Text

Units 1 & 2, Transmittal of Annual Radiological Environmental Operating Report
	ML081420434
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/14/2008
From:	Brandi Hamilton; Duke Energy Carolinas, Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081420434 (90)
	v • d • e

PDuke EEnergy BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MG01VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy. corn May 14, 2008 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report Pursuant to the requirements of Technical Specification 5.6.2, attached is the Annual Radiological Environmental Operating Report (AREOR) for the 2007 calendar year.

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

Bruce H. Hamilton

-3 5 www. duke-energy. com

U. S. Nuclear Regulatory Commission May 14, 2008 Page 2 Mr. John Stang, Project Manager U. S.' Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. Louis Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Division of Radiation Protection 3825 Barrett Drive Raleigh, N.C. 27609-7221 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Site

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Duke DEnergy° McGuire Nuclear Station Units 1 and 2 AREOR Annual Radiological Environmental Operating Report 2007

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B&Duke

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P4 Energy.

ANNUAL RALIOLOGICAL ENVIRONMENTAL OPERATING REPORT 0

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0 DUKE ENERGY CORPORATION MCGUIRE NUCLEAR STATION Units l and 2 0

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2007 0

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00 TABLE OF CONTENTS 0

0 1.0 Executive Summary 1-1 2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 2.3 Statistical and Calculational Methodology.

2-2 2.3.1 Estimation of the Mean Value.

2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2-3 2.3.3 Trend Identification.

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

3-5 3.3 Surface Water 3-7 3.4 Milk.

3-9 3.5 Broadleaf Vegetation.

3-10 3.6 Food Products 3-11 3.7 Fish.

3-12 3.8 Shoreline Sediment 3-15 3.9 Direct Gamma Radiation 3-18 3.10 Land Use Census 3-20 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-1 4.3 Comparison of Doses.

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

5-2 5.7 U.S. Nuclear Regulatory Commission Inspections 5-2 5.8 State of North Carolina Intercomparion Program 5-2 5.9 TLD Intercomparison Program 5-3 5.9.1 Nuclear Technology Services Intercomparison Program 5-3 5.9.2 State of North Carolina Intercomparison Program 5-3

5.9.3 Internal Crosscheck (Duke Energy) 5-3 6.0 References 6-1 0

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Appendices Appendix A: Environmental Sampling and Analysis Procedures A-I I.

Change of Sampling Procedures A-2 II.

Description of Analysis Procedures A-2 III.

Change of Analysis Procedures,;

A-3 IV. Sampling and Analysis Procedures A-3 A. 1 Airborne Particulate and RRadioiodine 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 M ilk.

B-6 Broadleaf Vegetation B-7 Food Products *.

B-8 Fish.

B-9 Shoreline Sediment B-10 Direct Gamma Radiation (TLD)

B-1 I Appendix C:. Sampling Deviations and Unavailable'Analyses C-I C. I Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 LIST OF FIGURES.

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2.1-1 Sampling Locations Map (0.5 Mile Radius) 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius)..

2-5 3.1 Concentration of Gross Beta in Air Particulate-.

3-3 3.2 Concentrationof Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water 3-7 3.7-1 Concentration of Cs-137 in Fish 3-13 3.7-2 Concentration of Co-60 in Fish 3-13 3.8-1.

Concentration of Cs-137.inShoreline Sediment 3-15

-3.8-2 Concentration of Co-60 in Shoreline Sediment 3-16

' 319 Direct Gamma Radiation (TLD) Results 3-18

- 3.10 2007 Land Use Census Map'

.3-21 LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 ii

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0 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2.2-B REMP Analysis Frequency 2.2-C Maximum Values for the Lower Limits of Detection 3.1-A Mean Concentrations of Radionuclides in Air Particulate 3.1-B Mean Concentrations of Air Radioiodine (171 31 )

3.2 Mean Concentrations of Radionuclides in Drinking Water 3.3 Mean Concentrations of Tritium in Surface Water 3.4 Mean Concentrations of Cs-137 in Milk 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation 3.6 Mean Concentrations of Cs-137 in Food Products 3.7 Mean Concentrations of Radionuclides in Fish 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment 3.9 Direct Gamma Radiation (TLD) Results 3.10 Land Use Census Results 4.1-A 2007 Environmental and Effluent Dose Comparison 4.1-B Maximum Individual Dose for 2007 based on Environmental Measurements for McGuire Nuclear Station 5.0-A 2007 Cross-Check Results for EnRad Laboratories 5.0-B 2007 Environmental Dosimeter Cross-Check Results LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order) 2-8 2-8 2-9 3-3 3-4 3-6 3-8 3-9 3-10 3-11 3-14 3-16 3-19 3-20 4-3 4-6 5-4 5-9 BW BiWeekly C

Control DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System LLD Lower Limit of Detection M

Monthly MDA Minimum Detectable Activity MNS McGuire Nuclear Station mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Process Q

Quarterly REMP RadioloFical Environmental Monitorint Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermolumninescent Dosimeter pCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W

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0 1.0 EXECUTIVE

SUMMARY

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This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2007.

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 0environmental measurements and effluent data, analysis of trends in environmental

radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results.

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

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLC's). Required analyses were performed and detection capabilities were met for all collected samples as required by SLC's.

Eleven-hundred fifty-five samples were

analyzed comprising 1,636 test results in order to compile data for the 2007 report. Based on the annual land use census, the current number of sampling sites for McGuire Nuclear

Station is sufficient.

0 0Concentrations observed in the environment in 2007 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline

sediment and fish are higher than the activities reported for samples collected prior to the 0operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLC's.

Additionally, environmental radiological monitoring data is consistent with 0

effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by 0environmental sampling data, excluding

TLD results, was 1.79E-1 mrem for 2007.

It is therefore concluded that station operations has had no significant radiological impact on the health and

safety of the public or the environment.

0 Vegetation Sampling 0

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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).

MNS consists of two pressurized water reactors. Each reactor unit is essentially a mirror image of the other joined by an auxiliary building housing both separate and common equipment. Each unit was designed to produce approximately 1200 gross Megawatts of electricity.

Unit 1

achieved criticality August 8, 1981 and Unit 2 on May 8, 1983.

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

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

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

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

existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.

The 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 0Commitments Manual, with regard to sample media, sampling locations, sampling frequency, 0and analytical sensitivity requirements.

Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures S

~Section 2 - Page 1 0

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0 from releases of radionuclides from McGuire Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the environment.

Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B lists the REMP analysis and frequency schedule..

The Annual, Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site, boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies,_the requirements of Section !V.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.10.,

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

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic.

This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):

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= xi N-Where:

x =estimate of the mean, i= individual sample, 0

.N = total number of samples with alnet activity (or concentration),

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

NOTE: "Net activity (or concentration)" "is the 'activity (or concentration) determined to be present in the sample.

No "Minimum Detectable; Activity", "Lower Limit of 0

Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.

Section 2 - Page2 2 0I

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0 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE

ACTIVITY 6

The Lower Level of Detection: (LLD) ý ahnd-Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program.,

0 LLD - The LLD, as definedin *he' Selected Licensee Commitments Manual is the smallest concentration of radioactive niaterial-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.ýý The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochenical yield, and'the'radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium

and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

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

2.3.3 TREND IDENTIFICATION

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

Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if' a trend exists.

A decrease in a particular radionuclide's 0concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but'that reacfor operations are not adding that radionuclide to' the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are 0influencing the concentration.

S Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a Sknowledge of the release of a radionuclide from the nuclear plant is necessary to Scompletely interpret the trends, or lack of trends, determined. from the environmental data.

Some factors that may affect environmental. levels of radionuclides include prevailing. weather conditions (periods of ;drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, Sand addition or deletion of other sources of radioactive materials (such as the Chernobyl 5

accident). Some of these factors may be obvious while others are sometimes unknown.

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

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~Section 2 -Page 3

Figure 2.1-1 Section 2 - Page 4

Figure 2.1-2 q

McGuire Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend

TLD Locations All Other locations

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Public Roads

/\\x/ Rail Roads

\\../"

County Boundary Incorporated Areas Water Approximate location of features shown 0

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3 Miles Projection NCSP NAD27 Section 2 - Page 5

TABLE 2.1-A MCGUIRE RADIOLOGICAL MONITORING PROGRAM

..... SAMPLING LOCATIONS 0

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0 Table 2.1-A Codes WWeekly SM Semtrimontfily."]

BW BiWeekly Q

Quarterly M

Monthly SA Semiannually C

Control Site Location Description*

Air Rad.

Surface Drinking ShIoreline Food Fish Milk Broad Nort

& Part.

Water Water Sedintent Products Lear Veg.

101 North Mecklenburg Water Treattient Facility (3:31 mi E)

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

M 120 Site Boundary ( 0.46 mi NNE)

W M(b) 121 Site Boundary (0.47 mi NE)

W 125 Site Boundary ( 0.38 mi SW )

W M(b) 128 Discharge Canal Bridge (0.45 mi NE)

M 129 Discharge Canal Entrance to Lake Norman ( 0.51 rni ENE)

SA SA 130 Hwy 73 Bridge Downstream.(0.52 mi SW)

SA 131 Cowans Ford Dam ( 0.64 mi WNW)

M 132 Charlotte Municipal Water Supply ( 11 1 mi SSE)

"_._M 133 Cornelius (6.23 mi ENE)

W 134 C East Lincoln Jr.High School ( 8.77 mi WNW)

W M (b) 135 C Plant Marshall Intake Canal ( 11.9 mi N )

M 136 C Mooresville Municipal Water Supply (12.7 mi NNE)

M 137 C Pinnacle Access Area ( 12.0 mi N)

SA SA 139 William Cook Dairy (2.49 mi E)

SM 141 C Lynch Dairy-Cows ( 14.8 mi WNW)

SM 188 5 mile radius Gardens ( 2.79 mi NNE)

M(a) 192 Peninsula ( 2.84 mi NNE)

W 193 Site Boundary ( 019 nii N )

I M(b) 194 East Lincoln County Water Supply ( 6.73 mi NNW)

M 195 Fishing Access Road ( 0.19 mi N)

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

GPS data reflect approximate accuracy to within2-5 meters. GPS fieldmeasurements were taken as close as possible to the-item of interest.:

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

Site Location Distance*

i;ecto 6:

.Site Location Distance*

Sector HAMBRIGHT&.

143 SITE BOUNDARY 0.27 miles I!- NW. 2.

__164 BEATTIES FORD ROAD 4.64-miles SSE 144 SITE BOUNDARY 0.46 miles NNE 165 ARTHER AUTEN ROAD 4.57 miles S

NECK ROAD 145

. SITE BOUNDARY 0.47 miles

-.NE

.166 REFUGE BOUNDARY 4.44 miles SSW LUCIA RIVERBEND HWY/

146 SITE BOUNDARY 0.42 miles ENE_.

167.

OLD.FIREHOUSE 4.87 miles SW 147 SITE BOUNDARY 0.44 miles E

168

.OLD PLANK ROAD BRIDGE

__4,60 miles WSW 148 SITE-BOUNDARY 0.46 miles ESE 169 GLOVER LANE 4.03 miles W

149 SITE BOUNDARY 0.50 miles 7SE 170 LITTLE EGYPT RO-AD 4-.32 miles WNW 151 SITE BOUNDARY 0.37 miles

'S........

171 TRIANGLE ACE HARDWARE 3.95 miles NW LAKESHORE SOUTH RD &

152 SITE BOUNDARY 0.44 miles SSW

.172

- ISLAKNDVIEW COURT 4.69 miles NNW KEISTLER STORE./

153 SITE BOUNDARY 0.47 miles SW 173 SI-GLENWOOD ROAD 8.39 miles NNW EAST LINCOLN JR. HIGH 154 SITE BOUNDARY 0.45-miles W

174 SI SCHOOL 8.77 miles WNW 156 SITE BOUNDARY 0.44-miles-WNW 175 C BOGER CITY 15.5 miles WNW

. BELMARROW ROAD/

189 SITE BOUNDARY 0.43 miles SSE 177 SI COULWOOD COMMUNITY 8.77miles S

FLORIDA STEEL 190 SITE BOUNDARY 0.33 miles WSW 178-8S1

-CORPORATION 9.32 miles SE

-..MOORESVILLE WATER 157 THE POINTE/MOORESVILLE 4.69 miles N

180 SI' TREATMENT FACILITY 12.7 miles NNE OLD DAVIDSON WATER 158 BETHEL CHURCH ROAD 4.33 miles NNE 181 S1 TREATMENT FACILITY 7.02 miles NE HENDERSON ROAD &

159 WEST CATAWBA AVENUE 4.73 miles NE 182 SI CORNELIUS / AIR SITE # 133

.6.23 miles ENE ANCHORAGE MARINE MCGUIRE FISHING ACCESS 160 SHOWROOM 4.89 miles ENE 186 SI ROAD ON PENINSULA 0.24 miles NNW SAM FURR.ROAD ENERGY EXPLORIUM P 161

& HWY 21 4.70 miles E

187 SI' AIRSITE #195 0.19 miles N

PENINSULA DEVELOPMENT!

162 RANSON ROAD 4.53 miles ESE 191 SI AIR SITE# 192 2.84 miles NNE 163 MCCOY ROAD 4.94 miles SE C = Control SI = Special Interest

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

Section 2 - Page 7

TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water A' ir Parficulates

Fish, Milk BroadLeaf (pCi/liter) or Gases (pCi/kg-wet)

(pCi/liter)

Vegetation (pCi/mrn )...

(pCi/kg-wet)

H -3 2 0,0 0 0 (a.

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300.

20,000 Zr-Nb-95 400 1-131..

2 0.9 3

100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) If no drinking water pathway exists, a value of-30, 000 pCi/liter may be used.

(b) H-3 Reporting level not applicable to surface water TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta Air Radioiodine Weekly X

Air Weekly X

X Direct Radiation Quarterly X

Surface Monthly Composite X

Water Quarterly Composite X

Drinking Monthly Composite X

(a)

X Water Quarterly Composite X

Shoreline Sediment Semiannually X

Milk Semimonthly X

X Fish Semiannually X

Broadleaf Vegetation Monthly(b)

X Food Products Monthly(b)

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

(b) When Available S

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GA..

7,

'7i/g*e' 0\\ket) (pCi/liter)

Vegetation (pCi/kg-dry)

(pCi/mr)

(pCi/kg-wet)

Gross Beta 4

0.01 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(b) 0.07 1

60.

6 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

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

Section 2 - Page 9

3.0 INTERPRETATION OF RESULTS Review of 2007 REMP analysis results was performed to detect and identify changes in 9

environmental levels as a result of station operation. The radionuclides with Selected Licensee Commitments reporting levels that indicate consistent detectable activity have been historically trended from preoperation to present. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses from 1981 were combined with the operational 0

analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year.

The highest annual mean concentration of applicable Selected Licensee Commitments 0

radionuclides from the indicator locations for each media type was used for trending purposes.

0 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 0

values were well below the 100% action level. The highest value reached during 2007 was 7.40% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location 10 1). Only Selected Licensee Commnitments radionuclides were detected in 2007.

Changes in sample location, analytical technique, and presentation of results must be considered S

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 S

period when many measurements yielded detectable low-level activity for both indicator and 5

control location samples. It is possible that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

This section includes tables and graphs containing the highest annual mean concentrations of any effluent related radionuclide detected since the change in analysis systems in 1987. Any zero concentrations used in tables or graphs represent activity measurements less than detectable

levels.

Only the specific radionuclides that represent the highest dose contributors or demonstrate consistent detectable activity are shown graphically.

Data presented in Sections 3.1 through 3.9 support the conclusion that there was no significant increase in radioactivity in the environment around McGuire Nuclear Station due to station operations in 2007. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2007 land use census data, shown in Section 3. 10, indicates that no program changes are required as a result of the census.

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3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2007, 364 particulate and radioiodine samples were analyzed, 312 at six indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

Gross beta analyses indicated 2.12E-2 pCi/m 3 at the location with the highest annual mean and 2.18E-2 pCi/m 3 at the control location. Detectable gamma emitting particulate activity was last observed in environmental air particulate samples in 2004 and is described in PIP G-04-00134.

No detectable 1-131 activity in any environmental air radioiodine samples was found in 2007. K-40 and Be-7 that occur naturally were routinely b

detected' in charcoal cartridges t

collected during the year.

Cs-137 activity was not detected on any 1W cartridges in 2007.

Cs-137 detection on the charcoal cartridge was deteirmined in 1990 to be an active constituent of the charcoal.

A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137. activities were not used in any dose calculations in Section 4.0 of this report.....

Figure.. 3.1 shows gross beta highest annual mean indicator and control location concentrations 0

since 1985.. There is no reporting Ievel for gross beta. Table 3.1-A shows indicator and control

location highest annual means for Cs-137 and gross beta.

Table 3.1-B gives indicator location'highest annual means and control means since 1979 for 1-13 1. Preoperational and ten year averagesI are "also shown. No.- -131 activity has been detected since 1989. Since no-activity was detected in 2007, no reporting levels were approached.

7S 0

Setion3-Pge20 S

S

0 0

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Figure 3.1 pue Concenlntdion of Qos Beta in Air Paticadae 1.00E-01 9.OOE-02 8.OE-Cr2 7AxOE-cY2 6.00&M0 5cXJE-cQ 4.OOE-02 ZcXJE-o2 U Irdcator Lxatim Ccltrd Lacatim 2001 200 2Dm 2m, There is no reporting level for Gross Beta in air particulate Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate 00 0

0 S

0 0

S S

YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m3)

(pCi/mn3)

(pCi/mn3) 1979*

4.40E-3 1.47E-3 1980*

6.70E-3 4.53E-3 1981

6.16E-3 5.32E-3 1982*

3.82E-3 2.29E-3 1983*

2.93E-3 3.21E-3 1984 1.74E-3 8.29E-4 1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 1986 4.98E-3 3.03E-3 2.64E-2 2.52E-2 1987 1.07E-2 7.91E-3 2.54E-2 2.59E-2 1988 0.OOEO O.OOEO 7.49E-2 5.51E-2 1989 0.OOEO O.00E0 2.22E-2 2.14E-2 1990 0.OOEO 0.OOEO 2.58E-2 2.37E-2 1991 0.00E0 0.OOE0 2.16E-2 2.15E-2 1992 0.00E0 0.OOEO 1.92E-2 2.02E-2 1993 O.00E0 0.00E0 1.93E-2 2.04E-2 1994 0.00E0 0.OOEO 2.28E-2 2.02E-2 1995 O.OOEO 0.OOEO 3.02E-2 5.17E-2 1996 O.OOEO 0.OOEO 3.11E-2 5.49E-2 1997 0.OOEO 0.OOEO 2.34E-2 3.62E-2 1998 O.OOEO 0.OOEO 1.86E-2 2.66E-2 1999 O.OOEO 0.OOEO 2.06E-2 3.47E-2 2000 0.OOEO 0.00E0 2.OOE-2 2.77E-2 2001 0.OOEO 0.003E0 1.79E-2 1.91 E-2 Section 3 -Page 3

Table 3.1-A continued YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m3)

(pCi/m3 ).

(pCi/m3)

(pCiUm 3) 2002 0.OOEO 0100E0 157E-2 1.72E-2 2003 0.OOEO 0.00E 150E-2 1.63E-2 2004 0.00E0 0.ODEO 1.67E-2 1.71E-2 2005 0.OOEO,

0.00E0

.1.68E-2 1.77E-2 2006 0.OOEO

.OOEO L79E-2 1.94E-2 Average ( 1997 - 2006)

NOT APPLICABLE.

NOT APPLICABLE 1.83E-2 2.32E-2 2007 01.OOEO 0.OOEO 2.12E-2 2.18E-2 0.OOEO ='no detectable measurements

Radioiodines and Particulates analyzed together

- Gross Beta analysis not performed Table 3.1-B Mean Concentrations of Air Radioiodine (1-131)

Year Indicator Location.(pCi/m3)

Control Location (pCi/mr3) 1979*.

3.28E-3 1.04E-3 1980*

2.01E-3 1.1OE-3 1981 4.17E-3 6.27E-4 1982*

1.42E-3 2.48E-3 1983*

1.99E-3 2.01E-4 1984

-3.17E-3 0.00E0 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 000E0 0.OOEO 1989 2.18E-2 0.OOEO 1990..

OOEO 0.OOEO 1991 0.OOEO 0.00E0 1992 0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.00E0 0.00E0 1995 0.OOEO 0.00E0 1996 0.OOEO 0.00E0 1997 0.00E0 0.OOEO 1998 0.00E0 0.00E0 1999 0.OOEO 0.00E0 2000 0.00E0 0.OOEO 2001 0.OOEO 0.00E0 2002 0.OOEO 0.OOEO 2003 0.00EC 0.00E0 2004 0.OOEO 0.OOEO 2005

.0.00E0

-0.OE 2006 0.OOEO 0.OOEO 2007.000E0 0.OOEO O.OOEO = no detectable mrnasurements

Radioiodines and Particulates analyzed together.

S 0

0 0

0 S

0 0

S 0

0 S

Section 3 - Page 4

0 0

0 S

S 0

0 0

0 S

0 0

3.2 DRINKING WATER In 2007, 65 drinking water samples were analyzed for gross beta and gamma emitting radionuclides.

Fifty-two samples were from the four indicator locations and 13 from the control location. Tritium (H-3) analyses WXer 'performed on 20 composite samples, 16 at indicator locations and four at the control location.

No detectable gamma activity was found in drinking water samples in 2007 and has not been detected since 1987. Gross beta analysesndicated 1.81 pCi/I at the location with the highest annual mean and 1.76 pCi/l at the contrQl, location. Tritium was detected in 14 of the 16 indicator composite samples taken in 2007 with the highest annual mean resulting in only 7.40% of the reporting level. The dose for consumption of water was less than one mrem per year, historically and for 2007; 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 annual means and control means since 1979 for tritium and gross beta. There is no reporting level for gross beta.

Drinking water Location 101 was added to the sampling program in 1999. Figure 3.2 shows an increase beginning in that year. There was an increase in drinking water tritium in 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, affecting the Catawba River Basin, resulted in less dilution volume available in Lake Norman. This may have contributed to the tritium concentrations detected in environmental samples in 2007.

Figure 3.2 Concentration of Tritium in Drinking Water 1985 1987 1989 1991 1993 1995 1997 1999 2001 2

Ind;cator Location Control Location 20% 1/Reporting Level 2005 2001 Section 3 - Page 5

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

Tritium (pCi/I)

YEAR Indicator Control Indicator Control Location Location Location Location 1979 2.40E0 2.03E0 1.65E2 1.50E2 1980 2.34E0 1.87E0 1.63E2 2.05E2 1981 2.79E0 2.41 E0 1.88E2 1.78E2 1982 2.62E0 2.43E0 2A3E2 1.45E2 1983 1.80E0 1.87E0 1.65E22 1.45E2 1984 2.78E0 1.81E0 5.77E2 2.45E2 1985 1.88E0 1.90E0 5.93E2 4.00E2 1986 2.13E0 2.15E0 1.14E3 4.37E2 1987 2.30E0 2.OOEO 1.35E3 7.75E2 1988 2.OOEO 2.OOEO.

9.92E2 7.11E2 1989 2.80E0 2.70E0 5.62E2 0.OOEO 1990 3.70E0 4.30E0 7.32E2 6.11E2 1991 2.40E0 2.50E0 5.22E2 0.OOEO 1992 2.OOEO 1.70E0 6.73E2 0.OOEO 1993 2.80E0 2.40E0 0.OOEO 0.OOEO 1994 2.47E0 2.90E0 0.00E0 0.OOEO 1995 4.20E0 3.30E01:

3.58E2 0.OOEO 1996 2.75E0 211E30 3160E2 0.OOEO 1997 2.70E0 2.24E0 2.90E2 0.OOEO 1998 2.75E0 2.33E0 2.68E2 0.OOEO 1999 2.48E0 2.17E0 5.49E2' 0.OOEO 2000 2.66E0 1.99E0 5.04E2 0.OOEO 2001 2.48E0 2,19E0 6.98E2 0.OOEO 2002 2.47E0:

2.08E0 5.64E2 0.OOEO 2003 1.81 E0 1.52E0 3.51E2 0.OOEO 2004 1.68E0 1.29E0 4.61E2 0.OOEO 2005 1.74E0 1.30E0 7.35E2 0.OOEO 2006 1.75E0 1.80E0 1.46E3 0.OOEO 2007 1.81E0 1.76E0 1.48E3 0.00E0 0.00E0 = no detectable measurements 00 0

0 0

0 S

0 0

00 Section 3 - Page 6

S 0

3.3 SURFACE WATER S

0 In 2007, 39 surface water samples were analyzed for gamma emitting radionuclides, 26 at the two indicator locations and 13 at the control location. Analyses for H-3 were performed on 12 samples, eight at indicator locations and four at the control location.

No detectable gamma activity was found

in surface water samples in 2007 and has not been detected since 1988.

Tritium was detected in all of the eight indicator composite samples taken in 2007.

Tritium was detected in two of the control location composite samples in

..2007.

Figure 3.3 shows tritium highest annual mean indicator and control location concentrations. Table 3.3 gives indicator

and control location highest annual means since 1979 for tritium.

There was an increase in surface water

tritium in 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, affecting the Catawba River Basin, resulted in less dilution volume available in Lake Norman.

0This may have contributed to the tritium concentrations detected in environmental samples in 2007.

Figure 3.3 0

There is no reporting level for tritium in surface water pCi/liter Concentration of Tritium in Surface Water 5000 04500 04000 03500 3000 2500 2000 0

1500 01000 50 0

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

-U--Indicator Location Control Location Section 3 - Page 7 0

0

0 0

Table 3.3 Mean Concentrations of Tritium in Surface Water 0O0 YEAR H-3 Indicator (pCi/l)

H-3 Control (pCi/I) 1979 z,

l85E2 1.66E2 1980 2.13E2 1.93E2.

1981 1.75E2

.1.70E2 1982 3.30E2 1.23E2 1983 5.75E2 3.67E2

.1984 4.10E2 2.65E2 1985 7.33E2 0.00E0 1986 2.33E3 6.13E2 1987 9,20E2 7.70E2 1988 9.40E2 0.OOEO 1989 8..22E2 0'0E0 1990 6.77E2 0.OOEO 1991 7.53E2 0.OOEO 1992 8.13E2..

OOEO

-1993 6.85E2 0OOEO 1994 0.OOEO 0.OOEO0

-1995 3.15E2

.0OOEO 1996 8.08E2 0.OOEO0

.1997 4.85E2 0.,OOEO 0

1998 3.40E2

.0.OOEO 1999 5.60E2 0.OOEO 2000 6.22E2

,OOEO0 2001 6.98E2

. 0,OOEO 2002 5.65E2 OOEO 2003 3.9 1E2

0.OOEO 2004 5.04E2 0.OOEO 2005 8.74E2....

OOEO0 2006 1.65E3 2.19E2 2007 1.68E3 3.42E2 0

O.OOEO = no detectable measurements 3 -Pg 8

0 0

'"0

,i0 0

0 0

0

.. Section 3 -Page 8 0

0

00 0

3.4 MILK In 2007, 52 milk samples were analyzed for low level 1-131 and other gamma emitting radionuclides, 26 at the indicator location and 2 6,at the. control location.

0No detectable actiyity was founldin milk s.ýmples~in.2007. other than naturally-occurring K-40.

Cs-137 has not.been detected. in milk. samples-since 1990 and all other.. radionuclides have not been detected since 1987.

Table 3.4 gives indicator location highest -annual meansand control means since 1979 for 0Cs-137.

Since no activity Was detected in 2007,;norr&porting levels were approached.

Table 3.4 Mean Concentrations of Cs-137 in Milk

'YEAR Cs-137 Indicator (pCi/l)

Cs-137 Control (pCi/I) 1979 2.48E1 6.04E0

.1980 1.72Et 4.13E0 198.1 2.04E 1 4.15E0 1982 L.21E1 5.20E0 1983 2.O0EI 2.82E0 1984 1.48E1 2.56E0 1985 1.42E I 2.72E0 1986 3.74E0 3.45E0

1987 5.20E0 8.60E0 1988 3.40E0 2.90E0 1989

-. 6.00EO 5.60E0

1990 i 5.30E0 2.60E0 1991

.0.OOEO 0.OOEO 1992 -

0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.OOEO 0.OOEO 1995

.*0.OOEO 0.OOEO 1996 0.OOEO 0.00E0 1997 0.OOEO 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 O.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.OOEO 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0.OOEO = no detectable measurements 00 0

0 0

Section 3 -Page 9 0

0

0 0

3.5 BROADLEAF VEGETATION 00 In 2007, 48 broadleaf vegetation samples were analyzed, 36 at the three indicator locations and 0

twelve at the control location.

One of the thirty-six samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in one.of the twelve. samples collected at Location 120 with a concentration of 13.4 pCi/kg which is-0.67% of the: reporting level. Cs-137 was not detected in any of the twelve control location samples.

No airborne Cs-137 has been released from the plant since 1998.

Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.

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

Table 3.5 Mean Concentration's of Cs-137 in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg).

Cs-137 Control (pCi/kg)

. 1979 2.19E I 1.93EI 1980 2.30EI

.1.92E13 1981 3.04E I 2.02E I 1982 2.46E 1,22E1 1983-9.07E0

.78E00 1984 1.02E I 1.05EI 1985 8.05E0 2.37E-2 1986.

4.03E]

1.27E 1987 2.20E I 1.70E]

1988.

3.90E I 3.40E1I 1989 9.60E I 0.00E0 1990 4.OOE 1 0.00E0 t 991...

3.30E 1 0.00130

, 1992 4.90E I 0.00E0 1993 1.60E 1.,

.00E0 2000 O.OOEO 0.OOEO 2001 O.OOEO

.OOEO S

19920...

0.OOEO 0.00E0 2003 0.00E0

... 0.00E0 19972

-0.00E0 0.00E0 1998 O....

.00E0 2.69E1 1999"':

0.00E0 0.00E0 2000..

0.0E0 0.0E0 2005 0.00E0 0.00E0 2004 0.00130 0.00E0 2005 0.00E0 0.00E0 2006 2.98E1 0.OOEO 2007 1.34E1 0.OOEO O.OOEO = no detectable measurements 0

0 Section 3 -Page 10 0

0 0

00 0

3.6 FOOD PRODUCTS 0

In 2007, 12 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media.

No detectable activity has been detected in this media since 1987. Table 3.6 shows Cs-137

indicator highest annual means with preoperational data. Since no activity was detected in 2007, no reporting levels were approached.

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

YEAR Cs-137 Indicator (pCi/kg) 1979 2.19E1 1980 2.30E1

1981 3.04E I 1982 2.46E1 1983 9.07E0 1984 8.45E0.

1985 7.99E0 1986 2.15E1 1987 2.90E1 1988 0.00E0

1989 0.00E0 1990 OOEO 1991 0.OOEO 1992 0.OOEO 1993 0.OOEO 1994 0.OOEO

1995 0.OOEO

1996 0.OOEO 1997 0.OOEO 1998 0.OOEO

1999 0.OOEO 2000 0.OOEO

2001 0.00E0

2002 0.OOEO 2003 0.OOEO 2004 0.OOEO 2005 0.00E0

-2006 OOEO 2007 OOEO.:..

0..OOEO = no detectable measurements Section 3-Pagell 0

0

3.7 FISH In 2007, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator location and six at the control location.

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

Table 3.7 gives, indicator location highest 'annual means since 1980 -for all radionuclides detected since the analysis change in 1988.

Co-58 activity was not detected in 2007 in any of the indicator or control samples. Cs-137 activity was detected in one of the six indicator samples taken at Location 129 with a mean concentration of 21.1 pCi/kg, which is. 1.06% of the reporting level. Cs-137 was detected in one of the six control. samples taken at Location 137 with a

mean concentration of 19.5 pCi/kg, which is 0.98% of the reporting level.

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

Section 3 - Page 12 S

0 0

S 0

0 0

S 0

0 0

S 0

0 S

0 0

0

0 S

S 0

0 0

0 S

0 0

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

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002

-U--Indicator Location

-+Control Location 15%

of Reporting Level 2004 2006 Figure 3.7-2 00 0

0 0

S 0

0 0

0 S

pCi/kg 300 500 o00 300 Concentration of Co-60 in Fish 200 100 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006

--E-Indicator Location

- Control Location 5% of Reporting Level Section 3 - Page 13

S 0

0 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

-2.71 E0

-2.98E0

-2.65E0

-1.99E0 1.80E 1 1982

-3.83E-8:16E0" 1-41.34E-1 8.22E-1 2.69E1 1983

-2.60E0 2.60E1 ilE1."

-132E0 6.03E1 1984 3.61E0 1:.45E2 2.82E1 3.11E]

4.38E1 1985 2.53E-1 7..19E0 1.72E

-1.56E0 1.86E1 1986 1.03E0 3.17E1 2.96E1 1.67E1 3.49E 1 1987 0.OOEO:

2.71E2 1.25E2 2.60E1 5.10E]

1988 1.20El 7.70E1 0.OOEO 2.70E1 3.60E1 1989 9.00E1 4.05E2 2.99E2 1.1OE1 3.50E1 1990 0.OOEO 5.60E1 4.10EI 0.OOEO 3.30E1 1991 6.20E0 1:40E1 6.50Ei 5:90E0 2.60E1 1992 0.00E0 O.OOE0, 0.00E0 O.OOEO 2.90E1 1993 0.OOEO 8.20El 1.30E1 0.OOEO 1.60E1 1994 0.OOEO O.OOEO 0.OOEO 0.OOEO 3.10E1 1995 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.70E 1 1996 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.78E1 1997 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.62E1 1998 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.21E]

1999 0.'OOEO 3.53E1 0.OOEO 0.OOEO 2.10EI 2000 0.OOEO 4.28E I 0.OOEO 0.OOEO 2.34E1 2001 0.OOEO I.32E1 0.00E0 0.OOEO 3.04E I 2002 0.00E0 0.OOEO 0.OOEO 0.OOEO 2.33E1 2003 0.OOEO 0.E" 0.00E0 0.00E0 3.05E1 2004 0.OOE0 0.0E0 0.OOEO 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.003E0 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.08E 1 2007 0.OOEO 0.OOEO 0.OOEO 0:OOEO 2.1 IE1 0.00E0 = no detectable measurements 5

All negative values have been replaced with zeros for calculational purposes 5

S0 0

0 0

0 S

0 Section 3 -Page 14 0

0 0

S S

0 0

0 3.8 SHORELINE SEDIMENT In 2007, six shoreline sediment samples were and two at the control location.

Figure 3.8-1 shows Cs-137 highest annual-mean indicator and control locationi.

concentrations since 1979.

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

Cs-137 activity was detected in one of the four indicator samples taken. The shoreline sediment location with the highest annual mean was Location 130 with a mean concentration of 114 pCi/kg. Cs-137 was not detected in any control location samples.

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

Figure 3.8-1 pCi/kg Concentration of Cs-137 in Shoreline Sediment 500 450 400 350 300 250 200 150 100 50 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 Indicator Location Control Location There is no reporting level for Cs-137 in shoreline sediment Section 3 - Page 15

0 0

Figure 3.8-2 pCVkg Concentration of Co-60 in Shoreline Sediment 300 250 O

200 150 O

100 500 0..

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 Indicator Location Control Location There is no reporting level for Co-60 in shoreline sediment Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)

Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 1979

- 1.07E 1 2.25E1

-6.50E0 O.OOEO 1.20E1 1980 1.06E 1

-8.74E0 2.36E 1

-3.53E0 1.44E1 I 1981 2.13E 1 1.20E 1 8.21 E0 3.97E1 3.36E1 1982 5.38E1 1.66E 1

- 1.69E0 7.67E1 4.40E 1 1983 4.40E0 3.43E 1 2.12E 1 7.65E1 8.02E1 I 1984 1.19E1 7.1 IE1 3.04E1 3.34Et 9.13E1 1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 1986 1.37E1 1.02E 1 1.16El 6.35E1 1.53E2 1987 0.OOEO 1.06E2 2.10E1 4.20E 1 1.65E2 0

1988 6.50E0 9.20E1 1.20E1 9.1OEO 2.66E2 1989 2.90E1 3.80E 1 2.90E1 5.30E1 6.50E1 1990 3.80E1 2.70E1 1.68E2 O.00E0 6.10El 0

1991 2.80E1 5.30E1 1.31E2 0.OOEO 1.03E2 1992 9.40E0 0.OOEO 5.10E31 9.20E0 8.60E 1 1993 0.OOEO 2.20E]

8.60E1 I0.OOEO 9.30E1 I 1994 4.10E1 0.OOEO 0.00E0 0.OOEO 8.OOE1 O

1995 1.70EI 0.OOEO 2.30E1 0.OOEO 1.38E2 1996 2.90E t 1.78E1 3.50E1 0.OOEO 1.47E2 1997 0.OOEO 0.OOEO 1.11 E2 3.10E1 1.36E2 0

1998 0.OOEO 0.00E0 5.21E1 0.00E0 9.97E 1 1999 0.00E0 2.47E1 8.49E1 0.OOEO 6.51E]

2000 0.OOEO 3.04E1 0.00E0 0.00E0 1.08E2 0

S Section 3 -Page 16O 0

S

00 0

0 0

0 Table 3.8 continued Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator -

Indicator Indicator Indicator 2001 0.00E0 O.0OE0 0.00E0 O.0OE0 2.77E1 2002 2.24E1 0.OOEO 0.OOEO 0.OOEO 1.59E2 2003 0.00E0 0.00E0 0.00E0 0.00E0

1. I I E2 2004 0.OOEO 0.00E0 0.00E0 0.00E0 7.17E 1 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 8.08E 1 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO

.1.59E2 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO

1. 14E2 Section 3 - Page 17

3.9 DIRECT GAMMA RADIATION In 2007, 161 TLDs were analyzed, 157 at indicator locations, four at the control location.

TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 108 milliroentgen.

The annual mean exposure for the control location was 90.0 milliroentgen.

Figure 3.9 and Table 3.9 show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year.

Preoperational data and ten year rolling averages are also given. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise a number of data points with the control average representing only one location.

The calculated total body dose from gaseous effluents for 2007 was 2.43E-1 millirem, which is 0.36% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact on the measured TLD values.

Figure 3.9 0

0 0

0 0I 0I 6I 6I 6

6 6

6 II II II II II II II II II I

I I

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

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 Inner Ring Outer Ring 0

Control 2001 2003 2005 2007 There is no reporting levelfor Direct Radiation (TLD)

Section 3 - Page 18

00 0

Table 3.9 Direct Gamma Radiation (TLD) Results 0

YEAR Inner Ring Average.

Outer Ring Average Control

.(mR/yr)

(mR/yr)

~~~1979

.7.91E1:.

I.

8.82E1 8.32E1 1980 7.54E1"

.8.29E1" 1.05E2 198 1.01 E2 9.31E]1 1.05E2 1982...

8.95E1I 8.97E1

1. 10E2 1983

.1.

16E2

1. 14E2 1.30E2 1984 7.85E1 7.83E1 9.02E1 1985 9.54E 1 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 4.34E 1 4.78E1 6.25E 1 1991 5.14E1 5.59El 6.80E1 1992 5.65E1 5.55E1 7.60E1 1993 5.61E1 5.71E1 7.20E1 1994 6.40E1 6.93E1 9.55E1 1995 8.36E 1 8.25E1 1.08E2 1996 7.18E I 7.02E 1 9.88E1 1997 6.22E 1 6.68E I 9.45E1 1998 6.59E1 6.32E1 8.69E I 1999 6.23E1 6,05E1 8.96Et 2000 6.50E1 6.08E1 8.97E1 2001 6.51E1 6.22EI 9.33E1 2002 6.57E1 6.43E1 9.48Ei 2003 6.74E 1 6.45E1 9.20E I 2004 6.46E 1 6.33E1 9.16E1 2005 6.62E 1 6.34E 1 9.44EI 2006 6.75E1 6.58E1 9.17El Average (1997 - 2006) 6.52E I 6.35E 1 9.19E I 2007 6.84E I 6.60E I 9.OOE I

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

S 0

0 0

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3.10 LAND USE CENSUS The land use census was conducted May 21 and May 22, 2007 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 2007 census, no new or closer, irrigated gardens -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 2007 land use census.

Table 3.10 McGuire 2007 Land Use Census Results Sector Distance Sector Distance (Miles)

(Miles)

Nearest Residence 2.53*

Nearest Residence 1.45 N

Nearest Garden (irrigated),

2.79 Nearest Garden 3.12 Nearest Milk Animal Nearest Milk Animal Nearest Residence 1.23, Nearest Residence 2.56 NNE Nearest Garden 2.53 SSW Nearest Garden 2.94 Nearest Milk Animal Nearest MilkAnimal Nearest Residence 1.21:

Nearest Residence 1.85 NE Nearest Garden (irrigated) 1.80 SW Nearest Garden 4.00 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.57 Nearest Residence 1.01 ENE Nearest Garden (irrigated) 2.54 WSW Nearest Garden 1.33 Nearest Milk Animal Nearest Milk Animal Nearest Residence

.48 Nearest Residence 1.15 E

Nearest Garden 1.86 W

Nearest Garden 1.23 Nearest Milk Animal (COW) 2.49 Nearest Milk Animal Nearest Residence 0.65 Nearest Residence 0.88 ESE Nearest Garden 1.15 WNW Nearest Garden 1.73 Nearest Milk Animal Nearest Milk Animal Nearest Residence 067 Nearest Residence 0.95 SE-Nearest Garden 1.18 NW Nearest Garden 1.68 Nearest Milk Animal Nearest Milk Animal Nearest Residence 1.06 Nearest Residence 1.48 SSE NearestGarden 2.18 NNW Nearest Garden (irrigated) 1.69 SSE Nearest Milk Animal N

Nearest Milk Animal 00 0

0 0

0

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

000000000000000000000000000F0000000000000000 Figure 3.10 Section 3 - Page 21

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0 4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS 0Annual doses to maximum exposed individuals were estimated based on measured

concentrations of radionuclides in 2007 MNS REMP samples. The primary purpose of 0estimating doses based on sample results is to allow comparison to effluent program dose estimates.

0Doses based on sample results were calculated using the methodology and data

presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, Saveraged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses.

Where applicable, average 0background concentration at the corresponding control location was subtracted.

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

Swater, 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.

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

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

than direct radiation from gaseous effluents) collected during 2007 was 1.58E-1 mrem to the maximum exposed child liver from the consumption of drinking water.

4.2 ESTIMATED DOSE FROM RELEASES 0

Throughout the year, dose estimates were calculated based on actual 2007 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 5calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

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~Section 4 -Page 1 0

00 The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas lexposure, there is no critical age group; as the maximum exposed individuals, are assu.Aed to receive the' same doses, regardless of their age group. For iodine, particulate, and tritium. exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, inhalation, milk and vegetation pathways.

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

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

In calculations based on liquid release pathways, drinking water and fish consumption were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2007 environmental sample results was 1.58E-1 mrem to the child liver. The maximum total organ dose of 2.43E-1 mrem for liquid effluent-based estimates was to the child liver.

O0 In calculations based on gaseous release pathways, inhalation was the predominant dose pathway for effluent samples. The maximum organ dose for, gaseous effluent estimates was 243E-1 mrem to the teen total body, liver, thyroid, kidney, lung, and GI-LLL The maximum environmental dose is 1. 14E-1 mrem to the child bone due to ground plane pathway.

Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.

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

00 0

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TABLE 4.1-A Page 1 of 3 MCGUIRE NUCLEAR STATION 2007 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 00 0

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0 LIQUID RELEASE PATHWAY Environmental or Critical Critical.

Maximum Dose (3)

Organ Effluent Data Age Pathway -2)

Location (mrem)

Skin Environmental Teen Sh0oreýline Sediment 130 (0.52 mi SW) 2.99E-04 Skin Effluent Teen Shorefine Sediment Discharge Pt.

5.91E-04 Bone Environmental Child Fish 129 (0.51 mi ENE) 3.61E-03 Bone Effluent Child Fish Discharge Pt.

5.05E-02 Liver Environmental Child Drinking Water 101 (3.31 mi E) 1.58E-01 Liver Effluent Child Drinking Water 3.31 mi E 2.43E-01 T. Body Environmental Child Drinking Water 101 (3.31 mi E) 1.55E-01 T. Body Effluent Child Drinking Water 3.31 mi E 1.98E-01 Thyroid Environmental Child Drinking Water 101 (3.31 mi E) 1.55E-01 Thyroid Effluent Child Drinking Water 3.31 mi E 1.89E-01 Kidney Environmental Child Drinking Water 101 (3.31 mi E) 1.56E-01 Kidney Effluent Child Drinking Water 3.31 mi E 2.06E-01 Lung Environmental Child Drinking Water 101 (3.31 mi E) 1.55E-01 Lung Effluent Child Drinking Water 3.31 mi E 1.95E-01 GI-LLI Environmental Child Drinking Water 101 (3.31 mi E) 1.55E-01 GI-LLI Effluent Child.

Drinking Water

.3.31 mi E, 1.89E-01 (1) Critical Age is the highest total dose (all pathways) to an age:group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

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

Section 4 - Page 3

0 00 0

Page 2 of 0

0 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

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

Section 4 -Page 4

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

Beta Environmental Not Sampled Beta Effluent' N/A Noble Gas 0.5 mi. NNE 4.46E-02 Gamma Environmental.

Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 1.64E-02 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dose for 2007 based on Environmental Measurements (mrem) for McGuire Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid. Kidney Lung GI-LLI Skin Infant

Airborne, 0.001E+00 O.OOE+00 O.OOE+00 O.OOE+OO O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 1.50E-01 1.50E-01 1.50E-01 1.50E-01 1.50E-01 1.50E-01 0.00E+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 TOTAL O.OOE+00 1.50E-01 1.50E-01:

1.50E-01 1.50E-O1 1.50E-01 1.50E-01 O.OOE+00 Child Airborne 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Drinking Water O.OOE+00 1.53E-01 1.53E-01 1.53E-01 1.53E-01 1.53E-01 1.53E-01 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.14E-01 1.09E-01 1.61E-02 O.OOE+00 3.55E-02 1.28E-02 6.83E-04 O.OOE+00 Fish 3.61E-03 5.14E-03 2.20E-03 1.69E-03 2.81E-03 2.09E-03' 1.71E-03 O.OOE+00 Shoreline Sediment O.OOE+00 0.00E+00 5.36E-05 O.OOE+00 O.OOE+00 0.00E+00 0.00E00F 6.26E-05 TOTAL 1.18E-01 2.67E-01 1.71E-01 1.55E-01 1.91E-01 1.68E-01 1.55E-01 6.26E-05 Teen Airborne O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 0.003E+00 Drinking Water O.OOE+00 8.OOE-02 8.00E-02 8.OOE-02 8.OOE-02 8.00E-02 8.OOE-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 0.0OE-00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Broadleaf Vegetation 6.30E-02 8.39E-02 2.92E-02 O.OOE+00 2.85E-02 1.11 E-02 1.19E-03 O.OOE+00 Fish 2.87E-03 5.86E-03 3.37E-03 2.04E-03 3.34E-03 2.55E-03 2.1OE-03 O.OOE+00 Shoreline Sediment O.OOE+00 0.00E+00 2.57E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.99E-04 TOTAL 6.59E-02 1.70E-01 1.13E-01 8.20E-02 1.12E-01 9.37E-02 8.33E-02 2.99E-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 1.13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-01 1.13E-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 6.84E-02 9.35E-02 6.12E-02 O.OOE+00 3.17E-02 1.05E-02 1.81E-03 0.00E+00 Fish 2.68E-03 6.32E-03 5.05E-03 2.65E-03 3.90E-03 3.07E-03 2.73E-03 0.00E+00 Shoreline Sediment O.OOE+00 O.OOE+00 4.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.36E-05 TOTAL 7.11E-02 2.13E-01 1.79E-01 1.16E-01 1.49E-0l 1.27E-01 1.18E-01 5.36E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6 ID~~~~

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McGuire Nuclear Station Dose from Drinking Water Pathway for 2007 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 Concentration Indicator Water Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 3.08E-05 NO DATA 1.84E-05 4.20E-08 2.06E-07 3.59E-05 3.77E-04

.5.22E-04 1.71E-04 NO DATA Liver 1.99E-05 3.60E-06

.3'5E-05 I.;08E-05 6.31 E-05 1.73E-08 5.02E-08 4.23E-051.

7.03E-04 6.11 E-04, 1.7 i E-07 3.08E-07 Ingestion Dose Factor

'Dose (mreni)

T. Body 4.51IE-06 8.98E-06 2.12E-05 2.55E-05 2.9 1E-05 L.0E-08

ý3.6E -68 1.86E.-05 7.IOF-05 4.33E-05~

8.81 E-06 3.08E-07 Thyroid Kidney Lung GI-LLI Location (pCi/I)

Bone Liver

T. Body Thyroid Kidney

Lung, GI-LLt NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.39E-02 NO DATA NO DATA NO DATA 3.08E-07 4.41E-06 NO DATA 7.311E-06 NO DATA NO DATA 8.97E-06 NO DATA 1.59E-05 2.57E-05 NO DATA NO DATA 2.57E-05 3.06E-05 NO DATA 5.33E-05 1.24E-08 NO DATA 1.46E-05 5.41E-08 NO DATA 2.50E-05 4.94E-05 NO DATA 1.51E-06 1.81E204 7.42E-05 1.91E:06 1.64E-04 6.64E-05 1.91E-06 4.06E-08 1.05E-07 4.20E-05 3.08E-07 3.08E-07 3.08E-07 ALL ALL.

ALL ALL.

ALL ALL ALL ALL ALL ALL ALL 101 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1480 0.OOE+00 0.00K+0.0 606E400 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00OE+00 O.OOE+00 0.0OE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOEO00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 I).OOE+00 0.06E+00 0.OOE+00 0.OOE+00 1.50E-01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 OOE+09

0,900E+00 0.004pq :q4)OE*t00!

0.OO11+00 0.60E+00 0.60E+00 0 00E+00 V00E+ý00

'006E'+00 0.OOE+00 0,OOE+00 0.OOE+00:- 0.OOE+00, O.OOE+00 0.OOE+00 0.OOE+00 0.0WE+00 0.OOE+00 0.OOE+00 0.O011+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.008E+00 0.OOE+0()

0.OOE+00 600E+00 0.OOE+00 0,OOE-*00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-.00 0.0OE+00 1.50E-01 1.50E-01 1.50E-01 1.50E-0 I 1.50E-01 Dose Commitment (mrem) =

0.OOE+00 1.50E-0 1 1.5013-01 1.50E-01I 1.50E-01 1.50E-0 I 1.50E-0I Section 4 - Page 7

McGuire Nuclear Station Dose from Drinking Water Pathway for 2007 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) =

510 1 Ingestion Dose Factor Radionuclide Mn-54 Co-58 F

?e-59 CO-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 1.65E-05 NO DATA i.37E-05 2.25E-08 1.16E-07 1.72E-05 2.34E-04 3.27E-04 8.31E-05 NO DATA Liver 1.07E-05 1.80E-06 2.67E-05 5.29E-06 3.65E-05 8.76E-09 2.55E-08 1.73E-05 3.84E-04 3.13E-04 7.28E-08 2.03E-07 T. Body 2.85E-06 5.51 E-06.

1.33E-05 1.56E-05 2.27E-05 6.26E-09 2.27E-08 9.83E-06 8.10E-05 4.62E-05 4.85E-06 2.03E-07 Thyroid Kidney NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 5.72E-03 NO DATA NO DATA NO DATA 2.03E-07 3.00E-06 NO DATA NO DATA NO DATA 2.30E-05 8.23E-09 3.65E-08 2.84E-05 1.19E-04 1.02E-04 2.37E-08 2.03E-07 Lung GI-LLI NO DATA 8.98E-06 NO DATA 1.05E-05 7.74E-06 2178E-05 NO DATA 2.93E-05 NO DATA 6.41E-06 NO DATA 1.62E-05 NO DATA 2.66E-05 NO DATA 1.54E-06 4.27E-05 2.07E-06 3.67E-05 1.96E-06 4.34E-08 4.21E-05 2.03E-07 2.03E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I)

Bone ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+-00 ALL 0.00 0.OOE+00 ALL' 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 101 1480 0.OOE+00 Liver 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.53E-01 T. Body 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.53E-01 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 1.53E-01 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.0OE+00 0.OOE+00 0.00E+00 1.53E-0 I Dose (mrem)

Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.53E-01 1.53E-01 Dose Commitment (mrem) =

Section 4 - Page 8 0.OOE+00 1.53E-01 1.53E-01 1.53E-01 1.53E-0 I 1.53E-01 1.53E-01 00*000 000 00000*0000 000 0400100100

McGuire Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Child Child Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) =

26 kg Radionuclide 1-131 Cs-134 Cs-137 Bone 1.72E-05 2.34E-04 3.27E-04 Ingestion Dose Factor Liver T. Body Thyroid Kidney Lung 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 3.13E-04 4.62E-05 NO DATA 1.02E-04:

3.67E-05 GI-LL1 1.54E-06 2.07E-06 1.96E-06 Highest Annual Net Mean Concentration Indicator Food Location (pCi/kg)

ALL 0.00 ALL 0.00 120 13.4 Bone Liver T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.14E-01 1.09E-01 1.61E-02 Dose (mrem)

Thyroid Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.55E-02 1.28E-02 6.83E-04 Dose Commitment (mrem) =

1. 14E-0 I 1.09E-01 1.6 1E-02 0.OOE+00 3.55E-02 1.28E-02 6.83E-04 Section 4 - Page 9

McGuire Nuclear Station Dose from Fish Pathway for 2007 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mreni/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 = 1338 pCi/l x 0.9 = 1204 pCi/kg Usage (intake in one year) =

6.9 kg Radionuclide Mn-54 Co-58 Fe-59 CO-60 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 1.65E-05 NO DATA 1.37E-05 2.34E-04 3.27E-04 NO DATA Liver 1.07E-05 1.80E-06 2.67E-05 5.29E-06 3.65E-05 3.84E-04 3.13E-04 2.03E-07 T. Body 2.85E-06 5.5 1E-06 1.33E-05 1.56E-05 2.27E-05 8.1OE-05 4.62E-05 2.03E-07 Ingestion Dose Factor Thyroid Kidney Lung NO DATA 3.OOE-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 7.74E-06 NO DATA NO DATA NO DATA NO DATA 2.30E-05 NO DATA NO DATA 1.19E-04 4.27E-05 NO DATA 1.02E-04 3.67E-05 2.03E-07 2.03E-07 2.03E-07 GI-LLL 8.98E-06 1.05E-05 2.78E-05, 2.93.E-05 6.41 E-06 2.07E-06 1.96E-06 2_03E-07 Highest Annual Net Mean.

Concentration Indicator Fish Location (pCi/kg)

ALL 0.00 ALL 0.00 ALL-0.00 ALL 0.00 ALL 0.00 ALL 0.00 129 1.60 128 1204 Bone 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.61 E-03 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.46E-03 I.69E-03 T. Body O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.10E-04 1.69E-03 Dose (mrem)

Thyroid Kidney 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-03 1.69E-03 1.69E-03 Long 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.05E-04 1.69E-03 GL-LL1 0.OOE+00 O.)OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.16E-05 1.69E-03 Dose Commitment (mrem) =

3.61E-03 5.14E-03 2.20E-03 1.69E-03 2.8 1E-03 2.09E-03 1.71E-03 Section 4 -Page 10

e@@e@@eeee0eeee@@@ee0eee00eO0ee@Oe0e0ee0e0s

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2007 Data Maximum Exposed Child Shoreline Recreation =

14 hr (in one year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (river shoreline - location 130)

Sediment Surface Mass =

40 kg/m2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m 2) x Shore Width Factor x Sediment Surface Mass :(kg/m 2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest-Annual:Net Dose on Contaminated Ground Mean Concentration Radionuclide Mn-54 Co-58 Co-60 Cs-134 Cs-137 (mrem/hr per pCi/m 2)

Indicator T. Body Skin Location 5.80E-09 6.80E-09 ALL 7.OOE-09 8.20E-09 ALL 1.70E-08 2.00E-08 ALL 1.20E-08 1.40E-08 ALL 4.20E-09 4.90E-09 130 Dose Commitment (mrem) =

Sediment (pCi/kg) 0.00 0.00 0.00 114 (mrem)

T. Body Skin 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.36E-05 6.26E-05 5.36E-05 6.26E-05 Section 4 - Page I I

McGuire Nuclear Station Dose from Drinking Water Pathway for 2007 Data Maximum Exposed Teen Teen 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 Ingestion Dose Factor Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 5.87E-06" NO DATA 5.76E-06 8.22E-09 4.12E-08 5.85E-06 8.37E-05 1.12E-04 2.84E-05 NO DATA Liver 5.90E-06 9.72E-07 1.37E-05 2.81 E-06 2.00E-05 4.56E-09 1.30E-08 8.19E-06 1.97E-04 1.49E-04 3.48E-08 1.06E-07 T. Body 1.17E-06 2.2411-06 5.29E-06 6.33E-06 9.33E-06 2.5111-09 8.94E-09 4.40E-06 9.14E-05 5.19E-05 1.83E-06 1.0611-07 Thyroid NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 2.39E-03 NO DATA NO DATA NO DATA 1.06E-07 Kidney 1.76E-06 NO DATA NO DATA NO DATA 1.28E-05 4.42E-09 1.91E-08 1.41 E-05 6.26E-05 5.07E-05 1.18E-08

!.06E-07 Lung GI-LLI NO DATA 1.21E-05 NO DATA 1.34E-05 4.32E-06 3.24E-05 NO DATA 3.66E-05 NO DATA 8.47E-06 NO DATA 1.95E-05 NO DATA 3.00E-05 NO DATA 1.62E-06 2.39E-05 2.45E-06 1.97E-05 2.12E-06 2.34E-08 4.38E-05 1.06E-07 1.06E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I)

Bone ALL 0.00 o.OOE+00 ALL 0.00 0.OOE+00 ALL.

0.00 O.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 101 1480 0.OOE+00 Dose (mrem)

Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OO11+00 0.OOE+00 0.OOE+00 0.OOE+00 8.00E-02 T. Body 0.OOE+00 0.OO11+00 0.OOE+00 0.OOE+00 0.OOE-i00 0.OO11+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.00E-02 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.0011-02 Kidney Lung GI-LLI 0.OOE+00 0.0O11+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O011+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.OOE.02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OO11+00 8.OOE11-2 0.OOE+00 0.00E4-00 0.OOE+00 0.OOE+00 0.OO11+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.OOE-02 Dose Commitment (mrem)=

0.OOE+00 8.OOE.02 8.OOE-02 8.OOE-02 8.OOE-02 8.OOE.02 8.OOE-02 Section 4 - Page 12 0000000000000000 16 0 0 0 0 0 0000000000

McGuire Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) =

Radionuclide 1-131 Cs-134 Cs-137 Bone 5.85E-06 8.37E-05 1.12E-04 42 kg In2estion Dose Factor Liver T. Body Thyroid Kidney Lung GI-LLI 8.19E-06 440E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 Highest Annual Net Mean Concentration Indicator Food Location (pCi/kg)

ALL 0.00 ALL 0.00 120 13.4 Bone Liver T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.30E-02 8.39E-02 2.92E-02 Dose (mrem)

Thyroid Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.85E-02 1.11 E-02 1.19E-03 Dose Commitment (mrem) =

6.30E-02 8.39E-02 2.92E-02 0.OOE+00 2.85E-02 1.IIE-02 1.19E-03 Section 4 - Page 13

McGuire Nuclear Station-Dose from Fish Pathway for 2007 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 = 1338 pCi/l x 0.9 = 1204 pCi/kg Usage (intake in one year) =

16 kg Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 5.87E-06 NO DATA 5.76E-06 8.37E-05 1.12E-04 NO DATA Liver 5.90E-06 9.72E-07 1.37E-05 2.8 1E-06 2.00E-05 i.97E-04 1.49E-04 1.06E-07 T.,Body 1.17E-06 2.24E-06 5.29E-06 6.33E-06 9.33E-06 9.14E-05 5.19E-05 1.06E-07 Ingestion Dose Factor Thyroid Kidney Lung NO DATA 1.76E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 4.32E-06 NO DATA NO DATA NO DATA NO DATA 1.28E-05 NO DATA NO DATA 6.26E-05 2.39E-05 NO DATA 5.07E-05 1.97E-05 1.06E-07 1.06E-07 1.06E-07 GI-LLI 1.2iEr05 1.34E-05 3.24E-05 3.66E-05 8.47E-06 2.45E-06 2.12E-06 1.06E-07 Highest Annual Net Mean Concentration Location (pCi/kg)

ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 129 1.60 128 1204 Bone 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 2.87E-03 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 3.81 E-03 2.04E-03 T. Body 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-03 2.04E-03 Dose (mrem)

Thyroid Kidney 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 1.30E-03 2.04E-03 2.04E-03 Lung 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 5.04E-04 2.04E-03 GI-LLI 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.43E-05 2.04E-03 Dose Commitment (mrem) =

2.87E-03 5.86E-03 3.37E-03 2.04E-03 3.34E-03 2.55E-03 2.1 OE-03 Section 4 - Page 14 010900000000000000000,oooooQoooooooiQooQDolo4000

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2007 Data.

Maximum Exposed Teen.

Shoreline Recreation =

67 hr (in one year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (r*iver shoreline - location 130)

Sediment Surface Mass =

40 kg/m 2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation,.(hr) x External Dose Factor (mrem/hr per pCi/m 2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration, (mrem/hr per pCi/m 2)

Radionuclide

'T. Body Skin Mn-54 5.80E-09 6.80E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Cs-134 1.20E-08 1.40E-08 Cs-137 4.20E-09 4.90E-09 Indicator Location ALL ALL ALL ALL 130 Sediment (pCi/kg) 0.00 0.00 0.00 0.00 114 (mrenl)

T. Body Skin 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 2.57E-04 2.99E-04 2.57E-04 2.99E-04 Dose Commitment (mrem) =

Section 4 - Page 15

McGuire Nuclear Station Dose from Drinking Water Pathway for 2007 Data Maximum Exposed Adult Adult Dose from Drinking WaterPathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration(pCi/l)

Usage (intake in one year) =

730 1 Highest Annual Net Mean Concentration Indicator Water Ingestion Dose Factor Dose (mrem)

Radionuclide Mn-54 Co-58 kF--59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-09 3.04E-08 4.16E-06 6.22E-05 7.97E-05 2.03E-05 NO DATA Liver 4.57E-06 7.45E-07 1.02E-05 2.14E-06 1.54E-05 3.46E-09 9.75E-09 5.95E-06 1.48E-04 1.09E-04 2.55E-08 1.05E-07 T. Body 8.72E-07 1.67E-06 3.9 1E-06 4.72E-06 6.96E-06 1.86E-09 6.60E-09 3.41 E-06 1.21E-04 7.14E-05 1.33E-06 1.05E-07 Thyroid Kidney Lung GI-LLI Location NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.95E-03 NO DATA NO DATA NO DATA 1.05E-07 1.36E-06 NO DATA 1.40E-05 NO DATA NO DATA 1.51E-05 NO DATA 2.85E-06 3.40E-05 NO DATA NO DATA 4.02E-05 1.03E-05 NO DATA 9.70E-06 3.42E-09 NO DATA 2.10E-05 1.53E-08 NO DATA 3.09E-05 1.02E-05 NO DATA 1.57E-06 4.79E-05 1.59E-05 2.59E-06 3.70E-05 1.23E-05 2.1 IE-06 8.67E-09 1.46E-08 4.18E-05 1.05E-07 1.05E-07 1.05E-07 ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL 101 (pCi/I)

Bone 0:.0 0.00E+00 0.00 0.OOE+00 0.00 O.OOE+00 0.00 O.OOE+0O 0.00 0.00E+00 0.00 0.OOE+00 0.00 0.00E+00 0.00 0.00E+00 0.00 0.OOE+00 0.00 0.OOE+00 0.00 0.OOE+00 1480 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-01 T. Body 0.OOE+00 (J.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-01 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-01 Kidney 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 1.1 3E-01I Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.09E+00 0.OOE+00 1.13E-01 0.OOE+00 O.OOE+00 0.OOE-i00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.13E-01 Dose Commitment (mrem) =

0.OOE+00

1. 13E-0 I 1.13E-01 1.13E-01 1.13E-01 1.13E-01

1. 13E-0 I Section 4 - Page 16

McGuire Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem)

Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) =

Radionuclide 1-131 Cs-134 Cs-137 Bone 4.16E-06 6.22E-05 7.97E-05 64 kg Ingestion Dose Factor Liver T. Body Thyroid Kidney Lung GI-LLI 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 1.09E 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 Highest Ainual Net Mean Concentration Indicator Food Location (pCi/kg)

ALL 0.00 ALL 0.00 120 13.4 Bone Liver T. Body 0.00E+00 0.OOE+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 6.84E-02 9.35E-02 6.12E-02 Dose (mrem)

Thyroid Kidney 0.00E+00 0.O0E+00 0.OOE+00 0.00E+00 0.OOE+00 3.17E-02 Lung GI-LLI 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 1.05E-02 1.8 IE-03 Dose Commitment (mrem) =

6.84E-02 9.35E-02 6.12E-02 0.OOE+00 3.17E-02 1.05E-02 1.81 E-03 Section 4 -Page 17

McGuire Nuclear Station Dose from Fish Pathway for 2007 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/I = 1338 pCi/! x 0.9 = 1204 pCi/kg Usage (intake in one year) =

21 kg Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-05 7.97E-05 NO DATA Liver 4.57E-06 7.45E-07 1.02E-05 2.14E-06 1.54E-05 1.48E.04 1.09E-04 1.05E-07 Ingestion Dose Factor T. Body Thyroid Kidney 8.72E-07.

NO DATA. 1.36E-06 1.67E-06 NO DATA NO DATA 3.91E-06 NO DATA NO DATA 4.72E-06 NO DATA NO DATA 6.96E-06 NO DATA 1.03E-05 1.21E-04 NO DATA 4.79E-05 7.14E-05 NO DATA 3.70E-05 1.05E-07 1.05E-07 1.05E-07 Lung NO DATA NO DATA 2.85E-06 NO DATA NO DATA 1.59E-05 1.23E-05 1.05E-07 GI-LLI I 40E-05 1.51E-05 3.40&~05 4.02E-05 9.70&~06 2.59E-06 2.11IE-06 1.05E-07 Highest Annual Net Mean Concentration Location (pCi/kg)

Bone ALL 0.00 0;00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00

-ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 129 1.60 2.68E-03 128 1204 0.00E+00 Liver 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.66E-03 2.65E-03 T. Body O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.40E-03 2.65E-03 Dose (mirem)

Thyroid Kidney 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.24E-03 2.65E-03 2.65E-03 Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 4.1 3E-04 2.65E-03 GI-LI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.09E-05 2.65E-03 Dose Commitment (mrem) =

2.68E-03 6.32E-03 5.05E-03 2.65E-03 3.90E-03 3.07E-03 2.73E-03 Section 4 - Page 18

000000009000000000000000000*000000000000000o Dose from McGuire Nuclear Station Shoreline Sediment Pathway for 2007 Data Maximum Exposed Adult Shoreline Recreation 12 hr (in one:year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (river shoreline - location 130)

Sediment Surface Mass =

40 kg/m 2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mreni/hr per pCi/im2) x Shore Width Factor x Sediment Surface Mass (kg/m 2) x Sediment Concentration (pCi/kg)

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

(mrem/hr per pCi/m 2)

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

T. Body Skin Mu'-54' 5.80E-09 6.80E-09 ALL 0.00 0.OOE+00 0.OOE+00 Co-58 7.0OE-09 8.20E-09 ALL 0.00 0.OOE+00 0.OOE+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.OOE+00 0.00E+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-09 130 114 4.60E-05 5.36E-05 Dose Commitment (mrem) =

4.60E-05 5.36E-05 Section 4 - Page 19

00 5.0 QUALITY ASSURANCE 05.1 SAMPLE COLLECTION 0

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

5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures.

EnRad SLaboratories is located in Huntersville, North

Carolina, at Duke Energy Corporation's Environmental Center.

5.3 DOSIMETRY ANALYSIS Duke Energy Corporation's

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

0 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0

5.4.1 DAILY QUALITY CONTROL 0

EnRad Laboratories has an internal qualityassurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control 0checks ensure that instruments are in proper working order and these checks

are used to monitor instrument performance.

0 5.4.2 CALIBRATION VERIFICATION

National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging

from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of

limits.

0 0

0

0 0

5.4.3 BATCH PROCESSING S

Method quality :control samples are analyzed with sample analyses that are processed' in batchies'... These include gross beta in drinking water and all tritium analyses..,

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories. participated. in the Duke Energy Nuclear Generation Department Intercomparison Program. during :.2007.

Interlaboratory. cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four

,.counting, -laboratories in. Duke.,,Energy: for this program;ý A summary of these Intercomparison Reports for 2007 is documented in Table 5.0-A.

5.6 DUKE ENERGY AUDITS The McGuire 'Radiation Prftec'tioni S ection was not audited by the Quality Assurance Group in 2007. The program was audited in 2006. There were some REMP areas for improvement identified as a result of the 2006 audit (PIP M-06-01151).

EnRad Laboratories was not audited.by the Quality Assurance Group in 2007. The program was audited in 2006. There were no REMP recommendations as a result of the 2006 audit.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 5S The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2007 (Reference 6.12). There were no findings identified by the audit.

5.8 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM 00 EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section.

sS 0

S S

S Section 5 -Page 2 5

0 S

0 0

0 S

0 0

0 S

0 0

0 S

0 0

5.9 TLD INTERCOMPARISONTPROGRAM 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

of RoS well,; GA!

Nualgea"-1i>,hn6logy. Services irradiates environmental dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.

5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM The State of North Carolina Radiation Protection Section suspended this program during 2007 as described in PIP G-07-00366.

5.9.3 INTERNAL CROSSCHECK (DUKE ENERGY)

Radiation Dosimetry and Records participates in

a. quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimete.rs quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-B.

,Section 5 - Page 3

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY-COMPARISON PROGRAM 2007 CROSSX:1HECK RESUILTS.FOR' ENRAL LABOkATORIES Cross-Check samples are normally analyzed a minimur"-of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated adccptance range. A status of "1 Pass" indicates that one analy'sis of the cross-check was performed.

If applicable,, footnote explanations are included folowing this data table.

Gamma in Water 3.5 liters Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

_________pCi/!,

pCi/

pCi/I.............

,6/26/2007.

Q072GWR Cr-51 1.06 -,!.88 E4-.

1.41 E4 1.37 E4 3 Pass Co-57 2.68 -4.76.E2.

3.58 E2

- 3.80 E2 3 Pass Co-60 1.46-2.59.E3 E3.

1.95 E3 1.94 E3 3 Pass Sr-85 1.83-3.24 E3

,2.44 E3 2.30 E3 3 Pass Y-88 2.82 -5.00 E3

.3.76 E3 3.62 E3 3 Pass Cd-109 0.77 - 136 E4

- 1.02-E4 1.07 E4 3 Pass Sn-113 1.40 - 2.49 E3 1.87 E3 1.85 E3 3 Pass Te-123M 3.73 -6.61 E2 4.9"7-E2, 4.78 E2 3 Pass

-Cs,137 1.13 - 2.00 E3.

1.51 E3

-1.45-E3 3 Pass 11/20/2007 Q074GWS Cr-51 2.96 - 5.24: ES 3.94 E5 3.97 E5 3 Pass Co-57 1.33-2.37 E4 1.78 E4-1.86 E4 3 Pass Co-60 7.33 - 12.99 Eý-

. 9.77 E4 9.69 E4 3 Pass Sr-85 7.21 - 12.78 E4 9.61 E4 9.48 E4 3 Pass Y-88 1.23-,2.9 E5 1.65 E5 1 !.64 E5 3 Pass Cd-109.,3.93

-6.96 E5 5.24 E5 5.31 E5 3 Pass Sn-11,3 6.18-,10;96 E4

.8.24 E4 8.29 E4 3 Pass Te-123M 1.61 - 2.85-E4 2.15 E4 2.20 E4 3 Pass Cs-!37...

6.07 - 10.76 E4 8.09 E4 7.82 E4 3 Pass Gamma in,,Water. 1.0 liter Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/I pCi/1

.6/26/2007 Q072GWR Cr-51 E"1.06-1.88 E4.-

I 41 E4 1.41 E4 3 Pass

- .Co-57

.--2.68.- 4.76.E2 3.58 E2

.3.89 E2 3 Pass Co-60

!-A 66-2.59 E3

. 1.95 E3 1.97 E3 3 Pass L

Sr-85 1:.83-3.24,E3 2.44 E3 2.37 E3 3 Pass Y-88-.

2.82 - 5.00' E3 3.76 E3 3.77 E3 3 Pass Cd-109..

0.77-1.36 E4

- 1.02 E4 1.06 E4 3 Pass Sn-i 13 1.40 - 2.49,.E3 1.87 E3 1.87 E3 3 Pass Te-123M

-. 3.73.- 661 E2 4.97 E2ý 5033 E2 3 Pass Cs-137 1A 33-2.00 E3

,,15 !.E3 E3 3 Pass

,lbo

3 P s S

0 0

S 0

0 0

0 S

0 0

0 Section 5 - Page 4

S 0

0 0

0 Gamma in Water 1.0 liter, continued 11/20/2007 Q074GWS Cr-51 2.96-5.24 E5 3.94 E5

.4.00 E5 3 Pass Co-57' 1.33-2.37 E4

'"1".781 E4 1.87 E4 3 Pass Co-60'

.7.3:-, 12.99 E#-,:9,77..E4 9.80 E4 3 Pass Sr-85 7.21 - 12.78, E4.

9:6I1 E4 9.61 E4 3 Pass Y-88 1.23-2.19 E5 1.65 E5 1.66 E5 3 Pass Cd-109 3.93 - 6.96 E5 5.24 E5 5.36 E5 3 Pass Sn-113 6.18-10.96 E4 8.24 E4 8.34 E4 3 Pass Te-123M 1.61-2.85 E4 2.15 E4 2.19 E4 3 Pass Cs-137 6.07-10.76 E4 8.09 E4 7.95 E4 3 Pass Gamma in Water 0.5 liter Reference Sample'l:D..

Nuclide "Acceptafic"-"'Refe'rence Mean Reported Crodss (lie"ck Date Range Value Value

Status, pCi/I pCi/I pCi/I 6/26/2007 Q072GW.R.

Cr-51 1.06-1.88 'E4" 4

141 'E4 1.41 E4

"3 Pass Co-57 2.68-4.76 E2 j 3.58 E2

.3.76 E2 3 Pass

- Co-60 1.46-2.59 E3 1.95 E3 1.97 E3 3 Pass Sr-85 1.83-3.24 E3

-2.44 E3 2.32 E3 3 Pass Y-88 2.82-5.00 E31 3.76 E3 3.62 E3 3 Pass Cd-109 0.77-1.36 E4.

1.02 E4 1.02 E4 3 Pass Sn-113 1.40-2.49 E3

-1.87 E3 1.87 E3 3 Pass Te-123M 3:73 -6.61 E2"

'-4.97 E2 4.88 E2

,3 Pass Cs-137 1.13 2.00 E3 1.51 E3 1.40 E3 3 Pass 11/20/2007 Q074GWS Cr-51 2.96-5.24."JE5.

3.94 E5 3.95 E5.

3 Pass Co-57 1.33-2.37 E4 1.78 E4 1.79 E4 3 Pass Co-60 7.33 - 12.99E4 9."77 E4 9.54 E4 3 Pass Sr-85 7.21 - 12.78 E4.

961 E4 9.28 E4 3 Pass Y-88.

1.23-2.19 E5 1.65 E5 1.61 E5 3 Pass Cd-109 3.93-6.96 E5 5.24 E5 5.26 E5 3 Pass Sn-113 6.18-10.96 E4t 8.24 E4 8.16 E4 3 Pass Te-123M 1.61 -2.85 E4 2.15 E4 213 E4 3 Pass Cs-137 6.07-10.76 E4 8.09'E4 7.59 E4

-3 Pass Gamma in Water 0.25 liter Reference Sample I.D.

-Noclide Ac~eptafke Reference Mean Rep~oed C!ossthck -*

Date Range Value Value Status

.pCi/I pCi/I pCi/I 6/26/2007:

Q072GWR Cr-Si..

1.06 - 1.88 E4 1.41 'E4 1.44 E4.Pa, Co-57

-2.68 -4.76 E2 3.59-'E2 3.95 E2 3 Pass Co-60 1.46-2.59 E3 1.95 -E3-..

1.93 E3 3 Pass Sr-85 1.83--3.24 E3 2-44-'E3

'2.42 E3 3 Pass Y-88 2.82-5.00 E3-3.76-E3 '...3.67 E3 3 Pass

-.Cd-109 0.77-1:36E4-"

1.02 E4 1.07 E4 3 Pass Sn-I 13 1.40-2Z49 E3 1'.7 E3 1.86 E3 3 Pass

-Te-123M 3.73 - 6.61 E2-

."4-97 E2 4.86 E2

.3 Pass

- Cs-137.., 1.13 -2.00 E3".

1.5 1 -E3 1.45 E3 3 Pass Section 5 - Page 5

Gamma in Water 0.25 liter, continued 11/20/2007 Q074GWS Cr-51

2.96 - *5.24 E5.

3.94 E5 3.90 E5 3 Pass Co-57 F.33 -. 2.37_E4.

1.784.17 1.82E4 3 Pass Co-60 7.33:._12.99. E4

. 9.77 _E4

-9.56 E4.

Pass Sr-85 7.21 - 127,8.E4..9.6. E4..

9.27, E4 3 Pass Y-88 1.23-2.19 E5 1.65 E5 1.62 E5 3 Pass Cd-109 3.93-6.96 E5 5.24 E5 5.12 E5 3 Pass Sn-113 6.18 - 10.96 E4, 8.24 E4

.8.08 E4.

3 Pass Te-123M 1.61 -2.85 E4 2.15 E4 2.15 E4 3 Pass Cs-137 6.07 - 10.76 E4 8.09 E4 7.67 E4 3 Pass Gamma in Filter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported "Cross Check Date

-Range.

Value Value Status pCi pCi pCi 6/14/2007 E5415-37 Cr-51 2.63 -4.67 E2 3.51 E2 3.25 E2 3 Pass Mn-54 0.86-1.52:E2 41.14 E2 1.18 E2 3 Pass Co-58 1.02-1.81i t2 1.36 E2 1.28 E2 3 Pass Fe-59 0.86-1.52 E2 1.14 E2 1.20 E2 3 Pass Co-60 1.22-2.17 E2 1.63 E2 1.57 E2 3 Pass Zn-65 1.72 -"3105 `E2

'2.29 E2 2.31 E2 3 Pass Cs-134 1.25-2.21 E2 1.66 E2 1.48 E2 3 Pass Cs-137 0.87-1.54 E2 1.16 E2 1.06 E2 3 Pass Ce-139 0.00- 0.00- EI 0.00E+"00

" 3.10 El1 3 Pass U Ce-141 1.03-1.82 E2 1.:37 E2 1.29 E2 3 Pass

.Iodine in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

pC i/l pC i/l s

pC i/I 5/15/2007 Q072LIWI

[-131 N/A 0.OOE+00 0.OOE+00 3 Pass 5/15/2007 Q072LIW2 1-131.

1.84-3.27 E3 2.46 E3 2.06 E3 3 Pass 5/15/2007 Q072LIW3-1.131 1.70- 3.01 'El

2.26 El 2.20 El 1

3 Pass lodine in -Milk Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/l 7/25/2007 Q073LIMI 1-131 0.95-1.68 E3 1.27 E3 1.11 E3 3 Pass 7/25/2007 Q073LIM2 1-131 3.62-8.34 EO 5.49 EO 5.65 EO 3 Pass 7/25/2007 Q073LIM3 1-131 2.30-4.07 El 3.06 E1 2.67 E1 3 Pass 0

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Iodine on Cartridge Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Rangeý,

Value Value Status pC.

pCi pCi 6/14/2007 E541'6-37 4-.

1-13 592-1049 E17 7.89 El 9.77 El 3 Pass Beta Air Particulate Reference Saripl-e ID..

Nuclide AccepWt.an ce R

ijftrece.

'Mean Reported Cross Check Date Rang...

Value Value Status

{ j p~~i

Yplue, Value,,

_I 6/14/2007 E5417-37 Cs-137 0.92-1.62 E2 1.22 E2 t.14. E2 3..Pass.

B eta in W ate...........

Reference Saniple I.D Nuclide Acceptance V

Reference Mean Reported Cross Check Date Ran Value.

Value Status...,

j 111 C~lpCi/l

.p~ilI 6/14/2007 E5418-37 Cs-137 p

I - 1.97 E2,

.1.48 E2 1.58 E2 3 Pass Beta Smear Reference.

Sample I.D:..

Nuclide-Acceptance-.

Reference-Mean Reported Cross Check Date Range Value Value Status

.--. dpm

.dpm.

dpm 1/11/2007 A21058-04 Beta 1.01 - 1.80 E4 1.35 E4

-1.32 E4 3 Pass Tritium in Water Reference

. Sample 10..

Nuclide..

. Acceptance Reference. Mean Reported Cross Check, Date Range Value Value Status j

pCi/I pCi/l pCi/l 6/25/2007 Q072TWR1 H-3 3.87 - 7.69 E2 5.45 E2 4.83 E2 3 Pass 6/25/2007 Q072TWR2 H-3 0.78 -,1.38 E4-104-,E4

-.-. 0.98 E4 3 Pass 6/25/2007 Q072TWR3 H4-3 1.32-2.34 E3 I-76 E3--.1,64

,E3 3 Pass -

10/7/2007.

Q074TWSLI I

-H-3.

.N/A 0.OOE+00 0.OOE+00 3 Pass 10/7/2007 Q074TWSL2 H-3 2.71 -4.81 E4 3.62 E4 3.63 E4

. 3, P.s_.

Section 5 - Page 7

Table 5.0-A Footnote Explanations (1)

Gamma in Filter, Sample ID E5415-37, Refetrence Date 6/14/2007 Ce-139 was identified in cross-check sample and reported.

The cross check supplier does not include this radionuclide on the certificate of analysis for this cross-check sample.

The radionuclide, was determined to be an inherent contaminant in the cross-check sample.

Section 5 - Page 8 0

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0 TABLE 5.0-B 2007 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2007 2nd Quarter 2007 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 102164 73.0 73.4 0.55

<+/-15%

Pass 102493 90.5 92.8 2.54

<+/-15%

Pass 102322 73.0 77.3 5.89

<+/-15%

Pass 102316 90.5 94.2 4.09

<+/-15%

Pass 102263 73.0 76.0 4.11

<+/-15%

Pass 102476 90.5 94.0 3.87

<+/-15%

Pass 102250 73.0 77.8 6.58

<+/-15%

Pass 102492 90.5 94.6 4.53

<+/-15%

Pass 102184 73.0 79.3 8.63

<+/-15%

Pass 102470 90.5 92.7 2.43

<+/-15%

Pass Average Bias (B) 5.15 Average Bias (B) 3.49 Standard Deviation (S) 3.04 Standard Deviation (S) 0.95 Measure Performance IBJ+S 8.19

<15%

Pass Measure Performance IBI+S 4.44

<15%

Pass 3rd Quarter 2007 4th Quarter 2007 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 102174 65.5 63.7

-2.75

<+/-15%

Pass 102006 92.2 99.0 7.38

<+/-15%

Pass 102220 65.5 67.7 3.36

<+/-15%

Pass 102093 92.2 97.5 5.75

<+/-15%

Pass 102236 65.5 64.5

-1.53

<+/-15%

Pass 102244 92.2 103.6 12.36

<+/-15%

Pass 102302 65.5 66.5 1.53

<+/-15%

Pass 102343 92.2 100.3 8.79

<+/-15%

Pass 102304 65.5 66.1 0.92

<+/-15%

Pass 102436 92.2 100.7 9.22

<+/-15%

Pass Average Bias (B) 0.31 Average Bias (B) 8.70 Standard Deviation (S) 2.44 Standard Deviation (S) 2.46 Measure Performance IBI+S 2.75

<15%

Pass Measure Performance IBI+S 11.16

<15%

Pass Section 5-Page 9

Internal Crosscheck (Duke Energy) 1st Quarter 2007 TLD Delivered Reported Bias Pass/Fail 2nd Quarter 2007 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem) 100770 24.0 22.3 100522 24.0 23.6 100041 24.0 22.0 100038 24.0 23.0 100762 24.0 21.1 100148 24.0 23.2 100279 24.0 23.0 100619 24.0 23.2 100784 24.0 22.0 100814 24.0 22.8 Average Bias (B)

Standard Deviation (S)

Measure Performance 1BI+S

(% diff)

Criteria Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail

-6.97

<+/-15%

-1.70

<+/-15%

-8.22

<+/-15%

-4.28

<+/-15%

-11.93

<+/-15%

-3.41

<+/-1 5%

-4.37

<+/-15%

-3.48

<+/-15%

-8.45

<+/-15%

-4.93

<+/-15%

-5.77 3.07 8.84

<15%

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 101190 48.0 47.1

-1.88

<+/-15%

Pass 100026 48.0 46.4

-3.33

<+/-15%

Pass 100148 48.0 46.3

-3.54

<+/-15%

Pass 100038 48.0 47.2

-1.67

<+/-15%

Pass 100096 48.0 46.4

-3.33

<+/-15%

Pass 100770 48.0 46.1

-3.96

<+/-15%

Pass 100740 48.0 46.9

-2.29

<+/-15%

Pass 100784 48.0 45.6

-5.00

<+/-15%

Pass 100619 48.0 47.1

-1.88

<+/-1 5%

Pass 100814 48.0 47.0

-2.08

<+/-15%

Pass Average Bias (B)

-2.90 Standard Deviation (S) 1.10

.Measure Performance JBI+S 4.00

<15%

Pass 1~

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(mrem) 100389 24.0 22.7 100407 24.0 22.8 100629 24.0 22.9 100409 24.0 23.7 100647 24.0 23.5 100274 24.0 22.8 100117 24.0 22.6 100162 24.0 22.1 100423 24.0 23.1 100611 24.0 23.6 Average Bias (B)

Standard Deviation (S)

Measure Performance IBI+S Bias Pass/Fail

(% diff)

Criteria

-5.42

<+/-15%

-5.00

<+/-15%

-4.58

<+/-15%

-1.25

<+/-15%

-2.08

<+/-15%

-5.00

<+/-15%

-5.83

<+/-15%

-7.92

<+/-15%

-3.75

<+/-15%

-1.67

<+/-15%

-4.25 2.09 6.34

<15%

Pass/Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 4th Quarter 2007 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 100412 12.0 11.9

-0.83

<+/-15%

Pass 100733 12.0 11.3

-5.83

<+/-15%

Pass 100477 12.0 11.6

-3.33

<+/-15%

Pass 100406 12.0 11.5

-4.17

<+/-15%

Pass 100863 12.0 11.8

-1.67

<+/-15%

Pass 100870 12.0 11.6

-3.33

<+/-15%

Pass 100752 12.0 12.1 0.83

<+/-15%

Pass 101021 12.0 11.6

-3.33

<+/-15%

Pass 100096 12.0 11.9

-0.83

<+/-15%

Pass 101307 12.0 11.4

-5.00

<+/-15%

Pass Average Bias (B)

-2.75 Standard Deviation (S) 2.08 Measure Performance IBI+S 4.83

<15%

Pass i

i ri

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0 0

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0 0

0

0 0

0

6.0 REFERENCES

6.1 McGuire Selected License Commitment Manual 0

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

6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2006 6.6 McGuire Annual Radioactive Effluent Release Report 2007 0

6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

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

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

Evaluating Compliance with 10CFR50, Appendix I.

0 6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software,

Canberra Version 3.5.1, DPC Revision #4.0 0

6.12 NRC Integrated Inspection Report (50-369/2007005, 50-370/2007005) 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 00 0

0 0

0 0Section 6 - Page 1 0

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APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page I

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APPENDIX A 0

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ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance With Station Selected Licensee Commitments.

Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities Were achieved. '

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

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

0 I. CHANGE OF SAMPLING PROCEDURES No changes were made to the sampIing procedures during 2007.

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

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

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

A0 0

Appendix A -Page 2 S

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0 Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Teinelec XLB Series 5 gas-flow proportional counters.

Samples are batch, processed with. a. blank to ensure sample contamination has not occurred.

11.

CHANGE OF ANAL'VSSPROC IDURES No analysis procedures were changed during 2007.

IV.

SAMPLING AND ANALYSIS PROC'CDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and riadioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant' flow rate (in order to: compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly.

A separate weekly gamma analysis was performed on each charcoal cartridge and air particulate.* i A; weekly gross beta analysis-was performed on each filter. The continuous composite samples were collected from the locations listed below.

Location 120 Location 121 Location 125 Location 133 Location 134 Location 192 Location 195 Site Boundary (0.46 mi. NNE)

Site Boundary (0.47 mi. NE)

Site Boundary (0.38 mi. SW)

Cornelius (6.23'mi. ENE)

East Lincoln Jr. High School (8.77 mi. WNW)

Peninsula (2.84 mi. NNE)

Fishing Access Road (0.19 mi. N)

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

Location 101 Location 119 Location 132 Location 136 Location 194 North Mecklenburg Water Treatment Facility (3.31 mi E)

Mt. Holly Municipal WaterSupply (7.40 mi. SSW)

CharlotteMunicipal Water Supply (11.1 mi. SSE)

Mooresville Municipal Water Supply (12.7 mi. NNE)

East Lincoln County Water Supply (6.73 mi. NNW)

Appendix A - Page 3

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

Location 128 Location 131 Location 135 Discharge Canal Bridge (0.45 mi. NE)

Cowans Ford Dam (0.64 mi. WNW)

Plant Marshall Intake Canal (11.9 mi. N)

A.4 MILK Biweekly grab samplesi were collected at each. dairy.

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

Location 139 Location 141 William Cook Dairy (2.49 mi. E)

Lynch Dairy - Cows (14.8 mi. WNW)

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

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0 Location 120 Location 125 Location 134 Location 193 Site Boundary (0.46 mi. NNE)

Site Boundary (0.38 mi. SW)

East Lincoln Junior High School (8.77 mi. WNW)

Site Boundary (0.19 mi. N)

A.6 FOOD PRODUCTS

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

Location 188

= -. 5 mile radius Gardens (2.79 mi NNE)

A.7 FISH..

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

Appendix A - Page 4

0 0

Location 129

=

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

Location 137

=

Pinnacle Access Area (12.0 mi. N) 0 A.8 SHORELINE SEDIMENT Semiannual samples were collected and a gamma analysis was performed on each following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 129

=

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

Location 130

=

Highway 73 Bridge Downstream (0.52 mi. SW)

Location 137

=

Pinnacle Access Area (12.0 mi. N)

A.9 DIRECT GAMMA RADIATION (TLD)

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

locations.

A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 221 -B. The TLDs were placed as indicated below.

An inner ring of 14 TLDs at the site boundary, one in each available

meteorological sector., The site boundary locations in the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March, 1991.

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

kilometer range.

The remaining TLDs were placed 'in special interest areas such as population centers, residential areas, schools, and control locations.

0 A.10 ANNUAL LAND USE CENSUS 0An annual Land Use Census. was conducted to 'identify within a distance of 8

kilometers (5.0'miles) from the station, the nearest location from the site boundary in 0each of the sixteen meteorological sectors, the following:

The Nearest Residence 0The Nearest Garden greater than 50 square meters or 500 square feet The Nearest Milk-giving Animal (cow, goat,,etc.)

0 The census was conducted during' the, growing season from 5/21 to 5/22/2007.

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

,during 2007 as a result of the 2007 census.

0 0

0

'Appendix A -Page 5 0

In the environmental program, the air deposition parameters (D/Q) are used to determine air, broadleaf vegetation and milk sampling locations. McGuire's sectors with the three highest values did not change in 2007.

V.

GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The McGuire site centerline used for GPS measurements was referenced from the McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1, Site Location. Waypoint coordinates used for MNS GPS measurements were latitude 35°-25'-59"N and longitude 80'-56'-55"W. Maps and tables were generated using North American Datum (NAD) 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement. GPS field measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.

Appendix A - Page 6 0

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APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PRO GRAM

SUMMARY

OF RESULTS 2007 Appendix B - Page I

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 Medium or Pathway Sampled Unit of Measurement Type and Total Number of Analyses Performed Lower Limit of Detection (LLD)

'All indicator.

Locations Mean (Fraction)

Range Location with Highest

'Annual Mean Name, Distance, Direction Control Location Mean (Fraction)

Range No.of Non-Routine Report Meas.

Location Mean (Fraction)

Code Range,

L I ____________________________

I I

Air Particulate (pCi/m3) 134 (8.77 mi WNW)

BETA 364 1.00E-02 2.02E-2 (312/312) 195 2.12E-2 (52/52) 2.18E-2 (52/52) 0 1.01E 3.76E-2 (0.19 mi N) 1.06E 3.52E-2 1.06E 3.97E-2 CS-134 364 5.00E-02 0.00 (0/3 12) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 364 6.OOE-02 0.00 (0/312) 0.00(0/52) 0.00 (0/52) 0 0.00- 0.00 0.00o- 0.00 0.00o- 0.00 1-131 364 7.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 o.o0 0 o.oo 0oo-o.oo 0.00- 0.00 S

0 0

S 0

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

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:11 Appendix B - Page 2

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Environmnental Radiologica AMonitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 Type and Lowe' INo. of Non-Meiu orLower,;*:,

i, Location~with Highest Total All Indicator; Lo.a...n..th HighestControl Routine Pathway ormota Limit of Ann'al' Mean Numbetion

,Locations

¢,::*:.

AniaMen r

I Lo',ation.,,

epr Pamhway Detection Name, Distance, Direction Sampled of Meas.

Unit of Analyses :

LL,)

Mean:(Fractionl)

-:L6dation Mean (Fraction)

"Mean (Fraction)

Measurement Performed Range

'Code Rang R n,6 Air Radioiodine 134.

(pCi/m3)

(8.77 mi WNW)

CS-134 364. 5.OOE-02 0.00(0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 CS-137 364 6.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 364 7.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:12 1

Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina.

Docket No.

50-369,370 Report Period: Ol-JAN-2007 to 31-DEC-2007 Medium or Pathway Sampled Unit of Measurement Type and Total Number of Analyses Performed Lower Limit of Detection (LLD)

All Indicator Locations Mean (Fraction)

Range

. Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Location Mean (Fraction)

Code Range

Mean (Fraction)

Range Drinking Water (pCi/liter) -;

136 (12.7 mi NNE)

BALA-140 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00-0.00 0.00.- 0.00' 0.00-0.00 BETA 65 4

1.76 (51/52) 119 1.81 (13/13) 1.76 (12/13) 0 0.73-2.68 (7.40 mi SSW) 0.73-2.68 1.27-2.71 CO-58 65 15 0.00 (0/52).000 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 65 18 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 65 30

. 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 H-3 20 2000 1054 (14/16) 101 1480 (4/4) 0.00 (0/4) 0 307-1951 (3.31 rni E) 1300- 1950 0.00-0.00 1-131 65 15 0.00 (0/52) 0.00 (0/13)

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

.0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 65 30 0.00(0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 65 15 0.00 (0/52).0.00 (0/13) 000 (0/13),

0 0.00 -0.00 0.00- 0.00 0.00 -0.00 0

0 0

0 S

0 0

0 S

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

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:17 Appendix B -Page 4

Environmental Radiological, Monitoring Program Summary 0

S S

0 0

0 S

0 0

0 S

0 0

Facility: McGuire Nuclear Station Location: Mecklenburg-County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower

l. l ndi Location with Highest Control Routine Pathway*

Number Limit Qf Annual Mean L,,a..

n i

Location Report Sampled of

LoctName, Distance,'Direction Meas.

Unit of Analyses

(

Mean(Fractioo),.'.Location Mean (Fraction) Mean (Fraction)

Measurement Performed.

(LLD Range Code Range Range Surface Water 135 (pCi/liter)

(11.9 mi N)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 10.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26).

0.00 (0/13)

.0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00o- 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13)

. 0.00 (0/13) 0 0.00 - 0.00 0.00- 0.00 0.00- 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12

. 2000 1298 (8/8) 128 1680(4/4) 342 (2/4) 0 814-2460 (0.45 mi NE) 1280-2460 339-344 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction 'of detectable 'mea'surements atIsliecified'locatibný is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report. Generated @ 2/25/2008 15:19 Appendix B - Page 5

Environmental Radiological-Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower Location withoHighest Control Routine Pathway Number Limit of Llcator Annualt Mean Locations Location Report Sampled of Detection Name, Distance, Direction

~Meas.

Unit of Analyses.

Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Milk 141 (pCi/liter)

(14.8 mi WNW)

BALA-140 52 15 0.00 (0/26) 0.00.(0/26) 0.00 (0/26) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 CS-134 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 52 18 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 52 15 0.00 (0/26) 0.001(0/26),

0.0.0 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 52 1

0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00"- 0.00 0.00 - 0.00 0

0 0

S 0

0 0

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

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:20 Appendix B - Page 6

00 0

S 0

0 S

0 0

0 S

0 0

0 Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lowe r

Location with Highest Pathway Number Limit of Llcaton Annual Mean Location Report Sampled of Detection Locations Name, Distance, Direction L

Repor Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

Measurement Performed (DRange

..... Code Range Range Broadleaf 134 Vegetation (8.77 mi WNW)

(pCi/kg-wet)

CS-134 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 48 80 13.4(1/36) 120 13.4(1/12) 0.00(0/12) 0 13.4-13.4 (0.46 mi NNE) 13.4-13.4 0.00-0.00 1-131 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:22

. Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370,

Report Period: 01-JAN-2007 to 31-DEC-2007 Medium or Pathway Sampled Unit of Measurement.

Type and Total Number of Analyses Performed Lower Limit of Detection (LLD)

All Indicator Locati.ons Mean (Fraction)

Range Location with Highest Annual Mean Name, Distance, Direction Location Mean' (Fraction)

Code RangeC" Control Location Mean (Fraction)

Range No. of Non-Routine Report Meas.

Food Products NO CONTROL (pCi/kg-wet).

LOCATION

.CS-134 12 60 0.00(0/12) 0.00 (0/t2) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 CS-137 12 80 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00

.. 1-131 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 2/25/2008 15:22 Appendix B -Page 8 00 0

0 0

0

0 0

S 0

0 0

0 S

S 0

0 0

0 Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 i

No.

of Non-Medium or Type and Total Lower A

Location with Highest No. of N.n.

MAll Indicator-.!

nu Cbntrol Routine Pathway Number Limit of.

Anua Meaoain Rpr Locations Anu 2...:;,.

Location Report Sampled of..

Detection Laon Name, Distance, Direction Meas i

Meas.

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

Mean :(Fraction)

Measurement Performed (LLD)

Range

Code, Range Range Fish 137 (pCi/kg-wet)

(12.0 mi N)

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60

.12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 CS-137 12 150 21.1 (1/6) 129 21.1 (1/6) 19.5 (1/6).....

0 21.1-21.1 (0.51 mi ENE) 21.1 -21.1 19.5 -19.5 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 S 0.00- 0.00 0.00- 0.00 b

0.00 - 0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/1/2008 13:43 Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower A

n Location with Highest Pathway Number Limit of Annual Mean.Loction Reorti Locations, Location Report Sampled of Detection Name; Distance, Direction Meas.

Unit of Analyses Mean (F'raction),

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (LD)

Range Code Range Range Shoreline.

137 Sediment (12.0 mi N)

(pCi/kg-dry)

MN-54 6

0 0.00 (0/4)ý 0.00 (0/2) 0.00 (0/2) 0.00- 0.00 0.00- 0.00 0.00 - 0.00 CO-58 6

0 0.00 (0/4) 0.00 (0/2)

.0.00 (0/2) 0 0.00 -0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6

0 0.00 (0/4) 0.00 (0/2).

0.00 (0/2) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 6

150 0.00(0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6

180 114(1/4) 130 114(1/2) 0.00(0/2) 0 114-114 (0.52 mi SW) 114-114 0.00-0.00 S

0 0

S 0

0 0

S 0

0 S

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

Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @2/25/2008 15:27 Appendix B - Page 10

0 S

0 0

0 S

0 0

0 Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Location: Mecklenburg County, North Carolina Docket No.

50-369,370 Report Period: 01-JAN-2007 to 31-DEC-2007 Type andMedim o Totl L~WC~

Al LoatiNo.

of Non-Typi r

Location with Highest Ncontro Routine Medium or Total

Lo~~r,,. *iAll Indicator Co,,." I' Rouin Pathway Sampled Number' Limit of Annual M Location Report LocaDetection Distance, Direction of DMeas.

Unit of Measurement Analyses (LLD)

Mean (Fraction): -1Location Mean (Fraction). Mean (Fraction)

Performed Range i Code Range Range..

Direct Radiation 175 TLD (15.5 mi WNW)

(mR/standard quarter) 161 0.OOE+00 17.4 (157/157)....

180 26.9 (4/4) 22.5 (4/4) 0 10.2 - 41.2 (12.7 mi NNE) 25.4-28.3 20.3 - 24.8 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements

Report Generated @ 2/25/2008 15:38 Appendix B - Page 11

0 0

S S

S 0

0 0

0 APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page I

APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLEREASON CODES...

BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1.

SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location.

Collection Dates Collection Dates Code Corrective Action Planned power interruption to site by Duke maintenance occurred 2/24/2007 from approximately 12:00 to 13:00 as requested by ix;otk request 40815. Safety-related maintenance was performed to replace electrical knife switch with breaker panel. Switch replacement was performed inconjunction with work request 40801 (restoration of power) 134 2/19 - 2/26/2007 2/19 - 2/26/2007 PI completed late 2006 for this location.

Drinking Water,,..

... : i

.Scheduled

-.A ctual :.,

Reason

- r...

Location 2,Collection Dates '-Collection Dates Code.

Corrective Action

.. Water plant personnel contacted Duke, indicating the water sampling equipment was making a strange noise and they had turned off the water supply @ 9/13/2007 11:00. Work request 48579 written.

Maintenance determined the noise was pipe chatter and was emanating from the water supply line, not the sampling equipment. Normal sampling was resumed 136 8/27 - 9/24/2007 8/27 - 9/24/2007 PS 9/18/2007 09:00.

00 0

0 0

0 Appendix C - Page 2

00 0

0 0

0 Surface Water Scheduled Actual.

Reason Location Collection Dates" CollectionDates.

C6d40 Corrective Action Onsite vehicle accident at Marshall station caused power interruption to sampling equipment 2/22/2007. Work request 42610 written. Power was restored and normal sampling resumed 2/27/2007 15:00. It is estimated sampling was 135 2/12 - 3/i2/2007 2/42-3i/12/2600z7

PI interrupted for about 5 days.

'Reservoir pump malfuncftion due' to, clogged intake line wasidentified. Work request 43766 written. Intake line was repaired and reservoir pump was replaced.

Normal sampling resumed 4/13/2007' 128 4/9 - 5/7/2007 4/13 - 5/7/2007 LC..

16:00.

Reservoir pump malfunction interrupted water flow to sample reservoirn,.Work request 45370 written. Flow restored and 135 6/4 - 7/2/2007 6/7 - 7/2/2007 PS normal sampling resumed..6/7/2007. 15:16.

Low Lake Norman water level due to exceptional drought conditions during 2007 caused loss of prime with the submersible pump., Work request 48738 written. The submersible pump was shut 8/27 - 9/24/2007 8/27 - 9/18/2007 down by maintenance on 9/1082007 to 9/24 - 10/22/2007 9/24 - 10/22/2007 prevent pump damage. Weekly grab 10/11 - 11/19/2007 10/22 - 11/19/2007 samples were initiated. PIP G-07-00791 135 11/19 - 12/17/2007 11/19 - 12/17/2007 PS was written.

C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 143 3/15 - 6/14/2007 VN TLD m ssing. 3rd quarter 2007 TLD pliked in field.

159 6/14 - 9/13/2007 CN TLDmissing. 4 th quarter 2007JTLD placed in field.

182

'6/14-9/13/2007.'.

'N..

TLDnrfiss-i q

4 th-. uar t

r 2007 TLD llcedfii field.

Appendix C - Page 3

0 0

0 S

0 0

0 S

0 0

0 APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2007 Radiological Environmental Monitoring Program Appendix D - Page 1

0 0

S 0

0 0

S 0

0 0

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2007. Appendix E is located separately from this report and is permanently archived at the Duke Energy Corporation Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

Appendix E - Page 1

ML081420434

Contents

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

Navigation menu

ML081420434

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

Navigation menu

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