ML051310022

Duke Power, Units 1 and 2, Annual Radiological Environmental Operating Report, 2004

ML051310022
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/31/2004
From:	Gordon Peterson Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051310022 (92)

Text

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Units 1 and 2 2004

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

2-2 2.3.1 Estimation of the Mean Value.

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

2-3 3.0 Interpretation of Results.

3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water.

3-5 3.3 Surface Water.

3-7 3.4 Milk.

3-9 3.5 Broadleaf Vegetation.

3-10 3.6 Food Products.

3-11 3.7 Fish.

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

4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis.

5-1 5.4 Laboratory Equipment Quality Assurance.

5-1 5.4.1 Daily Quality Control.

5-1 5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Duke Power Intercomparison Program.

5-2 5.6 Duke Power Audits.

5-2 5.7 U.S. Nuclear Regulatory Commission Inspections 5-2 5.8 State of North Carolina Intercomparion Program 5-2 5.9 TLD Intercomparison Program 5-3 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 Power) 5-3 6.0 References 6-1

ii Appendices Appendix A: Environmental Sampling and Analysis Procedures.

A-1 I.

Change of Sampling Procedures A-2 II.

Description of Analysis Procedures.

A-2 III.

Change of Analysis Procedures.

A-3 IV.

Sampling and Analysis Procedures A-3 A.1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water.

A-4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Food Products.

A-4 A.7 Fish A-4 A.8 Shoreline Sediment.

A-5 A.9 Direct Gamma Radiation (TLD).

A-5 A.10 Annual Land Use Census A-6 V. Global Positioning System (GPS) Analysis A-6 Appendix B: Radiological Env. Monitoring Program - Summary of Results B-1 Air Particulate.

B-2 Air Radioiodine.

B-3 Drinking Water.

B-4 Surface Water.

B-5 Milk.

B-6 Broadleaf Vegetation B-7 Food Products.

B-8 Fish.

B-9 Shoreline Sediment.

B-10 Direct Gamma Radiation (TLD)

B-11 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C.1 Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations.

D-1 Appendix E: Radiological Environmental Monitoring Program Results.

E-1 LIST OF FIGURES 2.1-1 Sampling Locations Map (0.5 Mile Radius).

2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-3 3.2 Concentration of Tritium in Drinking Water.

3-5 3.3 Concentration of Tritium in Surface Water.

3-7 3.7-1 Concentration of Cs -137 in Fish 3-13 3.7-2 Concentration of Co-60 in Fish.

3-13 3.8-1 Concentration of Cs -137 in Shoreline Sediment.

3-15 3.8-2 Concentration of Co-60 in Shoreline Sediment 3-16 3.9 Direct Gamma Radiation (TLD) Results 3-18 3.10 2003 Land Use Census Map 3-21 LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations.

2-6

iii 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-8 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection

. 2-9 3.1-A Mean Concentrations of Radionuclides in Air Particulate 3-3 3.1-B Mean Concentrations of Air Radioiodine (I-131).

3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water.

3-6 3.3 Mean Concentrations of Tritium in Surface Water 3-8 3.4 Mean Concentrations of Cs -137 in Milk 3-9 3.5 Mean Concentrations of Cs -137 in Broadleaf Vegetation 3-10 3.6 Mean Concentrations of Cs -137 in Food Products 3-11 3.7 Mean Concentrations of Radionuclides in Fish.

3-14 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment 3-16 3.9 Direct Gamma Radiation (TLD) Results 3-19 3.10 Land Use Census Results.

3-20 4.1-A 2004 Environmental and Effluent Dose Comp arison 4-3 4.1-B Maximum Individual Dose for 2004 based on Environmental Measurements for McGuire Nuclear Station 4-6 5.0-A 2004 Cross-Check Results for EnRad Laboratories 5-4 5.0-B 2004 Environmental Dosimeter Cross-Check Results

. 5-12 LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order)

BW BiWeekly C

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

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

Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter

µCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W

Weekly

Section 1 - Page 1 1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2004.

Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs).

Required analyses were performed and detection capabilities were met for all collected samples as required by SLCs. Eleven-hundred thirty-six samples were analyzed comprising 1,618 test results in order to compile data for the 2004 report. Based on the annual land use census, the current number of sampling sites for McGuire Nuclear Station is sufficient.

Concentrations observed in the environment in 2004 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment and fish are higher than the activities reported for samples collected prior to the operation of the station.

Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs.

Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 4.84E-2 mrem for 2004. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

Vegetation Sampling

Section 2 - Page 1

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station (MNS) is located geographically near the center of a highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land being used to support beef cattle and farming. The McGuire site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the north by 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Companys Cowans Ford Dam Hydroelectric Station. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals Hydroelectric Station is at the upper reaches of Lake Norman. Marshall Steam Station is located on the western shore of Lake Norman, approximately 16 miles upstream from the site (reference 6.3).

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

Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within 0.5 mile radius of MNS. Figure 2.1-2 comprises all sample locations within a ten mile radius of MNS.

2.2 SCOPE AND REQUIREMENTS OF THE REMP An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to operation of Unit 1 in 1981. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

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

Section 2 - Page 2 This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the environment. Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B lists the REMP analysis and frequency schedule.

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

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

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):

x

=

i i

N x

N

=

1 Where:

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

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

NOTE: Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.

Section 2 - Page 3 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program.

LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

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

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

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

Section 2 - Page 4 Figure 2.1-1

Section 2 - Page 5 Figure 2.1-2

Section 2 - Page 6 TABLE 2.1-A MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-A Codes W

Weekly SM Semimonthly BW BiWeekly Q

Quarterly M

Monthly SA Semiannually C

Control Site Location Description*

Air Rad.

& Part.

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

101 North Mecklenburg Water Treatment Facility (3.31 mi E)

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

BW 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 )

BW 129 Discharge Canal Entrance to Lake Norman ( 0.51 mi ENE)

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

SA 131 Cowans Ford Dam ( 0.64 mi WNW )

BW 132 Charlotte Municipal Water Supply ( 11.1 mi SSE )

BW 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 )

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

BW 137 C Pinnacle Access Area ( 12.0 mi N )

SA SA 139 William Cook Dairy ( 2.49 mi E )

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

SM 188 5 mile radius Gardens ( 2.79 mi NNE )

M (a )

192 Peninsula ( 2.84 mi NNE )

W 193 Site Boundary ( 0.19 mi N )

M ( b )

194 East Lincoln County Water Supply ( 6.73 mi NNW )

BW 195 Fishing Access Road ( 0.19 mi N )

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

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

Section 2 - Page 7 TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location Distance*

Sector Site Location Distance Sector 143 SITE BOUNDARY 0.27 miles NW 164 HAMBRIGHT &

BEATTIES FORD ROAD 4.64 miles SSE 144 SITE BOUNDARY 0.46 miles NNE 165 HORSESHOE BEND BEACH ROAD 5.11 miles S

145 SITE BOUNDARY 0.47 miles NE 166 RIVERBEND FOSSIL STATION 5.25 miles SSW 146 SITE BOUNDARY 0.42 miles ENE 167 LUCIA RIVERBEND HWY/

OLD FIREHOUSE 4.87 miles SW 147 SITE BOUNDARY 0.44 miles E

168 OLD PLANK ROAD BRIDGE 4.60 miles WSW 148 SITE BOUNDARY 0.46 miles ESE 169 GLOVER LANE 4.03 miles W

149 SITE BOUNDARY 0.50 miles SE 170 LITTLE EGYPT ROAD 4.32 miles WNW 151 SITE BOUNDARY 0.37 miles S

171 TRIANGLE ACE HARDWARE 3.95 miles NW 152 SITE BOUNDARY 0.44 miles SSW 172 WESTPORT COMMUNITY AT GOLF COURSE DRIVE 5.70 miles NNW 153 SITE BOUNDARY 0.47 miles SW 173 SI KEISTLER STORE /

GLENWOOD ROAD 8.39 miles NNW 154 SITE BOUNDARY 0.45 miles W

174 SI EAST LINCOLN JR. HIGH SCHOOL 8.77 miles WNW 156 SITE BOUNDARY 0.44 miles WNW 175 C BOGER CITY 15.5 miles WNW 189 SITE BOUNDARY 0.43 miles SSE 177 SI BELMARROW ROAD /

COULWOOD COMMUNITY 8.77 miles S

190 SITE BOUNDARY 0.33 miles WSW 178 SI FLORIDA STEEL CORPORATION 9.32 miles SE 157 THE POINTE/MOORESVILLE 4.69 miles N

180 SI MOORESVILLE WATER TREATMENT FACILITY 12.7 miles NNE 158 BETHEL CHURCH ROAD 4.33 miles NNE 181 SI OLD DAVIDSON WATER TREATMENT FACILITY 7.02 miles NE 159 HENDERSON ROAD 4.98 miles NE 182 SI CORNELIUS / AIR SITE # 133 6.23 miles ENE 160 ANCHORAGE MARINE SHOWROOM 4.89 miles ENE 186 SI MCGUIRE FISHING ACCESS ROAD ON PENINSULA 0.24 miles NNW 161 SAM FURR ROAD

& HWY 21 4.70 miles E

187 SI ENERGY EXPLORIUM /

AIR SITE # 195 0.19 miles N

162 RANSON ROAD 4.53 miles ESE 191 SI PENINSULA DEVELOPMENT /

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 8 TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water (pCi/liter)

Air Particulates or Gases (pCi/m3)

Fish (pCi/kg-wet)

Milk (pCi/liter)

BroadLeaf Vegetation (pCi/kg-wet)

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

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2

1 3

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

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

Air Weekly X

X Direct Radiation Quarterly X

Surface Monthly Composite X

Water Quarterly Composite X

Drinking Monthly Composite X

(a)

X Water Quarterly Composite X

Shoreline Sediment Semiannually X

Milk Semimonthly X

X Fish Semiannually X

Broadleaf Vegetation Monthly(b)

X Food Products Monthly(b)

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

(b) When Available

Section 2 - Page 9 TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION Analysis Water (pCi/liter)

Air Particulates or Gases (pCi/m3)

Fish (pCi/kg-wet)

Milk (pCi/liter)

BroadLeaf Vegetation (pCi/kg-wet)

Sediment (pCi/kg-dry)

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 I-131 1(b) 0.07 1

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

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

Section 3 - Page 1 3.0 INTERPRETATION OF RESULTS Review of 2004 REMP analysis results was performed to detect and identify changes in environmental levels as a result of station operation. The radionuclides with Selected Licensee Commitments reporting levels that indicate consistent detectable activity have been historically trended from preoperation to present. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year.

The highest annual mean concentration of applicable Selected Licensee Commitments radionuclides from the indicator locations for each media type was used for trending purposes. Trending was performed by comparing annual mean concentrations to historical results. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the radionuclides SLC reporting level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level. The highest value reached during 2004 was 3.21% for drinking water tritium at the North Mecklenburg Water Treatment Facility (Location 101).

Changes in sample location, analytical technique, and presentation of results must be considered when reviewing for trends. Calculation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net results (sample minus background) positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. All negative values were replaced with a zero for calculational and graphical purposes to properly represent environmental conditions. A change in gamma spectroscopy analysis systems in 1987 ended a period when many measurements yielded detectable low-level activity for both indicator and control location samples.

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

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

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

Data presented in Sections 3.1 through 3.9 support the conclusion that there was no significant increase in radioactivity in the environment around McGuire Nuclear Station due to station operations in 2004. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 2004 land use census data, shown in Section 3.10, indicates that no program changes are required as a result of the census.

Section 3 - Page 2 3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2004, 364 particulate and radioiodine samples were analyzed, 312 at six indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gamma and gross beta.

Radioiodine samples received a weekly gamma analysis.

Gross beta analyses indicated 1.67E-2 pCi/m3 at the location with the highest annual mean and 1.71E-2 pCi/m3 at the control location. Co-58 activity was detected in one indicator sample with an activity of 9.77E-2 pCi/m3. PIP G-04-00134 was written since Co-58 has not been detected in the past. Co-58 was being released from McGuire during the period that this air sample was collected.

Detectable gamma emitting particulate activity was last observed in environmental air particulate samples in 1987.

No detectable I-131 activity in any environmental air radioiodine samples was found in 2004. K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was detected on one cartridge in 2003 from the control location. Cs-137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

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

Table 3.1-B gives indicator location highest annual means and control means since 1979 for I-131. Preoperational and ten year averages are also shown. No I-131 activity has been detected since 1989. Since no activity was detected in 2004, no reporting levels were approached.

Section 3 - Page 3 Concentration of Gross Beta in Air Particulate 0.00E+00 1.00E-02 2.00E-02 3.00E-02 4.00E-02 5.00E-02 6.00E-02 7.00E-02 8.00E-02 9.00E-02 1.00E-01 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 pCi/m 3

Indicator Location Control Location Figure 3.1 There is no reporting level for Gross Beta in air particulate Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate YEAR Cs-137 Indicator (pCi/m3)

Cs-137 Control (pCi/m3)

Beta Indicator (pCi/m3)

Beta Control (pCi/m3) 1979*

4.40E-3 1.47E-3 1980*

6.70E-3 4.53E-3 1981*

6.16E-3 5.32E-3 1982*

3.82E-3 2.29E-3 1983*

2.93E-3 3.21E-3 1984 1.74E-3 8.29E-4 1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 1986 4.98E-3 3.03E-3 2.64E-2 2.52E-2 1987 1.07E-2 7.91E-3 2.54E-2 2.59E-2 1988 0.00E0 0.00E0 7.49E-2 5.51E-2 1989 0.00E0 0.00E0 2.22E-2 2.14E-2 1990 0.00E0 0.00E0 2.58E-2 2.37E-2 1991 0.00E0 0.00E0 2.16E-2 2.15E-2 1992 0.00E0 0.00E0 1.92E-2 2.02E-2 1993 0.00E0 0.00E0 1.93E-2 2.04E-2 1994 0.00E0 0.00E0 2.28E-2 2.02E-2 1995 0.00E0 0.00E0 3.02E-2 5.17E-2 1996 0.00E0 0.00E0 3.11E-2 5.49E-2 1997 0.00E0 0.00E0 2.34E-2 3.62E-2 1998 0.00E0 0.00E0 1.86E-2 2.66E-2 1999 0.00E0 0.00E0 2.06E-2 3.47E-2 2000 0.00E0 0.00E0 2.00E-2 2.77E-2 2001 0.00E0 0.00E0 1.79E-2 1.91E-2

Section 3 - Page 4 Table 3.1-A continued YEAR Cs-137 Indicator (pCi/m3)

Cs-137 Control (pCi/m3)

Beta Indicator (pCi/m3)

Beta Control (pCi/m3) 2002 0.00E0 0.00E0 1.57E-2 1.72E-2 2003 0.00E0 0.00E0 1.50E-2 1.63E-2 Average (1994 - 2003)

NOT APPLICABLE NOT APPLICABLE 2.15E-02 3.05E-02 2004 0.00E0 0.00E0 1.67E-2 1.71E-2 0.00E0 = no detectable measurements

• Radioiodines and Particulates analyzed together

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

Year Indicator Location (pCi/m3)

Control Location (pCi/m3) 1979*

3.28E-3 1.04E-3 1980*

2.01E-3 1.10E-3 1981*

4.17E-3 6.27E-4 1982*

1.42E-3 2.48E-3 1983*

1.99E-3 2.01E-4 1984 3.17E-3 0.00E0 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.00E0 0.00E0 1989 2.18E-2 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 0.00E0 = no detectable measurements

• Radioiodines and Particulates analyzed together.

Section 3 - Page 5 3.2 DRINKING WATER In 2004, 65 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Fifty-two samples were from the four indicator locations and 13 from the control location. Tritium (H-3) analyses were performed on 20 composite samples, 16 at indicator locations and four at the control location.

No detectable gamma activity was found in drinking water samples in 2004 and has not been detected since 1987. Gross beta analyses indicated 1.68 pCi/l at the location with the highest annual mean and 1.29 pCi/l at the control location. Tritium was detected in 9 of the 16 indicator composite samples taken in 2004 with the highest annual mean resulting in only 2.31% of the reporting level. The dose for consumption of water was less than one mrem per year, historically and for 2004; therefore low-level iodine analysis is not required.

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

Drinking water Location 101 was added to the sampling program in 1999. Figure 3.2 shows a slight increase beginning in that year.

Figure 3.2 Concentration of Tritium in Drinking Water 0

500 1000 1500 2000 2500 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 pCi/liter Indicator Location Control Location 10% Reporting Level

Section 3 - Page 6 Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCi/l)

Tritium (pCi/l)

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

Section 3 - Page 7 3.3 SURFACE WATER In 2004, 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 2004 and has not been detected since 1988. Tritium was detected in seven of the eight indicator composite samples taken in 2004. Tritium was not detected in any of the control location composite samples in 2004.

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.

Figure 3.3 There is no reporting level for tritium in surface water Concentration of Tritium in Surface Water 0

500 1000 1500 2000 2500 3000 3500 4000 4500 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 pCi/liter Indicator Location Control Location

Section 3 - Page 8 Table 3.3 Mean Concentrations of Tritium in Surface Water YEAR H-3 Indicator (pCi/l)

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

Section 3 - Page 9 3.4 MILK In 2004, 52 milk samples were analyzed for low level I-131 and other gamma emitting radionuclides, 26 at the indicator location and 26 at the control location.

No detectable activity was found in milk samples in 2004 other than naturally-occurring K-40. Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not been detected since 1987.

Table 3.4 gives indicator location highest annual means and control means since 1979 for Cs-137. Since no activity was detected in 2004, no reporting levels were approached.

Table 3.4 Mean Concentrations of Cs-137 in Milk YEAR Cs-137 Indicator (pCi/l)

Cs-137 Control (pCi/l) 1979 2.48E1 6.04E0 1980 1.72E1 4.13E0 1981 2.04E1 4.15E0 1982 1.21E1 5.20E0 1983 2.01E1 2.82E0 1984 1.48E1 2.56E0 1985 1.42E1 2.72E0 1986 3.74E0 3.45E0 1987 5.20E0 8.60E0 1988 3.40E0 2.90E0 1989 6.00E0 5.60E0 1990 5.30E0 2.60E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0

Section 3 - Page 10 0.00E0 = no detectable measurements

Section 3 - Page 11 3.5 BROADLEAF VEGETATION In 2004, 32 broadleaf vegetation samples were analyzed, 24 at the three indicator locations and eight at the control location.

No detectable activity was detected in any of the vegetation samples taken in 2004.

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

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

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

Cs-137 Control (pCi/kg) 1979 2.19E1 1.93E1 1980 2.30E1 1.92E1 1981 3.04E1 2.02E1 1982 2.46E1 1.22E1 1983 9.07E0 7.85E0 1984 1.02E1 1.05E1 1985 8.05E0 2.37E-2 1986 4.03E1 1.27E1 1987 2.20E1 1.70E1 1988 3.90E1 3.40E1 1989 9.60E1 0.00E0 1990 4.00E1 0.00E0 1991 3.30E1 0.00E0 1992 4.90E1 0.00E0 1993 1.60E1 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 2.69E1 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 0.00E0 = no detectable measurements

Section 3 - Page 12 3.6 FOOD PRODUCTS In 2004, 8 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media.

No detectable activity has been detected in this media since 1987. Table 3.6 shows Cs-137 indicator highest annual means with preoperational data and ten year averages. Since no activity was detected in 2004, no reporting levels were approached.

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

Section 3 - Page 13 3.7 FISH In 2004, 12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator location and six at the control location.

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

Table 3.7 gives indicator location highest annual means since 1980 for all radionuclides detected since the analysis change in 1988. No indicator samples were analyzed in 1979. Co-58 activity was not detected in 2004 in any of the six indicator samples. Cs-137 activity was not detected in 2004 in any of the six indicator samples taken. Cs-137 was not detected in any of the six control location samples. All other radionuclides not shown in the table have demonstrated no detectable activity since 1986. Since no activity was detected in 2004, no reporting levels were approached.

Section 3 - Page 14 Figure 3.7-1 Figure 3.7-2 Concentration of Cs-137 in Fish 0

20 40 60 80 100 120 140 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 pCi/kg Indicator Location Control Location 5% of Reporting Level Concentration of Co-60 in Fish 0

100 200 300 400 500 600 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 pCi/kg Indicator Location Control Location 5% of Reporting Level

Section 3 - Page 15 Table 3.7 Mean Concentrations of Radionuclides in Fish (pCi/kg)

YEAR Mn-54 Indicator Co-58 Indicator Co-60 Indicator Cs-134 Indicator Cs-137 Indicator 1980

-1.97E1 8.36E0

-2.25E1

-2.70E1

-4.13E0 1981

-2.71E0

-2.98E0

-2.65E0

-1.99E0 1.80E1 1982

-3.83E0 8.16E0

-4.34E-1

-8.22E-1 2.69E1 1983

-2.60E0 2.60E1 1.11E1

-1.32E0 6.03E1 1984 3.61E0 1.45E2 2.82E1 3.11E1 4.38E1 1985 2.53E-1 7.19E0 1.72E1

-1.56E0 1.86E1 1986 1.03E0 3.17E1 2.96E1 1.67E1 3.49E1 1987 0.00E0 2.71E2 1.25E2 2.60E1 5.10E1 1988 1.20E1 7.70E1 0.00E0 2.70E1 3.60E1 1989 9.00E1 4.05E2 2.99E2 1.10E1 3.50E1 1990 0.00E0 5.60E1 4.10E1 0.00E0 3.30E1 1991 6.20E0 1.40E1 6.50E1 5.90E0 2.60E1 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90E1 1993 0.00E0 8.20E1 1.30E1 0.00E0 1.60E1 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10E1 1995 0.00E0 0.00E0 0.00E0 0.00E0 2.70E1 1996 0.00E0 0.00E0 0.00E0 0.00E0 2.78E1 1997 0.00E0 0.00E0 0.00E0 0.00E0 1.62E1 1998 0.00E0 0.00E0 0.00E0 0.00E0 3.21E1 1999 0.00E0 3.53E1 0.00E0 0.00E0 2.10E1 2000 0.00E0 4.28E1 0.00E0 0.00E0 2.34E1 2001 0.00E0 1.32E1 0.00E0 0.00E0 3.04E1 2002 0.00E0 0.00E0 0.00E0 0.00E0 2.33E1 2003 0.00E0 0.00E0 0.00E0 0.00E0 3.05E1 2004 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 = no detectable measurements All negative values have been replaced with zeros for calculational purposes

Section 3 - Page 16 3.8 SHORELINE SEDIMENT In 2004, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.

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

Table 3.8 gives indicator location highest annual means since 1979 for all radionuclides detected since the analysis change in 1988.

There is no reporting level for shoreline sediment.

Figure 3.8-1 There is no reporting level for Cs-137 in shoreline sediment Concentration of Cs-137 in Shoreline Sediment 0

50 100 150 200 250 300 350 400 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 pCi/kg Indicator Location Control Location

Section 3 - Page 17 Concentration of Co-60 in Shoreline Sediment 0.00E+00 5.00E+01 1.00E+02 1.50E+02 2.00E+02 2.50E+02 3.00E+02 3.50E+02 4.00E+02 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 pCi/kg Indicator Location Control Location Figure 3.8-2 There is no reporting level for Co-60 in shoreline sediment Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)

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

-1.07E1 2.25E1

-6.50E0 0.00E0 1.20E1 1980 1.06E1

-8.74E0 2.36E1

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

-1.69E0 7.67E1 4.40E1 1983 4.40E0 3.43E1 2.12E1 7.65E1 8.02E1 1984 1.19E1 7.11E1 3.04E1 3.34E1 9.13E1 1985 4.77E0 1.46E1 9.20E0 2.02E1 1.61E2 1986 1.37E1 1.02E1 1.16E1 6.35E1 1.53E2 1987 0.00E0 1.06E2 2.10E1 4.20E1 1.65E2 1988 6.50E0 9.20E1 1.20E1 9.10E0 2.66E2 1989 2.90E1 3.80E1 2.90E1 5.30E1 6.50E1 1990 3.80E1 2.70E1 1.68E2 0.00E0 6.10E1 1991 2.80E1 5.30E1 1.31E2 0.00E0 1.03E2 1992 9.40E0 0.00E0 5.10E1 9.20E0 8.60E1 1993 0.00E0 2.20E1 8.60E1 0.00E0 9.30E1 1994 4.10E1 0.00E0 0.00E0 0.00E0 8.00E1 1995 1.70E1 0.00E0 2.30E1 0.00E0 1.38E2 1996 2.90E1 1.78E1 3.50E1 0.00E0 1.47E2 1997 0.00E0 0.00E0 1.11E2 3.10E1 1.36E2 1998 0.00E0 0.00E0 5.21E1 0.00E0 9.97E1 1999 0.00E0 2.47E1 8.49E1 0.00E0 6.51E1 2000 0.00E0 3.04E1 0.00E0 0.00E0 1.08E2

Section 3 - Page 18 Table 3.8 continued YEAR Mn-54 Indicator Co-58 Indicator Co-60 Indicator Cs-134 Indicator Cs-137 Indicator 2001 0.00E0 0.00E0 0.00E0 0.00E0 2.77E1 2002 2.24E1 0.00E0 0.00E0 0.00E0 1.59E2 2003 0.00E0 0.00E0 0.00E0 0.00E0 1.11E2 2004 0.00E0 0.00E0 0.00E0 0.00E0 7.17E1

Section 3 - Page 19 3.9 DIRECT GAMMA RADIATION In 2004, 162 TLDs were analyzed, 158 at indicator locations, four at the control location. TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 102.8 milliroentgen. The annual mean exposure for the control location was 91.6 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 2004 was 5.50E-1 millirem, which is 0.85% 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 There is no reporting level for Direct Radiation (TLD)

Direct Gamma Radiation (TLD) Results 0

20 40 60 80 100 120 140 160 180 200 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 mR/yr Inner Ring Outer Ring Control

Section 3 - Page 20 Table 3.9 Direct Gamma Radiation (TLD) Results YEAR Inner Ring Average (mR/yr)

Outer Ring Average (mR/yr)

Control (mR/yr) 1979 7.91E1 8.82E1 8.32E1 1980 7.54E1*

8.29E1*

1.05E2 1981 1.01E2 9.31E1 1.05E2 1982 8.95E1 8.97E1 1.10E2 1983 1.16E2 1.14E2 1.30E2 1984 7.85E1 7.83E1 9.02E1 1985 9.54E1 9.69E1 1.27E2 1986 8.91E1 9.35E1 1.10E2 1987 7.58E1 7.71E1 1.23E2 1988 6.03E1 6.42E1 5.48E1 1989 5.37E1 5.30E1 7.55E1 1990 4.34E1 4.78E1 6.25E1 1991 5.14E1 5.59E1 6.80E1 1992 5.65E1 5.55E1 7.60E1 1993 5.61E1 5.71E1 7.20E1 1994 6.40E1 6.93E1 9.55E1 1995 8.36E1 8.25E1 1.08E2 1996 7.18E1 7.02E1 9.88E1 1997 6.22E1 6.68E1 9.45E1 1998 6.59E1 6.32E1 8.69E1 1999 6.23E1 6.05E1 8.96E1 2000 6.50E1 6.08E1 8.97E1 2001 6.51E1 6.22E1 9.33E1 2002 6.57E1 6.43E1 9.48E1 2003 6.74E1 6.45E1 9.20E1 Average (1994 - 2003) 6.73E1 6.64E1 9.41E1 2004 6.46E1 6.33E1 9.16E1

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

Section 3 - Page 21 3.10 LAND USE CENSUS The land use census was conducted June 7 and June 8, 2004 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 2004 census, no new or closer irrigated gardens were identified. The nearest residence is located in the East sector at 0.48 miles. No program changes were required as a result of the 2004 land use census.

Table 3.10 McGuire 2004 Land Use Census Results Sector Distance (Miles)

Sector Distance (Miles)

N Nearest Residence Nearest Garden (irrigated)

Nearest Milk Animal 2.54 2.79 S

Nearest Residence Nearest Garden Nearest Milk Animal 1.45 3.21 NNE Nearest Residence Nearest Garden Nearest Milk Animal 1.23 2.35 SSW Nearest Residence Nearest Garden Nearest Milk Animal 2.56 2.94 NE Nearest Residence Nearest Garden Nearest Milk Animal 1.21 2.18 SW Nearest Residence Nearest Garden Nearest Milk Animal 1.85 1.89 ENE Nearest Residence Nearest Garden (irrigated)

Nearest Milk Animal 0.57 2.54 WSW Nearest Residence Nearest Garden Nearest Milk Animal 1.01 1.27 E

Nearest Residence Nearest Garden Nearest Milk Animal 0.48 0.48 2.48 W

Nearest Residence Nearest Garden Nearest Milk Animal 1.15 1.64 ESE Nearest Residence Nearest Garden Nearest Milk Animal 0.65 1.10 WNW Nearest Residence Nearest Garden Nearest Milk Animal 0.88 2.02 SE Nearest Residence Nearest Garden Nearest Milk Animal 0.67 1.18 NW Nearest Residence Nearest Garden Nearest Milk Animal 0.95 1.68 SSE Nearest Residence Nearest Garden Nearest Milk Animal 1.06 2.18 NNW Nearest Residence Nearest Garden (irrigated)

Nearest Milk Animal 1.48 1.69

- indicates no occurrences within the 5 mile radius

Section 3 - Page 22 Figure 3.10

Section 4 - Page 1 4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2004 MNS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program dose estimates.

Doses based on sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses. Where applicable, average background concentration at the corresponding control location was subtracted. Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. When the guide listed NO DATA as the dose factor for a given radionuclide and organ, a dose factor of zero was assumed.

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

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

Exposure estimates based upon REMP TLD results are discussed in Section 3.9.

The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2004 was 1.31E-1 mrem to the maximum exposed teen lung from inhalation. This is an annual dose based on one positive result from one on-site location during 2004 (environmental doses are based on a mean that includes only samples with a net positive activity). There were fifty-one non-positive results from this location that were not used in calculating the annual dose.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2004 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. The 2004 MNS Annual Radioactive Effluent Release Report (reference 6.6) included calendar year dose estimates for the location with the highest

Section 4 - Page 2 individual organ dose from liquid and gaseous effluent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

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

4.3 COMPARISON OF DOSES The environmental and effluent dose estimates given in Table 4.1-A agree reasonably well.

The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways. This indicates that effluent program dose estimates are both valid and reasonably conservative.

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

In calculations based on liquid release pathways, drinking water and fish consumption were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2004 environmental sample results was 4.84E-2 mrem to the child total body. The maximum total organ dose of 1.17E-1 mrem for liquid effluent-based estimates was to the child liver and GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 5.59E-1 mrem to the childs thyroid. Inhalation was the predominant dose pathway for environmental samples. Co-58 was detected in one environmental air sample during 2004 (PIP G-04-00134). The maximum total organ dose for gaseous environmental estimates was 1.31E-1 mrem to the teen lung.

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.

TABLE 4.1-A Page 1 of 3 MCGUIRE NUCLEAR STATION 2004 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Organ Environmental or Effluent Data Critical Age (1)

Critical Pathway (2)

Location Maximum Dose (3)

(mrem)

Skin Environmental Teen Shoreline Sediment 130 (0.52 mi. SW) 1.88E-04 Skin Effluent Teen Shoreline Sediment 0.5 mi. NNE 1.52E-03 Bone Environmental 0.00E+00 Bone Effluent Teen Fish 0.5 mi. NNE 2.87E-03 Liver Environmental Child Drinking Water 101 (3.31 mi. E) 4.83E-02 Liver Effluent Child Drinking Water 0.5 mi. NNE 1.17E-01 T. Body Environmental Child Drinking Water 101 (3.31 mi. E) 4.84E-02 T. Body Effluent Child Drinking Water 0.5 mi. NNE 1.14E-01 Thyroid Environmental Child Drinking Water 101 (3.31 mi. E) 4.83E-02 Thyroid Effluent Child Drinking Water 0.5 mi. NNE 1.14E-01 Kidney Environmental Child Drinking Water 101 (3.31 mi. E) 4.83E-02 Kidney Effluent Child Drinking Water 0.5 mi. NNE 1.15E-01 Lung Environmental Child Drinking Water 101 (3.31 mi. E) 4.83E-02 Lung Effluent Child Drinking Water 0.5 mi. NNE 1.14E-01 GI-LLI Environmental Child Drinking Water 101 (3.31 mi. E) 4.83E-02 GI-LLI Effluent Child Drinking Water 0.5 mi. NNE 1.17E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.

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

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

Section 4 - Page 3

Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM Organ Environmental or Effluent Data Critical Age (1)

Critical Pathway (2)

Location Maximum Dose (3)

(mrem)

Skin Environmental 0.00E+00 Skin Effluent All Ground Plane 0.5 mi. E 2.68E-02 Bone Environmental 0.00E+00 Bone Effluent Child Vegetation 0.5 mi. E 5.08E-05 Liver Environmental Teen Inhalation 195 (0.19 mi.N) 2.02E-04 Liver Effluent Child Vegetation 0.5 mi. E 5.50E-01 T. Body Environmental Child Inhalation 195 (0.19 mi.N) 3.09E-04 T. Body Effluent Child Vegetation 0.5 mi. E 5.50E-01 Thyroid Environmental 0.00E+00 Thyroid Effluent Child Vegetation 0.5 mi. E 5.59E-01 Kidney Environmental 0.00E+00 Kidney Effluent Child Vegetation 0.5 mi. E 5.50E-01 Lung Environmental Teen Inhalation 195 (0.19 mi.N) 1.31E-01 Lung Effluent Child Vegetation 0.5 mi. E 5.50E-01 GI-LLI Environmental Adult Inhalation 195 (0.19 mi.N) 1.04E-02 GI-LLI Effluent Child Vegetation 0.5 mi. E 5.50E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.

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

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

Section 4 - Page 4

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

Beta Environmental Not Sampled Beta Effluent N/A Noble Gas 0.5 mi. NNE 4.15E-02 Gamma Environmental Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 6.24E-02 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dose for 2004 based on Environmental Measurements (mrem) for McGuire Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 1.19E-04 1.78E-04 0.00E+00 0.00E+00 7.59E-02 1.09E-03 0.00E+00 Drinking Water 0.00E+00 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 4.70E-02 4.71E-02 4.69E-02 4.69E-02 1.23E-01 4.80E-02 0.00E+00 Child Airborne 0.00E+00 1.73E-04 3.09E-04 0.00E+00 0.00E+00 1.08E-01 3.36E-03 0.00E+00 Drinking Water 0.00E+00 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 0.00E+00 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 3.37E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.93E-05 TOTAL 0.00E+00 4.85E-02 4.87E-02 4.83E-02 4.83E-02 1.56E-01 5.17E-02 3.93E-05 Teen Airborne 0.00E+00 2.02E-04 2.71E-04 0.00E+00 0.00E+00 1.31E-01 9.30E-03 0.00E+00 Drinking Water 0.00E+00 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 0.00E+00 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.61E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.88E-04 TOTAL 0.00E+00 2.59E-02 2.61E-02 2.57E-02 2.57E-02 1.57E-01 3.50E-02 1.88E-04 Adult Airborne 0.00E+00 1.55E-04 2.02E-04 0.00E+00 0.00E+00 9.07E-02 1.04E-02 0.00E+00 Drinking Water 0.00E+00 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 0.00E+00 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 2.89E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.37E-05 TOTAL 0.00E+00 3.65E-02 3.65E-02 3.63E-02 3.63E-02 1.27E-01 4.67E-02 3.37E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

McGuire Nuclear Station Dose from Air Particulate Inhalation Pathway for 2004 Data Maximum Exposed Infant Infant Dose from Air Particulate Inhalation Pathway (mrem) = Usage (m3/yr) x Dose Factor (mrem/pCi inhaled) x Concentration (pCi/m3)

Breathing Rate (one year) 1400 m3/yr Highest Annual Net Mean Inhalation Dose Factor Concentration Dose (mrem)

Indicator Air Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/m3)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 195 9.77E-02 0.00E+00 1.19E-04 1.78E-04 0.00E+00 0.00E+00 7.59E-02 1.09E-03 Fe-59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose Commitment (mrem) =

0.00E+00 1.19E-04 1.78E-04 0.00E+00 0.00E+00 7.59E-02 1.09E-03 Section 4 - Page 7

McGuire Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) =

330 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 101 461 0.00E+00 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 Dose Commitment (mrem) =

0.00E+00 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 4.69E-02 Section 4 - Page 8

McGuire Nuclear Station Dose from Air Particulate Inhalation Pathway for 2004 Data Maximum Exposed Child Child Dose from Air Particulate Inhalation Pathway (mrem) = Usage (m3/yr) x Dose Factor (mrem/pCi inhaled) x Concentration (pCi/m3)

Breathing Rate (one year) 3700 m3/yr Highest Annual Net Mean Inhalation Dose Factor Concentration Dose (mrem)

Indicator Air Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/m3)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 195 9.77E-02 0.00E+00 1.73E-04 3.09E-04 0.00E+00 0.00E+00 1.08E-01 3.36E-03 Fe-59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose Commitment (mrem) =

0.00E+00 1.73E-04 3.09E-04 0.00E+00 0.00E+00 1.08E-01 3.36E-03 Section 4 - Page 9

McGuire Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) =

510 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 101 461 0.00E+00 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 Dose Commitment (mrem) =

0.00E+00 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 4.77E-02 Section 4 - Page 10

McGuire Nuclear Station Dose from Fish Pathway for 2004 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 504 pCi/l x 0.9 = 454 pCi/kg Usage (intake in one year) =

6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 128 454 0.00E+00 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 Dose Commitment (mrem) =

0.00E+00 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 6.36E-04 Section 4 - Page 11

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Child Shoreline Recreation =

14 hr (in one year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (river shoreline - location 130)

Sediment Surface Mass =

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

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2)

Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg)

T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 71.7 3.37E-05 3.93E-05 Dose Commitment (mrem) =

3.37E-05 3.93E-05 Section 4 - Page 12

McGuire Nuclear Station Dose from Air Particulate Inhalation Pathway for 2004 Data Maximum Exposed Teen Teen Dose from Air Particulate Inhalation Pathway (mrem) = Usage (m3/yr) x Dose Factor (mrem/pCi inhaled) x Concentration (pCi/m3)

Breathing Rate (one year) 8000 m3/yr Highest Annual Net Mean Inhalation Dose Factor Concentration Dose (mrem)

Indicator Air Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/m3)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 195 9.77E-02 0.00E+00 2.02E-04 2.71E-04 0.00E+00 0.00E+00 1.31E-01 9.30E-03 Fe-59 1.09E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose Commitment (mrem) =

0.00E+00 2.02E-04 2.71E-04 0.00E+00 0.00E+00 1.31E-01 9.30E-03 Section 4 - Page 13

McGuire Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) =

510 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 101 461 0.00E+00 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 Dose Commitment (mrem)=

0.00E+00 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 Section 4 - Page 14

McGuire Nuclear Station Dose from Fish Pathway for 2004 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 504 pCi/l x 0.9 = 454 pCi/kg Usage (intake in one year) =

16 kg Highest Annual Ingestion Dose Factor Net Mean Dose (mrem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 128 454 0.00E+00 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 Dose Commitment (mrem) =

0.00E+00 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 7.70E-04 Section 4 - Page 15

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Teen Shoreline Recreation =

67 hr (in one year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (river shoreline - location 130)

Sediment Surface Mass =

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

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2)

Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg)

T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 71.7 1.61E-04 1.88E-04 Dose Commitment (mrem) =

1.61E-04 1.88E-04 Section 4 - Page 16

McGuire Nuclear Station Dose from Air Particulate Inhalation Pathway for 2004 Data Maximum Exposed Adult Adult Dose from Air Particulate Inhalation Pathway (mrem) = Usage (m3/yr) x Dose Factor (mrem/pCi inhaled) x Concentration (pCi/m3)

Breathing Rate (one year) 8000 m3/yr Highest Annual Net Mean Inhalation Dose Factor Concentration Dose (mrem)

Indicator Air Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/m3)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.74E-04 9.67E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 195 9.77E-02 0.00E+00 1.55E-04 2.02E-04 0.00E+00 0.00E+00 9.07E-02 1.04E-02 Fe-59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.05E-06 1.29E-05 5.28E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.88E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.95E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 4.88E-06 6.13E-09 3.20E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose Commitment (mrem) =

0.00E+00 1.55E-04 2.02E-04 0.00E+00 0.00E+00 9.07E-02 1.04E-02 Section 4 - Page 17

McGuire Nuclear Station Dose from Drinking Water Pathway for 2004 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) =

730 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 101 461 0.00E+00 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 Dose Commitment (mrem) =

0.00E+00 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 Section 4 - Page 18

McGuire Nuclear Station Dose from Fish Pathway for 2004 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 504 pCi/l x 0.9 = 454 pCi/kg Usage (intake in one year) =

21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 128 454 0.00E+00 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 Dose Commitment (mrem) =

0.00E+00 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 Section 4 - Page 19

McGuire Nuclear Station Dose from Shoreline Sediment Pathway for 2004 Data Maximum Exposed Adult Shoreline Recreation =

12 hr (in one year)

Shore Width Factor =

0.3 (lake shore - location 129)

Shore Width Factor =

0.2 (river shoreline - location 130)

Sediment Surface Mass =

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

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

(mrem/hr per pCi/m2)

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

T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 71.7 2.89E-05 3.37E-05 Dose Commitment (mrem) =

2.89E-05 3.37E-05 Section 4 - Page 20

Section 5 - Page 1 5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad Laboratories is located in Huntersville, North

Carolina, at Duke Power Companys Environmental Center.

5.3 DOSIMETRY ANALYSIS The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

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

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

Duke Power Companys Environmental Center

Section 5 - Page 2 5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 DUKE POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2004. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2004 is documented in Table 5.0-A.

5.6 DUKE POWER AUDITS The McGuire Radiation Protection Section was audited by the Quality Assurance Group in January, 2004. One deviation was identified pertaining to several routine TLD locations with distances outside the six to eight km range as required by SLC Table 16.11.13-1. PIP G-04-00139 written to document corrective actions.

EnRad Laboratories was audited by the Quality Assurance Group in March, 2004.

Laboratory practices and procedures were reviewed. One example of insufficient documentation for a cross-check which yielded data outside of acceptance limits was identified and is described in PIP G-04-00140. Several areas for improvement were identified and are described in PIP G-04-00142. There were no significant findings as a result of this audit.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The McGuire Nuclear Station Radiological Environmental Monitoring Program was not audited by the NRC in 2004. The program was audited by the NRC in January of 2003 (Reference 6.12). There were no findings or issues identified by the audit.

EnRad Laboratories was not audited by the NRC in 2004.

5.8 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program.

Section 5 - Page 3 EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis.

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

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

5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2004 is documented in Table 5.0-B.

5.9.3 INTERNAL CROSSCHECK (DUKE POWER)

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

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2004 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one analysis of the cross-check was performed.

Footnote explanations are included following this data table.

Gamma in Water 3.5 liters Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.41 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.73 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.00 E3 3 Pass(1)

Co-58 7.07 - 12.53 E3 9.42 E3 9.40 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.80 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.85 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.21 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.22 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.80 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 6.10 E2 3 Pass(1)

Ce-141 0.76 - 1.35 E3 1.01E+03 1.01 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.56 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 1.86 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.06 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.64 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.76 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 5.43 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.78 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.36 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.96 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.96 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.39 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.45 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.10 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.30 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.51 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.31 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.68 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.25 E4 3 Pass Section 5 - Page 4

Gamma in Water 3.5 liters, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.27 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.18 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.52 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 2.01 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.07 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.95 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.47 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.83 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.24 E4 3 Pass Gamma in Water 1.0 liter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.55 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.73 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.02 E3 3 Pass(1)

Co-58 7.07 - 12.53 E3 9.42 E3 9.37 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.85 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.86 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.30 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.07 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.77 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.81 E2 3 Pass(1)

Ce-141 0.76 - 1.35 E3 1.01E+03 1.00 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.52 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 2.00 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.06 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.23 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.73 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 5.04 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.15 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.39 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.89 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.94 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.39 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.56 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 7.93 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.31 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.43 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.25 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.67 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.19 E4 3 Pass Section 5 - Page 5

Gamma in Water 1.0 liter, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.25 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.07 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.54 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.97 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.06 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.72 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.43 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.77 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 E4 3 Pass Gamma in Water 0.5 liter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.58 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.77 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.01 E3 3 Pass(1)

Co-58 7.07 - 12.53 E3 9.42 E3 9.35 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.83 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 6.89 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.45 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 4.87 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.78 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.89 E2 3 Pass(1)

Ce-141 0.76 - 1.35 E3 1.01E+03 1.05 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.53 E3 3 Pass Co-57 1.46 - 2.58 E2 1.94 E2 1.91 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.08 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.42 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.76 E3 3 Pass Cd-109 3.83 - 6.79 E3 5.11 E3 4.83 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.36 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.51 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.92 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 4.95 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.38 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.63 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.08 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.32 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.48 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.25 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.66 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.32 E4 3 Pass Section 5 - Page 6

Gamma in Water 0.5 liter, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.22 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.09 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.53 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.98 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.01 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.55 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.42 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.79 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 E4 3 Pass Gamma in Water 0.25 liter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041GWSL Cr-51 1.06 - 1.88 E3 1.41 E3 1.52 E3 3 Pass Mn-54 2.63 - 4.67 E4 3.51 E4 3.84 E4 3 Pass Co-57 0.00 - 0.00 E3 0.00E+00 1.02 E3 3 Pass(1)

Co-58 7.07 - 12.53 E3 9.42 E3 9.54 E3 3 Pass Fe-59 2.01 - 3.56 E3 2.67 E3 2.97 E3 3 Pass Co-60 4.86 - 8.62 E4 6.48 E4 7.04 E4 3 Pass Zn-65 4.42 - 7.84 E4 5.90 E4 6.54 E4 3 Pass Cs-134 4.26 - 7.56 E4 5.68 E4 5.00 E4 3 Pass Cs-137 3.67 - 6.51 E4 4.90 E4 4.87 E4 3 Pass Ce-139 0.00 - 0.00 E2 0.00E+00 5.85 E2 3 Pass(1)

Ce-141 0.76 - 1.35 E3 1.01E+03 1.05 E3 3 Pass 6/28/2004 Q042GWR Cr-51 3.52 - 6.25 E3 4.70 E3 4.45 E3 3 Pass Co-57 1.34 - 2.81 E2 1.94 E2 1.73 E2 3 Pass Co-60 0.81 - 1.44 E3 1.08 E3 1.07 E3 3 Pass Sr-85 7.47 - 13.25 E2 9.96 E2 9.15 E2 3 Pass Y-88 1.33 - 2.37 E3 1.78 E3 1.67 E3 3 Pass Cd-109 3.58 - 7.30 E3 5.11 E3 4.85 E3 3 Pass Sn-113 6.53 - 11.58 E2 8.71 E2 8.40 E2 3 Pass Te-123m 1.79 - 3.17 E2 2.38 E2 2.40 E2 3 Pass Cs-137 6.24 - 11.06 E2 8.32 E2 7.72 E2 3 Pass 9/8/2004 Q043GWSL Cr-51 3.84 - 6.82 E5 5.13 E5 5.03 E5 3 Pass Co-57 1.03 - 1.82 E4 1.37 E4 1.40 E4 3 Pass Co-60 5.07 - 8.99 E4 6.76 E4 6.74 E4 3 Pass Sr-85 6.40 - 11.35 E4 8.53 E4 8.18 E4 3 Pass Y-88 1.01 - 1.80 E5 1.35 E5 1.33 E5 3 Pass Cd-109 2.64 - 4.69 E5 3.52 E5 3.55 E5 3 Pass Sn-113 4.89 - 8.67 E4 6.52 E4 6.41 E4 3 Pass Te-123m 1.29 - 2.28 E4 1.71 E4 1.71 E4 3 Pass Cs-137 4.21 - 7.46 E4 5.61 E4 5.39 E4 3 Pass Section 5 - Page 7

Gamma in Water 0.25 liter, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 12/3/2004 Q044GWR Cr-51 0.97 - 1.72 E5 1.29 E5 1.25 E5 3 Pass Co-57 2.32 - 4.12 E3 3.10 E3 3.18 E3 3 Pass Co-60 1.18 - 2.09 E4 1.57 E4 1.55 E4 3 Pass Sr-85 1.58 - 2.81 E4 2.11 E4 1.97 E4 3 Pass Y-88 2.35 - 4.17 E4 3.14 E4 3.05 E4 3 Pass Cd-109 5.91 - 10.48 E4 7.88 E4 7.88 E4 3 Pass Sn-113 1.12 - 1.98 E4 1.49 E4 1.45 E4 3 Pass Te-123m 2.94 - 5.21 E3 3.92 E3 3.83 E3 3 Pass Cs-137 0.98 - 1.74 E4 1.31 E4 1.21 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 6/15/2004 1066324 Cr-51 0.97 - 1.94 E2 1.37 E2 1.52 E2 3 Pass Co-57 2.55 - 7.09 E0 4.25 E0 5.32 E0 3 Pass Co-60 1.66 - 3.20 E1 2.30 E1 2.32 E1 3 Pass Sr-85 1.82 - 3.22 E1 2.42 E1 2.54 E1 3 Pass Y-88 3.07 - 5.45 E1 4.10 E1 4.23 E1 3 Pass Cd-109 0.68 - 1.78 E2 1.10 E2 1.32 E2 3 Pass Sn-113 1.40 - 2.85 E1 1.99 E1 1.89 E1 3 Pass Te-123m 4.08 - 7.23 E0 5.44 E0 5.72 E0 3 Pass Cs-137 1.23 - 2.52 E1 1.76 E1 1.72 E1 3 Pass 12/9/2004 E4348-37 Cr-51 1.82 - 3.23 E2 2.43 E2 2.38 E2 3 Pass Mn-54 6.53 - 11.57 E1 8.70 E1 9.11 E1 3 Pass Co-57 0.00 - 0.00 E0 0.00E+00 4.06 E0 3 Pass(2)

Co-58 7.05 - 12.50 E1 9.40 E1 9.11 E1 3 Pass Fe-59 5.85 - 10.37 E1 7.80 E1 8.25 E1 3 Pass Co-60 0.84 - 1.49 E2 1.12 E2 1.09 E2 3 Pass Zn-65 0.95 - 1.68 E2 1.26 E2 1.23 E2 3 Pass Cs-134 0.82 - 1.45 E2 1.09 E2 0.98 E2 3 Pass Cs-137 6.08 - 10.77 E1 8.10 E1 7.80 E1 3 Pass Ce-141 0.77 - 1.37 E2 1.03 E2 1.00 E2 3 Pass Iodine in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 1/2/2004 Q041LIW1 I-131 6.00 - 10.64 E2 8.00 E2 7.94 E2 3 Pass 1/2/2004 Q041LIW2 I-131 6.38 - 11.32 E1 8.51 E1 9.12 E1 3 Pass 1/2/2004 Q041LIW3 I-131 N/A 0.00E+00 0.00E+00 3 Pass Section 5 - Page 8

Iodine in Water, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 7/14/2004 Q043LIW1 I-131 7.16 - 12.69 E2 9.54 E2 6.91 E2 3/3 Low(3) 7/14/2004 Q043LIW2 I-131 2.56 - 4.54 E2 3.41 E2 2.53 E2 2/3 Low(4) 7/14/2004 Q043LIW3 I-131 1.61 - 10.04 E0 4.02 E0 2.61 E0 3 Pass 12/2/2004 Q044LIW1 I-131 2.36 - 4.18 E1 3.15 E1 3.02 E1 3 Pass 12/2/2004 Q044LIW2 I-131 0.92 - 1.62 E2 1.22 E2 1.15 E2 3 Pass 12/2/2004 Q044LIW3 I-131 N/A 0.00E+00 0.00E+00 3 Pass Iodine in Milk Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 6/22/2004 Q042LIM1 Co-58 0.00 - 0.00 E0 0.00E+00 3.47 E0 3/3 High(5)

I-131 N/A 0.00E+00 0.00E+00 3 Pass 6/22/2004 Q042LIM2 I-131 0.82 - 1.45 E3 1.09 E3 0.91 E3 3 Pass 6/22/2004 Q042LIM3 I-131 1.87 - 3.31 E1 2.49 E1 2.09 E1 3 Pass Iodine on Cartridge Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/15/2004 1066-32-3 I-131 4.13 - 7.33 E6 5.51 E6 4.91 E6 3 Pass 12/9/2004 E4349-37 I-131 6.64 - 11.77 E1 8.85 E1 10.63 E1 3 Pass Beta in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/25/2004 E4056-37 Cs-137 2.07 - 3.67 E2 2.76 E2 2.60 E2 3 Pass 9/16/2004 E4233-37 Cs-137 1.69 - 2.99 E2 2.25 E2 2.34 E2 3 Pass Beta Smear Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status dpm dpm dpm 5/14/2004 A18024-37 Am-241 N/A Interference 4.71 E3 3 Pass Cs-137 1.01 - 1.80 E4 1.35 E4 1.35 E4 3 Pass Section 5 - Page 9

Tritium in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/17/2004 Q041TWSL1 H-3 2.70 - 4.79 E4 3.60 E4 3.17 E4 3 Pass 3/17/2004 Q041TWSL2 H-3 N/A 0.00E+00 0.00E+00 3 Pass 6/28/2004 Q042TWR1 H-3 5.24 - 9.29 E2 6.99 E2 7.33 E2 3 Pass 6/28/2004 Q042TWR2 H-3 2.29 - 5.59 E2 3.58 E2 4.12 E2 3 Pass 6/28/2004 Q042TWR3 H-3 N/A 0.00E+00 0.00E+00 3 Pass 9/8/2004 Q043TWSL1 H-3 N/A 0.00E+00 0.00E+00 3 Pass 9/8/2004 Q043TWSL2 H-3 6.18 - 10.96 E4 8.24 E4 7.94 E4 3 Pass 12/3/2004 Q044TWR1 H-3 N/A 0.00E+00 0.00E+00 3 Pass 12/3/2004 Q044TWR2 H-3 4.43 - 8.07 E2 5.98 E2 5.77 E2 3 Pass 12/3/2004 Q044TWR3 H-3 1.52 - 2.70 E3 2.03 E3 2.04 E3 3 Pass Section 5 - Page 10

Section 5 - Page 11 Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q041GWSL, Reference Date 3/17/2004: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Co-57 and Ce-139 were observed in cross-checks and attributed to a contaminant arriving with the source. The nuclides were determined to be present, but there was no reference activity applicable to the results.

(2) Gamma in Filter, Sample ID E4348-37, Reference Date 12/9/2004 Co-57 was observed in cross-check and attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.

(3) Iodine in Water, Sample ID Q043LIW1, Reference Date 7/14/2004 Three results for low-level I-131 [364.48 keV] analysis were reported, with all three being below acceptance limit. General Office PIP G-04-00280 was written to record investigative actions.

(4) Iodine in Water, Sample ID Q043LIW2, Reference Date 7/14/2004 Three results for low-level I-131 [364.48 keV] analysis were reported, with two of the three being below acceptance limit. General Office PIP G-04-00280 was written to record investigative actions.

(5) Iodine in Milk, Sample ID Q042LIM1, Reference Date 6/22/2004 Three results for low-level I-131 [364.48 keV] analysis were reported and were within acceptance limits. Co-58 was observed in all three analyses and was attributed to an unintended contaminant. General Office PIP G-04-00248 was written to record investigative actions.

TABLE 5.0-B 2004 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2004 2nd Quarter 2004 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 101150 90.5 98.5 8.84

<+/-15%

Pass 100380 65.5 66.6 1.68

<+/-15%

Pass 101147 90.5 96.6 6.74

<+/-15%

Pass 100215 65.5 66.1 0.92

<+/-15%

Pass 101175 90.5 95.4 5.41

<+/-15%

Pass 100240 65.5 66.9 2.14

<+/-15%

Pass 101173 90.5 96.0 6.08

<+/-15%

Pass 100045 65.5 66.9 2.14

<+/-15%

Pass 101374 90.5 95.3 5.30

<+/-15%

Pass 100040 65.5 63.0

-3.82

<+/-15%

Pass Average Bias (B) 6.48 Average Bias (B) 0.61 Standard Deviation (S) 1.44 Standard Deviation (S) 2.52 Measure Performance lBl+S 7.92

<15%

Pass Measure Performance lBl+S 3.14

<15%

Pass 3rd Quarter 2004 4th Quarter 2004 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 100178 94.0 100.2 6.60

<+/-15%

Pass 101290 71.7 67.8

-5.44

<+/-15%

Pass 100700 94.0 97.8 4.04

<+/-15%

Pass 101322 71.7 69.9

-2.51

<+/-15%

Pass 100821 94.0 99.3 5.64

<+/-15%

Pass 101370 71.7 70.7

-1.39

<+/-15%

Pass 101179 94.0 101.3 7.77

<+/-15%

Pass 101373 71.7 69.5

-3.07

<+/-15%

Pass 101376 94.0 97.5 3.72

<+/-15%

Pass 101418 71.7 70.1

-2.23

<+/-15%

Pass Average Bias (B) 5.55 Average Bias (B)

-2.93 Standard Deviation (S) 1.70 Standard Deviation (S) 1.53 Measure Performance lBl+S 7.26

<15%

Pass Measure Performance lBl+S 4.46

<15%

Pass State of North Carolina, Division of Radiation Protection Spring 2004 Fall 2004 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 101213 54.0 59.9 10.93

<+/-15%

Pass 100958 46.5 51.7 11.15

<+/-15%

Pass 101145 54.0 57.4 6.30

<+/-15%

Pass 100526 46.5 49.9 7.33

<+/-15%

Pass 101370 54.0 58.9 9.07

<+/-15%

Pass 100121 46.5 52.6 13.12

<+/-15%

Pass 101322 54.0 58.7 8.70

<+/-15%

Pass 100109 46.5 49.9 7.25

<+/-15%

Pass 101290 54.0 56.7 5.00

<+/-15%

Pass 100723 46.5 48.3 3.94

<+/-15%

Pass 101339 54.0 57.8 7.04

<+/-15%

Pass 100267 46.5 51.4 10.63

<+/-15%

Pass 101265 54.0 56.7 5.00

<+/-15%

Pass 100660 46.5 50.2 8.03

<+/-15%

Pass 101418 54.0 57.8 7.04

<+/-15%

Pass 100921 46.5 50.9 9.51

<+/-15%

Pass Average Bias (B) 7.38 Average Bias (B) 8.87 Standard Deviation (S) 2.07 Standard Deviation (S) 2.85 Measure Performance lBl+S 9.45

<15%

Pass Measure Performance lBl+S 11.71

<15%

Pass Section 5 - Page 12

Internal Crosscheck (Duke Power) 1st Quarter 2004 2nd Quarter 2004 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 100103 26.0 24.1

-7.31

<+/-15%

Pass 100080 19.0 19.0 0.19

<+/-15%

Pass 100794 26.0 24.6

-5.38

<+/-15%

Pass 100727 19.0 19.4 1.94

<+/-15%

Pass 100964 26.0 24.4

-6.15

<+/-15%

Pass 100964 19.0 19.1 0.44

<+/-15%

Pass 100940 26.0 25.4

-2.31

<+/-15%

Pass 101020 19.0 18.6

-1.93

<+/-15%

Pass 100747 26.0 24.6

-5.38

<+/-15%

Pass 100103 19.0 18.8

-0.99

<+/-15%

Pass 101020 26.0 24.3

-6.54

<+/-15%

Pass 100794 19.0 18.7

-1.46

<+/-15%

Pass 100080 26.0 24.5

-5.77

<+/-15%

Pass 101036 19.0 19.6 2.98

<+/-15%

Pass 100818 26.0 24.8

-4.62

<+/-15%

Pass 100176 19.0 19.7 3.62

<+/-15%

Pass 101122 26.0 24.1

-7.31

<+/-15%

Pass 100770 19.0 18.5

-2.42

<+/-15%

Pass 100727 26.0 25.5

-1.92

<+/-15%

Pass 101035 19.0 18.3

-3.44

<+/-15%

Pass Average Bias (B)

-5.27 Average Bias (B)

-0.11 Standard Deviation (S) 1.87 Standard Deviation (S) 2.37 Measure Performance lBl+S 7.14

<15%

Pass Measure Performance lBl+S 2.47

<15%

Pass 3rd Quarter 2004 4th Quarter 2004 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 100813 38.0 36.7

-3.43

<+/-15%

Pass 100079 63.0 61.0

-3.16

<+/-15%

Pass 100068 38.0 40.2 5.78

<+/-15%

Pass 100106 63.0 62.5

-0.72

<+/-15%

Pass 100940 38.0 39.4 3.74

<+/-15%

Pass 100148 63.0 62.0

-1.55

<+/-15%

Pass 100953 38.0 38.4 1.18

<+/-15%

Pass 100268 63.0 60.2

-4.46

<+/-15%

Pass 100251 38.0 39.4 3.80

<+/-15%

Pass 100110 63.0 61.8

-1.96

<+/-15%

Pass 100506 38.0 39.8 4.73

<+/-15%

Pass 100830 63.0 60.8

-3.54

<+/-15%

Pass 100654 38.0 40.6 6.74

<+/-15%

Pass 100801 63.0 61.9

-1.72

<+/-15%

Pass 101017 38.0 38.4 1.11

<+/-15%

Pass 100826 63.0 62.9

-0.19

<+/-15%

Pass 100252 38.0 38.5 1.42

<+/-15%

Pass 100439 63.0 64.5 2.34

<+/-15%

Pass 100150 38.0 39.2 3.22

<+/-15%

Pass 100953 63.0 61.3

-2.75

<+/-15%

Pass Average Bias (B) 2.83 Average Bias (B)

-1.77 Standard Deviation (S) 2.91 Standard Deviation (S) 1.94 Measure Performance lBl+S 5.74

<15%

Pass Measure Performance lBl+S 3.71

<15%

Pass Section 5 - Page 13

Section 6 - Page 1

6.0 REFERENCES

6.1 McGuire Selected License Commitments 6.2 McGuire Technical Specifications 6.3 McGuire Updated Final Safety Analysis Report 6.4 Duke Power Company McGuire Offsite Dose Calculation Manual 6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2003 6.6 McGuire Annual Radioactive Effluent Release Report 2004 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

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

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report (50-369/03-02, 50-370/03-02) 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001

Appendix A - Page 1 APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES

Appendix A - Page 2 APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments.

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

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

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

I. CHANGE OF SAMPLING PROCEDURES No changes were made to the sampling procedure during 2004.

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. Tritium samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable.

Appendix A - Page 3 Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.

III.

CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2004.

IV.

SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.

Location 120

=

Site Boundary (0.46 mi. NNE)

Location 121

=

Site Boundary (0.47 mi. NE)

Location 125

=

Site Boundary (0.38 mi. SW)

Location 133

=

Cornelius (6.23 mi. ENE)

Location 134

=

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

Location 192

=

Peninsula (2.84 mi. NNE)

Location 195

=

Fishing Access Road (0.19 mi. N)

A.2 DRINKING WATER Biweekly 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 biweekly from the locations listed below.

Location 101

=

North Mecklenburg Water Treatment Facility (3.31 mi E)

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

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

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

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

Appendix A - Page 4 A.3 SURFACE WATER Biweekly 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 biweekly from the locations listed below.

Location 128

=

Discharge Canal Bridge (0.45 mi. NE)

Location 131

=

Cowans Ford Dam (0.64 mi. WNW)

Location 135

=

Plant Marshall Intake Canal (11.9 mi. N)

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

Location 139

=

William Cook Dairy (2.49 mi. E)

Location 141

=

Lynch Dairy - Cows (14.8 mi. WNW)

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

Location 120

=

Site Boundary (0.46 mi. NNE)

Location 125

=

Site Boundary (0.38 mi. SW)

Location 134

=

East Lincoln Junior High School (8.77 mi. WNW)

Location 193

=

Site Boundary (0.19 mi. N)

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

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

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

Appendix A - Page 5 Location 129

=

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

Location 137

=

Pinnacle Access Area (12.0 mi. N)

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

Location 129

=

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

Location 130

=

Highway 73 Bridge Downstream (0.52 mi. SW)

Location 137

=

Pinnacle Access Area (12.0 mi. N)

A.9 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations. A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.

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

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

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

A.10 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

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

The census was conducted during the growing season from 6/7 to 6/8/2004. Results are shown in Table 3.10. No changes were made to the sampling procedures during 2004 as a result of the 2004 census.

Appendix A - Page 6 In the environmental program, the air deposition parameters (D/Q) are used to determine air, broadleaf vegetation and milk sampling locations. McGuires sectors with the three highest values did not change in 2004.

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 B - Page 1 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2004

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No.of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Air Particulate 134 (pCi/m3)

(8.77 mi WNW)

BETA 364 1.00E-02 1.60E-2 (312/312) 195 1.67E-2 (52/52) 1.71E-2 (52/52) 0 5.77E 3.51E-2 (0.19 mi N) 7.95E 3.51E-2 8.70E 2.56E-2 CO-58*

1 0.00E+00 9.77E-2 (1/1) 195 9.77E-2 (1/1) 0.00 (0/52) 9.77E 9.77E-2 (0.19 mi N) 9.77E 9.77E-2 0.00 - 0.00 CS-134 364 5.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 364 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 I-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

• Reference PIP G-04-00134 Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 2

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Air Radioiodine 134 (pCi/m3)

(8.77 mi WNW)

CS-134 364 5.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 364 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 I-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 @ 4/11/2005 2:16 PM Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Drinking Water 136 (pCi/liter)

(12.7 mi NNE)

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

1.63 (51/52) 119 1.68 (13/13) 1.29 (12/13) 0 0.81 - 2.94 (7.40 mi SSW) 0.82 - 2.53 0.67 - 2.07 CO-58 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 65 18 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 20 2000 375 (9/16) 101 461 (4/4) 0.00 (0/4) 0 221 - 642 (3.31 mi E) 287 - 642 0.00 - 0.00 I-131 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Surface Water 135 (pCi/liter)

(11.9 mi N)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12 2000 404 (7/8) 128 504 (4/4) 0.00 (0/4) 0 232 - 580 (0.45 mi NE) 302 - 580 0.00 - 0.00 I-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 5

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Milk 141 (pCi/liter)

(14.8 mi WNW)

BALA-140 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 52 18 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 52 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 52 1

0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Broadleaf 134 Vegetation (8.77 mi WNW)

(pCi/kg-wet)

CS-134 32 60 0.00 (0/24) 0.00 (0/8) 0.00 (0/8) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 32 80 0.00 (0/24) 0.00 (0/8) 0.00 (0/8) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 32 60 0.00 (0/24) 0.00 (0/8) 0.00 (0/8) 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 @ 4/11/2005 2:16 PM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

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

LOCATION CS-134 8

60 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 8

80 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 8

60 0.00 (0/8) 0.00 (0/8) 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 @ 4/11/2005 2:16 PM Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Fish 137 (pCi/kg-wet)

(12.0 mi N)

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detection All Indicator Locations Location with Highest Annual Mean Name, Distance, Direction Control Location No. of Non-Routine Report Meas.

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Shoreline 137 Sediment (12.0 mi N)

(pCi/kg-dry)

MN-54 6

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

0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6

0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 6

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

180 71.7 (1/4) 130 71.7 (1/2) 0.00 (0/2) 0 71.7 - 71.7 (0.52 mi SW) 71.7 - 71.7 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 4/11/2005 2:16 PM Appendix B - Page 10

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No.

50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2004 to 31-DEC-2004 Medium or Pathway Sampled Type and Total Number of Lower Limit of Detectio n

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

Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range Direct Radiation 175 TLD (15.5 mi WNW)

(mR/standard quarter) 162 0.00E+00 16.8 (158/158) 180 25.7 (4/4) 22.9 (4/4) 0 9.90 - 27.6 (12.7 mi NNE) 23.6 - 27.6 20.2 - 24.0 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 @ 4/11/2005 2:16 PM Appendix B - Page 11

Appendix C - Page 1 APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES

Appendix C - Page 2 APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 134 6/23-6/30/2004 6/23-6/30/2004 PI The primary and secondary air sampler experienced a power interruption during the composite period as both clocks indicated a run time of about 161 hours0.00186 days <br />0.0447 hours <br />2.662037e-4 weeks <br />6.12605e-5 months <br />.

The expected run time was about 166.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Both samplers were running at time of collection.

125 10/13-10/20/2004 10/14-10/20/2004 PI During sample collection on 10/13/2004 sampler 00302 caused the main breaker to trip. Collection personnel cannot reset the breaker that was tripped. Work request 10000 was written to restore power. Power was restored on 10/14/2004 at 08:48. Sampler 00302 was removed from service and returned to the lab for repairs.

Drinking Water Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 136*

6/9-7/7/2004 6/9-7/7/2004 OT Water treatment plant personnel isolated reservoir tank (turned off water supply) on approximately 6/16/2004. It was discovered during the 6/23/2004 collection and sampler was returned to normal operation.

Appendix C - Page 3 132*

6/9-7/7/2004 7/7-7/7/2004 OT During composite period, water treatment plant personnel turned off water supply valve. A grab sample was taken on 7/7/2004. Sampler was returned to normal operation 7/7/2004 at about 12:35.

101*

8/4-9/1/2004 8/4-9/1/2004 OT Water supply was turned off by water plant personnel. Sufficient volume of water was collected to obtain a full sample. The water supply was turned back on by sampling team member. The second half of the composite period was interrupted again by water plant personnel turning the water supply off. The water supply was restored and normal sampling was resumed on 9/1/2004 15:10.

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

Surface Water Location Scheduled Collection Dates Actual Collection Dates Reason Code Corrective Action 128 12/23-1/21/2004 1/7-1/21/2004 CN Work request 3022830 written to reconfigure water site for ISCO water sampler placement. During reconfiguration on 1/7/2004, most of the first half water composite inadvertently lost. A grab sample was taken on 1/7/2004 12:20. Composite period is 1/7/2004 12:20 to 1/21/2004 10:40. Sampling equipment reconfigured and restored to normal sampling.

135 5/12-6/9/2004 5/26-6/9/2004 PO Power failure for undetermined reason occurred. Grab sample collected on 5/26/2004 for normal sampling period 5/12/2004 - 5/26/2004. Work request 4013285 was written. Power restored to the site 6/3/2004 14:15. When reservoir pump started, the breaker tripped. ISCO sampler moved to pier, work request 4013879 written. Platform pump replaced and normal sampling resumed approximately 6/9/2004 10:05.

C.2 UNAVAILABLE ANALYSES TLD Location Scheduled Collection Dates Reason Code Corrective Action 181 12/18-3/18/2004 CN TLD missing. 2nd quarter 2004 TLD placed in field.

181 3/18-6/17/2004 OT TLD missing. 3rd quarter 2004 TLD placed in field.

Appendix D - Page 1 APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2004 Radiological Environmental Monitoring Program

Appendix E - Page 1 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2004. Appendix E is located separately from this report and is permanently archived at Duke Power Companys Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.