Text

Annual Radiological Environmental Operating Report for 2008 Calendar Year
	ML091410202
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/13/2009
From:	Brandi Hamilton; Duke Energy Carolinas, Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML091410202 (89)
	v • d • e

BRUCE H HAMILTON Vice President Duke Pahmnergy. McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamflton@duke-energy.com May 13, 2009 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 2008 calendar year.

Questions regarding this report should be directed to Kay Crane, McGuire Regulatory Compliance at (704) 875-4306.

Bruce H. Hamilton www. duke-energy.corn

U. S. Nuclear Regulatory Commission May 13, 2009 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 Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 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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S 0 AREOR 0 Annual Radiological Environmental 0

Operating Report 0

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" Duke e* WEnergy.

ANNUAL RADIOLOGICAL

ENVIRONMENTAL OPERATING REPORT 0

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DUKE ENERGY CORPORATION

MCGUIRE NUCLEAR STATION

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0 TABLE OF CONTENTS 0

1.0 Executive Summary . 1-1

2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 2.3 Statistical and Calculational Methodology . 2-2 2.3.1 Estimation of the Mean Value . 2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2-3 2.3.3 Trend Identification. 2-3 3.0 Interpretation of Results . 3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water. 3-5 3.3 Surface Water 3-7 3.4 Milk. 3-9 3.5 Broadleaf Vegetation. 3-10 3.6 Food Products 3-11 3.7 Fish. 3-12 3.8 Shoreline Sediment 3-15 3.9 Direct Gamma Radiation 3-18 3.10 Land Use Census 3-20 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-1 4.3 Comparison of Doses. 4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis . 5-1 5.4 Laboratory Equipment Quality Assurance 5-1 5.4.1 Daily Quality Control 5-1

5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Duke Energy Intercomparison Program 5-2 5.6 ERAProficiency Testing 5-2 5.7 Duke Energy Audits . 5-2 5.8 U.S. Nuclear Regulatory Commission Inspections 5-2 5.9 State of North Carolina Intercomparion Program 5-2 5.10 TLD Intercomparison Program . 5-3 5.10.1 Nuclear Technology Services Intercomparison Program 5-3 5.10.2 State of North Carolina Intercomparison Program 5-3 5.10.3 Internal Crosscheck (Duke Energy). 5-3 6.0 References 6-1 0

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Appendices Appendix A: Environmental Sampling and Analysis Procedures A-i I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A. 1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water. A-4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 0 A.6 Food Products. A-4 A.7 Fish A-5 A.8 Shoreline Sediment. A-5 A.9 Direct Gamma Radiation (TLD) A-5 A. 10 Annual Land Use Census A-5 V. Global Positioning System (GPS) Analysis A-6 Appendix B: Radiological Env. Monitoring Program - Summary of Results B-1 Air Particulate . B-2 Air Radioiodine. B-3 Drinking Water. B-4 Surface Water . B-5 Milk. B-6 Broadleaf Vegetation . B-7 Food Products . B-8 Fish .B-9 Shoreline Sediment B-10 Direct Gamma Radiation (TLD) . . . . . . . . B-11 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C. I Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 LIST OF FIGURES 2.1-1 Sampling Locations Map (0.5 Mile Radius) 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-3 3.2 Concentration of Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water. 3-7 3.7-1 Concentration of Cs-137 in Fish 3-13 3.7-2 Concentration of Co-60 in Fish . 3-13 3.8-1 Concentration of Cs-137 in Shoreline Sediment 3-15 3.8-2 Concentration of Co-60 in Shoreline Sediment 3-16 3.9 Direct Gamma Radiation (TLD) Results 3-18 3.10 2008 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 0

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2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-8 0 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection 2-9 3.1-A Mean Concentrations of Radionuclides in Air Particulate S 3.1--B Mean Concentrations of Air Radioiodine (1-131) 3-3 3-4 0 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 0 3.3 3.4 Mean Concentrations of Tritium in Surface Water Mean Concentrations of Cs-137 in Milk 3-8 3-9 0 3.5 Mean Concentrations of Cs- 137 in Broadleaf Vegetation 3-10 3.6 Mean Concentrations of Cs-137 in Food Products 3-11 3.7 Mean Concentrations of Radionuclides in Fish 3-14 0 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment 3-16 3.9 Direct Gamma Radiation (TLD) Results 3-19 0 3.10 Land Use Census Results . 3-20 4.1-A 2008 Environmental and Effluent Dose Comparison 4-3 0 4.1-B Maximum Individual Dose for 2008 based on Environmental Measurements for McGuire Nuclear Station 0 5.0-A 2008 Cross-Check Results for EnRad Laboratories 4-6 5-4 5.0-B 2008 Environmental Resource Associates QuikM Response Program 5-10 0 5.0-C 2008 Environmental Dosimeter Cross-Check Results . 5-11 0 LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder) 0 BW BiWeekly C Control DEHNR Department of Environmental Health and Natural Resources 0 DHEC EPA Department of Health and Environmental Control Environmental Protection Agency 0 ERA Environmental Resource Associates GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System LLD Lower Limit of Detection 0 M MDA Monthly Minimum Detectable Activity MNS McGuire Nuclear Station mrem millirem NIST National Institute of Standards and Technology S NRC ODCM Nuclear Regulatory Commission Offsite Dose Calculation Manual pCi/kg picocurie per kilogram 0 pCi/1 pCi/m3 picocurie per liter picocurie per cubic meter 0 PIP Problem Investigation Process Q Quarterly 0 REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter ptCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

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1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the McGuire

Nuclear Station Radiological Environmental

Monitoring Program (REMP), and the program results for the calendar year 2008.

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 0calculated 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 fifty samples were analyzed comprising 1,626 test results in order to compile data for the 2008 report. Based on the Sannual land use census, the current number of sampling sites for McGuire Nuclear Station

is sufficient.

0 Concentrations observed in the environment in 2008 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of 0data showed that radioactivity concentrations in surface water, drinking water, shoreline

sediment and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in 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 1.40E-1 mrem for 2008. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the 0public 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

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.

0Lake 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 0 6.3).

0 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 0*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

2.2 SCOPE AND REQUIREMENTS OF THE REMP 0An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977,

four years prior to operation of Unit 1 in 1981. The preoperational program provides data on the

existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. The operational program provides surveillance and backup support of detailed effluent monitoring

which is necessary to evaluate the significance, if any, of the contributions to the existing 0environmental 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 0comparison 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* Section 2 -Pagel1 0

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from releases of radionuclides from McGuire Nuclear Station. This program satisfies the S 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 0 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 0 Commitments provides for independent checks on the precision and accuracy of measurements 0 of radioactive material in REMP sample matrices. Such checks are performed as part of the 0 quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The 0 mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):

N 0 Where:

x = estimate of the mean, S i = individual sample, 0 N = total number of samples with a net activity (or concentration), 0 Xi = net activity (or concentration) for sample i. 0 NOTE: "Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the 0 calculation of the mean. 0 Section 2 - Page22

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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 0 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 0 size (mass or volume), the radiochemical yield, and the radioactive decay of the sample 0 between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

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

0 2.3.3 TREND IDENTIFICATION 5 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) 0 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 0 influencing the concentration.

0 Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to 0 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, 0 and addition or deletion of other sources of radioactive materials (such as the Chernobyl 0 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 U.

McGuire Nuclear Station Sampling Locations Map (0.5 Mile Radius)

Legend

TLD Locations A All Other Locations

/X/ Public Roads

- County Boundary Water Alpro~dm ate location of features sh~o N

w-*E 0 0.125 0.2,5 Miles Project on NCSP NAD27 b

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Figure 2.1-2 Section 2 - Page 5

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TABLE 2.1-A 0 0

MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 0

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W Weekly SM Semimonthly 0 BW BiWeekly Q Quarterly M Monthly SA Semiannually 0

C Control 0 Site S Location Description* Air Rad.

& Part.

Surface Water Drinking Water Shoreline Food Fish Milk Broad Sediment Products 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) 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 Charlotte Municipal Water Supply ( 11.1 mi SSE) M 133 Cornelius (6.23 mi ENE) W 0 134 C 135 C East Lincoln Jr.High School (8.77 mi WNW)

Plant Marshall Intake Canal (11.9 mi N )

W M

M (b) 0 136 C Mooresville Municipal Water Supply ( 12.7 mi NNE) M 137 C Pinnacle Access Area ( 12.0 mi N) SA SA 0 139 (T2) William Cook Dairy ( 2.49 mi E ) SM 141 C Lynch Dairy-Cows ( 14.8 mi WNW) SM 0 188 192 5 mile radius Gardens (2.79 mi NNE)

Peninsula ( 2.84 mi NNE ) W M (a) 0 193 194 Site Boundary ( 0.19 mi N))M(b)

East Lincoln County Water Supply ( 6.73 mi NNW) M 0

195 Fishing Access Road ( 0.19 mi N) W 0 (1) Control location 102 (Air Radioiodine, Air Particulate, Vegetation) was added as a replacement for control location 134 (Air Radioiodine, Air Particulate, Vegetation), which was removed from the program. Movement of the control air radioiodine, air particulate, and vegetation location is described in PIP G-07-00399. 0 (2) Indicator location 139 (Milk) was removed from the program due to dairy closure. No new milk animals were identified by the 2008 McGuire Land Use Census to 0 complement the existing program. Removal of indicator location 139 is described in PIP G-08-00977.

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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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S TABLE 2.1-B 0 MCGUIRE RADIOLOGICAL MONITORING PROGRAM 0 SAMPLING LOCATIONS 9

0 (TLD SITES) 0 Site Location Distance* Sector Site Location Distance* Sector HAMBRIGHT &

0 143 SITE BOUNDARY 0.27 miles NW 164 BEATTIES FORD ROAD 4.64 miles SSE 0 144 SITE BOUNDARY 0.46 miles NNE 165 ARTHER AUTEN ROAD NECK ROAD 4.57 miles S 145 SITE BOUNDARY 0.47 miles NE 166 REFUGE BOUNDARY 4.44 miles SSW LUCIA RIVERBEND HWY/

146 SITE BOUNDARY 0.42 miles ENE 167 OLD FIREHOUSE 4.87 miles SW 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 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 KEISTLER STORE /

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

189 SITE BOUNDARY 0.43 miles SSE 177 SI COULWOOD COMMUNITY 8.77 miles S 0 190 SITE BOUNDARY 0.33 miles WSW 178 SI FLORIDA STEEL CORPORATION 9.32 miles SE MOORESVILLE WATER 157 THE POINTE/MOORESVILLE 4.69 miles N 180 SI TREATMENT FACILITY 12.7 miles NNE S 158 BETHEL CHURCH ROAD 4.33 miles NNE 181 SI OLD DAVIDSON WATER TREATMENT FACILITY 7.02 miles NE HENDERSON ROAD &

159 WEST CATAWBA AVENUE 4.73 miles NE 182 SI CORNELIUS / AIR SITE # 133 6.23 miles ENE 0 ANCHORAGE MARINE MCGUIRE FISHING ACCESS 0 160 SHOWROOM SAM FURR ROAD 4.89 miles ENE 186 SI ROAD ON PENINSULA ENERGY EXPLORIUM /

0.24 miles NNW 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 S 163 MCCOY ROAD 4.94 miles SE S C = Control SI = Special Interest 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 2.2-A 0 0

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0

Analysis Water Air Particulates Fish Milk BroadLeaf 0 (pCi/liter) or Gases (pCi/m3)

(pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-wet) 0 H-3 20, 000(a)'(b) 0 Mn-54 1,000 30,000 0 Fe-59 400 10,000 Co-58 1,000 30,000 0 Co-60 300 10,000 Zn-65 300 20,000 0 Zr-Nb-95 400 0 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 Ba-La-140 200 300 0

(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 0 0

TABLE 2.2-B S REMP ANALYSIS FREQUENCY 0 0

Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta 0 Air Radioiodine Weekly X S Air Weekly X X Direct Radiation Quarterly X 0

Surface Monthly Composite X Water Quarterly Composite X Drinking Monthly Composite X (a) X 0

Water Quarterly Composite X S Shoreline Sediment Semiannually X 0 Milk Semimonthly X X Fish Semiannually X 0 Broadleaf Vegetation Monthly(b) X 0 Food Products Monthly(b) X 0

(a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is > 1 0 mrem per year. An LLD of 1 pCi/liter will be required for this analysis.

(b) When Available Section 2 - Page 8

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0 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION S Analysis Water Air Particulates Fish Milk BroadLeaf Sediment 0 (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry)

(pCi/m3) (pCi/kg-wet) 0 Gross Beta 4 0.01 H-3 2000 (a) 0 Mn-54 15 130 0 Fe-59 30 260 0 Co-58, 60 15 130 Zn-65 30 260 0 Zr-Nb-95 15 1-131 1(b) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 0 Cs-137 18 0.06 150 18 80 180 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 2008 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 0evaluated 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 2008 was

7.60% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location

101). Only Selected Licensee Commitments radionuclides were detected in 2008.

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 0period when many measurements yielded detectable low-level activity for both indicator and control location samples. It is possible that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

This section includes tables and graphs containing the highest annual mean concentrations of

any effluent related radionuclide detected since the change in analysis systems in 1987. Any 0zero 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 2008. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2008 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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3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0

In 2008, 364 particulate and radioiodine samples were analyzed, .

312 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.

Gross beta analyses indicated 1.92E-2 pCi/m 3 at the location with the highest annual mean and 1.93E-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 0 in 2004 (reference 6.15).

No detectable 1-131 activity in any environmental air radioiodine samples was found in 2008.

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 2008. Cs-137 0 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion.

Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

Figure 3.1 shows gross beta highest annual mean indicator and control location concentrations 0 since 1985. There is no reporting level for gross beta. Table 3.1-A shows indicator and control location highest annual means for Cs-137 and gross beta.

Table 3.1-B gives indicator location highest annual means and control means since 1979 for 0 1-131. Preoperational and ten year averages are also shown. No 1-131 activity has been detected 0 since 1989. Since no activity was detected in 2008, no reporting levels were approached.

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0 Figure 3.1 0 pCi/m 3

Concentration of Gross Beta in Air Particulate 1.OOE-01 0 9.OOE-02 0 8.OOE-02 0 7OOE-02 0 6.OOE-02 4.OOE-02 - -- - - - - - - - -

3.OOE-0:2 - - - - - - - -

- - -" - JL .

2.OOE-02 - - -

1.OO00E-02 0 O.OOE+O0 0 1985 1987 1989 1991 1993 1995 1997 9 CW,.l 1999 L.,.ti.

2001 I

2003 2005 2007 0 I + lIndicatorlmxAtion S There is no reportinglevel for Gross Beta in airparticulate 0 Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control 0 (pCi/m 3) (pCi/m 3) (pCi/m 3) (pCi/m 3) 1979* 4.40E-3 1.47E-3 ** **

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

0 1981

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

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

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

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

S 1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 1986 4.98E-3 3.03E-3 2.64E-2 2.52E-2 1987 1.07E-2 7.91E-3 2.54E-2 2.59E-2 1988 0.OOEO 0.OOEO 7.49E-2 5.51E-2 1989 0.00E0 0.OOEO 2.22E-2 2.14E-2 1990 O.00E0 0.OOEO 2.58E-2 2.37E-2 0 1991 0.OOEO 0.00E0 2.16E-2 2.15E-2 1992 0.OOEO O.00E0 1.92E-2 2.02E-2 0.00E0 0.OOEO 1.93E-2 2.04E-2 0 1993 1994 0.00E0 0.OOEO 2.28E-2 2.02E-2 0 1995 O.OOEO 0.00E0 3.02E-2 5.17E-2 1996 0.00E0 0.00E0 3.11E-2 5.49E-2 1997 0.OOEO 0.00E0 2.34E-2 3.62E-2 0 1998 0.OOEO 0.OOEO 1.86E-2 2.66E-2 0 1999 0.00E0 0.OOEO 2.06E-2 3.47E-2 2000 0.OOEO 0.OOEO 2.OOE-2 2.77E-2 2001 0.OOEO O.00E0 1.79E-2 1.91E-2 0

Section 3 - Page 3 0

S

0 0

0 Table 3.1-A continued 0 YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control 0

(pCi/m 3) (pCi/m 3) (pCi/m 3) (pCi/m 3 ) 0 2002 0.OOEO 0.OOEO 2003 O.OOEO 0.OOEO 1.57E-2 1.50E-2 1.72E-2 1.63E-2 0

2004 0.00E0 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 0 Average (1998 -2007) NOT APPLICABLE NOT APPLICABLE 1.80E-2 2.18E-2 2008 0.OOEO 0.OOEO 1.92E-2 1.93E-2 0 0,OOEO = no detectable measurements 0

Radioiodines and Particulates analyzed together

- Gross Beta analysis not performed 0

Table 3.1-B Mean Concentrations of Air Radioiodine (1-131) S 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 1983* 1.99E-3 2.01E-4 0

1984 3.17E-3 0.OOEO 0 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.1OE-3 0 1987 1.07E-2 6.60E-3 0 1988 0.00E0 0.OOEO 1989 2.18E-2 0.OOEO 0 1990 0.OOEO 0.OOEO 1991 0.OOEO 0.OOEO 0 1992 0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.OOEO 0.OOEO 0 1995 0.OOEO 0.OOEO 1996 0.OOEO 0.OOEO 0

1992 0.OOEO 0.OOEO 0

2005 0.OOEO 0.OOEO 0 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0

0 0

0 2007 0.OOEO 0.OOEO 0.00E0 = no detectable measurements

Radioijodines and Particulates analyzed together.

Section 3 - Page 4

0 0

3.2 DRINKING WATER 0

0 In 2008, 65 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Fifty-two samples were from the four indicator locations and 13 from the control location. Tritium (H-3) analyses were performed on 20 composite samples, 16 at 0 indicator locations and four at the control location.

0 No detectable gamma activity was found in drinking water samples in 2008 and has not been 0 detected since 1987. Gross beta analyses indicated 2.40 pCi/l at the location with the highest 0 annual mean and 1.87 pCi/l at the control location. Tritium was detected in all of the 16 indicator composite samples taken in 2008 with the highest annual mean resulting in only 0 7.60% of the reporting level. Tritium was detected in two of the four control location samples. The dose for consumption of water was less than one mrem per year, historically and for 2008; therefore low-level iodine analysis is not required.

S Figure 3.2 shows tritium highest annual mean indicator and control location concentrations 0 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 10 1 was added to the sampling program in 1999. Figure 3.2 shows an increase beginning in that year. There was an increase in drinking water tritium in 2006 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 an effort to balance the plant inventory. In addition, an extreme drought during the second half of 2007 and much of 2008 affecting the Catawba River Basin resulted in less dilution volume available in Lake Norman.

0 Figure 3.2 pCiIliter Concentration of Tritium in Drinking Water S 5000--------------------- --- - - -

0 4500 - - - - - - - - - - - - -

0 4000 - - - - - - - - - - - - -

3500 - - - - - - - - - - - - - - - - - - - - - - -

3000 - - - - - - - - - - - - - - - - -

0 2500 0

0 0 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 0 1 -*- Indicator Location Control Location - 20% Reporting Level 0

Section 3 - Page 5 0

0

0 0

0 Table 3.2 Mean Concentrations of Radionuclides in Drinking Water 0 0

Gross Beta (pCi/l) 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 1984 1.80E0 1.87E0 2.65E2 1.45E2 0 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.OOEO 9.92E2 7.111E2 0

1989 2.80E0 2.70E0 5.62E2 0.OOEO 0 1990 3.70E0 4.30E0 1991 2.40E0 2.50E0 7.32E2 5.22E2 6.11E2 0.OOEO 0

1992 2.OOEO 1.70E0 6.73E2 0.OOEO 0 1993 2.80E0 2.40E0 O.OOEO 0.OOEO 0 1994 2.47E0 2.90E0 0.OOEO O.OOEO 1995 4.20E0 3.30E0 3.58E2 0.OOEO 0 1996 2.75E0 2.11EO 3.60E2 O.OOEO 0 1997 2.70E0 2.24E0 2.90E2 0.OOEO 1998 2.75E0 2.33E0 2.68E2 0.OOEO 0 1999 2.48E0 2.17E0 5.49E2 0.OOEO 2000 2.66E0 1.99E0 5.04E2 0.OOEO 0

2001 2.48E0 2.19E0 6.98E2 0.OOEO 0 2002 2.47E0 2.08E0 5.64E2 0.OOEO 2003 1.81E0 1.52E0 3.51E2 0.00E0 0

2004 1.68E0 1.29E0 4.61E2 0.00E0 0 2005 2006 1.74E0 1.75E0 1.30E0 7.35E2 0.OOEO 0 1.80E0 1.46E3 0.OOEO 2007 1.81EO 1.76E0 1.48E3 0.OOEO 0 2008 2.40E0 1.87E0 1.52E3 2.26E2 0 0.OOEO = no detectable measurements 0

0 0

Section 3 - Page 6 0

S

3.3 SURFACE WATER 0

0 In 2008, 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 2008 and has not been detected since 1988. Tritium was detected in all of the eight indicator 0 composite samples taken in 2008.

Tritium was detected in two of the control location composite samples in 0 2008.

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

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 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 S second half of 2007 and much of 2008 affecting the Catawba River Basin resulted in less dilution volume available in Lake Norman.

Figure 3.3 0

There is no reporting level for tritium in surface water 0 pCi/liter Concentration of Tritium in Surface Water 5000 S

0 4500 4000 0 3500 3000 0 2500 0 1500 -- -

0 1000

-- 4 1 5000 0

S 1979 1981 1983 1985 1987 1989 1991 Indicator Location 1993 1995 1997 1999

-- Control Location 2001 2003 2005 2007 0

Section 3 - Page 7 0

S 0

0 Table 3.3 Mean Concentrations of Tritium in Surface Water YEAR H-3 Indicator (pCi/I) H-3 Control (pCi/1) 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 O.OOEO 1989 8.22E2 0.OOEO 1990 6.77E2 O.OOEO 1991 7.53E2 O.OOEO 1992 8.13E2 0.OOEO 1993 6.85E2 0.OOEO 1994 0.OOEO 0.OOEO 1995 3.15E2 0.OOEO 1996 8.08E2 0.OOEO 1997 4.85E2 0.OOEO 1998 3.40E2 0.OOEO 1999 5.60E2 0.OOEO 2000 6.22E2 0.OOEO 2001 6.98E2 0.OOEO 2002 5.65E2 0.OOEO 2003 3.91E2 0.OOEO 2004 5.04E2 0.OOEO 2005 8.74E2 0.OOEO 2006 1.65E3 2.19E2 0 2007 1.68E3 3.42E2 2008 1.67E3 3.13E2 0.OOE0 no detectable measurements S

S S

S o

S Section 3 -Page 8 5 0

S

3.4 MILK In 2008, 47 milk samples were analyzed for low level 1-131 and other gamma emitting radionuclides, 21 at the indicator location and 26 at the control location. Indicator milk location

139 was removed from the program during 2008 due to dairy closure. No new milk animals

were identified by the 2008 McGuire Land Use Census to complement the existing program.

Removal of indicator location 139 is described in reference 6.16. The control location continues to be sampled.

No detectable activity was found in milk samples in 2008 other than naturally-occurring K-40.

Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not

been detected since 1987.

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

Cs-137. Since no activity was detected in 2008, no reporting levels were approached.

Table 3.4 Mean Concentrations of Cs-137 in Milk YEAR Cs-137 Indicator (pCi/1) Cs-137 Control (pCi/I) 1979 2.48E1 6.04E0 1980 1.72E1 4.13E0 1.981 2.04E1 4.15E0 1982 1.21El 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.OOEO 5.60E0 1990 5.30E0 2.60E0 1991 0.OOEO 0.OOEO 1992 O.00E0 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.OOEO 0.OOEO 1995 0.OOEO O.OOEO 1996 0.OOEO 0.OOEO 1997 0.00E0 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.00E0 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO

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

Section 3 - Page 9 0

6 6

6 3.5 BROADLEAF VEGETATION 0 S

In 2008, 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 0 vegetation samples during 2008.

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.

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

Table 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation 0

YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg) 1979 2.19E1 1.93E1 1980 2.30E1 1.92E1 1981 3.04E1 2.02E1 1982 2.46E1 1.22E1 1983 9.07E0 7.85E0 1984 1.02E1 1.05El 1985 8.05E0 2.37E-2 1986 4.03E1 1.27E1 1987 2.20E1 1.70E1 1988 3.90E1 3.40E1 1989 9.60E1 0.OOEO 1990 4.OOEI 0.OOEO 1991 3.30E1 0.OOEO 1992 4.90E1 0.OOEO 1993 1.60El 0.OOEO 1994 0.OOEO 0.OOEO 1995 0.OOEO 0.OOEO 1996 0.OOEO 0.OOEO 1997 O.OOEO O.OOEO 1998 0.OOEO 2.69E1 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO O.OOEO 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 2.98E1 O.OOEO 2007 1.34E1 0.OOEO 2008 0.OOEO 0.OOEO 0.OOEO = no detectable measurements S

Section 3 - Page 10 5 0

0 0 O 3.6 FOOD PRODUCTS

In 2008, 12 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media.

No detectable activity has been detected in this

media Since 1987. Table 3.6 shows Cs-137 indicator highest annual means with preoperational data. Since no activity was

detected in 2008, no reporting levels were

approached.

0 0

Table 3.6 Mean Concentrations of Cs-137 in Food Products S

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.OOEO 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 0.00E0 2002 0.OOEO 2003 0.OOEO

2004 0.OOEO 2005 0.OOEO 2006 0.OOEO 2007 0.OOEO 2008 0.OOEO 0.OOEO = no detectable measurements S

D Section 3 -Page 11 D

D

S 0

3.7 FISH S

In 2008, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator 0 location and six at the control location.

Figure 3.7-1 shows Cs-137 highest annual mean indicator and control location concentrations S with comparisons to 5% of the reporting level. Figure 3.7-2 shows Co-60 highest annual mean 0 indicator and control location concentrations also with comparisons to 5% of the reporting level. 0 Table 3.7 gives indicator location highest annual means since 1980 for all radionuclides detected since the analysis change in 1988. 0 0

Co-58 activity was not detected in 2008 in any SD of the indicator or control samples. Cs-137 activity was detected in four of the six indicator 0

samples taken at Location 129 with a mean 6 concentration of 12.4 pCi/kg, which is 0.62% of 0 the reporting level. Cs-137 was not detected in 0 any of the six control samples.

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

0 0

I 6

I I

Section 3 - Page 12 I

I I

0 0

0 Figure 3.7-1 pCilkg Concentration of Cs-137 in Fish 0 140 0 120 S

S 100 80 0

60-S 40-20-0 ! 1 ! I 1 1 ! 1 ! .

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 I -U Indicator Location ControlLocation - 5% of Reporting Level I Figure 3.7-2 S

0 pCi/kg Concentration of Co-60 in Fish S 600 -----

500-0 0 400-------- --- -------- ----- -

S 300 0

200 0 100 - - -

0 0 - .. -, . _..A* .. . - . * * -

S 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 2008 S--- IndicatorLocation --- Control Location - 5%of Reporting Level I 0

0 Section 3 - Page 13 0

Table 3.7 Mean Concentrations of Radionuclides in Fish (pCi/kg) 0 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 -2.71 E0 -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 1.11El -1.32E0 6.03E 0 1984 3.61E0 1.45E2 2.82E1 3.11El 4.38E 1 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 1.20E1 7.70E1 0.00E0 2.70E1 3.60E1 1989 9.OOEl 4.05E2 2.99E2 1.10El 3.50E1 1990 0.OOEO 5.60E1 4.10E1 0.OOEO 3.30E1 1991 6.20E0 1.40El 6.50E1 5.90E0 2.60E1 1992 0.00E0 0.OOEO O.OOEO 0.OOEO 2.90E1 1993 0.OOEO 8.20E1 1.30E1 0.OOEO 1.60El 1994 0.00E0 0.OOEO 0.OOEO 0.OOEO 3.10EI 1995 0.OOEO 0.OOEO 0.OOEO 0.00E0 2.70E1 1996 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.78E1 1997 O.OOEO 0.OOEO 0.OOEO 0.OOEO 1.62E1 1998 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.21E1 1999 0.OOEO 3.53E1 0.OOEO 0.OOEO 2.1OE1 2000 0.OOEO 4.28E1 0.OOEO 0.OOEO 2.34E1 2001 O.OOEO 1.32E1 0.OOEO 0.OOEO 3.04E1 2002 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.33E1 2003 0.OOEO 0.OOEO 0.OOEO O.00E0 3.05E1 0 2004 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2006 0.00E0 0.OOEO 0.OOEO 0.00E0 1.08El 2007 0.00E0 0.00E0 0.00E0 0.00E0 2.11E1 2008 0.00E0 0.00E0 0.00E0 0.OOEO 1.24E1 0.OOEO = no detectable measurements All negative values have been replaced with zeros for calculational purposes 0 S

0 0

Section 3 -Page 14 0 0

0

0 3.8 SHORELINE SEDIMENT S In 2008, six shoreline sediment samples were analyzed, four from two indicator locations S and two at the control location.

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

0 Cs-137 activity was detected in two of the four indicator samples taken. The shoreline sediment location with the highest annual 0 mean was Location 130 with a mean concentration of 177 pCi/kg. Cs-137 was 0 not detected in any control location samples.

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

S 0 Figure 3.8-1 0

pCi/kg Concentration of Cs-137 in Shoreline Sediment 0 500-0 45;0 4 00 0 35)0 0 3 00 0

0 2502 S

0 50 114 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 4 l--ndicator Loca--on Control-Location I -

There is no reportinglevel for Cs-137 in shoreline sediment Section 3 - Page 15

0 0

0 Figure 3.8-2 pCi/kg Concentration of Co-60 in Shoreline Sediment 0

300 0 250 0

0 200 0

150 ------------- - - - - - - - - - -

S 100 0 0

0 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 0

-U-- Indicator Location 0 Control Location 0 0

There is no reportinglevel for Co-60 in shorelinesediment 6 0

Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg) 0 YEAR Mn-54 Indicator Co-58 Co-60 Cs-134 Cs-137 0 Indicator Indicator Indicator Indicator 1979 -1.07E1 2.25E1 -6.50E0 0.OOEO 1.20E1 1980 1.06El -8.74E0 2.36E1 -3.53E0 1.44E1 1981 2.13E1 1.20El 8.21E0 3.97E1 3.36E1 0 1982 5.38E1 1.66E1 -1.69E0 7.67E1 4.40E1 0 1983 4.40E0 3.43E1 2.12E1 7.65E1 8.02E1 1984 1.19El 7.11E1 3.04E1 3.34E1 9.13E1 0 1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 0 1986 1987 1.37E1 0.OOEO 1.02El 1.06E2 1.16El 2.10El 6.35E1 4.20E1 1.53E2 1.65E2 0

1988 6.50E0 9.20E1 1.20E1 9.1OEO 2.66E2 O 1989 2.90E1 3.80E1 2.90E1 5.30E1 6.50E1 O 1990 3.80E1 2.70E1 1.68E2 O.OOEO 6.10E1 1991 2.80E1 5.30E1 1.31E2 0.OOEO 1.03E2 O 1992 9.40E0 0.OOEO 5.10EI 9.20E0 8.60E1 O 1993 0.OOEO 2.20E1 8.60E1 0.00E0 9.30E1 1994 4.10El O.OOEO 0.00E0 0.OOEO 8.OOEl 1995 1.70El 0.OOEO 2.30E1 0.OOEO 1.38E2 1996 2.90E1 1.78E1 3.50E1 0.OOEO 1.47E2 1997 0.OOEO 0.00E0 1.11 E2 3.10E1 1.36E2 1998 0.OOEO 0.OOEO 5.21E1 O.OOEO 9.97E1 1999 0.00E0 2.47E1 8.49E1 0.00E0 6.51E1 2000 0.OOEO 3.04E1 0.OOEO O.OOEO 1.08E2 Section 3 - Page 16

0'

/

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

0 0

0 S

0 0

0 Section 3 - Page 17

0 0

0 3.9 DIRECT GAMMA RADIATION In 2008, 161 TLDs were analyzed, 157 at indicator 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 0 control location was 94.0 milliroentgen.

0 Figure 3.9 and Table 3.9 show TLD inner ring (site boundary), outer ring (4-5 miles), and control 0 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 2008 was 2.69E-1 millirem, which is 0.40% 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.

0 Figure 3.9 0

mR/yr Direct Gamma Radiation (TLD) Results 0 200 0 180 160 0 140 0

120 0 100 ---

0 6

6 60 19 1993 1995r 1 1 6 40 0

20 6

0 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2 001 2007 2003 2005

- A- InnerRing -U-- Outer Ring 4- ControlI There is no reportinglevel for DirectRadiation (TLD)

Section 3 - Page 18

Table 3.9 Direct Gamma Radiation (TLD) Results YEAR Inner Ring Average Outer Ring Average Control (mR/yr) (mR/'yr) (mR/yr) 1979 7.91E1 8.82E1 8.32E1 1980 7.54E1* 8.29E1* 1.05E2

1981 1.01E2 9.31E1 1.05E2 1982 8.95E1 8.97E1 1.10E2 1983 1.16E2 1.14E2 1.30E2 1984 7.85E1 7.83E1 9.02E1 1985 9.54E1 9.69E1 1.27E2 1986 8.91E1 9.35E1 1.10E2 1987 7.58E1 7.71E1 1.23E2 1988 6.03E1 6.42E1 5.48E1 1989 5.37E1 5.30E1 7.55E1 1990 4.34E1 4.78E1 6.25E1 1991 5.14E1 5.59E1 6.80E1 1992 5.65E1 5.55E1 7.60E1 1993 5.61E1 5.71E1 7.20E1 1994 6.40E1 6.93E1 9.55E1

!*1995 8.36E1 8.25E1 1.08E2 1996 7.18E1 7.02E1 9.88E1 1997 6.22E 1 6.68E 1 9.45E 1 1998 6.59E1 6.32E1 8.69E1 1999 6.23E 1 6.05E 1 8.96E 1 2000 6.50E 1 6.08E 1 8.97EI 2001 6.51El 6.22E1 9.33E1 2002 6.57E 16.43E1 9.48E1 2003 6.74E1 6.45E1 9.20E1 2004 6.46E 1 6.33E1 9.16E1

2005 6.62E 1 6.34E1 9.44E1 2006 6.75E1 6.58E1 9.17E 1 2007 6.84E1 6.60E 1 9.OOE1

Average (1998 - 2007) 6.52E1 6.35E1 9.19E1 2008 6.69E1 6.58E1 9.14E1

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

0 0

O ~Section 3 -Page 19 0

0

0 0

0 3.10 LAND USE CENSUS 0 0

The land use census was conducted May 20 and May 21, 2008 as required by SLC 16.11.14. 0 Table 3.10 summarizes census results. A map indicating identified locations is shown in Figure 3.10.

0 0

During the 2008 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. 0 No environmental program changes were required as a result of the 2008 land use census. 0 0

Table 3.10 McGuire 2008 Land Use Census Results 0

0 Sector Distance Sector Distance 0 (Miles) (Miles) 0 Nearest Residence 2.53 Nearest Residence 1.45 2.79 S Nearest Garden 3.12 0

N Nearest Garden (irrigated)

Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 1.23 Nearest Residence 2.56 0 2.53 SSW Nearest Garden 2.94 NNE Nearest Garden (irrigated)

Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 1.21 Nearest Residence 1.85 0 NE Nearest Garden 1.80 SW Nearest Garden 4.00 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.57 Nearest Residence 1.01 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 0 E Nearest Garden 1.86 W Nearest Garden 1.23 Nearest Milk Animal (COW) 2.49 Nearest Milk Animal - 0 Nearest Residence 0.65 Nearest Residence 0.88 0 ESE Nearest Garden Nearest Milk Animal 1.15 WNW Nearest Garden Nearest Milk Animal 1.73 0

Nearest Residence 0.67 Nearest Residence 0.95 0

SE Nearest Garden 1.18 NW Nearest Garden 1.68 0 Nearest Milk Animal Nearest Milk Animal -

0 Nearest Residence 1.06 Nearest Residence 1.48 NNW Nearest Garden (irrigated) 1.69 0

SSE Nearest Garden 2.18 Nearest Milk Animal - Nearest Milk Animal - 0

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

0 0

Section 3 - Page 20 0

0

Figure 3.10 McGuire Nuclear Station 2008 Land Use Census Map mn Legend Residence A Garden

- Milk Animal

/~/Public Roads

/\/ Railroad

>*', County Boundary V'Vater Apprcxmate Iocaton cf features sno '*

0 0-5 1 2 Miles SMounrtain I Island Prjedi nN sS A28

-Ise May 2008 Section 3 - Page 21

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 2008 MNS REMP samples. The primary purpose of estimating 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 0background 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 water, fish, and shoreline sediment sample results are reported in Table 4.1-A. The

individual critical population and pathway dose calculations are reported in Table 4.1-B.

0REMP-based dose estimates are not reported for airborne radioiodine or milk sample types because no radionuclides other than naturally occurring K-40 and Be-7 were

detected in the samples. Dose estimates are not reported for surface water because sampled surface water is not considered to be a potable drinking water source 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.

0 The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2008 was 1.63E-1 mrem 0to 0 the maximum exposed child liver 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

Section 4 -Pagel1 0

0

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.

4.3 COMPARISON OF DOSES 0 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.

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

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 2008 environmental sample results was 1.63E-1 mrem to the child liver. The maximum total organ dose of 2.50E-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 2.69E-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 40CFR190 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of MNS are being maintained well within regulatory limits.

Section 4 - Page2 0 0

0

0 0

TABLE 4.1-A 0 Page 1 of 3 0 MCGUIRE NUCLEAR STATION 0 2008 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

0 LIQUID RELEASE PATHWAY 0 Critical Maximum Dose (3)

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

Skin Environmental Teen Shoreline Sediment 130 (0.52 mi SW) 4.65E-04 Skin Effluent Teen Shoreline Sediment Discharge Pt. 1.02E-03 Bone Environmental Child Fish 129 (0.51 mi ENE) 2.80E-02 Bone Effluent Child Fish Discharge Pt. 5.21E-02 Liver Environmental Child Drinking Water 101 (3.31 mi E) 1.63E-01 Liver Effluent Child Drinking Water 3.31 mi E 2.50E-01 T. Body Environmental Child Drinking Water 101 (3.31 mi E) 1.40E-0 1 T. Body Effluent Child Drinking Water 3.31 mi E 2.04E-01 Thyroid Environmental Child Drinking Water 101 (3.31 mi E) 1.36E-01 Thyroid Effluent Child Drinking Water 3.31 mi E 1.95E-01 0

0 Kidney Environmental Child Drinking Water 101 (3.31 mi E) 1.44E-0 1 Kidney Effluent Child Drinking Water 3.31 mi E 2.13E-01 0

Lung Environmental Child Drinking Water 101 (3.31 mi E) 1.39E-01 0 Lung Effluent Child Drinking Water 3.31 mi E 2.02E-01 S GI-LLI Environmental Child Drinking Water 101 (3.31 mi E) 1.36E-01 0 GI-LLI Effluent Child Drinking Water 3.31 mi E 1.98E-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.

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

0 0

Section 4 - Page 3

0 0

Page 2 of 3 0

GASEOUS RELEASE PATHWAY 0

S 0

IODINE, PARTICULATE, and TRITIUM 0 S

0 0

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

0 Section 4 - Page 4

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

Beta Environmental Not Sampled 0 Beta Effluent N/A Noble Gas 0.5 mi. NNE 1.72E-02 0

Gamma Environmental Not Sampled 0 Gamma Effluent N/A Noble Gas 0.5 mi. NNE 4.73E-02 0

0 0

0 S

0 0

0 0 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dosefor 2008 based on EnvironmentalMeasurements (rnrem) for McGuire Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 O.OOE+00 Milk O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL O.OOE+00 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 0.00E+00 Child Airborne 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Drinking Water O.OOE+00 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 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 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 2.80E-02 2.85E-02 5.66E-03 1.71E-03 1.04E-02 4.85E-03 1.88E-03 O.OOE+00 Shoreline Sediment 0.00E+00 O.OOE+00 8.33E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 9.71E-05 TOTAL 2.80E-02 1.63E-01 1.40E-01 1.36E-01 1.44E-01 1.39E-01 1.36E-01 9.71E-05 Teen 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 7.OOE-02 7.OOE-02 7.OOE-02 7.00E-02 7.OOE-02 7.OOE-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fish 2.22E-02 3.16E-02 1.24E-02 2.07E-03 1.21E-02 5.98E-03 2.49E-03 O.OOE+00 Shoreline Sediment 0.00E+00 O.OOE+00 3.98E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 4.65E-04 TOTAL 2.22E-02 1.02E-01 8.28E-02 7.21E-02 8.21E-02 7.60E-02 7.25E-02 4.65E-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 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 O.OOE+00 Milk O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fish 2.08E-02 3.1 1E-02 2.13E-02 2.69E-03 1.23E-02 5.90E-03 3.24E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 7.14E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.33E-05 TOTAL 2.08E-02 1.30E-01 1.21E-01 1.02E-01 1.12E-01 1.05E-01 1.02E-01 8.33E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6 IsisOOOOOO0OOOOO*1**OOOOOOOOOOOOOOOOOOOOOOOOOOOOO0 000 0*

McGuireNuclear Station Dosefrom Drinking Water Pathwayfor 2008 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.OOE+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 2.9 1E-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.OOE-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 0.00E+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 6.11 E-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 1294 0.OOE+00 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 Dose Commitment (mrem) = 0.OOE+00 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 1.32E-01 Section 4 - Page 7

McGuire Nuclear Station Dosefrom Drinking Water Pathwayfor 2008 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/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 0.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.OOE+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.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+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 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 1294 0.OOE+00 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 Dose Commitment (mrem) = 0.OOE+00 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 1.34E-01 Section 4 - Page 8

McGuire Nuclear Station Dose from Fish Pathwayfor 2008 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 = 1357 pCi/l x 0.9 = 1221 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+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 0.00E+00 0.00E+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 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.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-06 129 12.4 2.80E-02 2.68E-02 3.95E-03 0.00E+00 8.73E-03 3.14E-03 1.68E-04 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 128 1221 0.OOE+00 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 Dose Commitment (mrem) = 2.80E-02 2.85E-02 5.66E-03 1.71E-03 1.04E-02 4.85E-03 1.88E-03 Section 4 - Page 9

McGuire NuclearStation Dosefrom Shoreline Sediment Pathwayfor 2008 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 (river2 shoreline - location 130)

Sediment Surface Mass = 40 kg/m 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 ) x 2

Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration 2

(mrem/hr per pCi/m ) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.OOE-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.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 177 8.33E-05 9.71E-05 Dose Commitment (mrem) = 8.33E-05 9.71E-05 Section 4 - Page 10 OOOOQOQOOOOOSOOOOQOOOOQQOOOQOQQ010O

McGuire Nuclear Station Dose from Drinking Water Pathwayfor 2008 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 O.OOE+00 0.00E+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 0.00E+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 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81E-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-400 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.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 0.00IE+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 0.00E+00 0.OOE+00 0.OOE+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.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-07 101 1294 0.OOE+00 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 Dose Commitment (mrem)= 0.OOE+00 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 7.OOE-02 Section 4 - Page 1

McGuire Nuclear Station Dose from Fish Pathwayfor 2008 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81E-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 CsT137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 129 12.4 2.22E-02 2.96E-02 1.03E-02 0.OOE+00 1.01E-02 3.91 E-03 4.21 E-04 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 128 1221 0.OOE+00 2.07E-03 2.07E-03 2.07E-03 2.07E-03 2.07E-03 2.07E-03 Dose Commitment (mrem) = 2.22E-02 3.16E-02 1.24E-02 2.07E-03 1.21E-02 5.98E-03 2.49E-03 Section 4 - Page 12

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McGuireNuclear Station Dosefrom Shoreline Sediment Pathwayfor 2008 Data Maximum Exposed Teen Shoreline Recreation 67 hr (in one year)

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

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

Sediment Surface Mass = 40 kg/mr Teen Dose from Shoreline Sediment Pathway (norem) = Shoreline Recreation (hr) x External 2 2 Dose Factor (mrem/hr per pCi/mr ) x Shore Width Factor x Sediment Surface Mass (kg/M ) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/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 0.00E+00 0.OOE+00 Co-58 7.OOE-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.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 177 3.98E-04 4.65E-04 Dose Commitment (mrem) = 3.98E-04 4.65E-04 Section 4 - Page 13

McGuireNuclear Station Dosefrom Drinking Water Pathwayfor 2008 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

Usage (intake in one year) = 730 1 Highest Annual Net Mean In2estion 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 1.51 E-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 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.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.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 O-OO.+f00 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 0.00E+~0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 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 1.2 1E-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.OOE+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 1294 0.OOE+00 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 Dose Commitment (mrem) = 0.OOE+/-00 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 Section 4 - Page 14 000 0 0 0 0000 000000000000 00

McGuire Nuclear Station Dosefrom Fish Pathwayfor 2008 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/l = 1357 pCi/I x 0.9 = 1221 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.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+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.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 0.00E+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-06 129 12.4 2.08E-02 2.84E-02 1.86E-02 0.OOE+00 9.63E-03 3.20E-03 5.49E-04 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 128 1221 0.OOE+00 2.69E-03 2.69E-03 2.69E-03 2.69E-03 2.69E-03 2.69E-03 Dose Commitment (mrem)= 2.08E-02 3.11E-02 2.13E-02 2.69E-03 1.23E-02 5.90E-03 3.24E-03 Section 4 - Page 15

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2008 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/m 2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External 2 2 Dose Factor (mrem/hr per pCi/m ) x Shore Width Factor x Sediment Surface Mass (kg/m ) x Sediment Concentration (pCi/kg)

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

(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 0.00E+00 0.00E+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.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 177 7.14E-05 8.33E-05 Dose Commitment (mrem) = 7.14E-05 8.33E-05 Section 4 - Page 16 000 0 000 0 00 00 0 000 0 0000 00 00 *0 0 00 0 00 00 00 0 00 00

0 0

0 5.0 QUALITY ASSURANCE 0

5.1 SAMPLE COLLECTION 0

0EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental 0sample collections as specified by approved sample collection procedures.

0 5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified

by approved analysis procedures. EnRad Laboratories is located in Huntersville, North Carolina, at Duke Energy Corporation's Environmental Center.

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

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0

5.4.1 DAILY QUALITY CONTROL 0EnRad Laboratories has an internal quality assurance program which monitors

each type of instrumentation for reliability and accuracy. Daily quality control 0checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION

National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations

are performed and documented should calibration verification data fall out of

limits.

0 0

Section 5 -Pagel1 0

0

0 0

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

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2008. 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 2008 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 2008 is documented in Table 5.0-B.

0 5.7 DUKE ENERGY AUDITS 0 0

The McGuire Radiation Protection Section was audited by the Quality Assurance Group in 2008. There were some TLD laboratory procedural enhancements identified as a result of the audit (reference 6.17).

EnRad Laboratories was audited by the Quality Assurance Group in 2008. There were some REMP recommendations as a result of the 2008 audit (reference 6.19).

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 5 0

The McGuire Nuclear Station Radiological Environmental Monitoring Program was not audited by the NRC in 2008. The program was audited in 2007 (Reference 6.12).

There were no findings identified by the audit.

5.9 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM S S

EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. EnRad Laboratories sends air, surface water, milk, crops, vegetation, Section 5 -Page 2 0 0

0

0 0

0 0 sediment, and fish samples which have been collected to the State of North Carolina S Radiation Protection Section.

0 5.10 TLD INTERCOMPARISON PROGRAM S 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 dosimeters quarterly and sends them to the Radiation Dosimetry and Records 0 group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in S Table 5.0-C.

0 5.10.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM 0 The State of North Carolina Radiation Protection Section suspended this 0 program during 2007 as described in reference 6.18.

0 5.10.3 INTERNAL CROSSCHECK (DUKE ENERGY) 0 0 Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of S the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-C.

S S

Section 5 - Page 3

0 0

0 TABLE 5.0-A 0 DUKE ENERGY 0 INTERLABORATORY COMPARISON PROGRAM S

2008 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES S

0 Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one 0

analysis of the cross-check was performed. 0 If applicable, footnote explanations are included following this data table.

S Gamma in Water 3. 5 liters 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S

Date Range Value Value Status S 3/5/2008 Q081GWR Cr-51 pCi/i 0.91- 1.61 E4 pCi/l 1.21 E4 pCi/l 1.22 E4 3 Pass S

Co-57 2.94-5.21 E2 3.91 E2 4.21 E2 3 Pass 0 Co-60 1.64-2.91 E3 2.19 E3 2.17 E3 3 Pass S Sr-85 Y-88 1.84-3.26 2.97-5.27 E3 E3 2.45 3.96 E3 E3 2.43 3.95 E3 E3 3

3 Pass Pass 0

Cd-109 0.84-1.49 E4 1.12 E4 1.13 E4 3 Pass S Sn-ll3 1.50-2.66 E3 2.00 E3 2.01 E3 3 Pass 0 Te-123M 3.88-6.88 E2 5.17 E2 5.18 E2 3 Pass Cs-137 1.32-2.35 E3 1.76 E3 1.71 E3 3 Pass 0 S

5/15/2008 Q082GWSL Cr-51 Mn-54 1.40-2.48 6.18 - 10.96 E5 E4 1.87 8.24 E5 E4 1.94 8.79 E5 E4 3

3 Pass Pass S

Co-58 3.69-6.54 E4 4.92 E4 4.88 E4 3 Pass S Fe-59 6.69- 11.87 E4 8.92 E4 9.29 E4 3 Pass S Co-60 Zn-65 4.44-7.88 5.92 - 10.49 E4 E4 5.93 7.89 E4 E4 6.04 8.16 E4 E4 3

3 Pass Pass S

Cs-134 3.33-5.91 E4 4.45 E4 4.00 E4 3 Pass S Cs-137 4.80-8.52 E4 6.41 E4 6.31 E4 3 Pass S Ce-141 1.55-2.74 E5 2.06 E5 2.07 E5 3 Pass S

S Gamma in Water 1.0 liter 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0

pCi/l pCi/l pCi/l 0 3/5/2008 Q081GWR Cr-51 0.91- 1.61 E4 1.21 E4 1.24 E4 3 Pass 0 Co-57 Co-60 2.94-5.21 E2 1.64-2.91 E3 3.91 E2 2.19 E3 4.12 E2 2.17 E3 3 Pass 3 Pass 0

Sr-85 1.84-3.26 E3 2.45 E3 2.41 E3 3 Pass 0 Y-88 2.97-5.27 E3 3.96 E3 3.99 E3 3 Pass 0 Cd-109 0.84-1.49 E4 1.12 E4 1.12 E4 3 Pass Sn-113 1.50-2.66 E3 2.00 E3 2.02 E3 3 Pass 0 Te-123M 3.88-6.88 E2 5.17 E2 5.28 E2 3 Pass 6 Cs-137 1.32-2.35 E3 1.76 E3 1.72 E3 3 Pass 6

6 Section 5 - Page 4 0 6

6

0 0

Gamma in Water 1.0 liter, continued 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/i pCi/I pCi/1 9 5/15/2008 Q082GWSL Cr-51 1.40-2.48 E5 1.87 E5 1.94 E5 3 Pass Mn-54 6.18-10.96 E4 8.24 E4 8.84 E4 3 Pass Co-58 3.69-6.54 E4 4.92 E4 4.85 E4 3 Pass Fe-59 6.69- 11.87 E4 8.92 E4 9.43 E4 3 Pass Co-60 4.44-7.88 E4 5.93 E4 6.04 E4 3 Pass 0 Zn-65 5.92 - 10.49 E4 7.89 E4 8.22 E4 3 Pass 0 Cs-134 Cs-137 3.33- 5.91 E4 4.80-8.52 E4 4.45 E4 6.41 E4 3.90 6.31 E4 E4 3

3 Pass Pass Ce-141 1.55- 2.74 E5 2.06 E5 2.03 E5 3 Pass 0 Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/i pCi/I pCi/l 5/15/2008 Q082GWSL Cr-51 1.40-2.48 E5 1.87 E5 1.92 E5 3 Pass Mn-54 6.18 - 10.96 E4 8.24 E4 8.76 E4 3 Pass 0 Co-58 3.69-6.54 E4 4.92 E4 4.79 E4 3 Pass Fe-59 6.69- 11.87 E4 8.92 E4 9.40 E4 3 Pass 0 Co-60 4.44-7.88 E4 5.93 E4 6.03 E4 3 Pass 0 Zn-65 5.92 - 10.49 E4 7.89 E4 8.28 E4 3 Pass 0 Cs-134 3.33- 5.91 E4 E4 4.45 6.41 E4 E4 3.77 6.22 E4 E4 3

3 Pass Pass Cs-137 4.80-8.52 0 Ce-141 1.55-2.74 E5 2.06 E5 2.01 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/l pCi/1 1.20 E4 3 Pass 3/5/2008 Q081GWR Cr-51 0.91- 1.61 E4 1.21 E4 Co-57 2.94-5.21 E2 3.91 E2 4.14 E2 3 Pass Co-60 1.64-2.91 E3 2.19 E3 2.20 E3 3 Pass 0 Sr-85 Y-88 1.84-3.26 E3 2.97-5.27 E3 2.45 E3 3.96 E3 2.34 4.00 E3 E3 3

3 Pass Pass Cd-109 0.84-1.49 E4 1.12 E4 1.17 E4 3 Pass Sn-i 13 1.50-2.66 E3 2.00 E3 1.99 E3 3 Pass Te-123M 3.88- 6.88 E2 5.17 E2 5.43 E2 3 Pass Cs-137 1.32-2.35 E3 1.76 E3 1.65 E3 3 Pass 0

0 Section 5 - Page 5 0

0 0

0 Gamma in Water 0.25 liter, continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status pCi/I pCi/I pCi/I 5/15/2008 Q082GWSL Cr-51 1.40- 2.48 E5 1.87 E5 1.94 E5 3 Pass 0 Mn-54 6.18 - 10.96 E4 8.24 E4 8.80 E4 3 Pass Co-58 3.69-6.54 E4 4.92 E4 4.82 E4 3 Pass Fe-59 6.69- 11.87 E4 8.92 E4 9.44 E4 3 Pass Co-60 4.44-7.88 E4 5.93 E4 6.08 E4 3 Pass Zn-65 5.92 - 10.49 E4 7.89 E4 8.15 E4 3 Pass Cs-134 3.33- 5.91 E4 4.45 E4 3.89 E4 3 Pass Cs-137 4.80-8.52 E4 6.41 E4 6.23 E4 3 Pass Ce-141 1.55-2.74 E5 2.06 E5 2.04 E5 3 Pass 0 0

Gamma in Water 0.05 liter 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status 0 pCi/I pCi/I pCi/I 3/5/2008 Q081GWR Cr-51 0.91-1.61 E4 1.21 E4 1.25 E4 3 Pass Co-57 2.94-5.21 E2 3.91 E2 4.15 E2 3 Pass Co-60 Sr-85 1.64-2.91 1.84-3.26 E3 E3 2.19

2.45 E3 E3 2.16 2.40 E3 E3 3

3 Pass Pass 0

Y-88 2.97-5.27 E3 3.96 E3 3.96 E3 3 Pass Cd-109 0.84-1.49 E4 1.12 E4 1.08 E4 3 Pass 0 Sn-113 Te-123M 1.50-2.66 3.88-6.88 E3 E2 2.00 5.17 E3 E2 2.04 5.02 E3 E2 3

3 Pass Pass 0

Cs-137 1.32-2.35 E3 1.76 E3 1.74 E3 3 Pass S Gamma in Filter 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 2/22/2008 A22337-48 Cr-51 pCi 0.78- 1.38 E5 pCi 1.04 E5 pCi 1.07 E5 3 Pass 0

Mn-54 1.10-1.96 E4 1.47 E4 1.58 E4 3 Pass 0 Co-58 1.03 -1.82 E4 1.37 E4 1.39 E4 3 Pass 0 Fe-59 1.73- 3.06 E4 2.30 E4 2.38 E4 3 Pass Co-60 2.64- 4.68 E4 3.52 E4 3.67 E4 3 Pass 0

Zn-65 1.64-2.90 E4 2.18 E4 2.23 E4 3 Pass 0 Cs-134 1.42-2.51 E4 1.89 E4 1.81 E4 3 Pass 0 Cs-137 1.61-2.86 E4 2.15 E4 2.10 E4 3 Pass Ce-141 4.89-8.67 E4 6.52 E4 6.57 E4 3 Pass 0

0 0

0 Section 5 - Page 6 0 0

0

0 0

0 0 Gamma in Filter,continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 pCi pCi pCi 4 6/19/2008 E6092-37 Cr-51 Mn-54 1.12-2.66 E2 1.27-2.25 E2 1.73 E2 1.69 E2 1.58 E2 1.57 E2 2 Pass 2 Pass Co-58 5.81 - 10.31 El 7.75 El 6.29 El 2 Pass S Fe-59 0.86- 1.53 E2 1.15 E2 1.02 E2 2 Pass 0 Co-60 Zn-65 0.98- 1.74 1.19-2.11 E2 E2 1.31 1.59 E2 E2 1.17 1.36 E2 E2 2

2 Pass Pass 0 Cd-109 0.00-0.00 El 0.OOE+00 5.69 El 2/2 High ')

0 Cs-134 7.21- 12.78 El 9.61 El 8.29 E1 2 Pass Cs-137 1.10- 1.94 E2 1.46 E2 1.26 E2 S Ce-141 1.64-2.90 E2 2.18 E2 1.78 E2 2 Pass 2 Pass 0

0 Iodine 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 5/19/2008 Q082LIWI 1-131 0.97- 1.72 E2 1.30 E2 1.05 E2 3 Pass 0

5/19/2008 Q082LIW2 1-131 1.38 - 2.45 El 1.84 El 1:30 El 2/3 Low(2 5/19/2008 Q082LIW3 1-131 1.92- 3.41 E3 2.56 E3 2.24 E3 3 Pass 0

0 0 Iodine in Milk S Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0 pCi/l pCi/l pCi/l 8/13/2008 Q083LIM1 1-131 2.16-3.83 El 2.88 El 2.50 El 3 Pass 0 8/13/2008 Q083LIM2 1-131 0.91- 1.62 E2 1.22 E2 1.11 E2 3 Pass 0

8/13/2008 Q083L1M3 1-131 4.68 - 8.30 El 6.24 E1 5.61 El 3 Pass 0

0 Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 9/18/2008 E6299-37 1-131 6.62 - 12.07 E1 8.94 E1 10.83 El 3 Pass 0

0 0 Section 5 - Page 7

0 S

0 Beta Air Particulate S

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status S 6/19/2008 E6094-37 Cs-137 pCi 1.49-2.63 E2 pCi 1.98 E2 pCi 1.79 E2 3 Pass S

S 6/19/2008 E6095-37 Cs-137 3.77-6.68 E1 5.02 E1 5.12 El 3 Pass S S

Beta in Water S Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range pCi/l Value pCi/i Value pCi/I Status S

5/13/2008 Q082ABW1 Cs-137 3.11-5.52 El 4.15 El 3.67 El 3 Pass S S

5/13/2008 Q082ABW2 Cs-137 5.52 9.78 El 7.36 El 7.09 El 3 Pass S

5/13/2008 Q082ABW3 Cs-137 2.10 - 3.73 El 2.80 El 2.69 El 3 Pass S S

Tritium in Water S

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status S 3/5/2008 Q081TWRI H-3 pCi/I 5.64 - 10.01 E3 pCi/l 7.53 E3 pCi/1 7.12 E3 3 Pass S

S 3/5/2008 Q081TWR2 H-3 0.80 - 1.42 E3 1.07 E3 0.96 E3 3 Pass S 3/5/2008 Q081TWR3 H-3 N/A 0.OOE+00 0.OOE+00 3 Pass S

0 5/15/2008 Q082TWSI H-3 4.12 - 7.30 E3 5.49 E3 4.79 E3 3 Pass S 5/15/2008 Q082TWS2 H-3 2.11- 3.74 E4 2.81 E4 2.50 E4 3 Pass S 0

0 S

S S

0 S

S S

Section 5 - Page 8 S S

S

Table 5.0-A Footnote Explanations (1) Gamma in Filter, Sample ID E6092-37, Reference Date 6/19/2008 0 Cd-109 was identified in the cross-check sample and reported. The cross check 0 supplier does not include this radionuclide on the certificate of analysis for this cross-check sample. The radionuclide Cd-109 was determined to be a misidentification by the software and was determined not to be present in the 0 cross-check sample. PIP G-09-00236 was written.

S 0 (2) Iodine in Water, Sample ID Q08LIW2, Reference Date 5/19/2008 0 Three results for this cross-check were reported. All three of the reported results trended low, with two of the results failing. PIP G-09-00329 was written.

0 0

0 S

0 0

S 0

0 0

Section 5 - Page 9

0 0

0 TABLE 5.0-B 0 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) 0 QUIK M T

RESPONSE PROGRAM 0 2008 PROFICIENCY TEST RESULTS FOR 0 ENRAD LABORATORIES 0 ERA LABORATORY CODE: D242401 0

0 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates 0 as described in the "Quik" Response instruction package within the study period. Proficiency test data 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 0

Gamma Emitters in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status 0 pCi/I pCi/1 pCi/I 0 1/8/2007 120507A* Ba-133 7.63 - 9.96 E1 9.05 E1 8.99 El Pass Cs-134 7.29 - 9.78 E1 8.89 E1 8.89 El Pass 0

Cs-137 2.08 - 2.56 E2 2.31 E2 2.19 E2 Pass 0 Co-60 0.909 - 1.13 E2 1.01 E2 1.01 E2 Pass Zn-65 3.15 - 4.08 E2 3.50 E2 3.53 E2 Pass 0 0

10/6/2006 020608G** Ba-133 5.86 - 7.72 El 7.02 El 7.32 El Pass Cs-134 2.34 - 32.9 El 2.99 El1 2.72 El Pass 0

Cs-137 7.04 - 8.87 E1 7.82 E1 7.40 El Pass 0 Co-60 Zn-65 5.61 2.49

- 7.10

- 3.24 El E2 6.23 2.77 El1 E2 6.62 El 2.79 E2 Pass Pass 0

0 Tritium in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check 0 Date Range Value Value Status pCi/I pCi/I pCi/1 0

1/8/2007 120507A* H-3 0.984 - 1.24 E4 1.13 E4 1.04 E4 Pass 0 7/10/2006 020608G** H-3 3.45 - 4.46 E3 4.05 E3 4.10 E3 Pass 0

0

ERA studyperiod 12/1/2007 - 1/17/2008, ERA data report issue date 1/21/2008 0

- ERA study period2/6/2008 - 3/13/2008, ERA datareport issue date 3/13/2008 0

0 0

Section 5 - Page 10 0 0

0 0

0 0 TABLE 5.0-C 0 2008 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS 0

0 Nuclear Technology Services 0

0 1st Quarter 2008 TLD Delivered Reported Bias Pass/Fail 2nd Quarter 2008 TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 0 102144 102222 71.3 71.3 72.1 72.5 1.12 1.68

<+/-15%

Pass Pass 100405 100415 88.5 88.5 87.2 86.6

-1.47

-2.15

<+/-15%

Pass Pass 0 102229 71.3 74.5 4.49 <+/-15% Pass 100417 88.5 95.4 7.80 <+/-15% Pass S 102345 71.3 73.8 3.51 <+/-15% Pass 100440 88.5 88.9 0.45 <+/--15% Pass 102413 71.3 74.6 4.63 <+/-15% Pass 100471 88.5 87.4 -1.24 <+/-15% Pass 0 Average Bias (B) 3.09 Average Bias (B) 0.68 S Standard Deviation (S) 1.61 Standard Deviation (S) 4.09 Measure Performance IBI+S 4.69 <15% Pass Measure Performance IB +S 4.77 <15% Pass 0

3rd Quarter 2008 4th Quarter 2008 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail 0 Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 0 102163 65.4 62.3 -4.74 <+/-15% Pass 102024 85.0 83.7 -1.53 <+/-15% Pass 101409 65.4 59.1 -9.63 <+/-15% Pass 102013 85.0 83.8 -1.41 <+/-15% Pass 0 100062 65.4 63.5 -2.91 <+/-15% Pass 102053 85.0 81.8 -3.76 <+/-15% Pass 101259 65.4 61.7 -5.66 <+/-15% Pass 102497 85.0 83.7 -1.53 <+/-15% Pass 101209 65.4 60.9 -6.88 <+/-15% Pass 102281 85.0 83.5 -1.76 <+/-15% Pass Average Bias (B) -5.96 Average Bias (B) -2.00 0 Standard Deviation (S) 2.51 Standard Deviation (S) 0.99 Measure Performance IBI+S 8.48 <15% Pass Measure Performance IBI+S 2.99 <15% Pass 0

0 0

S 0

0 0

Section 5 - Page 11 0

Internal Crosscheck (Duke Energy) 1st Quarter 2008 2nd Quarter 2008 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 100733 23.0 23.5 2.17 <+/-15% Pass 100307 12.0 11.3 -5.83 <+/-15% Pass 0 100477 100406 23.0 23.0 22.9 22.5

-0.43

-2.17

<+/-15%

Pass Pass 100477 100733 12.0 12.0 11.1 11.2

-7.50

-6.67

<+/-15%

Pass Pass 0

100863 23.0 23.3 1.30 <+/-15% Pass 100759 12.0 11.3 -5.83 <+/-15% Pass 0 100870 23.0 23.2 0.87 <+/-15% Pass 100041 12.0 10.5 -12.50 <+/-15% Pass 0 100752 23.0 23.5 2.17 <+/-15% Pass 101191 12.0 11.2 -6.67 <+/-15% Pass 101021 23.0 23.0 0.00 <+/-l 5% Pass 101021 12.0 11.4 -5.00 <+/-15% Pass 0 100096 23.0 22.6 -1.74 <+/-15% Pass 100279 12.0 11.1 -7.50 <+/-15% Pass 0 101307 23.0 22.5 -2.17 <+/-15% Pass 100982 12.0 11.3 -5.83 <+/-15% Pass 100412 23.0 23.6 2.61 <+/-l 5% Pass 100019 12.0 11.4 -5.00 <+/-15% Pass 0

Average Bias (B) 0.26 Average Bias (B) -6.83 0 Standard Deviation (S)

Measure Performance IBI+S 1.85 2.11 <15% Pass Standard Deviation (S)

Measure Performance IBI+S 2.18 9.01 <15% Pass 0

g.

0 3rd Quarter 2008 4th Quarter 2008 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail 0 Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 0 102344 15.0 15.4 2.67 <+/-15% Pass 100740 11.0 11.4 3.64 <+/-15% Pass 102372 15.0 15.2 1.331 <+/-15% Pass 100406 11.0 11.3 2.73 <+/-15% Pass 0

102381 15.0 15.0 0.00 <+/-15% Pass 101191 11.0 11.1 0.91 <+/-15% Pass 0 102508 102338 15.0 15.0 14.8 14.9

-1.33

-0.67

<+/-15%

Pass Pass 101021 100279 11.0 11.0 11.3 11.1 2.73 0.91

<+/-15%

Pass Pass 0

102509 15.0 15.3 2.00 <+/-15% Pass 100870 11.0 11.2 1.82 <+/-15% Pass 0 102479 15.0 16.3 8.67 0.00

<+/-15%

Pass Pass 101307 100984 11.0 11.0 11.0 11.8 0.00 7.27

<+/-15%

Pass Pass 0

102369 15.0 15.0 102318 15.0 15.0 0.00 <+/-15% Pass 100019 11.0 11.2 1.82 <+/-15% Pass 0 102329 15.0 15.5 3.33 <+/-15% Pass 100982 11.0 11.4 3.64 <+/-15% Pass 0 Average Bias (B) 1.60 Average Bias (B) 2.55 Standard Deviation (S) 2.90 Standard Deviation (S) 2.05 0 Measure Performance IBI+S I I 4.50 <15% Pass Measure Performance IBI+S 4.59 <15% Pass 0 0

0 0

0 Section 5 - Page 12 0 0

0

0 0

0

6.0 REFERENCES

0

6.1 McGuire Selected License Commitment Manual 0

6.2 McGuire Technical Specifications 6.3 McGuire Updated Final Safety Analysis Report 0

6.4 McGuire Offsite Dose Calculation Manual 6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2007 0

6.6 McGuire Annual Radioactive Effluent Release Report 2008 6.7 Probability and Statistics in Engineering and Management Science, Hines and

Montgomery, 1969, pages 287-293.

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

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual 0Doses to Man from Routine Releases of Reactor Effluents for the Purposes of

Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software,

Canberra Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report (50-369/2007005, 50-370/2007005) 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 0

6.14 Problem Investigation Process Database, V 3.0.33, Duke Power Company, G-07-00399 6.15 Problem Investigation Process Database, V 3.0.33, Duke Power Company, G-04-00134 0

6.16 Problem Investigation Process Database, V 3.0.33, Duke Power Company, G-08-00977 0

6.17 Radiological Effluents Controls Audit 08-22(INOS)(REC)(MNS)

S6.18 Problem Investigation Process Database, V 3.0.33, Duke Power Company, G-07-00366.

0

6.19 Radiological Effluent Controls Audit 08-23(INOS)(REC)(NGO) 0

~Section 6 -Page 1 0

0

0 0

0 S

0 0

0 APPENDIX A 0

0 0 ENVIRONMENTAL SAMPLING 0

0 &

0 ANALYSIS PROCEDURES 0

0 0

0 0 Appendix A - Page 1 0

0 0

0 APPENDIX A 0 o

ENVIRONMENTAL SAMPLING AND 0 ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.

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

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

I. CHANGE OF SAMPLING PROCEDURES 0

Control location 102 (Air Radioiodine, Air Particulate, Vegetation) was added as a replacement for control location 134 (Air Radioiodine, Air Particulate, Vegetation), which was removed from the program (reference 6.14). 0 0

Indicator location 139 (Milk) was removed from the program due to dairy closure (reference 6.16). No new milk animals were identified by the 2008 McGuire Land Use Census to complement the existing program.

II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.

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

0 0

Appendix A -Page 2 5 0

0 0

0 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.

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 0processed with a blank to ensure sample contamination has not occurred.

0 III. CHANGE OF ANALYSIS PROCEDURES

No analysis procedures were changed during 2008.

IV. SAMPLING AND ANALYSIS PROCEDURES 0A.1 0 AIRBORNE PARTICULATE AND RADIOIODINE

Airborne particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a

constant flow rate (in order to compensate for any filter loading) and are set to

sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each

filter. The continuous composite samples were collected from the locations listed

below.

Location 102 = Amity Church Road (9.89 mi. WNW)

Programmaticsampling initiated9/29/2008, 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 134 = East Lincoln Jr. High School (8.77 mi. WNW)

Programmaticsampling terminated9/29/2008, reference 614 Location 192 = Peninsula (2.84 mi. NNE)

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 0composites. The composites were collected monthly from the locations listed below.

0 0

0

Appendix A -Page 3 0

0 0

0 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) 0 Location 136 = Mooresville Municipal Water Supply (12.7 mi. NNE) 0 Location 194 = East Lincoln County Water Supply (6.73 mi. NNW) 0 A.3 SURFACE WATER 0 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 0 below. 0 0

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 0

A.4 MILK 0 Biweekly grab samples were collected at each dairy. A gamma and low-level 0

Iodine-131 analysis was performed on each sample. The biweekly grab samples 0 were collected from the locations listed below. 0 0

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

Programmaticsampling terminated 10/13/2008, reference 616 0 Location 141 = Lynch Dairy - Cows (14.8 mi. WNW) 0 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 0

Location 102 = Amity Church Road (9.89 mi. WNW)

Programmaticsampling initiatedOctober, 2008, reference 6.14 0 Location 120 = Site Boundary (0.46 mi. NNE) 0 Location 125 = Site Boundary (0.38 mi. SW) 0 Location 134 = East Lincoln Junior High School (8.77 mi. WNW)

Programmaticsampling terminatedSeptember, 2008, reference 6.14 0 Location 193 = Site Boundary (0.19 mi. N) 0 0

A.6 FOOD PRODUCTS 0

Samples were collected monthly when available during the harvest season and a 0 gamma analysis was performed on each. The samples were collected at the location 0 listed below. 0 0

0 0

Appendix A - Page 4 0

0 0

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

A.7 FISH S

0 Semiannual samples were collected and a gamma analysis was performed on the 0 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.

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

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

Semiannual samples were collected and a gamma analysis was performed on each 0 following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

0 0 Location 129 Discharge Canal Entrance to Lake Norman (0.51 mi. ENE) 0 Location 130 Highway 73 Bridge Downstream (0.52 mi. SW)

Location 137 Pinnacle Access Area (12.0 mi. N) 0 0 A.9 DIRECT GAMMA RADIATION (TLD) 0 Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one S locations. A gamma exposure rate was determined for each TLD. TLD locations are 0 listed in Table 2.1-B. The TLDs were placed as indicated below.

0 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 0 sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March, 1991.

0 0 An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 0 kilometer range.

0 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 An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

Appendix A - Page 5

0 0

The Nearest Residence 0

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

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

0 0

The census was conducted during the growing season from 5/20 to 5/21/2008.

Results are shown in Table 3.10. No changes were made to the sampling procedures 0

during 2008 as a result of the 2008 census. 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 with the three highest values did not change in 2008.

0 0

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS 0 0

The McGuire: site centerline used for GPS measurements was referenced from the McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1, 0

Site Location. Waypoint coordinates used for NMNS GPS measurements were latitude 0 35°-25'-59"N and longitude 80'-56'-55"W. Maps and tables were generated using North 0 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 the item of interest. Distances for the locations are displayed using three significant 0

figures. 0 0

0 0

Appendix A -Page 6 0

0 0

0 APPENDIX B 0

0 0

0 RADIOLOGICAL 0 ENVIRONMENTAL MONITORING 0

0 PRO GRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0 2008 0

0 0

0 Appendix B - Page 1 0

0

0 0

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

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 0

rType and No.of Non- 0 Medium or T a Lower All Idit Location with Highest Control Routine Pathway Total Limit of Locations Annual Mean Control Report Sampled Number Detection Name, Distance, Direction Location Meas.

Sampledso 0 0

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

Measurement Performed ( Range Code Range Range 0

0 Air Particulate 134 (8.77 mi WNW)* 0 (pCi/m3) 102 (9.89 mi WNW)*

0 BETA 364 1.OOE-02 1.81E-2 (312/312) 133 1.92E-2 (52/52) 1.93E-2 (52/52) 0 0 CS-134 364 5.OOE-02 4.76E 3.30E-2 0.00 (0/312)

(6.23 mi ENE) 5.36E 3.1OE-2 0.00 (0/52) 6.38E 3.37E-2 0.00 (0/52) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 364 6.OOE-02 0.00 (0/312) 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0

0 1-131 364 7.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 PIP G-07-00399 describes the installation of location 102 and the termination of location 134. 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 @ 4/27/2009 06:41 Appendix B - Page 2 0 0

0

0 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-2008 to 31-DEC-2008 S Medium or Type and No. of Non Mduor Total Lower AlIdctrLocation with Highest Control Routine 0

Pahwy Pathway umber Ttl Lii Limit off Indicator Locations All Annual A MeanCotlRuin uaMenLocation Report Sampled oe Detection Name, Distance, Direction Lepo.

Of Meas.

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

Measurement Performed Range Code Range Range Air Radioiodine 134 (8.77 mi WNW)*

(pCi/m3) 102 (9.89 mi WNW)*

0 CS-134 364 5.OOE-02 0.00 (0/312) 0.00 - 0.00 0.00 0.00 (0/52)

- 0.00 0.00 (0/52) 0.00 - 0.00 0

0 CS-137 364 6.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 364 7.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 PIP G-07-00399 describes the installationof location 102 and the termination of location 134.

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

S Report Generated @ 4/27/2009 06:41 Appendix B - Page 3

0 0

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

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 0

No. of Non- 0 Medium or Type and Total Lower All Idit Location with Highest Pathway Number Limit of Annual Mean Control Routine 0

Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

0 0

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

Measurement Performed Range Code Range Range 0 0

Drinking Water 136 0 (pCi/liter) (12.7 mi NNE) 0 BALA-140 65 15 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 BETA 65 4 2.17 (49/52) 119 2.40 (13/13) 1.87 (13/13) 0 0

0.69 - 3.86 (7.40 mi SSW) 0.69 - 3.86 0.83 - 3.54 0 CO-58 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 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0 CS-134 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 CS-137 65 18 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 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 0 H-3 20 2000 1020 (16/16) 101 1520 (4/4) 226 (2/4) 0 249- 1680 (3.31 mi E) 1190- 1680 179-273 0

1-131 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 MN-54 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 NB-95 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 ZN-65 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 0 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 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 @ 4/27/2009 06:41 0

Appendix B - Page 4 0 0

0

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 0 ControlNone No. of Non-Type and Total Lower Location with Highest 0 Medium or Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

0 Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range 0

Surface Water 135 (pCi/liter) (11.9 mi N) 0 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 0 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 0 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12 2000 1405 (8/8) 128 1670 (4/4) 313 (2/4) 0 1030-1980 (0.45 mi NE) 1490- 1980 284-342 S 1-131 39 15 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 NB-95 39 15 0.00 - 0.00 0.00 (0/26) 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 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 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 @ 4/27/2009 06:42 0 Appendix B - Page 5 0

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 No. of Non-Type and Total Lower Location with Highest ControlNone Medium or 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 Milk 141 (pCi/liter) (14.8 mi WNW)

BALA-140 47 15 0.00 (0/21) 0.00 (0/21) 0.00 (0/26) 0 0 CS-134 47 15 0.00 - 0.00 0.00(0/21) 0.00 0.00

- 0.00 (0/21) 0.00 - 0.00 0.00 (0/26) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 47 18 0.00 (0/21) 0.00 (0/21) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 47 15 0.00 (0/21) 0.00 (0/21) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 LLI-131 47 1 0.00 (0/21) 0.00 (0/21) 0.00 (0/26) 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 @ 4/27/2009 06:42 Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 9 No. of Non-0 Medium or Type and Total Lower All Idit Location with Highest Control Routine Rot Number Limit of l catosAnnual MeanLoto 0 Pathway Sampled of Detection Locations Name, Distance, Direction Location Report 0 Meas.

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

Measurement Performed ( Range Code Range Range 0

0 Broadleaf Vegetation 134 (8.77 mi WNW)*

102 (9.89 mi WNW)*

0 (pCi/kg-wet)

S CS-134 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 48 80 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

PIP G-07-00399 describes the installation of location 102 and the termination of location 134.

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

S Zero range indicates no detectable activity measurements 0

0 0

0 S

Report Generated @ 4/27/2009 06:41 Appendix B - Page 7

0 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-2008 to 31-DEC-2008 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 (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

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

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

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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

0 0

Report Generated @ 4/27/2009 06:41 Appendix B - Page 8

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

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 0

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

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range 0 Fish 137 (pCi/kg-wet) (12.0 mi N) 0 CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 S CO-60 12 130 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 12 150 12.4 (4/6) 129 12.4 (4/6) 0.00 (0/6) 0 3.84-20.0 (0.51 mi ENE) 3.84 -20.0 0.00-0.00 S 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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 S

0 0

0 Report Generated @ 4/27/2009 06:42 Appendix B - Page 9 0

0 Environmental Radiological Monitoring Program Summary 0 S

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

Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 0

Location with Highest ControlNone No. of Non- 0 Medium or Type and Total Lower Pathway Number Limit of Annual Mean 0 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 Shoreline 137 Sediment (12.0 mi N)

(pCi/kg-dry)

MN-54 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6 0 0.00 (0/4) 0.00 - 0.00 0.00 (0/2) 0.00 - 0.00 0.00 (0/2) 0.00 - 0.00 0 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 6 180 177 (2/4) 130 177 (2/2) 0.00 (0/2) 0 0 161-193 (0.52 mi SW) 161-193 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 0 0

0 0

0 Report Generated @ 4/27/2009 06:42 0

Appendix B - Page 10

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2008 to 31-DEC-2008 Medium or Type Totaland Lower All Indicator No. of Non-Location with Highest Control Routine Limit of Annual Mean Pathway Sampled Number Detection Locations Name, Distance, Direction Location Report of D Meas.

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

Unit of Measurement Performed Range Code Range Range 0 Direct Radiation 175 TLD (15.5 mi WNW)

(mR/standard quarter) 0 161 0.OOE+00 17.1 (157/157) 180 26.9 (3/3) 23.5 (4/4) 0 0 10.5 - 30.0 (127 mi NNE) 26.0 - 30.0 20.6 - 26.7 0

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

Zero range indicates no detectable activity measurements 0

0 0

S S

0 0

S 0

0 Report Generated @ 4/27/2009 06:42 Appendix B - Page 11

0 0

0 S

0 0

0 APPENDIX C 0

0 0 SAMPLING DEVIATIONS 0

0 &

0 UNAVAILABLE ANALYSES 0

0 0

0 0 Appendix C - Page 1 0

0 0

APPENDIX C 0 0

0 MCGUIRE NUCLEAR STATION 0 SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES 0 0

DEVIATION & UNAVAILABLE REASON CODES 0 BF Blown Fuse P0 Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair 0 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident 0 LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Tom Filter 0

PI Power Interrupt VN Vandalism 0 PM Preventive Maintenance CN Construction 0 0

C.1 SAMPLING DEVIATIONS 0 0

Drinking Water Scheduled Actual Reason 0

Location Collection Dates Collection Dates Code Corrective Action 0 Sampling equipment did not collect sufficient volume due to pump tubing 0

assembly failure. The collection team 0 identified and corrected the equipment problem. The collection team failed to 0

collect a grab sample on 3/10/2008, but 0 101 2/11 - 3/10/2008 3/11/2008 OT did collect a grab sample on 3/11/2008.

PIP G-08-00334 was written.

0 0

Surface Water 0 Scheduled Actual 'Reason 0 Location Collection Dates Collection Dates Code Corrective Action 0 Low Lake Norman water level due to exceptional drought conditions during 0

2007 and 2008 caused loss of prime with 0 the submersible pump. Work request 4873 8 written. The submersible pump was 0

shut down by maintenance on 9/18/2007 to 0 prevent pump damage. Weekly grab samples were initiated. PIP G-07-0079 1 0

was written. Water level rose to sufficient 0 level to allow for placement of sampling equipment on the pier at location 135 on 0

12/1 - 12/1

/14/008- /14/0082/18/2008. Work request 54088 written to 0 12/17 - 1/14/2008 12/17 - 1/14/2008 restore operation of submersible pump, 2/11 - 3/10/2008 2/11 - 3/10/2008 which was returned to operation 3/13/2008 0

135 3/10 - 4/7/2008 3/17 - 4/7/2008 PS and normal sampling resumed 3/17/2008. 0 0

Appendix C - Page 2 0 0

0

0 Surface Water, continued 0 Submersible pump malfunctioned during composite period. Work request 58667 0 written. Composite volume was available from 6/30 to 7/23/2008. The submersible pump was repaired and normal sampling 128 6/30 - 7/28/2008 6/30 - 7/28/2008 PS resumed 7/23/2008.

Breaker to sampling equipment was inadvertently turned off after about eight days of sampling (estimate). It is suspected Cowans Ford Dam personnel 0 interrupted sampling equipment by cutting S the power. The estimated sample period was 9/22/2008 10:36 to about 9/30/2008 0 18:36. A grab sample was collected on 0 10/20/2008 06:58. Breaker to sampling equipment was reset on 10/20/2008 and 0 131 9/22 - 10/20/2008 9/22 - 10/20/2008 PI normal sampling was resumed.

0 0 C.2 UNAVAILABLE ANALYSES 0

0 TLD Scheduled Reason S Location Collection Dates Code Corrective Action 0 170 159 12/13 - 3/13/2008 6/12 - 9/11/2008 CN VN TLD missing. 2nd quarter 2008 TLD placed in field.

TLD missing. 4' quarter 2008 TLD placed in field.

0 180 9/11 - 12/11/2008 VN TLD missing. 1st quarter 2009 TLD placed in field.

0 0

0 S

0 0 Appendix C - Page 3 0

0

0 0

0 APPENDIX D 0

S 0 ANALYTICAL DEVIATIONS 0

0 0

0 No Analytical deviations were incurred for the 2008 Radiological Environmental Monitoring Program 0

0 0

S 0

0 0

0 S

0 0

0 S

0 0

0 Appendix D - Page 1 0

0

0 0

S 0

0 0

0 APPENDIX E S

0 0

0 RADIOLOGICAL ENVIRONMENTAL MONITORING 0 PROGRAM RESULTS 0

0 0

0 This appendix includes all of the sample analysis reports generated from 0 each sample medium for 2008. Appendix E is located separately from this report and is permanently archived at the Duke Energy Corporation Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

0 S

S 0

0 0

0 Appendix E - Page 1 0

S

ML091410202

Contents

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2.0 INTRODUCTION

6.0 REFERENCES

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ML091410202

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6.0 REFERENCES

SUMMARY

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