 Concentration of Gross Beta in Air Particulate S 1.00E-01 9.00E-02 8.00E-02 0 _ __

0 8.OOE-02 6.00E-02 5.00E-02 _

0 4.00E-02 _____ ___

0 1.OOE-02 0.OOE+00 1985 1988 1991 1994 1997 2000 2003 2006 2009

--- Indicator Location Control Location There is no reportinglevel for Gross Beta in airparticulate 0 Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate 0 YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m 3) (pCi/m 3) (pCi/mr) (pCi/m3) 0 1979* 4.40E-3 1.47E-3 ** **

0 1980*

1981

6.70E-3 6.16E-3 4.53E-3 5.32E-3 0 1982* 3.82E-3 2.29E-3 ** **

0 1983* 2.93E-3 3.21E-3 ** **

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

0 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 0 1987 1.07E-2 7.91E-3 2.54E-2 2.59E-2 0 1988 0.00E0 0.OOEO 7.49E-2 5.5 1E-2 1989 0.00E0 0.00E0 2.22E-2 2.14E-2 0 1990 O.OOEO 0.00E0 2.58E-2 2.37E-2 1991 0.OOEO 0.00E0 2.16E-2 2.15E-2 0 1992 0.OOEO 0.00E0 1.92E-2 2.02E-2 1993 0.OOEO 0.00E0 1.93E-2 2.04E-2 0 1994 0.00E0 0.OOEO 2.28E-2 2.02E-2 1995 0.OOEO 0.OOEO 3.02E-2 5.17E-2 0 1996 0.OOEO 0.OOEO 3.11 E-2 5.49E-2 1997 0.OOEO 0.OOEO 2.34E-2 3.62E-2 1998 0.OOEO 0.00E0 1.86E-2 2.66E-2 1999 0.OOEO 0.00E0 2.06E-2 3.47E-2 2000 O.OOEO 0.00E0 2.OOE-2 2.77E-2 2001 0.OOEO 0.OOEO 1.79E-2 1.91E-2 Section 3 -Page 3

0 0

0 Table 3.1-A continued 0 YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m 3) (pCi/m 3) (pCi/m 3) (pCi/M3) 0 2002 0.OOEO 0.00E0 1.57E-2 1.72E-2 2003 0.OOEO 0.OOEO 1.50E-2 1.63E-2 0 2004 0.OOEO 0.OOEO 1.67E-2 1.71E-2 0 2005 0.OOEO 0.OOEO 1.68E-2 1.77E-2 2006 0.OOEO 0.OOEO 1.79E-2 1.94E-2 0 2007 0.OOEO 0.OOEO 2.12E-2 2.18E-2 2008 0.OOEO 0.OOEO 1.92E-2 1.93E-2 0 Average (1999 -2008) NOT APPLICABLE NOT APPLICABLE 1.81E-2 2.1OE-2 0 2009 0.OOEO 0.OOEO 1.79E-2 1.76E-2 0 0.OOEO = no detectable measurements

Radioiodines and Particulates analyzed together 0

- Gross Beta analysis not performed 0

Table 3.1-B Mean Concentrations of Air Radioiodine (1-131) 0 Year Indicator Location (pCi/m 3) Control Location (pCi/m3) 0 1979* 3.28E-3 1.04E-3 1980* 2.01E-3 1.1OE-3 0 1981* 4.17E-3 6.27E-4 1982* 1.42E-3 2.48E-3 0 1983* 1.99E-3 2.01E-4 0 1984 3.17E-3 0.OOEO 1985 3.15E-3 1.04E-3 S 1986 1.27E-2 6.10E-3 0 1987 1.07E-2 6.60E-3 1988 0.OOEO 0.OOEO 0

1989 2.18E-2 0.OOEO 0 1990 0.OOEO 0.OOEO 1991 0.OOEO 0.OOEO S 1992 0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 0

1994 0.OOEO 0.OOEO 1995 0.OOEO 0.OOEO 1996 0.OOEO 0.OOEO 1997 0.OOEO 0.OOEO 0 1998 0.OOEO 0.00E0 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 0 2001 0.OOEO 0.OOEO 0 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.OOEO 0

2004 0.OOEO 0.OOEO 0 2005 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 0

2007 0.OOEO 0.OOEO 0 2008 0.OOEO 0.OOEO 2009 0.OOEO 0.OOEO 0.OOEO = no detectable measurements

Radioiodines and Particulates analyzed together.

Section 3 - Page 4

0 0

3.2 DRINKING WATER 0 In 2009, 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 0 control location. Tritium (H-3) analyses were performed on 20 composite samples, 16 at indicator locations and four at the control location.

S 0 No detectable gamma activity was found in drinking water samples in 2009 and has not been detected since 1987. Gross beta analyses indicated 1.90 pCi/l at the location with the highest 0 annual mean and 1.81 pCi/1 at the control location. Tritium was detected in all of the 16 0 indicator composite samples taken in 2009 with the highest annual mean resulting in only 5.15% of the reporting level. Tritium was detected in one of the four control location 0 samples. The dose for consumption of water was less than one mrem per year, historically and for 2009; therefore low-level iodine analysis is not required.

0 Figure 3.2 shows tritium highest annual mean indicator and control location concentrations with comparisons to 20% 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.

0 Drinking water Location 101 was added to the sampling program in 1999. Figure 3.2 shows 0 an increase beginning in that year. There was an increase in drinking water tritium in 2006 0 due to silica removal from the spent fuel pools. This resulted in additional water volume being released from the plant. Controlled tritium releases to Lake Norman have continued in 0 an effort to balance the plant inventory. In addition, an extreme drought during the second 0 half of 2007 and much of 2008 affecting the Catawba River Basin resulted in less dilution volume available in Lake Norman.

0 0 Fiwure 3.2 S pCi/liter 5000 Concentration of Tritium in Drinking Water 0 4500 -

0 4000 -

3500 3000 -

2500 2000 -

1500 1000--

500-- - __ __ E__L-0 *-----________- -0O- -

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006

-U- Indicator Location -*- Control Location - 20%Reporting Level I Section 3 - Page 5

0 0

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water 0 0

Gross Beta (pCi/I) Tritium (pCi/I) 0 YEAR Indicator Control Indicator Control Location Location Location Location 0 1979 2.40E0 2.03E0 1.65E2 1.50E2 0 1980 2.34E0 1.87E0 1.63E2 2.05E2 1981 2.79E0 2.41E0 1.88E2 1.78E2 0

1982 2.62E0 2.43E0 2.43E2 1.45E2 0 1983 1.80E0 1.87E0 2.65E2 1.45E2 0 1984 2.78E0 1.81E0 5.77E2, 2.45E2 1985 1.88E0 1.90E0 5.93E2 4.00E2 0 1986 2.13E0 2.15E0 1.14E3 4.37E2 0 1987 2.30E0 2.OOEO 1.35E3 7.75E2 1988 2.OOEO 2.00E0 9.92E2 7.111E2 0

1989 2.80E0 2.70E0 5.62E2 0.OOEO 0 1990 3.70E0 4.30E0 2.50E0 7.32E2 5.22E2 6.11E2 0.00E0 0

1991 2.40E0 1992 2.00E0 1.70E0 6.73E2 0.00E0 0 1993 2.80E0 2.40E0 0.00E0 0.00E0 0 1994 2.47E0 2.90E0 0.00E0 0.OOEO 1995 4.20E0 3.30E0 3.58E2 0.00E0 0

1996 2.75E0 2.11 E0 3.60E2 0.OOEO 0 1997 2.70E0 2.24E0 2.90E2 0.00E0 1998 2.75E0 2.33E0 2.68E2 0.OOEO 0

1999 2.48E0 2.17E0 5.49E2 0.OOEO 0 2000 2.66E0 1.99E0 5.04E2 0.OOEO 0 2001 2.48E0 2.19E0 6.98E2 0.00E0 2002 2.47E0 2.08E0 5.64E2 0.00E0 0 2003 1.81E0 1.52E0 3.51E2 O.OOEO 0 2004 1.68E0 1.29E0 4.61E2 0.00E0 2005 1.74E0 1.30E0 7.35E2 O.OOEO 0 2006 1.75E0 1.80E0 1.46E3 0.OOEO 0 2007 1.81E0 1.76E0 1.48E3 0.OOEO 2008 2.40E0 1.87E0 1.52E3 2.26E2 0

2009 1.90E0 1.81E0 1.03E3 1.86E2 0 0.OOEO = no detectable measurements 0 0

0 0

Section 3 - Page 6 0

0

0 0

3.3 SURFACE WATER 0 In 2009, 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 0 samples, eight at indicator locations and four at the control location.

0 0 No detectable gamma activity was found in surface water samples in 2009 and has 0 not been detected since 1988. Tritium S was detected in all of the eight indicator composite samples taken in 2009.

0 Tritium was detected in one of the 0 control location composite samples in 2009.

0 Figure 3.3 shows tritium highest annual 0 mean indicator and control location concentrations. Table 3.3 gives indicator and control location highest annual means since 1979 for tritium.

0 0 There was an increase in surface water tritium in 2006 due to silica removal from the spent fuel pools. This resulted in additional water 0 volume being released from the plant. Controlled tritium releases to Lake Norman have continued in an effort to balance the plant inventory. In addition, an extreme drought during the 0 second half of 2007 and much of 2008 affecting the Catawba River Basin resulted in less dilution volume available in Lake Norman.

0 Figure 3.3 There is no reportinglevel for tritium in surface water 0

pCi/liter Concentration of Tritium in Surface Water 0 5000 4500 -

0 4000 --

0 3500 -

0 3000 2500 -

2000 -

1500 -

1000 -

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 I -U- Indicator Location --*- Control Location I Section 3 - Page 7

0 0

0 Table 3.3 Mean Concentrations of Tritium in Surface Water 0 0

YEAR H-3 Indicator (pCiA) H-3 Control (pCi/A) 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 O.OOEO 1986 2.33E3 6.13E2 1987 9.20E2 7.70E2 1988 9.40E2 0.OOEO 1989 8.22E2 0.OOEO 1990 6.77E2 0.OOEO 1991 7.53E2 0.OOEO 1992 8.13E2 0.OOEO 1993 6.85E2 0.OOEO 1994 O.OOEO 0.OOEO 1995 3.15E2 0.OOEO 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 3.9 1E2 0.00E0 2004 5.04E2 0.00E0 2005 8.74E2 0.00E0 0 2006 1.65E3 2.19E2 2007 1.68E3 3.42E2 0

.2008 1.67E3 3.13E2 0 2009 1. 18E3 1.41E2 0

0.00E0 no detectable measurements 0 0

0 0

0 0.OOO =no dtecabl meaureent 0

0 0

Secton 3- Pae 8 S

S

0 0

3.4 MILK

In 2009, 26 milk samples were analyzed for low level 1-131 and other gamma emitting radionuclides. One control location was sampled. No indicator dairies were identified by the 2009 land use census.

No detectable activity was found in milk samples in 2009 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.

0Table 3.4 gives indicator location highest annual means and control means since 1979 for

Cs-137. Since no activity was detected in 2009, no reporting levels were approached.

0 Table 3.4 Mean Concentrations of Cs-137 in Milk YEAR Cs-i37 Indicator (pCi/I) Cs-137 Control (pCi/I) 1979 2.48E1 6.04E0 1980 1.72E1 4.13E0 1981 2.04E 1 4.15E0 1982 1.21E 1 5.20E0 1983 2.01El 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 0 1997 0.00E0 0.00E0 0 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 t*2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 2005 0.00E0 0.00E0 2006 0.00E0 0.00E0 2007 0.00E0 0.00E0 2008 0.00E0 0.00E0 2009 0.00E0 0.00E0

00.OE0 no detectable measurements""

O ~Section 3 - Page 9

3.5 BROADLEAF VEGETATION In 2009, 48 broadleaf vegetation samples were analyzed, 36 at the three indicator locations and twelve at the control location.

The control location was relocated during 2008 (reference 6.14). There were no gamma emitting radionuclides identified in any indicator location or control location broadleaf vegetation samples during 2009.

No airborne Cs-137 has been released from the plant since 1998. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.

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

Since no activity was detected in 2009, no reporting levels were approached.

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 1.02El 1.05El 1985 8.05E0 2.37E-2 1986 4.03E1 1.27E1 1987 2.20E1 1.70El 1988 3.90E1 3.40E1 1989 9.60E1 0.OOEO 1990 4.00E1 0.OOEO 1991 3.30E1 0.OOEO 1992 4.90E1 0.00E0 1993 1.60El 0.00E0 1994 0.00E0 0.00E0 1995 0.OOEO 0.00E0 1996 0.OOEO 0.00E0 1997 0.00E0 O.O0EO 1998 0.OOEO 2.69E1 1999 0.OOEO 0.00E0 2000 0.00E0 0.OOEO 2001 0.00E0 0.00E0 2002 0.OOEO 0.00E0 2003 0.00E0 0.OOEO 2004 0.OOEO 0.00E0 2005 0.OOEO 0.00E0 2006 2.98E1 0.00E0 2007 1.34E1 0.OOEO 2008 0.OOEO 0.OOEO 2009 0.00E0 0;OOEO 0.OOEO no detectable measurements Section 3 - Page 10

0 0

0 O 3.6 FOOD PRODUCTS

In 2009, 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 Z indicator highest annual means with preoperational data. Since no activity was

detected in 2009, no reporting levels were

approached.

0 0* 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.OOEO 1989 0.OOEO 1990 0.OOEO 1991 0.00E0 1992 0.OOEO 1993 0.OOEO 1994 0.OOEO 1995 0.OOEO 1996 0.OOEO 1997 0.OOEO 1998 0.OOEO 1999 0.OOEO 2000 0.OOEO 2001 0.OOEO 2002 0.OOEO 2003 0.OOEO 2004 0.OOEO

2005 0.OOEO 2006 0.OOEO 2007 0.OOEO 2008 0.OOEO 2009 0.OOEO 0.OOEO no detectable measurements 0 Section 3-Page 11 0

0

0 0

3.7 FISH 0 0

In 2009, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator 0 location and six at the control location.

0 Figure 3.7-1 shows Cs-137 highest 0 annual mean indicator and control 0 location concentrations with 0 comparisons to 5% of the reporting level. Figure 3.7-2 shows Co-60 0 highest annual mean indicator and 0 control location concentrations also , ,7 0 with comparisons to 5% of the 0 reporting level. Table 3.7 gives indicator location highest annual 0 means since 1980 for all radionuclides 0 detected since the analysis change in 0 1988. 0 Co-58 activity was not detected in 2009 in any of the indicator or control samples. Cs-137 0 activity was detected in one of the six indicator samples taken at Location 129 with a mean 0 concentration of 17.6 pCi/kg, which is 1.76% of the reporting level. Cs-137 was detected in one 0 of the six control samples.

0 All other radionuclides not shown in the table have demonstrated no detectable activity since 0 1986. 0 0

0 0

0 Section 3 - Page 12 0 0

0

0 0

0 0 Figure 3.7-1 0

0 0

Figure 3.7-2 0

0 pCi/kg Concentration of Co-60 in Fish S 600 0 500 400-0 300 -- _ _ _ _ _ _

200 -- ----- -- - I__ ___- _ ,

0 100 - A \1 L_

0 0--0 0~~ pp askegIsa I 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 0 -AN- Indicator Location --- Control Location - 5% of Reporting Level 0

0 0

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 3.11EI 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.OOEO 2.71E2 1.25E2 2.60E1 5.10El 1988 1.20El 7.70E1 0.OOEO 2.70E1 3.60E1 1989 9.OOE1 4.05E2 2.99E2 1.1OEI 3.50E1 1990 0.OOEO 5.60E1 4.10E1 0.OOEO 3.30E 0 1991 6.20E0 1.40El 6.50E1 5.90E0 2.60E1 1992 0.00E0 0.OOEO 0.OOEO 0.OOEO 2.90E1 1993 0.OOEO 8.20E1 1.30E1 0.00E0 1.60E1 1994 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.10E1 1995 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.70E1 1996 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.78E1 1997 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.62E1 1998 0.OOEO 0.00E0 0.OOEO 0.OOEO 3.21E1 1999 0.00E0 3.53E1 0.OOEO 0.OOEO 2.10E 1 2000 0.OOEO 4.28E1 0.OOEO 0.OOEO 2.34E1 2001 0.OOEO 1.32E1 0.OOEO 0.OOEO 3.04E1 2002 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.33E1 2003 0.OOEO 0.00E0 0.OOEO 0.OOEO 3.05E1 2004 0.OOEO 0.OOEO 0.00E0 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.OOEO 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.08El 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.11E1 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.24E1 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.76E1 0.OOEO = no detectable measurements All negative values have been replaced with zeros for calculational purposes S

S S

0 S

S S

Section 3 -Page 14 5 S

0

0 0

0 3.8 SHORELINE SEDIMENT 0 In 2009, six shoreline sediment samples were analyzed, four from two indicator locations 0 and two at the control location.

0 Figure 3.8-1 shows Cs-137 highest annual mean indicator and control location S concentrations since 1979. Figure 3.8-2 0 shows Co-60 highest annual mean indicator and control location 0 concentrations since 1979.

Cs-137 activity was detected in two of the four indicator samples taken. The 0 shoreline sediment location with the highest annual mean was Location 130 0 with a mean concentration of 50.8 pCi/kg. Cs-137 was not detected in any control location samples.

0 Table 3.8 gives indicator location highest annual means since 1979 for all radionuclides 0 detected since the analysis change in 1988. There is no reporting level for shoreline sediment.

0 0 Figure 3.8-1 0 pCi/kg Concentration of Cs-137 in Shoreline Sediment 0 500 450 0 400 350 0 300 -

0 200 /-

0 150 -

100 50 _____

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009

- Indicator Location - Control Location I There is no reportinglevelfor Cs-137 in shoreline sediment Section 3 - Page 15

0 0

0 Figure 3.8-2 0 0

pCi/kg Concentration of Co-60 in Shoreline Sediment 300 250 0 0

200 0

150 100 ____

50 0 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 0

-U--Indicator Location - Control Location I 0

There is no reportinglevel for Co-60 in shorelinesediment 0

0 Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/ka 0 Mn-54 Co-58 Co-60 Cs-134 Cs-137 0

YEAR Indicator Indicator Indicator Indicator Indicator 0 1979 -1.07El 2.25E1 -6.50E0 0.00E0 1.20El 0 1980 1.06El -8.74E0 2.36E1 -3.53E0 1.44E1 1981 2.13E1 1.20E1 8.21E0 3.97E1 3.36E1 0

1982 5.38E1 1.66E1 -1.69E0 7.67E1 4.40E1 0 1983 1984 4.40E0 1.19El 3.43E1 7.11El 2.12E1 3.04E1 7.65E1 3.34E1 8.02EI 9.13E1 0

1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 0 1986 1.37E1 1.02E1 1.16El 6.35E1 1.53E2 0 1987 0.OOEO 1.06E2 2.10El 4.20E1 1.65E2 1988 6.50E0 9.20E1 1.20E1 9.1OEO 2.66E2 0 1989 2.90E1 3.80E1 2.90E1 5.30E1 6.50E1 0 1990 3.80E1 2.70E1 1.68E2 0.OOEO 6.10El 0

00 1991 2.80E1 5.30E1 1.31E2 O.OOEO 1.03E2 1992 9.40E0 0.OOEO 5.10El 9.20E0 8.60E1 1993 0.OOEO 2.20E1 8.60E1 0.OOEO 9.30E1 00 1994 4.10E1 0.OOEO 0.OOEO 0.OOEO 8.OOE1 00 1995 1.70El 0.OOEO 2.30E1 0.OOEO 1.38E2 1996 2.90E1 1.78E1 3.50E1 0.OOEO 1.47E2 00 1997 O.00E0 0.00E0 1.11 E2 3.10E1 1.36E2 0 1998 1999 0.OOEO 0.OOEO 0.OOEO 2.47E1 5.21E1 8.49E1 0.OOEO 0.OOEO 9.97E1 6.51E1 0

2000 0.OOEO 3.04E1 0.00E0 0.00E0 1.08E2 01 Section 3 - Page 16

0 0 Table 3.8 continued Mn-54 Co-58 Co-60 Cs-134 Cs-137 0 YEAR Indicator Indicator Indicator Indicator Indicator 2001 0.00E0 0.OOEO 0.00E0 0.00E0 2.77E1 0 2002 2.24E1 0.OOEO 0.OOEO 0.OOEO 1.59E2 2003 0.00E0 0.OOEO 0.00E0 0.00E0 1.11E2 0 2004 0.00E0 0.OOEO 0.00E0 0.OOEO 7.17E1 2005 0.00E0 0.00E0 0.00E0 0.00E0 8.08E1 2006 0.00E0 0.00E0 0.00E0 0.00E0 1.59E2 2007 0.OOEO 0.OOEO 0.OOEO 0.00E0 1.14E2 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.77E2 0 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.08E1 S

0 0

0 Section 3 - Page 17

0 S

3.9 DIRECT GAMMA RADIATION In 2009, 162 TLDs were analyzed, 158 at indicator i 0 locations, four at the control location. TLDs are 0 collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 108 0

milliroentgen. The annual mean exposure for the control location was 91.2 milliroentgen.

0 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 0 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 0 points with the control average representing only one location.

The calculated total body dose from gaseous effluents for 2009 was 1.98E- 1 millirem, which is 0 0.30% of the average inner ring TLD values. Therefore, it can be concluded that discharges 0 from the plant had very little impact on the measured TLD values.

Figure 3.9 0

mR/year 250 Direct Gamma Radiation (TLD) Results 0 0

200 150 _____

0 150 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 20 I -- Inner Ring Outer Ring -- Control There is no reporting levelfor DirectRadiation (TLD)

Section 3 - Page 18

0 0

Table 3.9 Direct Gamma Radiation (TLD) Results 0

YEAR Inner Ring Average Outer Ring Average Control (mR*yr) (mR/,r) (mR/yr) 1979 7.91E1 8.82E1 8.32E1 1980 7.54E1* 8.29E1* 1.05E2 1981 1.01E2 9.31El 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 1.1 0E2 1987 7.58E1 7.71E1 1.23E2 1988 6.03EI 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 8.96EI 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 2005 6.62E 1 6.34E1 9.44E 1 2006 6.75E1 6.58E1 9.17E 1 2007 6.84E1 6.60E1 9.OOE1 2008 6.69E1 6.58E1 9.14El Average (1999 -2008) 6.59E1 6.37E1 9.19El 2009 6.67E1 6.53E1 9.12E1

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

0 0

0 0 Section 3 -Page 19 0

0

3.10 LAND USE CENSUS The land use census was conducted May 18 and May 19, 2009 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 2009 census, no new residences, irrigated gardens (superior to existing gardens) or milk locations were identified. The nearest residence is located in the East sector at 0.48 miles.

No environmental program changes were required as a result of the 2009 land use census.

Table 3.10 McGuire 2009 Land Use Census Results 0

0 Sector Distance Sector Distance 0 (Miles) (Miles)

Nearest Residence 2.53 Nearest Residence 1.45 0

N Nearest Garden (irrigated) 2.79 S Nearest Garden 3.12 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 1.23 Nearest Residence 2.56 2.53 SSW Nearest Garden 3.15 0

NNE Nearest Garden (irrigated)

Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 1.21 Nearest Residence 1.85 0 1.80 SW Nearest Garden 4.00 NE Nearest Garden Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 0.57 Nearest Residence 1.01 0 ENE Nearest Garden 2.54 WSW Nearest Garden 1.33 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.48 Nearest Residence 1.15 E Nearest Garden 2.10 W Nearest Garden 1.23 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.65 Nearest Residence 0.88 0 ESE Nearest Garden 1.20 'WNW Nearest Garden 2.15 Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 0.67 Nearest Residence 0.95 0 SE Nearest Garden Nearest Milk Animal 1.18 NW Nearest Garden Nearest Milk Animal 1.68 0

Nearest Residence 1.06 Nearest Residence 1.48 0

SSE Nearest Garden 2.18 NNW Nearest Garden (irrigated) 1.69 0 Nearest Milk Animal - Nearest Milk Animal -

"-" indicates no occurrences within the 5 mile radius 0

0 0

0 Section 3 - Page 20 0

0 0

OOOOOOOO**OOOOOOOOOOO00000000000QOFigureOO3.

Figure 3.10 Attachment 3 McGuire Nuclear Station 2009 Land Use Census Map Legend Residence A Garden Public Roads Railroad County Boundary Water Approximate location of features shown N

0 0.5 1 2 Miles Projection NCSP NAD27 May 2009 I __________________________________________

Section 3 - Page 21

0 0

0

4.0 EVALUATION OF DOSE 0

4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS 0Annual doses to maximum exposed individuals were estimated based on measured

concentrations of radionuclides in 2009 MNS REMP samples. The primary purpose of 0estimating doses based on sample results is to allow comparison to effluent program dose estimates.

0Doses 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.

0Regulatory 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 0water, 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 or milk sample 0* types because no radionuclides other than naturally occurring K-40 and Be-7 were 0 detected in the samples. Dose estimates are not reported for surface water because 0sampled surface water is not considered to be a potable drinking water source although surface water tritium concentrations are used in calculating doses from fish. Exposure estimates based upon REMP TLD results are discussed in Section 3.9.

0The maximum environmental organ dose estimate for any single sample type (other

than direct radiation from gaseous effluents) collected during 2009 was 8.73E-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 0

Throughout the year, dose estimates were calculated based on actual 2008 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).

0 O Section 4 - Page 1 0

0 The effluent-based liquid release doses are summations of the dose contributions from 0 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.

0 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 0 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.

0 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 2009 environmental sample results was 8.86E-2 mrem to the child liver, total body, thyroid, kidney, lung, and GI-LLI. The maximum total organ dose of 1.76E-1 mrem for liquid effluent-based estimates was to the child liver.

In calculations based on gaseous release pathways, inhalation was the predominant dose pathway for effluent samples. The maximum organ dose for gaseous effluent estimates was 1.98E-1 mrem to the teen liver, total body, thyroid, kidney, lung, and GI-LLI. No radioactivity was detected from gaseous pathways in environmental samples; therefore, there is no calculated dose.

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 40CFRI90 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.

0 0

0 Section 4 -Page 2 0

0

TABLE 4.1-A Page 1 of 3 MCGUIRE NUCLEAR STATION 2009 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

0 LIQUID RELEASE PATHWAY Critical Critical Maximum Dose (3)

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

Skin Environmental Teen Shoreline Sediment 130 (0.52 mi SW) 1.33E-04 Skin Effluent Teen Shoreline Sediment Discharge Pt. 6.67E-04 Bone Environmental 0.OOE+00 Bone Effluent Child Fish Discharge Pt. 2.8 1E-03 Liver Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 Liver Effluent Child Drinking Water 3.31 mi E 1.76E-01 T. Body Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 T. Body Effluent Child Drinking Water 3.31 mi E 1.73E-01 6

0 Thyroid Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 0 Thyroid Effluent Child Drinking Water 3.31 mi E 1.73E-0I 0 Kidney Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 Kidney S Effluent Child Drinking Water 3.31 mi E 1.74E-01 Lung Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 0 Lung Effluent Child Drinking Water 3.31 mi E 1.73E-01 0 GI-LLI Environmental Child Drinking Water 101 (3.31 mi E) 8.86E-02 GI-LLI Effluent Child Drinking Water 3.31 mi E 1.75E-01 0

(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

0 0

0 Page 2 of 3 0 GASEOUS RELEASE PATHWAY 0 0

0 0

IODINE, PARTICULATE, and TRITIUM 0

S 0

0 0

S 0

0 0

(1) Critical Age is the highest total dose (all pathways) to an age group. 0 (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. 0 0

0 Section 4 - Page 4

0 0

0 Page 3 of 3 NOBLE GAS 0

Air Environmental or Critical Critical Maximum Dose Dose Effluent Data Age Pathway (mrad)

Beta Environmental - Not Sampled Beta Effluent N/A Noble Gas 0.5 mi. NNE 6.97E-02 0

Gamma Environmental -- Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 2.5 1E-02 0

0 0

0 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dosefor 2009 based on EnvironmentalMeasurements (mrem) for McGuire Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Drinking Water O.OOE+00 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

+/- .OOE+00 O.OOE+00 TOTAL O.OOE+00 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 O.OOE+00 Child Airborne 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Fish O.OOE+00 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.39E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.79E-05 TOTAL O.OOE+00 8.86E-02 8.86E-02 8.86E-02 8.86E-02 8.86E-02 8.86E-02 2.79E-05 Teen Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish O.OOE+00 1.59E-03 1.59E-03 1.59E;03 1.59E-03 1.59E-03 1.59E-03 O.OOE+00 Shoreline Sediment O.OOE+00 0.00E+00 1.14E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.33E-04 TOTAL 0.00E+00 4.72E-02 4.73E-02 4.72E-02 4.72E-02 4.72E-02 4.72E-02 1.33E-04 Adult Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 O.OOE+00 Milk 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish O.OOE+00 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.05E-05 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 2.39E-05 TOTAL O.OOE+00 6.67E-02 6.67E-02 6.67E-02 6.67E-02 6.67E-02 6.67E-02 2.39E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6 010 0 0 0* 0 0 0 0 40 0 0 00 00 lee 0 0 (beO

McGuireNuclear Station Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41 E-08 NO DATA 2.50E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 101 843 0.OOE+00 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 Dose Commitment (mrem) = 0.OOE+00 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 8.57E-02 Section 4 - Page 7

McGuire Nuclear Station Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (1)x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 O.OOE÷00 0.OOE--00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOEO00 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+0O 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.OOE+/-00 0.OOE+00 0.0OE+/-06 0.OOE+00 0.OOE+/-00 0.OOE+/-00 0.OOE+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 101 843 0.OOE+00 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 Dose Commitment (mrem) = 0.OOE+00 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 8.73E-02 Section 4 - Page 8

McGuire NuclearStation Dosefrom Fish Pathwayfor 2009 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 1040 pCi/I x 0.9 = 936 pCi/kg Usage (intake in one year) ý 6.9 kg High4est Annual Ne t Mean Ingestion Dose Factor Conecentration Dose (mrem)

Indicat or Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Locati.on (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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 128 936 0.OOE+00 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 Dose Commitment (mrem) = 0.OOE+00 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 1.31E-03 Section 4 - Page 9

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2009 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/mr Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m 2 ) x Shore Width Factor x Sediment Surface Mass (kg/M 2) 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.OOE+00 0.00E+00 Co-58 7.OOE-09 8.20E-09 ALL 0.00 0.00E+00 0.OOE+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 50.8 2.39E-05 2.79E-05 Dose Commitment (mrem) = 2.39E-05 2.79E-05 Section 4 - Page 10 0000000000000000000000000OOOOOQOQOOQOOOOO000o

McGuire NuclearStation Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (i) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.2 1E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Co-60 NO DATA 2.81IE-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2.51 E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.OOE+00 0.OOE+0O O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE+00 0,0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 101 843 0.OOE+00 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 Dose Commitment (mrem)ý 0.OOE+00 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 4.56E-02 Section 4 - Page 11

McGuireNuclear Station Dose from Fish Pathwayfor 2009 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 1357 pCi/I x 0.9 = 1221 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.8 1E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Cs-137 1.12E-04 1.49E-04 5. 19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 128 936 0.OOE+00 1.59E-03 1.59E-03 1.59E-03 1.59E-03 1.59E-03 1,59E-03 Dose Commitment (mrem) = 0.OOE+/-00 1.59E-03 1.59E-03 1.59E-03 1.59E-03 1.59E-03 1.59E-03 Section 4 - Page 12

McGuire NuclearStation Dosefrom Shoreline Sediment Pathwayfor 2009 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) 2 Sediment Surface Mass = 40 kg/m Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m 2 ) 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/m 2) 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.OOE+00 0.OOE+00 Co-58 7.OOE-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 50.8 1.14E-04 1.33E-04 Dose Commitment (mrem) 1.14E-04 1.33E-04 Section 4 - Page 13

McGuire NuclearStation Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Fe-59 4.34E-06 1.02E-05 3.9 1E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 101 843 0.OOE+00 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 Dose Commitment (mrem) = 0.OOE+00 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 Section 4 - Page 14 910 00 0 1* 000 0010*** s***40000QQOOOQO O0 000

0000000000000009000000000000000000000000000o McGuire NuclearStation Dose from Fish Pathwayfor 2009 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 1040 pCi/I x 0.9 = 936 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+06 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 128 936 0.OOE+00 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 Dose Commitment (mrem) = 0.OOE+00 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 2.06E-03 Section 4 - Page 15

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2009 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/mi2) 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/m 2) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.OOE+00 0.OOE+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.OOE+00 0.OOE+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.OOE+00 0.OOE+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 50.8 2.05E-05 2.39E-05 Dose Commitment (torero) = 2.05E-05 2.39E-05 Section 4 - Page 16 0 00 40 0 *00 0 4010 000 000000 0 0040 0 0 000

0 0

0 0 O 5.0 QUALITY ASSURANCE 0

5.1 SAMPLE COLLECTION 0

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 0Laboratories is located in Huntersville, North Carolina, at Duke Energy Corporation's Environmental Center.

5.3 DOSIMETRY ANALYSIS Duke Energy Corporation's

Environmental Center 5 The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

S 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE

5.4.1 DAILY QUALITY CONTROL 0

EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control 5checks ensure that instruments are in proper working order and these checks 0are used to monitor instrument performance.

0 5.4.2 CALIBRATION VERIFICATION

National Institute of Standards and Technology (NIST) standards that represent 0counting 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.

0 0

Section 5 -Pagel1 0

0

0 0

0 5.4.3 BATCH PROCESSING 0

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.

S 5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during .2009. 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. A summary of the EnRad Laboratory program results for 2009 is documented in Table 5.0-A.

5.6 ERA PROFICIENCY TESTING 0 0

EnRad Laboratories performed method proficiency testing through a program administered by Environmental Resource Associates (ERA) of Arvada, CO. ERA supplied requested method proficiency samples for analysis and nuclide concentration determination. ERA reported proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Health Drinking Water Laboratory Certification Program. A summary of these proficiency test data for 2009 is documented in Table 5.0-B.

5.7 DUKE ENERGY AUDITS 0

The McGuire Radiation Protection Section was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.16). There were some TLD laboratory procedural enhancements identified as a result of the 2008 audit.

EnRad Laboratories was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.17). There were some REMP recommendations as a result of the 2008 audit.

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS S 0

The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2009 (reference 6.12). There were no findings identified by the audit.

5.9 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM 5 0

EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison Section 5 -Page 2 0

5 0

0

0 0

S 0

0 program. EnRad Laboratories sends air, surface water, milk, crops, vegetation, sediment, and fish samples which have been collected to the State of North Carolina 0 Radiation Protection Section.

0 0 5.10 TLD INTERCOMPARISON PROGRAM 0 5.10.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM 0 Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

0 of Roswell, GA. Nuclear Technology Services irradiates environmental 0 dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary 0 of the Nuclear Technology Services Intercomparison Report is documented in 0 Table 5.0-C.

S 5.10.2 INTERNAL CROSSCHECK (DUKE ENERGY) 0 Radiation Dosimetry and Records participates in a quarterly TLD 0 intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits 0 them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-C.

0 0

0 S

0 0

Section 5 - Page 3

0 0

0 TABLE 5.0-A 0 DUKE ENERGY 0 INTERLABORATORY COMPARISON PROGRAM 0 2009 CROSS-CHECK RESULTS FOR 0 ENRAD LABORATORIES 0 Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all 0 three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one 0 analysis of the cross check was performed 0

If applicable, footnote explanations are included following this table. 0 Gamma in Water 3.5 liters 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi/I Value pCi/I Value pCi/I Status 0

3/5/20.09 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.06 E5 3 Pass 0 Mn-54 .4.68- 8.30 E4 6.24 E4 6.47 E4 3 Pass 0 Co-58 4.88- 8.65 E4 6.50 E4 6.52 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.15 E4 3 Pass 0 Co-60 5.08- 9.02 E4 6.78 E4 7.05 E4 3 Pass 0 Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass 0

Cs-134 3.38- 5.99 E4 4.50 E4 4.13 E4 3 Pass Cs-137 3.96- 7.03 E4 5.28 E4 5.05 E4 3 Pass 0

Ce-141 4.55- 8.07 E4 6.07 E4 5.99 E4 3 Pass 0 0

7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.73 E5 2 Pass 0 Co-60 1.88- 3.33 E5 2.50 E5 2.65 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.63 E5 2 Pass 0 Sn-l13 1.91 -3.38 E5 2.54 E5 2.46 E5 2 Pass Cs-137 3.28-5.81 E5 4.37 E5 4.46 E5 2 Pass 0

0 0

Gamma in Water 1. 0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 pCi/l pCi/l pCi/I 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.04 E5 3 Pass 0

Mn-54 4.68-8.30 E4 6.24 E4 6.53 E4 3 Pass 0

Co-58 4.88- 8.65 E4 6.50 E4 6.48 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.17 E4 3 Pass 0 Co-60 5.08- 9.02 E4 6.78 E4 6.96 E4 3 Pass Zn-65 5.79 - 10.26 E4 7.72 E4 7.98 E4 3 Pass 0

Cs-134 3.38-5.99 E4 4.50 E4 4.03 E4 3 Pass 0 Cs-137 3.96-7.03 E4 5.28 E4 5.03 E4 3 Pass 0 Ce-141 4.55- 8.07 E4 6.07 E4 5.94 E4 3 Pass 0 0

0 Section 5 - Page 4 0

0 Gamma in Water 1. 0 liter, continued 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/I 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 0 1.62 E5 1.64 E5 3 Pass Co-60 1.88- 3.33 E5 2.50 E5 2.59 E5 3 Pass Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 3 Pass 0 Sn-I13 1.91-3.38 E5 2.54 E5 2.40 E5 3 Pass 0 Cs-137 3.28- 5.81 E5 4.37 E5 4.28 E5 3 Pass 0

0 Gamma in Water 0.5 liter 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date 0 Range pCi/I Value pCi/I Value pCi/I Status 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.05 E5 3 Pass Mn-54 4.68- 8.30 E4 6.24 E4 6.35 E4 3 Pass 0 Co-58 4.88-8.65 E4 6.50 E4 6.27 E4 3 Pass Fe-59 4.40-7.80 E4 5.87 E4 6.10 E4 3 Pass 0 Co-60 5.08- 9.02 E4 6.78 E4 6.94 E4 3 Pass Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass 0 Cs-134 3.38-5.99 E4 4.50 E4 3.88 E4 3 Pass 0 Cs-137 3.96-7.03 E4 5.28 E4 4.90 E4 3 Pass 0 Ce-141 4.55- 8.07 E4 6.07 E4 5.80 E4 3 Pass 0

7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.61 E5 3 Pass 0 Co-60 1.88- 3.33 E5 2.50 E5 2.55 E5 3 Pass Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 3 Pass 0

Sn-I 13 1.91-3.38 E5 2.54 E5 2.36 E5 3 Pass S Cs-137 3.28- 5.81 E5 4.37 E5 4.27 E5 3 Pass 0

Gamma in Water 0.25 liter 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 pCi/I pCi/I pCi/I 0 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.08 E5 3 Pass Mn-54 4.68-8.30 E4 6.24 E4 6.51 E4 3 Pass Co-58 4.88- 8.65 E4 6.50 E4 6.43 E4 3 Pass Fe-59 4.40-7.80 E4 5.87 E4 6.15 E4 3 Pass Co-60 5.08- 9.02 E4 6.78 E4 7.13 E4 3 Pass Zn-65 5.79 - 10.26 E4 7.72 E4 7.93 E4 3 Pass Cs-134 3.38- 5.99 E4 4.50 E4 4.00 E4 3 Pass Cs-137 3.96-7.03 E4 5.28 E4 5.07 E4 3 Pass Ce-141 4.55- 8.07 E4 6.07 E4 5.97 E4 3 Pass Section 5 - Page 5

0 0

0 Gamma in Water 0.25 liter, continued 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/l pCi/l pCi/l 0 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0 Co-60 1.88-3.33 E5 2.50 E5 2.57 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0 1.91-3.38 E5 2.54 E5 2.32 E5 2 Pass Sn-113 0

Cs-137 3.28-5.81 E5 4.37 E5 4.13 E5 2 Pass 0

0 Gamma in Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0

Date Range Value Value Status 0 pCi pCi pCi 0

6/18/2009 E6701-37 Cr-51 0.29- 10.17 E2 1.73 E2 1.61 E2 2 Pass Mn-54 4.45- 7.89 El 5.93 El 5.96 El 2 Pass 0

Co-58 2.94-5.36 El 3.97 El 3.95 El 2 Pass 0

Fe-59 2.06 - 13.54 El 5.29 El 4.50 El 2 Pass 0 Co-60 1.01- 1.80 E2 1.35 E2 1.36 E2 2 Pass 0 Zn-65 5.68 - 10.07 El 7.57 El 8.01 El 2 Pass 0 Cs-134 5.38-9.54 El 7.17 El 6.50 El 2 Pass 0 Cs-137 6.23 - 11.04 El 8.30 El 7.61 El 2 Pass 0

Ce-141 0.92-1.64 E2 1.23 E2 1.30 E2 2 Pass 0

0 Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0

Date Range Value Value Status 0 pCi/I pCi/1 pCi/l 2.29 E2 3 Pass 0

7/21/2009 Q093LIW1 1-131 1.99-3.53 E2 2.65 E2 0

7/21/2009 Q093LIW2 1-131 0.87- 1.55 El 1.16 El 0.89 El 1/3 Low(1) 0 0

7/21/2009 Q093LIW3 1-131 5.09-9.03 E2 6.79 E2 5.99 E2 3 Pass 0 0

0 0

Section 5 - Page 6 0

0 0

Fndiia in;ITtIL-0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 pCi/l pCi/l pCi/I Q091LIM2 1-131 3.30- 5.85 E3 4.40 E3 2.65 E3 3/3 Low (2) 3/4/2009 0

0 3/4/2009 Q091LIM3 1-131 1.41 -2.51 E2 1.88 E2 1.38 E2 2/3 Low(3)

S 6/8/2009 Q092LIM1 1-131 3.36- 5.95 E2 4.48 E2 4.54 E2 3 Pass 0

6/8/2009 Q092LIM2 1-131 0.86- 1.53 E3 1.15 E3 1.08 E3 3 Pass 0

0 6/8/2009 Q092LIM3 1-131 7.49-13.28 El 9.99 El 9.61 E1 3 Pass 0

Iodine on Cartridge 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0 pCi pCi pCi 0 6/18/2009 E6702-37 1-131 7.24- 12.83 El 9.65 El 9.53 El 3 Pass S

0 Beta Air Particulate 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status IpCi pCi pCi 0 12/10/2009 E6903-37 Cs-137 1.97 - 3.50 E2 2.63 E2 2.36 E2 3 Pass 0 Tritium in Water S Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 0 1/28/2009 Q091TWR1 H-3 4.30-7.62 E3 5.73 E3 5.54 E3 3 Pass 0

1/28/2009 Q091TWR2 H-3 0.86- 1.53 E4 1.15 E4 1.09 E4 3 Pass 0

7/22/2009 Q093TWSI H-3 0.88- 1.56 E4 1.18 E4 1.13 E4 3 Pass 0

7/22/2009 Q093TWS2 H-3 3.43- 6.61 E2 4.76 E2 5.10 E2 3 Pass 0

11/12/2009 Q094TWS1 H-3 5.30- 9.40 E8 7.07 E8 7.82 E8 3 Pass 11/12/2009 Q094TWS2 H-3 0.77- 1.36 E5 1.02 E5 0.97 E5 3 Pass Section 5 - Page 7

0 0

Table 5.0-A Footnote Explanations 0 0

(1) Iodine in Water, Sample ID Q093LIW2, Reference Date 7/21/2009 0

0 One of three results was outside of the acceptance range (reference 6.18). 0 0

(2) Iodine in Milk, Sample ID Q091LIM2, Reference Date 3/4/2009 0

Three results for this cross-check were reported. All three of the reported results 0 trended low and were outside of the acceptance range (reference 6.19). 0 (3) Iodine in Milk, Sample ID Q091LIM3, Reference Date 3/4/2009 0

0 Three results for this cross-check were reported. Two of the three reported results 0 trended low and were outside of the acceptance range (reference 6.19). 0 0

0 0

0 Section 5 - Page 8 0

0

0 0

TABLE 5.0-B 0 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

QUIKVM RESPONSE PROGRAM 0

0 2009 PROFICIENCY TEST RESULTS FOR ENRAD LABORATORIES ERA LABORATORY CODE: D242401 0

0 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates as described in the "Quik" Response instruction package within the study period. Proficiency test data 0 are reported to ERA for evaluation. ERA reports proficiency test results to the North Carolina Department of 0 Health and Human Services, North Carolina Public Drinking Water Laboratory Certification Program.

0 If applicable, footnote explanations are included following this data table.

0 Gamma Emitters in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check 0 Date Range pCi/I Value pCi/I Value pCi/1 Status 0 4/6/2009 RAD-77* Ba-133 4.34 - 5.83 El 5.27 E1 6.18 El High ()

Cs-134 5.95 - 8.02 E1 7.29 E1 6.86 El Pass 0

Cs-137 1.51 - 1.87 E2 1.68E2 1.52E2 Pass 0 Co-60 8.00 - 10.0 El 8.89 E1 9.56 El Pass 0 Zn-65 7.60 - 10.1 El 8.44 E1 9.97 El Pass 0

0 10/5/2009 RAD-79** Ba-133 7.83 - 10.2 El 9.29 E1 9.35 El Pass 0 Cs-134 6.50 - 8.73 El 7.94 E1 7.60 El Pass Cs-137 4.91 - 6.29 El 5.46 E1 5.51 El Pass Co-60 1.05 - 1.31 E2 1.17 E2 1.15 E2 Pass 0 Zn-65 8.96- 11.9 El 9.95 E1 1.11 E2 Pass 0

0 Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/I pCi/l pCi/I 4/6/2009 RAD-77* H-3 1.78 - 2.23 E4 2.03 E4 1.87 E4 Pass 10/5/2009 RAD-79** H-3 1.43 - 1.80 E4 1.64 E4 1.53 E4 Pass

ERA study period 4/6/2009 - 5/21/2009, ERA datareport issue date 6/3/2009

- ERA study period 10/5/2009 - 11/19/2009, ERA datareport issue date 12/4/2009 Section 5 - Page 9

0 0

Table 5.0-B Footnote Explanations 0 0

0 (1) Gamma Emitters in Water, Sample ID RAD-77, Reference Date 4/6/2009 0

Reported result for Ba-133 was above the acceptance range limit (reference 6.20). 0 0

0 0

0

.0 0

0 0

Section 5 - Page 10 0 0

0 0

0 0 TABLE 5.0-C 0 2009 ENVIRONMENTAL DOSIMETER 0 CROSS-CHECK RESULTS 0

0 0 Nuclear Technology Services 0

1st Quarter 2009 2nd Quarter 2009 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 100125 110.1 104.0 5.87 <+/-15% Pass 102077 106 101.0 4.95 <+/-15% Pass 100203 109.2 104.0 5.00 <+/-15% Pass 102243 100 101.0 -0.99 <+/-15% Pass 101141 105.4 104.0 1.35 <+/-15% Pass 102244 108 101.0 6.93 <+/-15% Pass 100210 104.5 104.0 0.48 <+/-15% Pass 102323 102 101.0 0.99 <+/-15% Pass 100386 108.6 104.0 4.42 <+/-15% Pass 102329 101 101.0 0.00 <+/-15% Pass Average Bias (B) 3.42 Average Bias (B) 2.38 Standard Deviation (S) 2.37 Standard Deviation (S) 3.40 Measure Performance IBI+S 5.79 <15% Pass Measure Performance IBI+S 5.78 <15% Pass 3rd Quarter 2009 4th Quarter 2009

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 102228 69.5 70.2 -1.00 <+/-15% Pass 100140 14.0 14.0 0.00 <+/-15% Pass 102492 71.1 70.2 1.28 <+/-15% Pass 100358 14,0 14.0 0.00 <+/-15% Pass 102007 69.9 70.2 -0.43 <+/-15% Pass 100404 13.0 14.0 -7.14 <+/-15% Pass 102041 73.4 70.2 4.56 <+/-15% Pass 100405 14.0 14.0 0.00 <+/-15% Pass 102078 70.6 70.2 0.57 <+/-15% Pass 100415 15.0 14.0 7.14 <+/-15% Pass

Average Bias (B) 1.00 Average Bias (B) 0.00 Standard Deviation (S) 2.18 Standard Deviation (S) 5.05 Measure Performance IBI+S 3.17 <15% Pass Measure Performance IBI+S 5.05 <15% Pass Section 5 - Page I I

Internal Crosscheck (Duke Energy) 0 1st Quarter 2009 2nd Quarter 2009 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 101297 18.3 19.0 -3.95 <+/-15% Pass 102325 49.1 50.0 -1.78 <+/-15% Pass 101286 18.5 19.0 -2.58 <+/-15% Pass 102491 48.7 50.0 -2.68 <+/-15% Pass 101258 18.2 19.0 -4.26 <+/-15% Pass 102374 48.4 50.0 -3.26 <+/-15% Pass 101216 18.4 19.0 -3.42 <+/-15% Pass 102084 47.6 50.0 -4.88 <+/-15% Pass 101252 18.1 19.0 -4.74 <+/-15% Pass 102404 51.3 50.0 2.56 <+/-15% Pass 101356 18.7 19.0 -1.74 <+/-15% Pass 102396 47.8 50.0 -4.32 <+/-15% Pass 101339 18.2 19.0 -4.32 <+/-15% Pass 102346 48.7 50.0 -2.60 <+/-15% Pass 101127 17.6 19.0 -7.47 <+/-15% Pass 102485 48.6 50.0 -2.80 <+/-15% Pass 101278 19.4 19.0 1.89 <+/-15% Pass 102059 48.2 50.0 -3.68 <+/-15% Pass 101305 18.4 19.0 -3.05 <+/-15% Pass 102263 50.0 50.0 -0.08 <+/-15% Pass Average Bias (B) -3.36 Average Bias (B) -2.35 Standard Deviation (S) 2.40 Standard Deviation (S) 2.18 Measure Performance IBI+S 5.76 <15% Pass Measure Performance IBI+S 4.53 <15% Pass 3rd Quarter 2009 4th Quarter 2009 0 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 S 102400 25.9 27.0 -3.93 <+/-15% Pass 100955 20.4 22.0 -7.14 <+/-15% Pass 0

-4.70 <+/-15% Pass 100050 20.0 22.0 -9.18 <+/-15% Pass 102486 102402 25.7 25.9 27.0 27.0 -4.04 <+/-15% Pass 100885 21.2 22.0 -3.68 <+/-15% Pass 0

102406 26.9 27.0 -0.44 <+/-15% Pass 101409 19.2 22.0 -12.77 <+/-15% Pass 0 102435 26.6 27.0 -1.63 <+/-15% Pass 100389 20.3 22.0 -7.82 <+/-15% Pass 102442 25.3 27.0 -6.48 <+/-15% Pass 100401 20.4 22.0 -7.18 <+/-15% Pass 0 102436 25.9 27.0 -3.93 <+/-15% Pass 101383 21.0 22.0 -4.45 <+/-15% Pass 102440 25.1 27.0 -7.19 <+/-15% Pass 100551 20.4 22.0 -7.14 <+/-15% Pass 0

102479 25.2 27.0 -6.81 <+/-15% Pass 100748 20.9 22.0 -4.95 <+/-15% Pass 0 27.0 -3.67 <+/-15% Pass 100263 20.9 22.0 -4.91 <+/-15% Pass 102384 26.0 Average Bias (B) -4.28 Average Bias (B) -6.92 0

Standard Deviation (S) 2.17 Standard Deviation (S) 2.68 0 Measure Performance IBI+S 6.45 <15% Pass Measure Performance IBI+S 9.61 <15% Pass 0 0

Section 5 - Page 12

0 0

0 S

6.0 REFERENCES

6.1 McGuire Selected License Commitment Manual 6.2 McGuire Technical Specifications 6.3 McGuire Updated Final Safety Analysis Report 6.4 McGuire Offsite Dose Calculation Manual 0

6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2008 6.6 McGuire Annual Radioactive Effluent Release Report 2008 0

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.

S 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 0*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 0

6.12 NRC Integrated Inspection Report (50-369/2009004, 50-370/2009004) 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 0

6.14 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-07-00556 6.15 Problem Investigation Process Database V 3.2.27, Duke Power Company, G-04-00134 6.16 Radiological Effluents Controls Audit 08-22(INOS)(REC)(MNS)

6.1 Radiological Effluents Controls Audit 08-22(IOS)(REC)(MNS)

[ 6.17 Radiological Effluent Controls Audit 08-23(INOS)(REC)(NGO) 6.18 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-01278 0

6.19 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-00423 0 6.20 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-0 1295

Section 6 -Pagel1 0

0 0

0 APPENDIX A 0

0 0 ENVIRONMENTAL SAMPLING 0

0 0

ANALYSIS PROCEDURES 0

0 0

0 Appendix A - Page 1

0 0

APPENDIX A 0 ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES 00 S

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 Indicator location 103 (Air Radioiodine, Air Particulate) was added as a replacement for indicator location 192 (Air Radioiodine, Air Particulate), which was removed from the program (reference 6.14).

II. DESCRIPTION OF ANALYSIS PROCEDURES 0

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 0 pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system or Perkin-Elmer 2900TR liquid scintillation system. Tritium samples are distilled and batch processed with a tritium spike and blank to verify instrument performance and sample preparation technique are acceptable.

A 0

Appendix A -Page 2 0 0

0 0

0

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 0

No analysis procedures were changed during 2009.

IV. SAMPLING AND ANALYSIS PROCEDURES S

A.1 AIRBORNE PARTICULATE AND RADIOIODINE 0 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 0 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 102 = Amity Church Road (9.89 mi. WNW)

Location 103 = Cottonwood (4.20 mi. NE)

Programmaticsampling initiated10/5/2009,reference 6.14 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 192 Peninsula (2.84 mi. NNE)

Programmaticsampling terminatedlO0/5/2009, reference 6.14

Location 195 Fishing Access Road (0.19 mi. N)

A.2 DRINKING WATER 0 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)

A 0

Appendix A -Page 3 0

0 0

A.3 SURFACE WATER 0

Monthly composite samples were collected. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly 0 composites sample. The composites were collected monthly from the locations listed below.

0 S

Location 128 Discharge Canal Bridge (0.45 mi. NE)

Location 131

- Cowans Ford Dam (0.64 mi. WNW) 0 Location 135 = Plant Marshall Intake Canal (11.9 mi. N) 0 A.4 MILK 0 0

Biweekly grab samples were collected at one location. A gamma and low-level Iodine-131 analysis was performed on each sample, The biweekly grab samples 0 were collected from the location listed below.

S Location 141 Lynch Dairy - Cows (14.8 mi. WNW) 0 A.5 BROADLEAF VEGETATION 0 Monthly samples were collected as available and a gamma analysis was performed 0 on each sample. The samples were collected from the locations listed below.

0 Location 102 = Amity Church Road (9.89 mi. WNW) S Location 120 - Site Boundary (0.46 mi. NNE) 0 Location 125 = Site Boundary (0.38 mi. SW)

Location 193 = Site Boundary (0.19 mi. N) 0 A.6 FOOD PRODUCTS 0

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 0

listed below. 0 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.

Appendix A - Page 4

0 0

0

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

Location 137 = Pinnacle Access Area (12.0 mi. N) 0A.8 SHORELINE SEDIMENT 0Semiannual 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) 0*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.

0 A.10 ANNUAL LAND USE CENSUS 0An 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 0* The Nearest Garden greater than 50 square meters or 500 square feet S* The Nearest Milk-giving Animal (cow, goat, etc.)

0

The census was conducted during the growing season from 5/18 to 5/19/2009.

Results are shown in Table 3.10. No changes were made to the sampling procedures during 2009 as a result of the 2009 census.

0 0

Appendix A -Page 5 0

0 0

In the environmental program, the air deposition parameters (D/Q) are used to 0

determine air, broadleaf vegetation and milk sampling locations. McGuire's sectors 0 with the three highest values did not change in 2009. 0 0

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS 0 The McGuire site centerline used for GPS measurements was referenced from the 0 McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1, 0 Site Location. Waypoint coordinates used for MNS GPS measurements were latitude 0 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 0

from point of measurement. GPS field measurements were taken as close as possible to 0 the item of interest. Distances for the locations are displayed using three significant 0 figures. 0 0

0 0

0 Appendix A - Page 6 0

0 0

S 0

0 0

0 0 APPENDIX B 0

0 0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0 PROGRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0

0 2009 0

S 0

0 0

Appendix B - Page 1 0

0 0

S Environmental Radiological Monitoring Program Summary S

Facility: McGuire Nuclear Station Docket No. 50-369,370 0

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 Medium or Type and Total Lower All Indicator Location with Highest Locat w est Control No.of Non-Routine 0

Pathway Nubr Limit of LatosAnnual Mean Lcto eot of Detection Locations Name, Distance, Direction Meas.

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

Measurement Performed Range Code Range Range Air Particulate 102 (9.89 mi WNW)

(pCi/m3)

BETA *363 1.OOE-02 1.74E-2 (311/311) 125 1.79E-2 (51/51) 1.76E-2 (52/52) 0 6.81E 2.75E-2 (0.38 mi SW) 7.64E 2.71E-2 8.99E 2.72E-2 0 CS-134 363 5.OOE-02 0.00 (0/311) 0.00 (0151) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 363 6.OOE-02 0.00 (0/311) 0.00 (0/51) 0.00 (0/52) 0 0.00 - 0.00 0,00 - 0.00 0.00 - 0.00 1-131 363 7.OOE-02 0.00 (0/311) 0.00 (0/51) 0.00 (0/52) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 S

0 0

Report Generated @ 4/26/2010 16:42 Appendix B - Page 2

0 0

0 0 Environmental Radiological Monitoring Program Summary 0 Facility: McGuire Nuclear Station Docket No. 50-369,370 0 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 S Mduor Type and Location with HighestNoofon No. of Non-Medium or Tyead Lower Pathway Total Limit of All Indicator Loc a l M ean Control Routine NumberL Locations Annual Mean Location Report Sampled of Detection Name, Distance, Direction Meas.

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

Measurement Performed (LLD)Range Code Range Range Air Radioiodine 102 (9.89 mi WNW)

(pCi/m3)

CS-134 363 5.OOE-02 0.00 (0/311) 0.00(0/52) 0.00 (0/52) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 363 6.OOE-02 0.00 (0/311) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 363 7.OOE-02 0.00 (0/311) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

Report Generated @4/26/2010 16:42 Appendix B - Page 3

0 0

Environmental Radiological Monitoring Program Summary 0

0 Facility: McGuire Nuclear Station Docket No. 50-369,370 0 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

0 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

Unit of Analyses Mean (Fraction) Location

Mean (Fraction) Mean (Fraction)

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 1.81 (50/52) 119 1.90 (12/13) 1.81 (13/13) 0 0.67 - 3.00 (7.40 mi SSW) 1.08 - 2.40 1.29 - 2.27 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 0 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 0

FE-59 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 20 2000 700 (16/16) 101 1029 (4/4) 186 (1/4) 0 0

189-1170 (3.31 mi E) 922- 1170 186-186 0 1-131 65 15 0.00 (0/52) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

0 MN-54 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0 NB-95 65 15 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0 0

0.00 -0.00 0.00 -0.00 0.00 -0.00 0 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 @ 4/26/2010 16:42 Appendix B - Page 4

0 0

Environmental Radiological Monitoring Program Summary 0

0 Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

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 0 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12 2000 937 (8/8) 128 1181 (4/4) 141 (1/4) 0 384-1610 (0.45 mi NE) 904- 1610 141-141 0 1-131 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 0 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 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 0 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 0

0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements Report Generated @ 4/26/2010 16:42 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-2009 to 31-DEC-2009 Type and Total Lower Location with Highest ControlNone No. of Non-Medium or M All Indicator Control Routine Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code, Range Range Milk NO INDICATOR 141 (pCi/liter) LOCATION (14.8 mi WNW)

BALA- 140 26 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 0

CS-134 26 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0 CS-137 26 18 0.00 - 0.00 0.00 (0/26) 0.00 0.00

- 0.00 (0/26) 0.00 0.00

- 0.00 (0/26) 0 S

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S 1-131 26 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 26 1 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 4/26/2010 16:42 Appendix B - Page 6

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: McGuire Nuclear Station Docket No. 50-369,370 0

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 S No. of Non-0 Medium or Type and Total Lower All Idit Location with Highest Control Routine Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

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

Measurement Performed Range Code Range Range Broadleaf 102 (9.89 mi WNW)

Vegetation (pCi/kg-wet)

CS-134 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 48 80 0.00 (0/36) 0.00 - 0.00 0.00 0.00 (0/12)

- 0.00 0.00 0.00 (0/12)

- 0.00 0

S 1-131 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 4/26/2010 16:42 Appendix B - Page 7

0 0

0 Environmental Radiological Monitoring Program Summary 0

0 Facility: MeGuire Nuclear Station Docket No. 50-369,370 0 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet) LOCATION 0

0 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 0

CS-137 12 80 0.00(0/12) 0.00(0/12) 0.00(0/0) 0 0 1-131 12 60 0.00- 0.00 0.00 (0/12) 0.00 - 0.00 0.00 (0/12) 0.00 - 0.00 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 4/26/2010 16:42 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-2009 to 31-DEC-2009 Type and Total Lower Location with Highest No. of Non-Medium or Number Limit of Indicator AllLocations Annual Mean Control Routine Pathway Location Report Sampled of Detection Name, Distance, Direction Leaor Meas.

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

Measurement Performed (LLD) 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 12 150 17.6 (1/6) 12.9 17.6 (1/6) 17.6 (1/6) 0 17.6- 17.6 (0.51 mi ENE) 17.6- 17.6 17.6- 17.6 0 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 0 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0

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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

0 Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

S 0

0 0

0 Report Generated @ 4/26/2010 16:42 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-2009 to 31-DEC-2009 0 Lower Location with Highest No. of Non-Medium or Type and Total All Indicator Control Routine Number Limit of Annual Mean Pathway of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed (LLD) 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CO-58 6 0 0.00 (0/4) 0.00 - 0.00 0.00 (0/2) 0.00 - 0.00 0.00 (0/2) 0.00 - 0.00 0

0 CO-60 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 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 0 CS-137 6 180 50.8(2/4) 130 50.8(2/2) 0.00(0/2) 0 0 38.2 - 63.4 (0.52 mi SW) 38.2 - 63.4 0.00 - 0.00 0

0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 0 0

0 0

Report Generated @ 4/26/2010 16:42 Appendix B - Page 10

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: McGuire Nuclear Station Docket No. 50-369,370 0 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

0 0

0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 S

0 0

0 Report Generated @ 4/26/2010 16:42 Appendix B - Page 11 0

0 0

0 0 APPENDIX C 0

0 0 SAMPLING DEVIATIONS S

0 0

UNAVAILABLE ANALYSES 0

0 0

S S

S Appendix C - Page 1

0 0

0 I 0 0

APPENDIX C 0 0

0 MCGUIRE NUCLEAR STATION 0

SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES 0 0

DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage 0

FZ Sample Frozen PS Pump out of service / Undergoing Repair 0 IW Inclement Weather LC Line Clog to Sampler SL SM Sample Loss/Lost due to Lab Accident Motor / Rotor Seized 0

OT Other TF Tom Filter 0 PI Power Interrupt VN Vandalism 0 PM Preventive Maintenance CN Construction 0

0 C.1 SAMPLING DEVIATIONS 0

Air Particulate and Air Radioiodines 0 Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action 0 Power interrupted to sampling equipment during composite period for about 10.9 0 hours0 days 0 hours 0 weeks 0 months . Suspected cause inclement 0 125 7/20 - 7/27/2009 7/20 - 7/27/2009 P1 weather.

Power interrupted to sampling equipment 0 during composite period for about 8.62 0 195 9/21 - 9/28/2009 9/21 - 9/28/2009 PI hours due to indeterminate cause.

Power interrupted to sampling equipment 0

during composite period for about 27.3 0 hours0 days 0 hours 0 weeks 0 months . Work request 72478 written to 195 9/28 - 10/5/2009 9/28 - 10/5/2009 PI investigate power delivery stability.

0 Breaker mistakenly turned off by 0 unknown individual. PIP G-09-01255 written. Sample for preceding composite 0 period (11/30 - 12/7/2009) unavailable 0 due to this problem. Breaker labeled, 125 12/7 - 12/14/2009 12/8 - 12/14/2009 P0 reset, and normal sampling resumed. 0 0

Drinking Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Water plant maintenance work interrupted water supply during composite period 119 8/24 - 9/21/2009 8/24 - 9/21/2009 PS from 9/12 - 9/16/2009.

Appendix C - Page 2

0 0

0 Surface Water S Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action S Submersible pump malfimction. Work request 64072 written. Grab sample. taken 1/12/2009 and combined with composite.

Repair work spanned two composite 0 12/15 - 1/12/2009 12/15 - 1/12/2009. periods. Submersible pump replaced and 128 1/12 - 2/9/2009 1/12 - 2/9/2009 PS water flow restored 1/13/2009.

0 Power outage to site. Work request 65833 written. Grab sample taken 3/9/2009 and combined with composite. Repair work 0 135 2/9 - 3/9/2009 3/9 - 4/6/2009 2/9 - 3/9/2009 3/9 - 4/6/2009 PO spanned two composite periods. Power restored, sampling resumed 3/10/2009.

0 0 C.2 UNAVAILABLE ANALYSES 0

0 Air Particulate and Air Radioiodines Scheduled Reason 0 Location Collection Dates Code Corrective Action Power interruption due to breaker trip. Insufficient volume collected. Work request 74373 written.

Breaker reset did not restore power to sampling 0 equipment. Maintenance determined power supply had been inadvertently turned off in building 7478 at 0 breaker CKT5. PIP G-09-01255 written. Power 0 interruption affected the start of the next scheduled 125 11/30 - 12/7/2009 PO composite period (12/7 - 12/14/2009).

0 TLD 0 Scheduled Reason Location Collection Dates Code Corrective Action 0 158 9/17- 12/17/2009 I CN ITLD missing. lt quarter 2010 TLD placed in field.

159 9/17 - 12/17/2009 CN TLD missing. 1st ýuarter 2010 TLD placed in field.

0 0

0 Appendix C - Page 3

0 0

S 0

0 APPENDIX D 0

0 0 ANALYTICAL DEVIATIONS 0

0 No Analytical deviations were incurred for the 0 2009 Radiological Environmental Monitoring Program 0

0 0

0 Appendix D - Page 1

0 0

0 0 APPENDIX E 0

0 RADIOLOGICAL 0 ENVIRONMENTAL MONITORING 0

0 PROGRAM RESULTS 0

0 0

This appendix includes all of the sample analysis reports generated from 0 each sample medium for 2009. Appendix E is located separately from this report and is permanently archived at the Duke Energy Corporation 0 Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

0 0

0 Appendix E - Page 1

ML101440041

Contents

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2.0 INTRODUCTION

6.0 REFERENCES

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ML101440041

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6.0 REFERENCES

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