Text

Annual Radiological Environmental Operating Report 2011, Cover Through Section 4 - Page 15
	ML12145A050
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/10/2012
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12145A050 (61)
	v • d • e

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AREOR 0 Annual 0 Radiological Environmental 0 Operating Report 0

2011

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ffEnergy.

ANNUAL RADIOLOGICAL

ENVIRONMENTAL OPERATING REPORT 0

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DUKE ENERGY CORPORATION

MCGUIRE NUCLEAR STATION

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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 3-3 3.2 Drinking Water. 3-8 3.3 Surface Water 3-10 3.4 Milk. 3-12 3.5 Broadleaf Vegetation. 3-14 3.6 Food Products 3-16 3.7 Fish . 3-18 3.8 Shoreline Sediment . 3-21 3.9 Direct Gamma Radiation 3-24 3.9.1 Environmental TLD. . . . . . . . . . 3-24 3.9.2 ISFSI 3-24 3.10 Land Use Census 3-29 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 5-1 5.5 Duke Energy Intercomparison Program 5-2 5.6 Eckert & Ziegler Analytics Cross Check Program 5-2 5.7 ERA Proficiency Testing . 5-2 5.8 Duke Energy Audits . 5-2 5.9 U.S. Nuclear Regulatory Commission Inspections 5-2 5.10 State of North Carolina Intercomparison Program 5-2 5.11 TLD Intercomparison Program . 5-3 5.11.1 Nuclear Technology Services Intercomparison Program 5-3 5.11.2 Internal Crosscheck (Duke Energy). 5-3 0 S6.0 References . . . . . . . . . . . . . 6-1 0

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Appendices Appendix A: Environmental Sampling and Analysis Procedures A-1 I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A.1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water . . . . A-3 A.3 Surface Water. A-4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Food Products. A-4 A.7 Fish A-4 A.8 Shoreline Sediment. A-5 A.9 Direct Gamma Radiation (TLD) . . . A-5 A.10 Annual Land Use Census A-5 V. Global Positioning System (GPS) Analysis A-6 Appendix B: Radiological Env. Monitoring Program - Summary of Results B-1 Air Particulate . B-2 Air Radioiodine. B-3 Drinking Water. B-4 Surface Water . B-5 Milk. B-6 Broadleaf Vegetation B-7 Food Products . B-8 Fish . B-9 Shoreline Sediment B-10 Direct Gamma Radiation (TLD) B-11 Air Particulate Excluding Fukushima Daiichi B-13 Air Radioiodine Excluding Fukushima Daiichi B-14 Milk Excluding Fukushima Daiichi B-15 Broadleaf Vegetation Excluding Fukushima Daiichi B-16 Food Products Excluding Fukushima Daiichi B-17 Fukushima Daiichi Radioactivity Detected in Environmental Media (2011). B-19 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C.1 Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations . D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 Appendix F: Errata to Previous Reports F-1 0

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 3-5 3.2 Concentration of Tritium in Drinking Water 3-8 3.3 Concentration of Tritium in Surface Water. 3-10 3.7-1 Concentration of Cs-137 in Fish 3-19 3.7-2 Concentration of Co-60 in Fish . 3-19 3.8-1 Concentration of Cs-137 in Shoreline Sediment . 3-21 3.8-2 Concentration of Co-60 in Shoreline Sediment 3-22 3.9-1 Direct Gamma Radiation (TLD) Results 3-25 3.9-2 McGuire Inner Ring (TLD) Results 3-27 0

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3.9-3 McGuire Outer Ring (TLD) Results . . . . 3-28 3.10 2011 Land Use Census Map 3-30

LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-8 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection . 2-9 3.1-A Mean Concentrations of Radionuclides in Air Particulate 3-5 3.1-B Mean Concentrations of Air Radioiodine (1-131) 3-7 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-9 3.3 Mean Concentrations of Tritium in Surface Water 3-11 3.4 Mean Concentrations of Cs-137 in Milk 3-13 3.5 Mean Concentrations of Cs- 137 in Broadleaf Vegetation 3-15 3.6 Mean Concentrations of Cs-137 in Food Products 3-17 3.7 Mean Concentrations of Radionuclides in Fish (pCi/kg) 3-20 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg) 3-22 3.9-A Direct Gamma Radiation (TLD) Results 3-26 3.9-B Direct Gamma Radiation (TLD) Results Inner Ring (mR/year) 3-27 3.9-C Direct Gamma Radiation (TLD) Results Outer Ring (mR/year) . 3-28 3.10 McGuire 2011 Land Use Census Results 3-29 4.1-A 2011 Environmental and Effluent Dose Comparison 4-3 4.1-B Maximum Individual Dose for 2011 based on Environmental Measurements for McGuire Nuclear Station 4-5 5.0-A Duke Energy Interlaboratory Comparison Program 2011 Cross-Check Results For EnRad Laboratories 5-4 5.0-B Eckert & Ziegler Analytics Cross Check Program 2011 Cross-Check Results for EnRad Laboratories 5-9 0 5.0-C 2011 Environmental Resource Associates Quikm Response Program 5-12 5.0-D 2011 Environmental Dosimeter Cross-Check Results . 5-14 0

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0 LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder) 0 0

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BiWeekly Control 0

DEHNR DHEC Department of Environmental Health and Natural Resources Department of Health and Environmental Control 0

EPA Environmental Protection Agency 0 ERA Environmental Resource Associates GI-LLI Gastrointestinal - Lower Large Intestine 0 GPS ISFSI Global Positioning System Independent Spent Fuel Storage Installation 0 LLD M

Lower Umit of Detection Monthly 0

MDA MNS Minimum Detectable Activity McGuire Nuclear Station 0

mrem millirem 0 NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual 0 pCi/kg pCi/l picocurie per kilogram picocurie per liter 0

pCi/m3 PIP picocurie per cubic meter Problem Investigation Program 0

Q REMP Quarterly Radiological Environmental Monitoring Program 0

SA Semiannually 0 SLCs SM Selected Licensee Commitments Semimonthly 0 TECH SPECs TLD Technical Specifications Thermoluminescent Dosimeter 0

AiCi/ml UFSAR microcurie per milliliter Updated Final Safety Analysis Report 0

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0 1.0 EXECUTIVE

SUMMARY

S This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Monitoring Program (REMP), and the

program results for the calendar year 2011.

0 Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental

radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Evaluation of the effect of trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011

Tohoku earthquake is included for affected sample media. Quality assurance practices,

sampling deviations, unavailable samples, and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments

(SLC's). Required analyses were performed and detection capabilities were met for all 0collected samples as required by SLC's. Eleven-hundred thirty-one samples were

analyzed comprising 1,586 test results in order to compile data for the 2011 report.

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

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Following the March 11, 2011 Tohoku earthquake in Japan, radioactive material

migrated from the Fukushima Daiichi power plant to the United States. Radioactive material was detected at numerous U.S. nuclear plants (including all three Duke nuclear

plants) and detected by state and federal monitoring agencies. Where applicable in this report, radioactive material determined to be from the Fukushima Daiichi power plant has

been identified and distinguished from effluents from McGuire Nuclear Station.

Concentrations observed in the environment in 2011 for station related radionuclides 0were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all

positively identified measurements attributable to station operation 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 0the maximum exposed member of the public as calculated by environmental sampling

data, excluding TLD results, was 1.12E- 1 mrem for 2011. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of 0 the public or the environment.

Section I - Page 1

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2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS

McGuire Nuclear Station (MNS) is located geographically near the center of a highly

industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land being used for farming. The McGuire site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina. The site is

bounded to the west by the Catawba River channel and to the north by 32,510 acre Lake

Norman. Lake Norman is impounded by Duke Energy Corporation's Cowans Ford Dam

Hydroelectric Station. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals

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

6.3).

0MNS consists of two pressurized water reactors. Each reactor unit is essentially a mirror image

of the other joined by an auxiliary building housing both separate and common equipment. Each

unit was designed to produce approximately 1200 gross Megawatts of electricity. Unit 1 achieved criticality August 8, 1981 and Unit 2 on May 8, 1983.

Figures 2.1 -1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within

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

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

four years prior to operation of Unit 1 in 1981. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. The 0operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee

Commitments Manual, with regard to sample media, sampling locations, sampling frequency, and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-0made" environmental radioactivity. The environmental monitoring program also verifies 0projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from McGuire Nuclear Station. This program satisfies the 0

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0 requirements of Section IV.B.2 of Appendix I to IOCFR50 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 0 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 0 modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.10.

Participation in an interlaboratory comparison program as required by Selected Licensee 0 Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data 0 generated by the sampling and analysis of the various media in the Radiological 0 Environmental Monitoring Program. "Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or 0 concentrations are included in the calculation of the mean. The following equation was used to estimate the mean (reference 6.8):

E Xi

=N X

Where:

x = estimate of the mean, i = individual sample, O N = total number of samples with a net activity (or concentration), 0 Xi = net activity (or concentration) for sample i. 0 0

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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 0smallest concentration of radioactive material in a sample that will yield a net count,

above the system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the

standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed

in Table 2.2-C.

MDA - The MDA is the net counting rate (sample after subtraction of background) that must be surpassed before a sample is considered to contain a scientifically measurable

amount of a radioactive material exceeding background amounts. The MDA is

calculated using a sample background and may be thought of as an "actual" LLD for a particular sample measurement.

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

Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding

that radionuclide to the environment in quantities exceeding the preoperational level and 0that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release 0from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Some factors that may affect environmental levels of radionuclides include 0prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chemobyl accident). Some of these factors may be obvious while others are sometimes unknown.

0Therefore, how trends are identified will include some judgment by plant personnel.

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Figure 2.1-1 McGuire Nuclear Station Sampling Locations Map (0.5 Mile Radius)

Legend

TLD Locations

All Other Locations N/MNSRailroads MVINSRoads 7 States

[Z] Counties NHDWaterbody Approximate location of features shown 0 0.125 0.25 Mile Projedcon NCSP NAD27 4

Section 2 - Page 4

Figure 2.1-2 Section 2 - Page 5

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TABLE 2.1-A S

MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS S

0 Table 2.1-A Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly 0 M Monthly SA Semiannually C Control I Indicator 0 S

Site

Measure Type Location Deescription* Air Rad.

& Part.

Surfaee Drinking Shoreline Food Fish Milk Broad S

Water Water Sediment Products Leaf Veg.

101 I North Mecklenburg Water Treatment Facility ( 3.31 mi E )

M 0 102 103 C

1 Amity Chuch Road (9.89 mi WNW)

Cottonwood Substation ( 4.20 mi NE)

W W

M(b) 0 Mt. Holly Municipal Water Supply M 119 I (7.40 mi SSW) 120 I Site Boundary (0.46 mi NNE) W M (b) 121 125 I

I Site Boundary (0.47 mi NE )

Site Boundary(0.38 mi SW)

W W M (b) 0 128 I Discharge Canal Bridge (0.45 mi NE) M Discharge Canal Entrance to Lake Norman SA SA 129 I (0.51 miENE) 130 1 Hwy 73 Bridge Downstream (0.52 mi SW)

SA 0 131 I Cowans Ford Dam (0.64 mi WNW)

Charlotte Municipal Water Supply M

M 0

132 I (11.1 miSSE) 0 133 I Cornelius (6.23 mi ENE) W 135 C Plant Marshall Intake Canal ( 11.9 min ) M Mooresville Municipal Water Supply M 136 C ( 12.7 mi NNE) 137 141 C

C Pinnacle Access Area ( 12.0 mi N)

Lynch Dairy-Cows ( 14.8 mi WNW)

SA SA SM 0 188 I 5 mile radius Gardens ( 2.79 mi NNE) M (a) 193 I Site Boundary ( 0.19 mi N ) - M(b) 194 I East Lincoln County Water Supply (6.73 mi NNW)

M S 195 I Fishin AccessRoad(0.9mi N) W S (a) During Harvest Season S

(b) When Available 0

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as S close as possible to the item of interest. S Section 2 - Page 6

TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES) 0 Table 2.1-B Codes 0 IR C

Inner Ring Control OR SI Outer Ring Special Interest 0

Site Measure Location Distance* Sector Site Measure Location Distance* Sector N Type (miles) # Type nmiles)

S 143 IR SITE BOUNDARY 0.27 NW 164 OR HAMBRIGHT &

BEATTIES FORD ROAD 4.64 SSE 144 IR SITE BOUNDARY 0.46 NNE 165 OR ARTHER AUTEN ROAD 4.57 S NECK ROAD 0 145 IR SITE BOUNDARY 0.47 NE 166 OR REFUGE BOUNDARY LUCIA RIVERBEND 4.44 SSW 0 146 IR SITE BOUNDARY 0.42 ENE 167 OR HWY/OLD FIREHOUSE 4.87 SW OLD PLANK ROAD 147 IR SITE BOUNDARY 0.44 E 168 OR BRIDGE 4.60 WSW 148 IR SITE BOUNDARY 0.46 ESE 169 OR GLOVER LANE 4.03 W 0 149 IR SITE BOUNDARY 0.50 SE 170 OR LITTLE EGYPT ROAD TRIANGLE ACE 4.32 WNW 0 151 1R SITE BOUNDARY 0.37 S 171 OR HARDWARE LAKESHORE S RD 3.95 NW 152 IR SITE BOUNDARY 0.44 SSW 172 OR ISLAND VIEW COURT 4.69 NNW KEISTLER STORE /

0 153 IR SITE BOUNDARY 0.47 SW 173 SI GLENWOOD ROAD EAST LINCOLN JR.

8.39 NNW 154 IR SITE BOUNDARY 0.45 W 174 SI HIGH SCHOOL 8.77 WNW 0 156 IR SITE BOUNDARY 0.44 WNW 175 C BOGER CITY 15.5 WNW BELMARROW RD /

189 JR SITE BOUNDARY 0.43 SSE 177 SI COULWOOD 8.77 S FLORIDA STEEL 190 IR SITE BOUNDARY 0.37 WSW 178 Sl CORPORATION 9.36 SE THE POINTE MOORESVILLE WATER 157 IR (MOORESVILLE) 4.69 N 180 SI TREATMENT FACILITY 12.7 NNE OLD DAVIDSON 158 OR BETHEL CHURCH RD 4.33 NNE 181 SI WATER FACILITY 7.02 NE HENDERSON ROAD & CORNELIUS 159 OR W CATAWBA AVENUE 4.73 NE 182 SI AIR SITE # 133 6.23 ENE ANCHORAGE MARINE MCGUIRE FISHING 160 OR SHOWROOM 4.89 ENE 186 SI ACCESS ROAD 0.24 NNW SAM FURR ROAD ENERGY EXPLORIUM /

161 OR & HWY 21 4.70 E 187 SI AR SITE # 195 0.19 N PENINSULA DEV. /

162 OR RANSON ROAD 4.53 ESE 191 SI JOHN CONNOR ROAD 2.84 NNE 163 OR MCCOY ROAD 4.94 SE

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

REPORTING LEVELS FOR RADIOACTIVITY 0 CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0 Analysis Water Air Particulates Fish Milk BroadLeaf 0 (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/rn3) (pCi/kg-wet)

H-3 2 0 ,000(a),(b) 0 Mn-54 1,000 30,000 Fe-59 400 10,000 0 Co-58 Co-60 1,000 300 30,000 10,000 0

Zn-65 300 20,000 Zr-Nb-95 400 0 1-131 2 0.9 3 100 0 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 0 Ba-La-140 200 300 _ j 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

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TABLE 2.2-B 0 REMP ANALYSIS FREQUENCY 0

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

Water Quarterly Composite X Drinking Monthly Composite X (a) X 0 Water Quarterly Composite X Shoreline Sediment Semiannually X 0 Milk Semimonthly X X Fish Semiannually X 0

Broadleaf Vegetation Monthly° X Food Products Monthly"b) X (a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is > 1 mrem per year. An LLD of I pCi/liter will be required for this analysis.

(b) When Available Section 2 - Page 8

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TABLE 2.2-C 0 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 0 Analysis Water (pCi/liter)

Air Particulates or Gases Fish (pCi/kg-wet)

Milk (pCi/liter)

BroadLeaf Vegetation Sediment (pCi/kg-dry) 0 (pCi/m3) (pCi/kg-wet)

Gross Beta 4 0.01 0 H-3 2000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1() 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 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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0 3.0 INTERPRETATION OF RESULTS

Review of 2011 REMP analysis results was performed to detect and identify changes in environmental levels as a result of station operation. The radionuclides with Selected Licensee Commitments reporting levels that indicate consistent detectable activity have been historically 0trended from preoperation to present. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year.

0The highest annual mean concentration of applicable Selected Licensee Commitments radionuclides from the indicator locations for each media type was used for trending purposes.

Trending was performed by comparing annual mean concentrations to historical results. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the

radionuclide's SLC reporting level (Table 2.2-A). All maximum percent of reporting level

values attributable to MNS plant operation were well below the 100% action level. The highest

value attributable to MNS plant operations during 2011 was 6.8% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location 101). Only Selected Licensee

Commitments radionuclides were detected in 2011.

No Selected Licensee Commitments radionuclides reporting levels were exceeded in 2011 due to MNS station operations. However, during the Fukushima Daiichi fallout period several samples exceeded Selected Licensee Commitment reporting levels for 1-131 and are

indicated in the table below.

Sample Media Date Locations Milk 3/28/2011 141 Milk 4/11/2011 141 Broadleaf Vegetation 4/4/2011 102, 120, 193 Crops 4/4/2011 188 Because the radioactivity exceeding reporting levels was attributed to Fukushima Daiichi no reports were made to the NRC.

Trending was performed by comparing annual mean concentrations of any effluent related

detected radionuclide to historical results. Levels of 1-131 and Cs-137 increased during the

Fukushima Daiichi fallout period and comparisons were made to distinguish Fukushima

Daiichi activity and normal activity. Samples taken during media-specific Fukushima Daiichi fallout periods (table below) were included in the trend evaluations for applicable sample media.

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0 Sample Media Fukushima Daiichi Period Air Particulate/Radioiodine 3/14/2011 - 4/18/2011 Milk 4/4/2011 Broadleaf Vegetation 4/4/2011 Crops 4/4/2011 Changes in sample location, analytical technique, and presentation of results must be considered when reviewing for trends. Calculation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net results (sample minus background) positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. All negative values were replaced with a zero for calculational and graphical purposes to properly represent environmental conditions. A change in gamma spectroscopy analysis systems in 1987 ended a period when many measurements yielded detectable low-level activity for both indicator and control location samples. It is possible that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

S This section includes tables and graphs containing the highest annual mean concentrations of any effluent related radionuclide detected since the change in analysis systems in 1987. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels. Only the specific radionuclides that represent the highest dose contributors or 0 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 0 operations in 2011. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2011 land use census data, shown in Section 3.10, indicates that no program changes are required as a result of the census.

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0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0 In 2011, 364 particulate and radioiodine samples were analyzed, 312 at six indicator locations 0 and 52 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis. During 2011 there was an 0 increase in 1-131 and Cs-137 concentrations due to Fukushima Daiichi fallout activity as 0 indicated in the tables below.

0 Air Particulate Annual Concentration with Annual Concentration without Andlysis FCkushimarDaiichi FpCi/ma Fukushima Daiichi pCi/m) 0 Indicator FRu I Control FRL Indicator FRL Control FRL 1-131 2.08E-2 2.31E-2 1.54E-2 1.71E-2 0.00 0 0.00 0 Cs-137 7.06E-3 3.53E-4 0.00 0 0.00 0 0.00 0 FRL = Fraction of Selected Licensee Commitment Reporting Level Air Radioiodine 0 I Annual Concentration with Annual Concentration without Analysis Fukushima Daiichi (pCi/m 3) Fukushima Daiichi (pCi/m 3)

Indicator FRL Control !FRL Indicator FRL Control FRI, 1-131 6.OOE-2 6.67E-2 5.46E-2 6.07E-2 0.00 0 0.00 0 FRL = Fraction of Selected Licensee Commitment Reporting Level 0

0 Gross beta analyses indicated 1.99E-2 pCi/m 3 at the location with the highest annual mean and 2.OOE-2 pCi/mi at the control location. The control location was relocated during 2008.

Detectable gamma emitting particulate activity (Co-58) was last observed in environmental air 0 particulate samples in 2004 (reference 6.15).

0 No detectable 1-131 activity in any environmental air radioiodine samples was found in 2011 due to MNS plant operations. K-40 and Be-7 that occur naturally were routinely detected in 0 charcoal cartridges collected during the year. Cs-137 activity was not detected on any cartridges in 2011. Cs-137 detection on the charcoal cartridge was determined in 1990 to be 0 an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion (reference 6.13). Therefore, any Cs-137 activities were not used in any dose 0 calculations in Section 4.0 of this report.

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

Table 3.1-B gives indicator location highest annual means and control means since 1979 for 1-131 (including Fukushima Daiichi ). Preoperational and ten year averages are also shown. No 1-131 activity due to MNS plant operation has been detected since 1989.

Section 3 -Page 3

0 0

0 Radioactivity identified in MNS airborne particulate and airborne radioiodine samples during the 0 period of 3/14/2011 through 4/11/2011 was determined to be from the Fukushima Daiichi 0 incident based on the following:

0 (1) The quantities of radioactive airborne effluents from McGuire Nuclear Station during 0 2011 did not increase significantly compared to year 2010. 0 (2) REMP sample results have not detected the presence of these isotopes in airborne 0 particulate and airborne radioiodine samples since 1989. 0 (3) Concentrations detected in the indicator samples were also identified at similar levels in 0 the control samples for McGuire Nuclear Station.

(4) Similar results were seen at other US nuclear plants and state and local government 0

monitoring agencies.

0 0

As such, the atypical detection of these radionuclides in both indicator and control samples is 0 credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake and is not related to the operations of McGuire 0 Nuclear Station. 0 0

0 0

,0 0

0 0

0 Section 3 - Page 4 0

0

Figure 3.1 0 pCi/m 3 Concentration of Gross Beta in Air Particulate 0 1.00E-01 I 0 t 1.o--....

9.OOE-02 - --

8.OOE-02 ..... -- . . . . . .

0 . ...

----_--_..... ÷ 1 - -

I _

0 6.00E-02 ..... +-

0 5.00E-02 . -. . .. .-....

4.00E-02 --

2.00E-02 1.. .-

0 1.O OE-0 2 . ... -.. --.. . . . .. . .. .. . . . . . .-... . . .. . . . . . .

0 O.OOE+O0 . - . ...

0 1985 1988 1991 1994 1997 2000 2003 2006 2009 0 I -U-- Indicator Location -- Control Location ]

There is no reportinglevel for GrossBeta in airparticulate 0

Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate S YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control 3

(pCi/r?) (pCi/m3) (pCim ) (pCi/m) 1979* 4.40E-3 1.47E-3 ** **

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

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

0 1982* 3.82E-3 2.29E-3 ** **

0 1983*

1984 2.93E-3 1.74E-3 3.21E-3 8.29E-4 0 1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 0 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 0 1988 O.OOEO 0.OOEO 7.49E-2 5.51E-2 1989 0.OOEO 0.OOEO 2.22E-2 2.14E-2 1990 0.OOEO 0.OOEO 2.58E-2 2.37E-2 0 1991 O.OOEO 0.00E0 2.16E-2 2.15E-2 0 1992 0.OOEO O.OOEO 1.92E-2 2.02E-2 1993 O.OOEO 0.OOEO 1.93E-2 2.04E-2 0 1994 0.OOEO O.OOEO 2.28E-2 2.02E-2 1995 0.OOEO O.OOEO 3.02E-2 5.17E-2 1996 O.OOEO 0.OOEO 3.11E-2 5.49E-2 1997 0.OOEO 0.00E0 2.34E-2 3.62E-2 1998 0.OOEO 0.OOEO 1.86E-2 2.66E-2 1999 0.00E0 0.OOEO 2.06E-2 3.47E-2 2000 O.OOEO O.OOEO 2.OOE-2 2.77E-2 2001 O.OOEO 0.OOEO 1.79E-2 1.91E-2 Section 3 - Page 5

0 0

Table 3.1-A continued 0

YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control 0

(]pCi/mn) (pCi/) (i/rm) (pCi/m3 ) S 2002 0.00E0 0.00E0 1.57E-2 1.72E-2 2003 0.00E0 0.00E0 1.50E-2 1.63E-2 S 2004 0.OOEO 0.OOEO 1.67E-2 1.71E-2 S 2005 0.00E0 0.OOEO 1.68E-2 1.77E-2 2006 0.00E0 0.OOEO 1.79E-2 1.94E-2 2007 0.OOEO 0.OOEO 2.12E-2 2.18E-2 9 2008 0.OOEO 0.OOEO 1.92E-2 1.93E-2 2009 0.OOEO 0.00E0 1.79E-2 1.76E-2 0 2010 0.00E0 0.00E0 2.01E-2 1.95E-2 Average (2001 - 2010) NOT APPLICABLE NOT APPLICABLE 1.78E-2 1.85E-2 2011 7.06E-3 0.OOEO 1.99E-2 2.00E-2 0.OOEO = no detectable measurements

Radioiodine and Particulates analyzed together ** Gross Beta analysis not performed 0

2011 concentration affected by Fukushima Daiichi 0

0 0

0 S

0 0

0 Section 3 - Page 6

0 0

Table 3.1-B Mean Concentrations of Air Radioiodine (1-131)

Year Indicator Location (pCi/m3) Control Location (pCi/rm) 1979* 3.28E-3 1.04E-3 1980* 2.01E-3 1.10E-3 1981* 4.17E-3 6.27E-4 1982* 1.42E-3 2.48E-3 1983* 1.99E-3 2.01E-4 1984 3.17E-3 0.OOEO 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.OOEO 0.OOEO 1989 2.18E-2 0.00E0 1990 0.OOEO O.00E0 1991 0.OOEO 0.00E0 1992 0.00E0 0.OOEO 1993 0.00E0 0.00E0 1994 0.OOEO 0.OOEO 1995 0.OOEO 0.OOEO 1996 0.OOEO 0.OOEO 1997 0.OOEO 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.00E0 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.OOEO 2004 0.OOEO O.OOEO 2005 0.OOEO O.OOEO 2006 0.OOEO 0.00E0 2007 0.00E0 0.OOEO 2008 0.OOEO 0.OOEO 2009 O.OOEO 0.OOEO 2010 0.OOEO 0.OOEO 2011 6.OOE-2 5.46E-2 0.OOEO = no detectable measurements

Radioiodine and Particulate analyzed together.

2011 concentration affected by Fukushima Daiichi 0

S 0

0 0

0

Section 3 -Page 7 0

0

0 0

3.2 DRINKING WATER 0 In 2011, 65 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Fifty-two samples were from the four indicator locations and 13 from the 0 control location. Tritium (H-3) analyses were performed on 20 composite samples, 16 at indicator locations and four at the control location.

S No detectable gamma activity was found in drinking water samples in 2011 and has not been detected since 1987. Gross beta analyses indicated 1.77 pCi/1 at the location with the highest annual mean and 1.75 pCi/l at the control location. Tritium was detected in thirteen of the 16 indicator composite samples taken in 2011 with the highest annual mean resulting in only 0 4.99% of the reporting level. Tritium was not detected in any of the four control location samples. The dose for consumption of water was less than one mrem per year, historically 0 and for 2011; therefore low-level iodine analysis is not required.

Figure 3.2 shows tritium highest annual mean indicator and control location concentrations with comparisons to 20% of the reporting level. Table 3.2 gives indicator location highest 0 annual means and control means since 1979 for tritium and gross beta. There is no reporting level for gross beta.

0 Drinking water Location 101 was added to the sampling program in 1999. Figure 3.2 shows 0 an increase beginning in that year. There was an increase in tritium releases in 2006 due to silica removal from the spent fuel pools. This resulted in additional water volume being released from the plant. An extreme drought during the second half of 2007 and much of 0 2008 affecting the Catawba River Basin resulted in less dilution volume available in Lake Norman. 0 Figure 3.2 0 pCi/liter 5000 Concentration of Tritium in Drinking Water S 4500 0

4000 0

3500 0

3000 0

2500 '--

0 2000 4 1000 --------- -------.

500 -- _ _

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 1 -U- Indicator Location --Control Location 120%Reporting Level Section 3 - Page 8

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Tritium (pCi/I) 0 YEAR Gross Beta (pCi/I)

Indicator Control Indicator Control Location Location Location Location 0 1979 1980 2.40E0 2.34E0 2.03E0 1.87E0 1.65E2 1.63E2 1.50E2 2.05E2 1981 2.79E0 2.41E0 1.88E2 1.78E2 1982 2.62E0 2.43E0 2.43E2 1.45E2 1983 1.80E0 1.87E0 2.65E2 1.45E2 0 1984 2.78E0 1.81E0 5.77E2 2.45E2 0 1985 1.88E0 1.90E0 5.93E2 4.00E2 1986 2.13E0 2.15E0 1.14E3 4.37E2 1987 2.30E0 2.00E0 1.35E3 7.75E2 1988 2.00E0 2.OOEO 9.92E2 7.11E2 1989 2.80E0 2.70E0 5.62E2 0.00E0 0 1990 1991 3.70E0 2.40E0 4.30E0 2.50E0 7.32E2 5.22E2 6.11E2 0.00E0 1.70E0 6.73E2 0.OOEO 0 1992 1993 2.00E0 2.80E0 2.40E0 0.OOEO 0.OOEO 1994 2.47E0 2.90E0 0.00E0 0.OOEO 0 1995 4.20E0 3.30E0 3.58E2 O.00E0 1996 2.75E0 2.11EO 3.60E2 O.00E0 0 1997 2.70E0 2.24E0 2.90E2 O.OOEO 1998 2.75E0 2.33E0 2.68E2 0.00E0 S 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 2002 2.47E0 2.08E0 5.64E2 0.00E0 0 2003 2004 1.81E0 1.68E0 1.52E0 1.29E0 3.51E2 4.61E2 0.OOEO 0.OOEO 0 2005 1.74E0 1.30E0 7.35E2 0.OOEO 0 2006 2007 1.75E0 1.81E0 1.80E0 1.76E0 1.46E3 1.48E3 0.00E0 0.OOEO 2008 2.40E0 1.87E0 1.52E3 2.26E2 0 2009 2010 1.90E0 1.85E0 1.81E0 1.74E0 1.03E3 7.20E2 1.86E2 0.OOEO 2011 1.77E0 1.75E0 9.97E2 0.OOEO 0 0.OOEO = no detectable measurements S

Section 3 - Page 9

0 0

3.3 SURFACE WATER 0 0

In 2011, 39 surface water samples were analyzed for gamma emitting radionuclides, 26 at the two indicator locations and 13 at the control location. Analyses for H-3 were performed on 12 samples, eight at indicator locations and four at the control location.

0 No detectable gamma activity was found S in surface water samples in 2011 and has not been detected since 1988. Tritium was detected in all of the eight indicator 0 composite samples taken in 2011.

Tritium was detected in one of the four control location composite samples in 0 2011.

Figure 3.3 shows tritium highest annual mean indicator and control location S

concentrations. Table 3.3 gives indicator 0 and control location highest annual 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 0 volume being released from the plant. 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 0 Lake Norman.

Figure 3.3 There is no reportinglevel for tritium in surface water 0 pCi/liter Concentration of Tritium in Surface Water S 5000 0 4500 0

4000 0 3500 0 3000 0 2500 0 2000 1500 1000 500 AL~g*0 0

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 I -- W-Indicator Location -* Control Location I Section 3 - Page 10

Table 3.3 Mean Concentrations of Tritium in Surface Water YEAR H-3 Indicator (pCi/l) H-3 Control (pCi/l) 1979 1.85E2 1.66E2 1980 2.13E2 1.93E2 1981 1.75E2 1.70E2 1982 3.30E2 1.23E2 1983 5.75E2 3.67E2 1984 4.10E2 2.65E2 1985 7.33E2 O.00E0 1986 2.33E3 6.13E2 1987 9.20E2 7.70E2 1988 9.40E2 0.OOEO 1989 8.22E2 0.00E0 1990 6.77E2 0.OOEO 1991 7.53E2 0.OOEO 1992 8.13E2 0.OOEO 1993 6.85E2 0.00E0 1994 0.00E0 0.OOEO

1995 3.15E2 .. 0.OOEO

1996 8.Q8E2 ,.OOEO 1997 4.85EI 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 2007 1.68E3 3.42E2 2008 1.67E3 3.13E2 2009 1.1883 1.41E2 2010 1.09E3 0.OOEO 2011 1.19E3 2.94E2 0.OOEO = no detectable measurements S

0 0

0 O ~Section 3 -Page 11 0

0

0 0

3.4 MILK 0 In 2011, 26 milk samples were analyzed for low level 1-131 and other gamma emitting radionuclides. One control location was sampled. No indicator dairies were identified by the 0 2011 land use census. Iodine-131 was identified in three milk samples due to Fukushima 0 Daiichi fallout activity as indicated in the table below.

Milk Annual Concentration with Annual Concentration without 0 Analysis Fukushima D CnrchilpCi/l Fukushima Daiichi (pCi/I)

Indicator FRL Control FRi Indicator FRL Control FRL LLI-131 NA NA 4.80 1.60 NA NA 0.00 0 0 FRL = Fraction of Selected Licensee Commitment Reporting Level 0 No detectable activity due to MNS plant operations 0 was found in milk samples in 2011. Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not been detected since 1987. K-40 is a naturally occurring radionuclide observed in milk samples in 2011. S Table 3.4 gives indicator location highest annual 0 means and control means since 1979 for Cs-137. 0 Since no Cs-137 was detected in 2011, no reporting levels were approached. 0 0

Radioactivity identified in the MNS milk samples collected during the period of 3/28/2011 through 4/25/2011 was determined to be from the Fukushima Daiichi incident based on the following: 0 (1) The quantities of radioactive airborne effluents from McGuire Nuclear Station during 0 2011 did not increase significantly compared to year 2010.

0 (2) REMP sample results have not detected the presence of radionuclides in milk samples since 1990.

0 (3) There are no indicator milk locations for McGuire Nuclear Station. Concentrations 0

being detected were identified in the control samples only for McGuire Nuclear Station. 0 (4) Similar results were seen at other US nuclear plants and state and local government 0 monitoring agencies.

As such, the atypical detection of these radionuclides in control samples is credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake and is not related to the operations of McGuire Nuclear Station.

Section 3 - Page 12

Table 3.4 Mean Concentrations of Cs-137 in Milk

YEAR Cs-137 Indicator (pCi/l) Cs-137 Control (pCi/l) 1979 2.48E1 6.04E0 1980 1.72E1 4.13E0 1981 2.04E1 4.15E0 1982 1.21E1 5.20E0 1983 2.01El 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 O.OOEO 1992 0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.OOEO 0.OOEO 1995 0.OOEO 0.OOEO 1996 0.00E0 0.OOEO 1997 0.OOEO 0.OOEO 1998 0.00E0 0.00E0

- 1999 0.OOEO 0.OOEO 2000 O.00E0 0.OOEO

2001 0.OOEO 0.00E0 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.00E0 2004 0.00E0 0.00E0 2005 0.00EO 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.00E0 0.OOEO 2008 0.OOEO 0.OOEO 2009 0.OOEO 0.OOEO 2010 0.OOEO O.OOEO 2011 0.OOEO 0.OOEO 0.OOEO = no detectable measurements Section 3 - Page 13

0 0

3.5 BROADLEAF VEGETATION 0 In 2011, 48 broadleaf vegetation samples were analyzed, 36 at the three indicator locations and 0 twelve at the control location. During 2011 there was an increase in 1-131 and Cs-137 0 concentrations due to Fukushima Daiichi fallout activity as indicated in the table below. 0 Broadleaf Vegetation 0 Annual Concentration with Annual Concentration without 0 Analysis Fukushima Daiichi (pCi/kg) Fukushima Daiichi (pCi/kg) 0 Indicator FL Control FR31 Indicator FRL Control FR0.

nc1-131 316 3.16 168 1cao68 1R0.00 0 0.00 0 0 Cs-137 22.9 0.01 0.00 0.00 0.00 0 0.00 0 0 FRL = Fraction of Selected Licensee Commitment Reporting Level 0

The control location was relocated during 2008. There were no gamma emitting radionuclides 0 attributable to MNS station operation identified in any indicator location or control location 0 broadleaf vegetation samples during 2011.

0 No airborne Cs-137 has been released from the plant since 1998. Cs-137 attributable to past 0 nuclear weapons testing is known to exist in many environmental media at low and highly 0 variable levels. 0 Table 3.5 gives indicator and control location highest annual means since 1979 for Cs-137. 0 0

Radioactivity identified in the MNS broadleaf vegetation samples collected 4/4/2011 was 0 determined to be from the Fukushima Daiichi incident based on the following: 0 (1) The quantities of radioactive airborne effluents from McGuire Nuclear Station during 0 2011 did not increase significantly compared to year 2010. 0 (2) REMP sample results do not typically detect the presence of these isotopes in broadleaf 0 vegetation samples. 0 (3) Similar results were seen at other US nuclear plants and state and local government 0 monitoring agencies.

0 As such, the atypical detection of these radionuclides in both indicator and control samples is 0 credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi 0 following the March 11, 2011 Tohoku earthquake and is not related to the operations of McGuire 0 Nuclear Station.

0 0

0 Section 3 - Page 14 0

0

Table 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg)

1979 2.19El 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 0.00E0

1990 4.OOEl 0.00E0 1991 3.30E1 0.00E0 1992 4.90E1 0.OOEO 1993 1.60E1 0.OOEO 1994 0.OOEO 0.00E0 1995 0.OOEO 0.OOEO 1996 O.OOEO 0.OOEO 1997 0.OOEO 0.OOEO

1998 0.OOEO 2.69E1 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.00E0 2001 0.00E0 0.00E0 2002 0.OOEO 0.00E0 0 2003 0.OOEO 0.00E0 2004 0.OOEO 0.00E0 2005 0.00E0 0.00E0

2006 2.98E1 0.00E0 2007 1.34E1 O.OOEO 2008 0.00E0 0.00E0

2009 0.00E0 0.00E0 2010 0.00E0 0.00E0

2011 2.29E1 0.00E0 0.OOEO = no detectable measurements 2011 concentration affected by Fukushima Daiichi 0

0 0

0 O ~Section 3 -Page 15 0

0

0 0

3.6 FOOD PRODUCTS In 2011, 12 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media. During 2011 there was an increase in 1-131 and Cs-137 concentrations due to Fukushima Daiichi fallout activity as indicated in the table below.

0 Food Products (Crops)

Annual Concentration with Annual Concentration without Analysis Fukushinm Daiichi (pCi/k) FukushimaDDaichi (eCi/k* 0 Indicator FRL Control FRL Indicator FRL Control FRL 1-131 142 1.42 NA NA 0.00 0 0.00 0 0

Cs-137 30.6 0.02 NA NA 0.00 0 0.00 0 FRL = Fraction of Selected Licensee Commitment Reporting Level No detectable activity attributable to MNS station operation has been detected in this media since 1987. Table 3.6 shows Cs-137 indicator highest annual means (including Fukushima S

Daiichi) with preoperational data.

0 Radioactivity identified in the MNS food 0 products (crops) samples collected 4/4/2011 was determined to be from the Fukushima Daiichi S incident based on the following:

S (1) The quantities of radioactive airborne effluents from McGuire Nuclear Station during 2011 did not increase significantly compared to year 2010. 0 (2) REMP sample results have not detected the presence of radionuclides in food products 0 (crops) samples since 1987. S (3) There is no control location sampled at McGuire Nuclear Station for this media.

0 (4) Similar results were seen at other US nuclear plants and state and local government monitoring agencies.

S S

As such, the atypical detection of these radionuclides in both indicator and control samples is S credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi S following the March 11, 2011 Tohoku earthquake and is not related to the operations of McGuire Nuclear Station.

Section 3 - Page 16

0 0 Table 3.6 Mean Concentrations of Cs-137 in Food Products

YEAR Cs-137 Indicator (pCi/kg) 1979 2.19E1 1980 2.30E1 1981 3.04E1 1982 2.46E1 1983 9.07E0

1984 8.45E0 1985 7.99E0 1986 2.15E1 1987 2.90E1 1988 0.00E0 1989 0.OOEO 1990 0.OOEO 1991 0.00E0 1992 0.00RE 1993 O.OOEO

1994 0.OOEO

1995. O.OOEO S1996", ' 0.OOEO 0 '" '-:. *1997 '" *."1998 .. 0.OOEO 0.00 0 1999 0.OOEO 2000 O.OOEO 2001 O.OOEO 2002 O.00E0 2003 0.OOEO 2004 O.OOEO 2005 0.OOEO 2006 O.OOEO 2007 0.OOEO 2008 0.OOEO 2009 0.OOEO 2010 0.OOEO 2011 3.06E1 0.OOEO = no detectable measurements 2011 concentration affected by Fukushima Daiichi 0

0 0

0 O ~Section 3 -Page 17 0

0

0 0

0 3.7 FISH 0 0

In 2011, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator S location and six at the control location.

S Figure 3.7-1 shows Cs-137 highest annual mean indicator and control location concentrations with comparisons to 5% of the reporting level. Figure 3.7-2 shows Co-60 highest annual mean indicator and control location concentrations also with 0 comparisons to 5% of the reporting level. S Table 3.7 gives indicator location highest annual means since 1980 for all radionuclides detected since the analysis change in 1988. 0 Co-58 activity was not detected in 2011 in any of the indicator or control samples. Cs-137 S

activity was detected in one of the six indicator samples taken at Location 129 with a mean 0 concentration of 22.3 pCi/kg, which is 1.12% of the reporting level. Cs-137 was not detected in S any of the six control samples. S All other radionuclides not shown in the table have demonstrated no detectable activity since 1986.

0 0

S 0

0 0

S S

S Section 3 - Page 18 S

0 0

0 Figure 3.7-1 0

0 pCi/kg Concentration of Cs-137 in Fish 140 -

0 120 4-100 +4 80 ....

0 60 ~--

0 40 +-

0 0 20 0 0 "I 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010 0 -M- Indicator Location ---- Control Location 5% of Reporting Level 0

Figure 3.7-2 0

S pCi/k g Concentration of Co-60 in Fish 0 600 0 500 0 400 0 300 0

200 0 100 t - - - --- - -

S 0 ama mm.... ppm au-. mt 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010 I -U-*Indicator Location - 0-Control Location -5% of Reporting Level Section 3- Page 19

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

Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 1980 -1.97E1 8.36E0 -2.25E1 -2.70E1 -4.13E0 1981 -2.71E0 -2.98E0 -2.65E0 -1.99E0 1.80El 1982 -3.83E0 8.16E0 -4.34E-1 -8.22E-1 2.69E1 1983 -2.60E0 2.60E1 1.11EL -1.32E0 6.03E1 1984 3.61E0 1.45E2 2.82E1 3.11 El 4.38E1 1985 2.53E-1 7.19E0 1.72E1 -1.56E0 1.86E1 1986 1.03E0 3.17E1 2.96E1 1.67E1 3.49E1 1987 0.OOEO 2.71E2 1.25E2 2.60E1 5.10E1 1988 1.20E! 7.70E1 0.OOEO 2.70E1 3.60E1 1989 9.OOE1 4.05E2 2.99E2 1.10El 3.50E1 1990 0.00E0 5.60E1 4.1OE1 0.00E0 3.30E1 1991 6.20E0 1.40E1 6.50E1 5.90E0 2.60E1 1992 0.0OEO 0.00E0 0.OOEO 0.00E0 2.90E1 1993 0.00E0 8.20E1 1.30El O.OOEO 1.60El 1994 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.10E1 1995 O.OOEO 0.OOEO 0.00E0 0.OOEO 2.70E1 1996 0.00E0 0.OOEO 0.00E0 0.OOEO 2.78E1 1997 0.00E0 0.OOEO 0.OOEO 0.00E0 1.62E1 1998 0.OOEO 0.OOEO 0.OOEO O.OOEO 3.21E1 1999 0.OOEO 3.53E1 0.00E0 0.OOEO 2.10El 2000 0.OOEO 4.28E1 0.OOEO 0.00E0 2.34E1 2001 0.00E0 1.32E1 0.00E0 0.00E0 3.04E1 2002 0.OOEO 0.OOEO 0.00E0 0.00E0 2.33E1 2003 0.00E0 0.OOEO 0.00E0 0.OOEO 3.05E1 2004 0.00E0 0.OOEO 0.OOEO 0.00E0 0.OOEO 2005 0.OOEO 0.00E0 0.OOEO 0.00E0 0.00E0 2006 0.OOEO 0.OOEO 0.OOEO 0.00E0 1.08E1 2007 0.OOEO 0.OOEO 0.OOEO O.00E0 2.1 El 2008 0.00E0 0.OOEO 0.00E0 O.OOEO 1.24E1 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.76E1 2010 0.00E0 0.00E0 0.00E0 0.00E0 2.33E1 2011 0.00E0 0.00E0 0.OOEO 0.00E0 2.23E1 0.OOEO no detectable measurements All negative values have been replaced with zeros for calculational purposes 0

0 0

Section 3 - Page 20 0 0

0

0 0 3.8 SHORELINE SEDIMENT 0 In 2011, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.

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

0 0 Cs- 137 activity was detected in two of the 0 four indicator samples taken. The shoreline sediment location with the 0 highest annual mean was Location 130 0 with a mean concentration of 102 pCi/kg. Cs-137 was not detected in any control location samples...

0 Table 3.8 gives indicator location highest annual means since 1979 for all radionuclides 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 500-f 0 400 .

0 0 250 1 - --- ---------

S 0

250 0

0 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 I -U- Indicator Location - Control Location I There is no reporting level for Cs-137 in shoreline sediment Section 3 - Page 21

0 Figure 3.8-2 pCi/kg Concentration of Co-60 in Shoreline Sediment 0 300 0

250 0 S

200 4 0

100 0

- g n- g 0 50 n 0

1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 0 Indicator Location Control Location I 0

There is no reporting level for Co-60 in shoreline sediment 0

Table 3.8 Mean Concentrations of Radionudides in Shoreline Sediment (pCi/ka) 0 Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator 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 0 1981 2.13E1 1.20El 8.21E0 3.97E1 3.36E1 0 1982 5.38E1 1.66E1 -1.69E0 7.67E1 4.40E1 1983 4.40E0 3.43E1 2.12E1 7.65E1 8.02E1 0 1984 1.19E1 7.11El 3.04E1 3.34E1 9.13E1 0 1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 1986 1.37E1 1.02El 1.16EI 6.35E1 1.53E2 0 1987 0.00E0 1.06E2 2.10El 4.20E1 1.65E2 1988 6.50E0 9.20E1 1.20E1 9.10EO 2.66E2 S 1989 2.90E1 3.80E1 2.90E1 5.30E1 6.50E1 0 1990 3.80E1 2.70E1 1.68E2 O.OOEO 6.10El 1991 2.80E1 5.30E1 1.31E2 O.OOEO 1.03E2 1992 9.40E0 O.OOEO 5.10E1 9.20E0 8.60E1 1993 0.OOEO 2.20E1 8.60E1 0.OOEO 9.30E1 1994 4.10E1 O.OOEO 0.OOEO 0.OOEO 8.OOE1 1995 1.70E1 0.OOEO 2.30E1 0.OOEO 1.38E2 1996 2.90E1 1.78E1 3.50E1 0.OOEO 1.47E2 1997 0.00E0 0.00E0 1.11E2 3.10E1 1.36E2 1998 O.OOEO 0.00E0 5.21E1 O.00E0 9.97E1 1999 0.OOEO 2.47E1 8.49E1 O.OOEO 6.51E1 2000 0.OOEO 3.04E1 0.OOEO 0.OOEO 1.08E2 Section 3 - Page 22

Table 3.8 continued Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 2001 0.OOEO 0.OOEO 0.OOEO 0.00E0 2.77E1 2002 2.24E1 0.OOEO 0.00E0 0.00E0 1.59E2 2003 0.OOEO 0.00E0 0.OOEO 0.OOEO 1.11E2 2004 0.OOEO 0.00E0 0.OOEO O.OOEO 7.17El 2005 0.OOEO 0.OOEO 0.00E0 0.00E0 8.08E1 2006 O.OOEO 0.OOEO O.00E0 0.00E0 1.59E2 2007 0.OOEO 0.OOEO O.OOEO 0.00E0 1.14E2 2008 0.OOEO 0.00E0 0.00E0 O.OOEO 1.77E2 2009 0.OOEO 0.OOEO 0.00E0 0.00E0 5.08E1 2010 0.OOEO 0.OOEO 0.00E0 0.OOEO 7.58E1 2011 O.00E0 0.OOEO 0.00E0 0.OOEO 1.02E2 0

0 0

S 0

0 0

0 Section 3 - Page 23

3.9 DIRECT GAMMA RADIATION 3.9.1 ENVIRONMENTAL TLD 0 In 2011, 163 TLDs were analyzed, 159 at indicator locations, four at the control location. TLDs are collected and analyzed quarterly. A transit background for environmental TLDs is determined based on ANSI N545. The highest annual mean exposure for an indicator location was 106 milliroentgen. The annual mean exposure for the control location was 94 milliroentgen.

Figure 3.9-1 and Table 3.9-A show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year. Preoperational data and ten year rolling averages are also given. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise a number of data points with the control average representing only one location.

The control location has historically been higher than indicator locations. This is most likely an artifact of the underlying geologic structures at the control location. TLDs located greater than 5 miles from the plant demonstrate a wide range of background radiation levels. The control location is 15.5 miles WNW, well beyond the influence of the plant.

The calculated total body dose from gaseous effluents for 2011 was 2.92E-1 millirem, which is 0.45% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact on the measured TLD values.

A TLD intercomparison program is conducted as part of the quality assurance program. Results of this program are included in section 5.10.

Figures 3.9-2 and 3.9-3 show the TLD mean for each inner and outer ring TLD location from 1987 through 2011.

3.9.2 ISFSI 0 The McGuire ISFSI is located inside the protected area on the west side of the plant approximately 244 meters from plant centerline. The ISFSI protected area fence on the north side is approximately 60 meters from the owner control fence atop the berm adjacent to Lake Norman and just west of the intake structure. At a distance of 425 meters the ISFSI is closest to the Exclusion Area Boundary (EAB) on the west side along the Catawba River. The nearest resident to the ISFSI is just over a kilometer away in the east sector with the next closest resident at 1.1 kilometers in the WNW sector.

Section 3 - Page 24 0

0 0

0 The ISFSI is situated in a slight depression in relationship to other structures inside the protected area. The ISFSI direct radiation to the north is shielded by the berm on the south boundary of Lake Norman. The EAB to the west of ISFSI is shielded from direct radiation by the drop in elevation from 754' at the ISFSI to the river bank below the Cowan's Ford Dam. These features lessen the dose impact to the public accessing the EAB west of ISFSI and the Lake Norman shoreline inside the EAB north of ISFSI.

0 0 There are 38 loaded casks currently in the ISFSI. There are no effluent releases from the fuel canisters stored inside the shielded casks to the environment. Doses measured by 0 environmental TLDs show little or no change since the current TLD system was 0 implemented.

0 0

0 Figure 3.9-1 mR/year Direct Gamma Radiation (TLD) Results 250 ý 0

0 200 0

150 0

0 100 0 50 0

0 0 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 S --- InnerRing Outer Ring -- Control 0

S There is no reporting level for Direct Radiation (TLD) 0 Section 3 - Page 25

Table 3.9-A Direct Gamma Radiation (TLD) Results YEAR Inner Ring Average Outer Ring Average Control

( ymR/r) (mR/yr) (mR/yr) 0 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 9.02E13 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 6.25E13 1991 5.14E1 5.59E1 6.80E1 1992 5.65E1 5.55E1 7.60E1 1993 5.61E1 5.71E1 7.20E1 1994 6.40E1 6.93E1 9.55E1 1995 8.36E1 8.25E1 1.08E2 1996 7.18E1 7.02E1 9.88E1 1997 6.22E1 6.68E1 9.45E1 1998 6.59E1 6.32E1 8.69E1 1999 6.23E1 6.05E1 8.96E1 2000 6.50E1 6.08E1 8.97E1 2001 6.51E1 6.22E1 9.33E1 2002 6.57E1 6.43E1 9.48E1 2003 6.74E1 6.45E1 9.20E1 2004 6.46E1 6.33E1 9.16El 2005 6.62E1 6.34E1 9.44E1 2006 6.75E1 6.58E1 9.17E1 2007 6.84E1 6.60E1 9.00E1 2008 6.69E1 6.58E1 9.14E1 2009 6.67E1 6.53E1 9.12El 2010 6.63E1 6.53E1 8.92E1 Average (2001 - 2010) 6.65E1 6.46E1 9.20E1 2011 6.51El 6.64E1 9.40E1 Values are based on two quarters due to change in TLD locations.

0 0

0 Section 3 - Page 26 0

0

0 0

Figure 3.9-2 0

0 mR/year McGuire Inner Ring (TID) Results 120 0 110 100 90 S 80 70 0

0 60 0 50 -

40 , . J.

0 30 0

20 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW

(144) (145) (146) (147) (148) (149) (189) (151) (152) (153) (190) (154) (156) (143) ----

-- 2011 -1987-20101lIgh/Low/Mean 0

Table 3.9-B Direct Gamma Radiation (TLD) Results Inner Rin2 (mR/year) 0 Sector 1987 - 2010 1987 - 2010 1987 - 2010 0 (Location) Mean Low High 2011 6.20E+01 0 NNE (144) 5.99E+01 3.88E+01 8.02E+01 6.32E+01 NE (145) 5.96E+01 3.75E+01 7.59E+01 ENE (146) 5.79E+01 3.64E+01 8.13E+01 5.80E+01 E (147) 6.16E+01 3.89E+01 8.69E+01 6.12E+01 0 ESE (148) 5.43E+01 3.75E+01 7.50E+01 5.52E+01 0 SE (149) 5.14E+01 3.11E+01 6.70E+01 5.12E+01 0 SSE (189) 6.17E+01 4.73E+01 7.20E+01 6.32E+01 S (151) 6.16E+01 3.97E+01 8.45E+01 6.OOE+01 S SSW (152) 5.79E+01 3.80E+01 7.64E+01 6.OOE+01 SW (153) 7.66E+01 4.89E+01 9.89E+01 7.88E+01 WSW (190) 8.45E+01 6.38E+01 9.41E+01 7.92E+01 W (154) 8.18E+01 4.88E+01 9.93E+01 8.72E+01 WNW (156) 7.74E+01 6.31E+01 1.02E+02 7.12E+01 NW (143) 6.28E+01 3.87E+01 8.15E+01 6.60E+01 NNE (144) 5.99E+01 3.88E+01 8.02E+01 6.20E+01 NE (145) 5.96E+O1 3.75E+01 7.59E+01 6.32E+01 Section 3 - Page 27

0 0

Figure 3.9-3 0

mR/year McGuire Outer Ring (TLD) Results 0

120 0 110 0 100 0 go ~ S 80 0 70 - 0 60 0 50 ,

0 40 0 30 0 20 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0

(157) (158) (159) (160) (161) (162) (163) (164) (165) (166) (167) (168) (169) (170) (171) (172) 0 S---2011 - 1987-201OHigh/Low/Mean 0 0

0 Table 3.9-C Direct Gamma Radiation (TLD) Results Outer Rini! (mR/year) 0 Sector 1987 - 2010 1987 - 2010 1987 - 2010 0

(Location) Mean Low High 2011 0 N (157) 6.39E+01 4.27E+01 8.56E+01 6.12E+01 0 NNE (158) 6.14E+01 4.37E+01 8.24E+01 6.20E+01 0 NE (159)

ENE (160) 6.64E+01 6.71E+01 5.23E+01 4.82E+01 8.90E+01 8.29E+01 9.32E+01 7.40E+01 0

E (161) 6.16E+01 4.07E+01 7.68E+01 6.32E+01 0

ESE (162) 4.88E+01 3.50E+01 6.70E+01 5.OOE+01 0 SE (163) 6.17E+01 4.40E+01 9.64E+01 5.OOE+01 0 SSE (164)

S (165) 4.68E+01 7.18E+01 3.26E+01 4.05E+01 6.37E+01 9.OOE+01 4.52E+01 7.52E+01 0

SSW (166) 5.62E+01 3.43E+01 7.38E+01 7.32E+01 0

SW (167) 7.56E+01 6.20E+01 8.94E+01 7.60E+01 0 WSW (168) 6.18E+01 4.17E+01 7.61E+01 6.52E+01 0 W (169) 5.96E+01 4.04E+01 7.81E+01 5.60E+01 0 WNW (170) 8.32E+01 6.18E+01 1.03E+02 8.32E+01 NW (171) 6.73E+01 4.98E+01 9.57E+01 6.72E+01 0

NNW (172) 6.76E+01 4.42E+01 8.46E+01 7.OOE+01 0

0 0

0 S

0 Section 3 - Page 28 0

3.10 LAND USE CENSUS The land use census was conducted May 20, 2011 as required by SLC 16.11.14. Table 3.10 summarizes census results. A map indicating identified locations is shown in Figure 3.10.

During the 2011 census, no new residences (nearer to the plant), irrigated gardens (superior to existing gardens) or milk locations were identified. The nearest residence is located in the East sector at 0.48 miles. No environmental program changes were required as a result of the 2011 land use census.

Table 3.10 McGuire 2011 Land Use Census Results 0 Sector Distance Sector Distance (Miles) (Miles) 0 Nearest Residence 2.53 Nearest Residence 1.45 S Nearest Garden 3.14 0 N Nearest Garden (irrigated)

Nearest Milk Animal 2.79

- Nearest Milk Animal -

S Nearest Residence 1.23 - Nearest Residence 2.56 NNE Nearest Garden (irrigated) 4.27 SSW Nearest Garden 2.94 0 Nearest Milk Animal Nearest Milk Animal -

Nearest Residence 1.21 Nearest Residence 1.85 NE Nearest Garden 1.80 SW Nearest Garden 1.98

. NearestMilk Animal- - Nearest Milk Animal -

Nearest Residence 0.57 Nearest Residence 1.01 0 ENE Nearest Garden Nearest Milk Animal 1.98 WSW 'Nearest Garden Nearest Milk Animal 1.33 Nearest Residence 0.48 Nearest Residence 1.15 0 E Nearest Garden 2.07 w Nearest Garden 1.23 Nearest Milk Animal - Nearest Milk Animal -

Nearest Residence 0.65 Nearest Residence 0.88 0 ESE Nearest Garden 1.20 WNW Nearest Garden 2.06 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.67 Nearest Residence 0.95 1.68 SE Nearest Garden 1.18 NW Nearest Garden 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 1.06 Nearest Residence 1.48 1.69 0 SSE Nearest Garden Nearest Milk Animal 1.26 NNW Nearest Garden (irrigated)

Nearest Milk Animal -

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

Section 3 - Page 29

Figure 3.10 McGuire Nuclear Station 2011 Land Use Census Map Legend A MNSGardens J* MNSResidence

,N/ MNSRailroads

/ NavteqHwys

/'-. NavteqStreets States i---"] Counties ANHDWaterbody A*,Approximate location of features shown W

0 0.5 1 2 Miles Projection NCSP NAD2 Section 3 -Page 30

0

S 4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2011 MNS REMP samples. Only those samples that

were not affected by the Fukushima Daiichi fallout were used to calculate doses. The 0primary 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 background concentration at the corresponding control location was subtracted.

Regulatory Guide 1.109 consumption rates for the maximum exposed individual were

used in the calculations. When the guide listed "NO DATA" as the dose factor for a given radionuclide and organ, a dose factor of zero was assumed.

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

individual critical population and pathway dose calculations are reported in Table

4.1-B.

0* REMP-based dose estimates are not reported for airborne radioiodine, milk or 0vegetation sample types because no radionuclides attributable to MNS station operations were detected. Naturally occurring K-40 and Be-7 were detected in some samples but were not included in any REMP-based dose estimates. Dose estimates are 0not reported for surface water because sampled surface water is not considered to be a Spotable drinking water source although surface water tritium concentrations are used in 0calculating doses from fish. Exposure estimates based upon REMP TLD results are

discussed in Section 3.9.

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

(excluding TLD results) collected during 2011 was 1.03E-1 mrem to the maximum

exposed child liver, total body, thyroid, kidney, lung, and GI-LLI from the consumption of drinking water.

4.2 ESTIMATED DOSE FROM RELEASES 0

Throughout the year, dose estimates were calculated based on actual 2011 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 - Page 1 0

0

0 S

The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, inhalation, milk and vegetation pathways.

4.3 COMPARISON OF DOSES The environmental and effluent dose estimates given in Table 4.1-A agree reasonably well. The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways. This indicates that effluent program dose estimates are both valid and reasonably conservative.

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

S Additionally, in 2010 McGuire began reporting estimated dose from effluent Carbon 14 (C-14). This change came about with the issuing of Regulatory Guide 1.21, Revision 2, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste. A description of this change is found in the 2010 Annual Radiological Effluent Release Report. C-14 is not measured in the environment and therefore, environmental and effluent doses from C-14 cannot be compared directly.

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 2011 environmental sample results was 1.52E-1 mrem to the child liver. The maximum total organ dose of 1.86E-1 mrem for liquid effluent-based estimates was to the child GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum organ dose for gaseous effluent estimates was 8.70E-1 mrem to the child bone. No radioactivity was detected from gaseous pathways in environmental samples; therefore, there is no calculated dose.

The doses calculated do not exceed 40CFR190 or I0CFR50 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of MNS are being maintained well within regulatory limits.

0 0

Section 4 - Page 2 0 0

0

0 0

0 TABLE 4.1-A Page 1 of 2 MCGUIRE NUCLEAR STATION 0

2011 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

LIQUID RELEASE PATHWAY 0

0 Dose (Maximum 3)

Environmental or Critical Critical (mrem) 0 Organ Effluent Data Age (1) Pathway (2) Location 0

0 Teen Shoreline Sediment 130 (0.52 mi SW) 2.68E-04 Skin Environmental Skin Effluent Teen Shoreline Sediment Discharge Pt. 2.90E-03 Bone Environmental Child Fish 129 (0.51 mi ENE) 5.03E-02 Bone Effluent Child Fish Discharge Pt. 1.01E-02 Liver Environmental Child Drinking;Water 101 (3.31 mi E) 1.52E-01 Liver Effluent Child Drinking Water 3.31 mi E 1.85E-01 T. Body Environmental Adult Drinking Water 101 (3.31 mi E) 1.12E-01 T. Body Effluent Child Drinking Water 3.31 mi E 1.79E-01 Thyroid Environmental Child Drinking Water 101 (3.31 mi E) 1.04E-01 Thyroid Effluent Child Drinking Water 3.31 mi E 1.76E-01 Kidney Environmental Child Drinking Water 101 (3.31 mi E) 1.20E-01 Kidney Effluent Child Drinking Water 3.31 mi E 1.79E-01 Lung Environmental Child Drinking Water 101 (3.31 mi E) 1.1OE-01 0 Lung Effluent Child Drinking Water 3.31 mi E 1.77E-01 0

GI-LLI Environmental Child Drinking Water 101 (3.31 mi E) 1.04E-01 0 1.86E-01 GI-LLI Effluent Child Drinking Water 3.31 mi E 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 2 0

GASEOUS RELEASE PATHWAY 0

S IODINE, PARTICULATE, and TRITIUM 0

0 Critical Critical Location Maximum Dose (3) S Organ Environmental or Effluent Data Age (1) Pathway (2) (mrem)

Skin Environmental - - O.OOE+00 Skin Effluent All Ground Plane 1.5 mi. NE 4.20E-07 Bone Environmental - - O.OOE+00 Bone Effluent Child Vegetation 1.5 mi. NE 8.70E-01 Liver Environmental - - O.OOE+00 Liver Effluent Child Vegetation 1.5 mi. NE 2.92E-01 T. Body Environmental - - O.OOE+00 T. Body Effluent Child Vegetation 1.5 mi. NE 2.92E-01 Thyroid Environmental - - O.OOE+00 Thyroid Effluent Child Vegetation 1.5 mi. NE 2.92E-01 0 0

Kidney Environmental - - O.OOE+00 0 Kidney Effluent Child Vegetation 1.5 mi. NE 2.92E-01 0 Lung Environmental - - O.OOE+00 S Lung Effluent Child Vegetation 1.5 mi. NE 2.92E-01 S

GI-LLI Environmental - - O.OOE+00 GI-LLI Effluent Child Vegetation 1.5 mi. NE 2.92E-01 0 0

(1) Critical Age is the highest total dose (all pathways) to an age group. 0 (2) Critial Pathway is the highest individual dose within the identified Critical Age group.

0 (3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.

0 Section 4 - Page 4

TABLE 4.1-B Maximum IndividualDose for 2011 based on Environmental Measurements (torem) for McGuire Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 Drinking Water O.OOE+00 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-O1 1.01E-O1 O.OOE+O0 Milk O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL O.OOE+00 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-01 O.OOE+00 Child Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-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 5.03E-02 4.93E-02 8.24E-03 1.13E-03 1.68E-02 6.78E-03 1.43E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 4.80E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.60E-05 TOTAL 5.03E-02 1.52E-01 1.11E-01 1.04E-01 1.20E-01 1.10E-01 1.04E-01 5.60E-05 Teen Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 5.39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation O.OO0E+ O.OOE+0 O.OOE++ O.OOE+ 00 0.0013E+00 -OOE+00 O.OOE+00 Fish 4.OOE-02 5.45E-02 1.99E-02 1.37E-03 1.95E-02 8.40E-03 -2T.13E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.30E-04 O.OOE+00 O.OOE+00 O.OOE+00 -O.OOE+00 2.68E-04 TOTAL 4.OOE-02 1.08E-01 7.40E-02 5.53E-02 7.34E-02 6.23E-02 5.60E-02 2.68E-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 7.64E-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 0.00E+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 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 3.73E-02 5.28E-02 3.52E-02 1.78E-03 1.91E-02 7.54E-03 2.77E-03 0.00E+00 Shoreline Sediment O.OOE+00 'O.OOE+00 4.11 E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.80E-05 TOTAL 3.73E-02 1.29E-01 1.12E-01 7.82E-02 9.55E-02 8.39E-02 7.92E-02 4.80E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 -Page 5

McGuire Nuclear Station Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (i) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4ALE-06 NO DATA 7.31E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0013+00 0.00E+00 CO-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 Fe-59 3.08E-05 5.3SE-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E,+00 0.00E+00 0.00E+00 0.OO13+00 0.00E+00 Zn-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.7313-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Zr-9S 2.06E.-7 5.02E-08 3.56E-08 NO DATA 5AIE-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+a00 0.OOE+00 0.00E+00 0.00E+00 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1-S1E-06 ALL 0.00 0.00E+00 0.00E.00 0.00E+00 0.0013+00 0.OOE+00 0.00E+00 0.00E+00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0013+00 0.00E+00 0.00E+00 Cs-137 5.22E-04 6.1113-04 4.3313-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.0013+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 101 997 0.00E+00 1L01E-01 1.01E-01 1.01E-01 1.01E-01 1.01"I0 1.O1E.01 Dose Commitment (mrem) = 0.OOE+00 1.01E-01 1.01E-01 1.O1E-01 1.01E-01 1.O1E-01 1.01E-01 Section 4 -Page 6

McGuire Nuclear Station Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed,Child Child Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/i)

Usage (intake in one year) = 510 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 -3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E4.00 0.00E+00 0.OOE+00 0.00E+00 0.00E-+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00' 0.00E+00: 0.00E4'00 0.O0E+00 0.OOE+00 0.00E+00 0.OOE-400 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;00OE-i00 0.00E+00 0.O0E+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 * '0.00E+00 0.0-O.OOE+00 0.00 OO0E+00 0.OOE+00 0.00E+00 0.OOE+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL '0.00 0.00E+00 0.00E+00 0.OOE+00W 0.'OE+00 0.OOE+00 0.00E+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 0.00E+00 0.OOE+00 0.00E+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 0.00E-i00 0.OOE+00 0.O0E+00 0.00E+00 0.00E-i00 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.00E4-00 0 OOE+00 0.00E+00 0.O0E+00 0.OOE+00 0.00E4.i00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 101 997 0.OOE+00 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 Dose Commitment (mrem) = 0.00E+00 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 1.03E-01 Section 4 - Page 7

McGuire Nuclear Station Dose from Fish Pathwayfor 2011 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 897 pCi/I x 0.9 = 807 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator 'Fish Radionuclide Bone Liver T. Body. Thyroid Kidney , Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.O0E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6AI1E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.0713-06 ALL 0.00 0.OOE+00 0.0011+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 129 22.3 5.03E-02 4.82E-02 7.11E-03 0.00E+00 1.57E-02 5.65E-03 3.02E-04 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 128 807 0.00E+00 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 Dose Commitment (mrem) = 5.03E-02 4.9313-02 8.24E-03 1.13E-03 1.68E-02 6.78E-03 1.43E-03 Section 4 - Page 8

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2011 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

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

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

Sediment Surface Mass = 40 kg/rn Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mnrenm/hr per pCi/mr) x Shore Width Factor x Sediment SurfaceMass (kg/mn) x Sediment Concentration (pCi/kg)

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

(rirem/hr per pCi/m ) Indicator Sediment. (mdrem)

T. Body Skin Radionuclide T. Body Skin Location (pCi/kg)

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 0.00E+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 102 4.80E-05 5.60E-05 Dose Comnitment (aiWrem) = 4.80E-05 5.60E-05 Section 4 - Page 9

McGuire Nuclear Station Dosefrom DrinkingWater Pathwayfor 2011 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.%0E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.00E+O0 0.00E+00 0.00E+00 0.00K400 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00K400 0.00E+00 0.00E+00 0.00E-i40 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.00E400 0.00KEi40 0.00E+00 0.00K+00 0.00E+00 0.00EiA00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E.+00 0.00E+00 0.00K+00 0.00E440 0.00E+i00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA &47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+i00 0.00E44) 0.00E+t00 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 0.00K+Q0 0.00E+00 0.00E+00 0.00E+00 0.00K+00 0.00K+00 Zr-95 4.12E-08 1.30E-08 8,94E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05 ALL 0.00 0.00E+00 0.00E400 0.00E400 0.OOE.I00 0.00K400 0.OOE+00 0.00E+00O 1-131 5.M5E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.OOK.*00 O.00K+00 0.00E+00 0.OOK+00 0.OOE+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00K+00 0.00E+00 0.00E+i00 0.00E+00 0.00E+0 0.00KEiOO Cs-137 1.12E-04 1.49E-0 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OE00K 0.00E+00 0.00E-i40 0.OOE.*00 0.00KI40 0.OE00K Ba~A-140 2.84E-05 3.48K-OS 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+O0 0.00E+00 0.00E400 0.00E+00 0.00E+i00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 101 997 O.OOE+00 5-39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 Dose Comnmitnent (mrem)= 0.00E+O0 5.39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 5.39E-02 Section 4 - Page 10

McGuire Nuclear Station Dose from Fish Pathwayfor 2011 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 = 897 pCi/I x 0.9 = 807 pCi/kg Usage (intake in one year) 16 kg Highest Annual Ingestion Dose Factor Net Mean Dose '(irem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCilkg) 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 0.00E+001 0 OOE+00 O.ooE+00 0.OOE+00 0.OOE+00 0.00E+60 Co-58 NO DATA 9.72E-07 2.2411-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.00E+ý00' 0.00E+00 0.00E+00 0.OOE+00 0.00E+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 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.O0E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6-33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00, 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.0011+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00: *.. OOE+00 0.00E+00 0.00E+00 0.00E+00 O.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-06 129 22.3 4.OOE.02 5.32E-02 1.85E-02 0.00E+00 1.81E-02 7.03E-03 7.56E-04 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 128 807 0.00E+00 1.37E-03 1-37E-03 1.37E-03 1.37E-03 1.37E-03 1.37E-03 Dose Commitment (mrem) = 4.OOE.02 5.45E-02 1.99E-02 1.37E-03 1.95E-02 8A40E-03 2.13E-03 Section 4 - Page 11

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2011 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

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

Shore Width Factor = 0.2 (river shoreline - location 130) 2 Sediment Surface Mass = 40 kg/m Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External 2

Dose Factor (mrem/hr per pCi/m ) x Shore Width Factor x Sediment Surface Mass (kg/rm) x Sediment Concentration (pCi/kg)

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

(mrem/hr per pCi/n ) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.OOE+00 0.00E+00 Co-58 7.OOE-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 O.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 130 102 2.30E-04 2.68E-04 Dose Commitment (mnrem) = 2.30E-04 2.68E-04 Section 4 - Page 12 000090000000000000001000000000000000000000000

McGuire NuclearStation Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1AOE-05 ALL 0.00 0.00E+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Fe-59 4.34E-06 1.0213-05 3.9113-06 NO DATA NO DATA 2.85E-06 3AOE-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.1413-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 - 0.00E+00 0.00E+00 0.0011+00 0.00E+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 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3A2E-09 NO DATA 2.10E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.OOE+00 0.O0E+00 0.0013+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+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 O.OOE+00 0.00E+00 0.0013+00 0.00E+00 0.O0E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.2113-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00i 0.00E+00O 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0011+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+,00 0.00E+00 0.0013+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.0011+00 H-3 NO DATA 1.0513-07 1.0513-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 101 997 0.OOE+00 7.6413-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 Dose Commitment (mrem) = 0.O0E+00 7.64E-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 7.64E-02 Section 4 - Page 13

McGuire Nuclear Station Dosefrom Fish Pathwayfor 2011 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 897 pCi/! x 0.9 = 807 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T.Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.0E+00 Co-58 NO DATA 7.45E-07 1.67E-0 NO DATA NO DATA NO DATA I.SlE-05 ALL 0.00 0.OOE+O0 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1-54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 O.00E+O0 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Cs-134 6.22E-05 1.48E-44 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.OOE+00 0.00E+00 0.00E400 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 129 22.3 3.73E-02 5.10E-02 3.34E-02 0.00E+00 1.73E-02 5.76E-03 9M8E-04 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.OSE-07 1.05E-07 128 807 0.OOE+00 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 1.78E-03 Dose Commitment (mrem) = 3.73E-02 5.28E-02 3.52E-02 1.78E-03 1.91E-02 7.54E-03 2.77E-03 Section 4 - Page 14 0000000000000000000000100000000

90 0

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2011 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) kgm_2 Sediment Surface Mass = 40 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation'(hr) x External 2

Dose Factor (mremlhr per pCi/rn ) x Shore Width Factor x Sediment Surface Mass (kg/r*) x Sediment Concentration (pCi/kg)

External Dose Factor Standing T [ighest Annual Net Dose on Contaminated Ground Nvlean Concentration:

(mrem)

(mrem/hr per pCi/mi) 2 ndicator Sediment, Radionuclide T. Body Skin I Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 O.OOE+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+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 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 102 4.11E-05 4.80E-05 Dose Commitment (mrem) = 4.11E-05 4.80E-05 Section 4 - Page 15

ML12145A050

Text

SUMMARY

2.0 INTRODUCTION

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