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Annual Radiological Environ Operating Rept for 1998. with
	ML20206H906
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/31/1998
From:	Barron H; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9905120047
	Download: ML20206H906 (95)
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12700 Hagers Ferry Road Huntersville. NC 28078-9340 (704) 875-4800 omcs fI. B. Barron Via 1%sident IIOA)NIS*NN09 "

May 3, 1999

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U.

S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

20555

Subject:

McGuire Nuclear Stat. ion Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report Please find attached the McGuire Nuclear Station Annual Radiological Environmental Operating Report for 1998 pursuant to McGuire Technical Specification 5.6.2 Questions with respect to this report should be directed to Key Crane, at (704) 875-4306.

Very truly yours, H.

B.

Barron, Vice President McGuire Nuclear Station Mr. Frank Rinaldi, Project Manager Mr. Dayne Brown Office of Nuclear Reactor Regulation Division of Radiation Protection i

U.

S.

Nuclear Regulatory Commission P.O.

Box 27687 Washington, D.C.

20555

Raleigh, N.C.

27611-7687 Mr. Luis Reyes ANI Library U. S. Nuclear Regulatory Commission Town Center, Suite 3005 Region II 29 South Main Street 101 Marietta Street, NW - Suite 2900 West Hartford, CT Atlanta, Georgia 30323 06107-2445 Mr. Scott Shaeffer Senior Resident Inspector McGuire Nuclear Site

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING RF; PORT DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Units 1 and 2 1998

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l TABLE OF CONTENTS 1.0 Esecutiv e Summary l-1 2.0 inIroduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of Environmental Monitoring Program.

2-1 2.3 Statistical and Calculational Methodology 2-2 2.3.l Estimation of the Mean Value 2-2 2.3.2 Lower Level of Detection, Minimum Detectable Activity, and Critical Level 2-3 2.3.3 Trend IdentiGcation.

2-3 3.0 Interpretation of Resuln 3-1 3.1 Airborne Radiciodine 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 Procucts 3-1l 3.7 Fish 3-12 3.8 Shoreline Sediment 3-15 3.9 Direct Gamma Radiation 3-17 3.10 Land Use Census 3-19 4.0 Esaluation of Dose 4-1 4.1 Dose from Environmental Measurements 41 4.2 Estimated Dose from Releases 4-1 4.3 Comparison of Doses.

4-1 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 Verincation 5-1 5.4.3 Batch Processing 5-2 5.5 Environmental Protection Agency Intercomparison Program 5.2 5.6 Duke Power Intercomparison Program 5.2 5.7 Duke Power Audits 5-2 5.7.1 Radiation Protection Section 5-2 5.7.2 EnRad Laboratories.

5-2 5.8 U.S. Nuclear Regulatory Commission Inspections 5-2 5.9 State of South Carolina Intercomparion Program.

5-3 5.9.1 Environmental Samples 5-3 5.9.2 TLD Intercomparison Program.

5-3 6.0 References 6-1

)

Appendices Appendix A: Environmental Sample and Analysis Procedures A-1 1.

Change of Sampling Procedures.

A-2 II. Description of Analysis Procedures A-2 111. Change of Analysis Procedures.

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

A4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Food Products.

A-4 A.7 Fish A-5 A.8 Shoreline Sediment.

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

A-5 A.10 Annualland Use Census A-6 Appendix B: Radiological Environmental Monitoring Program - Summary of Results Air Particulate B-2 Air Radioiodine.

B3 Drinking Water.

B-4 Surface Water B-5 Milk B-6 j

Broadleaf Vegetation B-7 Food Products.

B-8 Fish B-9 Shoreline Sediment B-10 Direct Gamma Radiation (TLD)

B-li Appendix C: Sampling Deviations and Unavailable Analyses C-1 C.! Sampling Deviations C-2 C.2 Unavailable Analyses C-2 Appendix D: Analytical Deviations Lower Limits of Detection.

D-1 Appendix E: Radiological Environmental Monitoring Program Results El LIST OF FIGURES 2.1-1 Sampling Locations Map (Site Boundary) 2-6 2.1-2 Sampling Locations Map (Ten Mile Radius) 27 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-l 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 3-17 3.10 Land Use Census Map 3-21 LIST OF TAHLES 2.1 A Radiological Monitoring Program Sampling Locations 2-4 2.1 B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-5 2.2-A Reporting Levels for Radioactivity Concentrations in ii

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Environmental Samples 7-8

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12-B REMP Analysis Frequency 2-9 22-C Maximum Values for the Lower Limits of Detection 2-10

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3. ; - A Mean Concentrations of Radionuclides in Air Particulate 3-3 3.1 B Mean Concentrations of Air Radiciodine (1-131) 3-4

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3.2 Mean Concentrations of Radionuclides in Drinking Water.

3-6

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3.3 Mean Concentrations of Tritium in Surface Water 38 3.4 Mean Concentrations of Cs 137 in Milk 3-9

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3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation 3-10

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3.6 Mean Concentrations of Cs-137 in Food Products 3-1I 3.7 Mean Concentrations of Radionuclides in Fish 3 14

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3.8 Mean Concentrations of Radionuclides in Shoreline Sediment 3 16

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3.9 Direct Gamma Radiation (TLD) Results 3-18 3.10 Land Use Census Results 3 20 4.1 - A 1998 Environmental and EfHuent Dose Comparison 4-3

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4.1 B Maximum Individual Dose for 1998 based on Environmental Measurements for McGuire Nuclear Station 4-6

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5.0- A Environmental Protection Agency Interlaboratory Comparison Program 5-4

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5.0-B Duke Power Company Interlaboratory Comparison Program 5-6 5.0-C State of North Carolina Department of Environmental Health and Natural

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Resources 1998 Environmental Dosimeter Cross-Check Results,

5-11

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LIST OF ACRONYMS USED IN Tills TEXT (in a/.habc/icalorder) f

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llW lliWeekly

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C Control CL Critical Level

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DEllNR Department of Environmental llealth and Natural Resources DiiEC Department of llealth and Environmental Control EPA Environmental Protection Agency

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GILLI Gastrointestinal - Lower Large intestine LLD Lower Limit of Detection M

Monthly f

MDA Minimum Detectable Activity mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission i

ODCM OfTsite Dose Calculation Manual f

pCilkg picoeurie per kilogram j

pCi/l picocurie per liter

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pCi/m3 picoeurie per cubic meter Q

Quarterly REMP Radiological Environmental Monitoring Program

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SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECilSPECs Technical Speci6 cations TLD Thermoluminescent Dosimeter pCi/mi microcurie per milliliter UFSAR Updated Final Safety Analysis Report W

Weekly

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 1998.

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.

1 Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLC's). Required analyses were performed and detection capabilities were met for all collected samples as required by SLC's. Twelve-hundred thirty-six samples were analyzed comprising 1392 test results in order to compile data for the 1998 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 1998 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 SLC's.

Additionally, environmental radiological g.,

97 monitoring data is consistent with effluents 4tef#

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introduced into the environment by plant r;t operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 6.95E-02 mrem for 1998. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

Shoreline sediment sampling

)

Section 1 Page l

2.0 INTRODUCTION

2.1 SITE I)ESCRIPTION ANI) SAMPI,E LOCATIONS McGuire Nuclear Station is located geographically near the center of a highly industrialized region of the Carolinas. The land is predominantly rural non-fami with a small amount ofland being used to support beef cattle and farming. Recreation in the area is confined mostly to the lake and shores of Lake Norman and Mountain Island reservoir. 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 Company's Cowans Ford Dam Hydroelectric Station, which is located immediately west of the site and on the Catawba River channel. 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 Nonnan, approximately 16 miles upstream from the site (reference 6.3). The site exclusion radius is 2500 feet.

Tables 2.1-A and 2.1-B define the sampling and TLD locations for the McGuire Radiological l

Monitoring Program. Figures 2.1-1 and 2.1-2 illustrate these locations as compared to McGuire l

Nuclear Station.

l 2.2 SCOPE ANI) REOUIREMENTS OF Tile REMP l

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. 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.

Section 2 Page I

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The Annual Land Use Census, required by Selected Licensee Commitments, is performed to

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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 f

changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to f

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 f

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 STATISTICAls AND CAI CUl>ATIONAl, METilODOl>OGY l

)

2.3.1 ESTIM ATION OF Tile MEAN val,UE There was one (1) basic statistical calculation perfomled 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 f

mean is a widely used statistic. This value was used in the reduction of the data f

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

N{X, 7=

1 N

Where:

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

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 2

2.3.2 LOWER LEVEL OF DETECTION, MINIMUM DETECTABLE ACTIVITY, AND CRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), and Critical Level (CL) 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 bwer 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.

CL - The CL is defined as the net count rate which must be exceeded before a sample is considered to contain any measurable activity above the 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, detennined 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 3

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TAllLE 2.1-A 4

MCGUIRE IIADIOLOGICAL MONITORING PROGRAM SAMPI ING LOCATIONS Table 2.1 A Codes W

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Control Site Location Descriation

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119 Mt llolly Municipal Water Supply ( 7.4 mi SSW )

BW 120 Site Boundary ( 0 5 mi NNE )

W M(h) 121 Site lloundary ( 0 $ mi NE )

W 125 Site Boundary ( 0 4 mi SW )

W M(b) 128 Diecharge Canal liridge ( 0 4 nu NE )

BW 129 Discharge Canal Entrance to Lake Norman ( 0 5 mi ENE)

SA SA 130 Hwy 73 Bridge Downstream ( 0 5 mi SW )

SA 131 Cowans Ford Dam ( 0 6 mi WNW )

BW 132 Charlotte Municipal Water Supply ( l1.2 mi SSE )

BW 133 Cornelius ( 6 2 mi NE )

W 134 C East !.incoln Jr liigh School ( 8 8 mi WNW )

W M(b) 135 C Plant Marshall intake Canal ( lI 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 I38 llenry Cook Dairy ( 3 i mi ESE )

SM 139 William Cook Dairy ( 2 5 mi E )

SM 140 Kidd Dairy-Cows ( 2 8 mi SSE )

SM 14 I C l.ynch Dairy Cows ( 14 8 mi WNW )

SM 188 5 mile radius Gardens ( 2.8 mi N )

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192 Peninsula ( 2.8 mi NNE )

W 193 Site Boundary ( 0 2 mi N )

M(b) 194 East Lincoln County Water Supply ( 6 7 mi NNW )

BW 195 Fishing Access Road ( 0 2 mi N )

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

Section 2

PagC 4

TAllLE 2.1-11 MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location Description Site Location Description v

m 143 SITE BOUNDARY 0.3 miles NW 167 4-5 MILE RADIUS 4.9 miles SW 144 SITE BOUNDARY 0.5 miles NNE 168 4-5 MILE RADIUS 4.6 miles WSW I45 SITE BOUNDARY 0.5 miles NE 169 4-5 MILE RADIUS 4.0 miles W 146 SITE BOUNDARY 0.4 miles ENE 170 4-5 MILE RADIUS 4.3 miles WNW 147 SITE BOUNDARY 0.4 miles E 171 4-5 MILE RADIUS 4.0 miles NW 148 SITE BOUNDARY 0.5 miles ESE 172 4-5 MILE RADIUS 5.7 miles NNW I49 SITE BOUNDARY 0.5 miles SE 173 SPECI AL INTEREST 8.4 miles NNW 151 SITE BOUNDARY 0.4 miles S 174 SPECI AL INTEREST 8.8 miles WNW 152 SITE BOUNDARY 0.4 miles SSW 175 CONTROL 15.5 miles WNW 153 SITE BOUNDARY 0.5 miles SW 176 SPECI AL INTEREST I 1.0 miles SW 154 SITE BOUNDARY 0.5 miles W 177 SPdCI AL INTEREST 8.8 miles S 156 SITE BOUNDARY 0.5 miles WNW 178 SPE CI AL INTEREST 9.3 miles SE 189 SITE BOUNDARY 0.4 miles SSE 179 SP'.iCI AL INTEREST 10.6 miles ESE 190 SITE BOUNDARY 0.4 miles WSW 180 SPECIAL INTEREST 12.7 miles NNE 157 4-5 MILE RADIUS 4.7 miles N 181 SPECI AL INTEREST 7.0 miles NE 158 4 5 MILE RADIUS 4.3 miles NNE 182 SPECI AL INTEREST 6.2 miles NE 159 4-5 MILE RADIUS 5.0 miles NE 183 SPECI AL INTEREST 5.8 miles S 160 4 5 MILE RADIUS 4.9 miles ENE 186 SPECI AL INTEREST 0.2 miles NNW 161 4-5 MILE RADIUS 4.7 miles E 187 SPECI AL INTEREST 0.2 miles N 162 4-5 MILE RADIUS 4.5 miles ESE 191 SITE BOUNDARY 2.8 miles NNE 163 4 5 MILE RADIUS 4.9 miles SE 196 SPECIAL INTEREST 1.0 miles S 164 4-5 MILE RADIUS 4.6 miles SSE 197 SPECI AL INTEREST 1.1 miles S 165 4-5 MILE RADIUS 5.1 miles S 198 SPECI AL INTEREST 1.3 miles S 166 4-5 MILE RADIUS 5.3 miles SSW 199 SPECI AL INTEREST l.5 miles S

All TLDs are collected quarterly Section 2. Page 5

McGuire Nuclear Station Figure 2.1-1 Sampling Locations Map (Site Boundary)

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s e TLD Locations A All Other Locations Secuon 2 - Page 7

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t 1,

h' TAILLE 2.2-A 9

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water.

Air Particulates Fish.

Milk Broadleaf

'(pCi/ liter) or Gases (pCi/kg-wet)

(pCi/ liter)

Vegetation 3

(Pci/m )

(pCi/kg wet) 4 H-3 20,000

s 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 l-131 2

1 3

100 Cs-134 30 10 1,000 60 1,000 Cs l37 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of30,000 pCi/ liter may be used Section 2 Page 8

)

1 TAlli,E 2.2-11 ItEhlP ANAINSIS FitEQUENCY Sampic Analysis Gamma Tritium Low Level Gross TLD Medium Schedule isotopic l-131 Beta Air Radiciodine Weekly X

Air Weekly X

Particulates Quarterly X

Composite Direct Radiation Quarterly X

Monthly Surface Composite X

Water Quarterly Composite X

Monthly Drinking Composite X

X Water Quarterly Composite X

Shoreline Sediment Semiannually X

Milk Semimonthly X

X Fish Semiannually X

Broadleaf Monthly Vegetation (when available)

X Monthly Food Products (during harvest X

season)

)

Section 2 - Page 9

)

TAIILE 2.2-C MAXIMUM VALUES FOR Tile LOWER LIMITS OF DETECTION Air Analysis Water,

Particulates -

Fish,

- (pCi/ liter)

Vegetation Milk Broadleaf Sediment

- (pCi/ liter) or Gases (pCi/kg-wet)

. pCi/kg-dry)

(

(pCi/m')

(pCi/kg-wet)

Gross Beta 4

H-3 2000N Mn-54 15 130 Fe 59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 l 131 1*

0.07 1

60 Cs-134 15 0.05 130 15 60 ISO Cs-137 I8 0.06 150 18 80 180 Ba-La-140 15 15 (a) Ifno drinking water pathway exists, a value of 3000 pCi/ liter may be used (b) Ifno drinking water pathway exists, the LLD ofgamma isotopic analysis may be used

)

Section 2 Page 10 l

3.0 INTERPRETATION OF RESU.LTS This section provides a summary and review of all 1998 REMP analysis results 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 adionuclide 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 radionuclide's NRC 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 1998 was 1.93% for surface water tritium at the discharge canal (Location 128). Only Selected Licensee Commitments radionuclides were detected in 1998.

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 IEMP. 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 1998. Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas. The 1998 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 1

3.1 AIRilORNE RADIOIODINE AND PARTICUl>ATES In 1998,364 particulate and radiciodine samples were analyzed,312 at six indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gross beta. Gamma analysis was Performed on 28 particulate composite samples,24 at the six indicator locations and four at the control location. Radiciodine samples received a weekly gamma analysis.

Per Selected Licensee Commitments, if gross beta in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be perfonned on 3

individual samples. As in previous years, the location with the highest mean (1.86E-2 pCi/m )

3 in 1998 was less than ten times the yearly mean of the control location (2.66E-2 pCi/m ).

Therefore, gamma isotopic analysis was perfonned quarterly on composite particulate filters. No detectable gamma emitting particulate activity has been found in environmental air samples since 1987.

No detectable I-131 activity in any environmental air radiciodine samples was found in 1998.

Cs-137 was not found in any environmental air radiciodine samples during 1998. Cs-137 was found in five indicator samples and in one of the control samples in 1997. However, no Cs-137 was found on the corresponding particulate tilters. An investigation performed in 1990 concluded that Cs-137 activity detected only on the cartridges was not attributed by station eflluents but was an ntive constituent of the charcoal media (reference 6.5). Therefore, the Cs-137 activity was not used to calculate doses.

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. Since no gamma activity was detected in 1998, no reporting levels were approached.

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 radionuclides were detected in 1998, no reporting levels were approached.

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seaion 3. Page 2

)

Figure 3.1 pcum Concentration of Gross Beta in Air Particulate 8

1.00E 01 9 00E-02 8 00E-02 7.00E-02 6 00E 02 5 00E-02 p

4 00E 02 3 00E-02 2 00E-02 d-

~

Z 1.00E 02

{-

I 0 00E+00 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

-e-Indicator Location

--+- Control Location t-There is no reporting levelfor Gross Beta in air particulate Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate YEAR Cs-137 Indicator Cs-137 Control Beta indicator Beta Control (pCi/m')

(pCi/m')

1979*

4.40E-3 1.47 E-3 I980*

6.70E-3 4.53 E-3 1981*

6.16E-3 5.32 E-3 1982*

3.82 E-3 2.29E-3 1983*

2.93 E-3 3.2 l E-3 1984 1.74E-3 8.29E-4 1985 1.86E-3 1.32E-3 2.44 E-2 2.40 E-2 1986 4.98 E-3 3.03 E-3 2.64E 2 2.52 E-2 1987 1.07E-2 7.9 I E-3 2.54E 2 2.59 E-2 1988 0.00EO 0.00E0 7.49E-2 5.5 I E-2 1989 0.00E0 0.00E0 2.22 E-2 2.14 E-2 1990 0.00E0 0.00E0 2.58 E-2 2.37 E-2 1991 0.00EO 0.00E0

2. I 6 E-2

2. I 5 E-2 1992 0.00E0 0.00E0 1.92E-2 2.02 E-2 1993 0.00E0 0.00E0 1.93 E-2 2.04 E-2 1994 0.00E0 0.00E0 2.'28 E-2 2.02E 2 1995 0.00E0 0.00E0 3.02 E-2 5.17E-2 1996 0.00E0 0.00E0

3. I 1 E-2 5.49E-2 1997 0.00E0 0.00E0 2.34 E-2 3.62 E-2 Average (1988 - 1997)

NOT APPLICABLE NOT APPLICABLE 2.9 I E-2 3.25 E-2 1998 0.00E0 0.00E0 1.86E-2 2.66E-2 0.00E0 = no detectable measurements

Radiciodines and Particulates analyzed together

" Gross Beta analysis not perfonned

)

Section 3 - Page 3

)

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

Year indicator Location (pCi/m*)

Control Location (pCi/m )

3 19798 3.28E-3 1.04E-3 1980*

2.01 E-3 1.10 E-3 1981*

4.17E-3 6.27 E-4 1982*

l.42E-3 2.48E-3 1983*

1.99E-3 2.01 E-4 1984 3.17E-3 0.00E0 1985 3.15E-3 1.04 E-3 1986 1.27 E-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 0.00E0 = no detectable measurements

Radiciodines and Particulates analyzed together.

)

Section 3 Page 4

)

3.2 DRINKING WATER In 1998, 52 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Thirty nine samples were from the three indicator locations and 13 from the control location. Tritium (H-3) analyses were perfonned on 16 composite samples,12 at indicator locations and four at the control location.

No detectable gamma activity was found in drinking water samples in 1998 and has not been detected since 1987. Gross beta analyses indicated 2.75 pCi/l at the location with the highest annual mean and 2.33 pCi/l at the control location. Tritium was detected in three of the 12 indicator composite samples taken in 1998 with the highest annual mean resulting in only 1.34% of the reporting level. The dose for consumption of water was less than one mrem per year, historically and for 1998; 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.

Figure 3.2 pcViiter Concentration of Tritium in Drinking Water 2500 2000 f

1500 1000 500 M'

=

r 1

1 v

0 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

-G

--*- Control Location 10% Reporting Level

. - _ -Indicator Location i

)

Section 3 Page 5

)

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCill)

Tritium (pCi/l)

YEAR Indicator Control Indicator Control Location Location Location Location 1979 2.40E0 2.03E0 1.65E2 1.50E2 1980 2.34E0 1.87E0 1.63 E2 2.05E2 1981 2.79E0 2.41 E0 l.88E2 1.78E2 1982 2.62E0 2.43 E0 2.43 E2 1.45 E2 1983 1.80E0 1.87E0 2.65 E2 1.45E2 1984 2.78E0 1.81E0 5.77E2 2.45 E2 1985 1.88E0 1.90E0 5.93E2 4.00E2 1986 2.13E0 2.15E0 1.14 E3 4.37E2 1987 2.30E0 2.00E0 1.35 E3 7.75 E2 1988 2.00E0 2.00E0 9.92 E2 7.11 E2 1989 2.80E0 2.70E0 5.62E2 0.00E0 1990 3.70E0 4.30E0 7.32E2 6.1 I E2 1991 2.40E0 2.50E0 5.22E2 0.00E0 1992 2.00E0 1.70E0 6.73 E2 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 2.75 E0

2. I I E0 3.60E2 0.00E0 1997 2.70E0 2.24E0 2.90E2 0.00E0 1998 2.75 E0 2.33E0 2.68E2 0.00E0 0.00E0 = no detectable measurements 3

)

Section 3 - Page 6

)

3.3 SURFACE WATER In 1998,39 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 perfonned on 12 samples, eight at indicator locations and four at the control location.

No detectable gamma activity was found in u

surface water samples in 1998 and has not been detected since 1988.

Tritium was N_.

detected in six of the eight indicator

4. '.,

d.y n.

ea y.._.

composite samples taken in 1998 with the ut.

3 ;p q;

highest annual mean resulting in only 1.7%

>le of the reporting level.

Figure 3.3 shows tritium highest annual mean indicator and control location concentrations with comparisons to 20% of a

the reporting level. Table 3.3 gives indicator

(

and centrol location highest annual means since 1979 for 11-3.

_ _ _ _ _ _1 Surface Water Sampling at McGuire Nuclear Station Figure 3.3 I

pCUliter Concentration of Tritium in Surface Water 4500 l

l l

4000 3500 3000 2500 2000 1500 1000

- -t

[

500 l'

1 I'

I I

i 0"

1979 1980 1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 f

--G-Indicator Location

-+- Control Location

-20% Reporting Level

)

Section 3 - Page 7

)

Table 3.3 Mean Concentrations of Tritium in Surface Water YEAR II-3 Indicator (pCi/l) 11-3 Control (pCi/l) 1979 1.85 E2 1.66E2 1980 2.13 E2 1.93 E2 198I 1.75 E2 1.70E2 1982 3.30E2 1.23 E2 1983 5.75 E2 3.67E2 1984 4.10E2 2.65 E2 1985 7.33 E2 0.00E0 1986 2.33 E3 6.13 E2 1987 9.20E2 7.70E2 1988 9.40E2 0.00E0 1989 8.22E2 0.00E0 1990 6.77E2 0.00E0 1991 7.53 E2 0.00E0 1992 8.13 E2 0.00E0 1993 6.85E2 0.00E0 1994 0.00E0 0.00E0 1995 3.15 E2 0.00E0 1996 8.08E2 0.00E0 1997 4.85 E2 0.00E0 1998 3.40E2 0.00E0 0.00E0 = no detectable measurements

)

Section 3 Page 8

)

l 3.4 MILK in 1998,104 milk samples were analyzed for low level I-131 and other gamma emitting radionuclides,78 at the three indicator locations and 26 at the control location.

No detectable activity was found in milk samples in 1998. 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 1998, no reporting levels were approached.

Table 3.4 Nfcan Concentrations of Cs-137 in NIilk YEAR Cs-137 indicator (pCi/l)

Cs-137 Control (pCill) 1979 2.48El 6.04E0 1980 l.72El 4.13 E0 1981 2.04El 4.15 E0 l982 1.2 ] El 5.20E0 1983 2.0l E l 2.82E0 1984 1.48E l 2.56E0 1985 1.42 El 2.72E0 1986 3.74 E0 3.45 E0 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 0.00E0 = no detectable measurements

)

Section 3 - Page 9

)

3.5 HROADLEAF VEGETATION In 1998,40 broadleaf vegetation samples were analyzed,30 at the three indicator locations and ten at the control location.

Cs 137 was detected in one control location sample. No other detectable gamma activity

~

j was found in vegetation samples in 1998.

Cs-137 has not been detected in vegetation samples since 1993 and all other radionuclides have not been detected since 1987. Table 3.5 gives indicator and control location highest annual means since 1979 for Cs-137.

l Broadleaf Vegetation Sampling at McGuire Nuclear Station Table 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg)

Cs-137 Control (pCi/kg) 1979 2.19EI l.93 E I 1980 2.30EI l.92 EI 1981 3.04E1 2.02EI 1982 2.46E I l.22EI 1983 9.07E0 7.85 E0 1984 1.02EI 1.05 EI 1985 8.05E0 2.3 7E-2 1986 4.03 EI 1.27E I 1987 2.20E I l.70EI 1988 3.90E I 3.40EI 1989 9.60EI 0.00E0 1990 4.00EI 0.00E0 1991 3.30EI 0.00E0 1992 4.90El 0.00E0 1993 1.60E l 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00EO 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 2.69E I 0.00E0 = no detectable measurements

)

Section 3 Page 10

)

3.6 FOOD PRODUCTS In 1998,12 food products (crops) samples were analyzed, all at one indicator location. There is no control location for this media.

No detectable activity has been detected in this media since 1987. Table 3.6 shows Cs-137 indicator highest annual means with preoperational data and ten year averages. Since no activity was detected in 1998, no reporting levels were approached.

Table 3.6 Mean Concentrations of Cs-137 in Food Products YEAR Cs-137 Indicator (pCi/kg) 1979 2.19E I 1980 2.30E l 1981 3.04El 1982 2.46E l 1983 9.07E0 1984 8.45 E0 1985 7.99E0 1986 2.15 El 1987 2.90E I 1988 0.00E0 l989 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 0.00E0 = no detectable measurements

)

section 3 Page iI

)

3.7 FISIl In 1998,12 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. These two radionuclides represent the highest dose contributors for fish.

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.

Only Cs-137 activity was detected in 1998 in one of the six indicator samples. All other radionuclides not shown in the table have demonstrated no detectable activity since 1986.

The highest annual mean for Cs-137 activity resulted in only 1.61% of the reporting level.

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Fish Sampling at McGuire Nuclear Station

)

section 3. Page 12

)

Figu re 3.7-1 pcukg Concentration of Cs 137 in Fish 140 120 100 80 60 40 d- -- _

0j i

l l

O 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 r

y

[ Indicator Location

-*-- Control Location 5% of Reporting Level

]

Figu re 3.7-2 pci/kg Concentration of Co-60 in Fish 600 500 400 300 200 too O !b :

0 0

0

-E-

=

1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 I

-G-Indicator Location

-*-- Control Location 5% of Reporting Level l.

.J i

)

S tion 3 - Page 13

)

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

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

-1.97 E l 8.36E0

-2.25El

-2.70E l

-4.13 E0 1981

-2.71E0

-2.98 E0

-2.65 E0

-1.99 E0 1.80E l 1982

-3.83 E0 8.16E0

-4.34 E-l

-8.22 E-l 2.69E l 1983

-2.60 E0 2.60E l

1. l l E l

-1.32 E0 6.03 E l 1984 3.61 E0 1.45E2 2.82 E l

3. l l E l 4.38E l 1985 2.53 E-l 7.19E0 1.72E l

- 1.56 E0 1.86E l 1986 1.03 E0 3.17E l 2.96E l I.67E l 3.49E l 1987 0.00E0 2.71 E2 1.25 E2 2.60E l 5.10E l 1988 1.20E l 7.70E l 0.00E0 2.70E l 3.60E l 1989 9.00El 4.05 E2 2.99E2 1.10E l 3.50E l 1990 0.00E0 5.60El 4.10E l 0.00E0 3.30E l 1991 6.20E0 1.40E l 6.50E l 5.90E0 2.60 E l 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90El 1993 0.00E0 8.20E l 1.30E l 0.00E0 1.60El 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10E l 1995 0.00E0 0.00E0 0.00E0 0.00E0 2.70E l 1996 0.00E0 0.00E0 0.00E0 0.00E0 2.78 E l 1997 0.00E0 0.00E0 0.00E0 0.00E0 1.62E l 1998 0.00E0 0.00E0 0.00E0 0.00EO 3.21 E1 0.00E0== no detectable measurements All negative values have been replaced with zeros for calculational purposes

)

sanon 3.Page i4

)

3.8 SIIORELINE SEDIMENT In 1998, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.

Figure 3.81 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. These two radionuclides represent the highest dose contributors fbr shoreline sediment.

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.

Figu re 3.8-1 pCi/kg Concentration of Cs-137 in Shoreline Sediment 500 450 400 350 300 250 I

200 150 M'

N

\\

x W+%

Ib::/

\\.

e 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997

_-5-Indicator Location - Control Location There is no reporting levelfor Cs-l37 in shoreline sediment

)

section 3.Page 15

)

Figure 3.8-2 pci/kg Concentration of Co-60 in Shoreline Sediment 180 160 140 i

120 100 80 8

60 40

\\

20

=

- -f-0' 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997

! -Indicator Location Control Location

.]

There is no reporting levelfor Co-60 in shoreline sediment Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (nCi/ke)

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

-l.07E l 2.25E l

-6.50E0 0.00E0 1.20El 1980 1.06E l

-8.74 E0 2.36E l

-3.53 E0 1.44 E l 1981 2.13 E l 1.20E l 8.2 ] E0 3.97El 3.36El i,'182 5.38E l 1.66El

- 1.69E0 7.67E l 4.40E l 1983 4.40E0 3.43 E l 2.12E l 7.65 El 8.02El 1984 1.19E l

7. l l E l 3.04 E l 3.34El 9.13 El 1985 4.77E0 1.46E l 9.20E0 2.02 E l I.6 l E2 1986 1.37E l 1.02E l I.16E l 6.35 E l 1.53 E2 1987 0.00E0 1.06E2 2.10E l 4.20El 1.65 E2 1988 6.50E0 9.20E l 1.20E l 9.10E0 2.66E2 1989 2.90E l 3.80El 2.90E l 5.30E l 6.50E l 1990 3.80El 2.70E l I.68E2 0.00E0 6.10E l 1991 2.80El 5.30E l 1.31 E2 0.00E0 1.03 E2 1992 9.40E0 0.00E0 5.10E l 9.20E0 8.60E l 1993 0.00E0 2.20E l 8.60E l 0.00E0 9.30El 1994 4.10El 0.00E0 0.00E0 0.00E0 8.00E l 1995 1.70E l 0.00E0 2.30El 0.00E0 1.38 E2 1996 2.90E l 1.78E l 3.50El 0.00E0 1.47E2 1997 0.00E0 0.00E0 1.IIE2 3.10E l 1.36E2 1998 0.00E0 0.00E0 5.21El 0.00E0 9.97El

)

section 3 - Page 16

)

3.9 I)lRECT G AMM A IIAI)l ATION In 1998,187 TLDs were analyzed,183 at indicator locations, four at the control location. TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 107.6 milliroentgen. The annual mean exposure for the control location was 86.8 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 millirem per year. Preoperational data and fifteen year 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 control averages representing only one location.

The calculated total body dose from gaseous effluents for 1998 was 1.41E-l millirem, which is 0.2% 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 Direct Gamma Radiation (TLD) Results mR/yr 200 180 160 140 1

__p I __

%I a

40 20 0

1979 1981 1983 1985 1987 1989 1991 1993 1995 1997

-&-Inner Ring

-e-Outer Ring Control There is no reporting levelfor Direct Radiation (TLD) section 3.Page 17

Table 3.9 Direct Gamma Radiation (TLD) Results YEAR Inner Ring Average Outer Ring Average Control (mR/yr)

(mR/yr)

(mR/yr) 1979 7.9 I E I 8.82 E I 8.32EI 1980 7.54 E I

8.29 E 1

1.05E2 1981 1.0lE2 9.3 l E l 1.05E2 1982 8.95 E 1 8.97E I 1.10E2 1983 1.16E2 1.14E2 1.30E2 1984 7.85 E I 7.83 E I 9.02E I 1985 9.54 E I 9.69EI 1.27E2 1986 8.9 I E I 9.35 E i 1.10E2 1987 7.58E l 7.71 E l 1.23 E2 1988 6.03 E I 6.42E I 5.48E I 1989 5.37EI 5.30E I 7.55 EI g

I990 4.34E 1 4.78EI 6.25EI 1991 5.14 E l 5.59El 6.80E l 1992 5.65 E l 5.55E l 7.60E l 1993 5.6i E 1 5.7IEI 7.20E I I994 6.40E I 6.93 E I 9.55 E I 1995 8.36El 8.25 E l 1.08E2 1996 7.18E l 7.02E l 9.88E l 1997 6.22E l 6.68E l 9.45 El Average (1982 1997) 7.17EI 7.32EI 9.35EI 1998 6.59E l 6.32 E l 8.69E l

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

NOTE: The expected background for North Carolina is 120 mrem per year (Reference 6.3).

)

secnon 3. rage is I

3.10 LAND USE CENSUS The land use census was conducted June 15 - June 16,1998 and the results are shown in Table 3.10 and Figure 3.10.

During the 1998 census, no new or closer irrigated gardens were identified. The census revealed six milk animal locations that were not included in the 1998 sampling program. Five of the locations (goats) do not produce sullicient volume to be added to the program and the sixth (cow) was not added due to lower deposition factor value compared to the other three REMP sites. The nearest residence is located in the East sector at 0.46 miles. No program changes were required as a result of the 1998 land use census.

I

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l

)

l

)

Table 3.10 f

McGuire 1998 Land Use Census liesults

)

Sector Distance Sector Distance (Miles)

(Miles)

Nearest Residence 2.50 Nearest Residence 1.62 Nearest Garden 2.79 g

Nearest Garden 3.04 N

Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.01 Nearest Goat

)

Nearest Goat Nearest Residence 1.29 Nearest Residence 2.57 Nearest Garden 2.87 ggg Nearest Garden 2.95 NNE Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 2.75

)

Nearest Goat Nearest Goat Nearest Residence 1.20 Nearest Residence 1.80 gg Nearest Garden 2.10 Nearest Garden 1.80 gg Nearest Milk Cow Nearest Milk Cow i

f Nearest Beef Cow Nearest Beef Cow Nearest Goat Nearest Goat Nearest Residence 0.56 Nearest Residence 1.01 ENE Nearest Garden 2.55 ggg Nearest Garden 1.16 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 3.81 Nearest Beef Cow l.32 Nearest Goat Nearest Goat 3.97 Nearest Residence 0.46 Nearest Residence 0.82 f

E hearest Garden 0.47 gy Nearest Garden 0.90 Nearest Milk Cow 2.46 Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow Nearest Goat Nearest Goat 3.83 Nearest Residence 0.67 Nearest Residence 0.91 Nearest Garden 0.85 Nearest Garden 2.15 l

ESE gyggy f

Nearest Milk Cow 3.07 Nearest Milk Cow Nearest Beef Cow l.30 Nearest Beef Cow Nearest Goat 1.40 Nearest Goat Nearest Residence 1.17 Nearest Residence 0.93 gg Nearest Garden 1.21 gg Nearest Garden 1.37 Nearest Milk Cow Nearest Milk Cow f

Nearest Beef Cow 2.79 Nearest Beef Cow 3.85 Nearest Goat Nearest Goat Nearest Residence 1.06 Nearest Residence 1.53 Nearest Garden 1.26 Nearest Garden 1.77 SSE NN\\Y Nearest Milk Cow 2.76 Nearest Milk Cow Nearest Beef Cow l.48 Nearest Beef Cow 3.67 i

Nearest Goat 1.30 Nearest Goat

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

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l 4.0 EVALUATION OF DOSE l

l 4.1 DOSE FROM ENVIRONMENTAL, MEASUREMENTS Doses were estimated for measured concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology and factors. A dose factor of zero was used when the Reg. Guide listed "NO DATA" for a factor. The highest annual mean i

values for each sample type and radionuclide as given in Appendix B were used aller the background concentrations, as measured at the control location, had been subtracted. The j

I maximum exposed individual doses are summarized in Tables 4.1-A and 4.1-B. Dose calculations sheets for each age and pathway that indicated environmental doses greater than zero can be found following Tables 4.1-A and 4.1-B.

4.2 ESTIMATED DOSE FROM REl, EASES Throughout the year, dose estimates were calculated based on actual 1998 liquid and gaseous effluent release data. Eftluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. The 1998 MNS Annual Radioactive Eftluent Release Report (reference 6.6) included calendar year dose estimates for the location with the highest indivdual organ dose from liquid and gaseous eftluent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

The efiluent-based liquid release doses are summations of the dose contributions from the drinking water and fish pathways. Shoreline sediment dose was not required to be calculated per the ODCM. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas j

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 eftluent-based gaseous release doses are summations of the dose contributors from ground / plane, inhalation and vegetation l

r pathways.

4.3 COMPARISON OF DOSES i

The environmental and release data doses given in Table 4.1-A agree reasonably well, j

The similarity of the doses indicate that the radioactivity levels in the environment do j

l not differ significantly from those expected based on effluent measurements and l

1 modeling of the environmental exposure pathways.

This indicates that eftluent program dose estimates are both valid and reasonably conservative.

l 1

Section 4 - Page 1 l

In calculations based on liquid release ellluent pathways, drinking water and tish consumption were the predominant dose path based on ellluent data for 1998. For 1998 environmental samples, drinking water also was the predominant dose path followed by fish. The only radionuclide detected in drinking water in 1998 was tritium. The only radionuclide detected in fish in 1998 was Cs-137. Tritium from surface water samples also was included in the fish pathway.

No environmental doses resulted from the gaseous pathway in 1998.

Broadleaf vegetation, milk, and airborne radioiodines and particulates indicated no activity in 1998.

The efiluent dose for iodine, particulate, and tritium is based on the potential goat milk pathway to the infant.

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.

1

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section 4 Page2

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TAllLE 4.1-A I

Page 1 of 3 MCGUIRE NUCLEAR STATION i

1998 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON I

LIOUID RELEASE PATHWAY l

I Organ Location Effluent Data Age Pathway (mrem) l Skin Environmental Teen Shoreline Sediment 129 (0.5 mi ENE) 1.10E-03 I

Skin Effluent 1.0 mi ESE Not Calculated Bone Environmental Child Fish 129 (0.5 mi ENE) 7.26E-02 Bone Efnuent Child Fish 1.0 mi ESE 5.62E-03 Liver Environmental Child Fish 129 (0.5 mi ENE) 9.77E-02 Liver Efnuent Child Drinking Water 1.0 mi ESE 2.71E-02 i

, T. Body Environmental Adult Fish 129 (0.5 mi ENE) 6.95 E-02 T. Body Effluent Child Drinking Water 1.0 mi ESE 2.25 E-02

> Thyroid Environmental Child Drinking Water 132 (11.2 mi SSE) 2.83 E-02 l Thyroid Efiluent Child Drinking Water 1.0 mi ESE 2.14E-02 Kidney Environmental Child Drinking Water 132 (11.2 mi SSE) 5.09E-02 Kidney Eftluent Child Drinking Water 1.0 mi ESE 2.32E-02 l

i Lung Environmental Child Drinking Water 132 (11.2 mi SSE) 3.65E-02 Lung Efiluent Child Drinking Water 1.0 mi ESE 2.21 E-02

> GI-LLI Environmental Child Drinking Water 132 (11.2 mi SSE) 2.88E-02

' GI-LLI Effluent Child Drinking Water 1.0 mi ESE 2.26E-02 Maximum dose is a summation of the Ash, drinking water and shoreline sediment pathways.

)

Section 4 - Page 3

)

D D

D Page 2 of 3 I

GASEOUS RELEASE PATHWAY D

D D

g IODINE, PARTICULATE, and TRITIUM i

Environmental or Critical Critical Maximum Dose

I Effluent Data Age Pathway (mrem) p Skin Environmental 0.00E+00 Skin Effluent All Ground / Plane 1.0 mi ESE 3.84E-06 g

I Bone Environmental 0.00E+00 Bone Effluent Infant Goat Milk 1.0 mi ESE 6.21 E-05 Liver Environmental 0.00E+00 g

Eftluent Infant Goat Milk 1.0 mi ESE 5.21 E-01

> Liver

> T. Body Environmental 0.00E+00 '

) T. Body Eftluent Infant Goat Milk 1.0 mi ESE 5.21 E-01

> Thyroid Environmental 0.00E+00 I Thyroid Effluent Infant Goat Milk 1.0 mi ESE 5.44E-01 l

0.00E+00

) Kidney Environmental p Kidney Effluent Infant Goat Milk 1.0 mi ESE 5.21 E-01 Lung Environmental 0.00E+00 Lung Effluent Infant Goat Milk 1.0 mi ESE 5.21 E-01 ll l} GI-LLI Environmental 0.00F+00 GI-LLI Effluent Infant Goat Milk 1.0 mi ESE 5.21 E-01 II Maximum dose is a summation of the ground / plane, inhalation, milk and vegetation pathways.

)

Secuon 4 - Page 4

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I Page 3 of 3 D

NOllLE G AS I

)

Air Environmental or Critical Critical Maximum Dose g

9 h Dose Effluent Data Age Pathway (mrad)

Not Sampled Beta Environmental I

Beta Effluent N/A Noble Gas 1.0 mi NNE 5.77E-02

) Gamma Environmental Not Sampled Gamma Effluent N/A Noble Gas 1.0 mi NNE 1.41 E-01 r

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5.0 QUALITY ASSURANCE 5.1 SANIPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SANIPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified

'(

by approved analysis procedures. EnRad Laboratories is located in Huntersville, N hd des a

2 North Caroh,na, at Duke Power Company's

, A[

=- --

Environmental Center.

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.z 5.3 DOSINIETRY ANALYSIS ouke Power company's Ens ironmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

5.4 LAllORATORY EOUIPNIENT OUALITY ASSURANCE 5.4.1 DAILY OUALITY 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 CALIllR ATION 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 efliciency 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.

Section 5. Page I

4 5.4.3 IIATCil PROCESSING Method spike and blank samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 ENVIRONNIENTAL PROTECTION AGENCY INTERCONIPARISON PROGRANI EnRad Laboratories participated in the Environmental Protection Agency (EPA) cross check program during 1998. Results of these cross-checks are displayed in Table 5.0-A.

5.6 DlIKE POWER INTERCONIPARISON PROGRANI EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1998. 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 1998 is documented in Table 5.0-B.

5.7 DUKE POWER AUDITS 5.7.1 RADIATION PROTECTION SECTION The McGuire Nuclear Station Radiation Protection Section participated in a Duke Power Quality Assurance audit in 1997.

This audit is performed biannually; therefore, no audit was conducted in 1998.

5.7.2 ENRAD I.AllORATORIES EnRad Laboratories participated in a Duke Power Quality Assurance audit in February 1997. This audit is performed biannually; therefore, no audit was conducted in 1998.

5.8 U.S. NUCLEAR REGUl>ATORY CONINilSSION INSPECTIONS The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in October 1998. There were no findings from this audit. EnRad Laboratories was not audited by the NRC in 1998.

)

Section 5 Page 2

)

5.9 STATE OF NORTil CAROLINA INTERCOMPARISON PROGRAM 5.9.1 ENVIRONM ENTAL SAM PLES EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEllNR) in an intercomparison program.

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

5,9.2 TLD 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 1998 is documented in Table 5.0-C.

)

sunon 5 Page 3

)

TABLE 5.0-A

'U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1998 CitOSS-CllECK ItESULTS FOlt ENitAD LAllOIIATORIES 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"I Pass" indicates that one analysis of the cross-check was performed.

Garntna in Water Ret' rence Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check e

Date Range Value Value Status pCi/l pCi/l pCi/l 4/21/98 Blind B Co-60 4.13 El 5.87 El 5.00 E l 5.14 El 3 Pass Cs 134 1.33 El - 3.07 El 2.20 El 2.15 El 3 Pass Cs137 1.30 EO - 1.87 El 1.00 E l 1.07 El 3 Pass 6/5/98 Mixed Co-60 3.30 EO - 2.07 El 1.20 E l 1.43 El 3 Pass Gamma Zn-65 8.67 El - 1.21 E2 1.04 E2 1.06 E2 3 Pass Cs 134 2.23 El - 3.97 El 3.10 El 2.93 El 3 Pass Cs-137 2.63 El 4.37 El 3.50 EI 3.46 EI 3 Pass Ba 133 3.13 El - 4.87 El 4.00 E l 4.08 El 3 Pass 10/20/98 Blind B Co-60 1.23 El - 2.97 El 2.10 El 2.30 El 3 Pass Cs 134 0.00 EO - 1.47 El 6.00 EO 6.17 E0 3 Pass Cs.137 4.13 El - 5.87 El 5.00 El 4.72 EI 3 Pass i I/6/98 Mixed Co-60 2.93 El 4.67 El 3.80 El 3.88 El 3 Pass Gamma Zn-65 1.08 E2 1.53 E2 1.31 E2 1.46 E2 3 Pass Cs-134 9.63 El - 1.14 E2 1.05 E2 9.96 E I 3 Pass Cs-137 1.01 E2 - 1.21 E2 1.11 E2 1.13 E2 3 Pass Ba 133 4.56 El - 6.64 El 5.60 E l 5.71 El 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 I/30/98 N/A bel'A U.00 EO - 1.26 E l 3.90 E l 7.3 3 EU 3 Pass 10/20/98 l Blind B l BETA l 7.67 El 1.1I E2 l 9.40 El l 7.22 E2 l 3/3 liigh W 11/13/98 l

N/A l

BElA l 0.00 E0 - 1.22 El l 3.50 E0 l 3.8; EO l

3 Pass (l) Faihng results most likely due to prenration error associated with the initial cross. check sample dilution Results could not be reproduced during the subsequent investigation.

)

Section 5. Page 4

)

I Tritiurnin Water Reference Sample i.D.

Nuclide Acceptance Reference Mean Reported Cross theck Date Range Value Value Status pCi/l pCi/l pCi/l 3/13/98 N/A 11 3 1.S$ E3 - 2.76 E3 2.16 E3 2.24 E3 3 Pass 8/7/98 l

N/A l

11 3 l 1.49 E4 - 2.1 i E4 l 1.80 E4 l 1.66 E4 l

3 Pass Iodinein Water Reference Sample 1.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/6/98 N/A l-131 8.67 El - 1.23 E2 1.05 E2 1.13 E2 3 Pass 9/lI/98 l

N/.

l l 131 l 2.60 EO - 9.6 E0 l 6.10 E0 l 8.0$ E0 l

3 Pass "'

(2) This sample was not reported to EPA by the required due date so it was not included in the EPA summary report l

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l t

f Section 5 Page 5

l TABLE 5.0-B DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 1998 CitOSS-CllECK llESULTS FOR ENilAD 1 AllORATORIES 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"I Pass" indicates that one analysis of the cross-check was performed.

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 3/2/98 Q981GWS Cr-S i 4.03 - 7.14 E4 5.37 E4 5.26 E4 3 Pass Mn 54 2.12 - 3.77 E4 2.83 E4 2.80 E4 3 Pass Fe-59 1.73 3.07 E4 2.31 E4 2.35 E4 3 Pass Co-60 1.34 2.37 E 4 1.78 E4 1.72 E4 3 Pass Zn-65 2.28 - 4.04 E4 3.04 E4 3.03 E4 3 Pass Cs-134 1.32 2.34 E4 1.76 E4 1.63 E4 3 Pass Cs 137 2.51 - 4.45 E4 3.34 E4 3.16 E4 3 Pass Cc-141 1.35 - 2.40 E4 1.80 E4 l.79 E4 3 Pass 5/26/98 Q9820WR Mn 54 1.98 - 3.50 E2 2.64 E2 2.95 E2 3 Pass Fe-59 0.35 - 1.39 E2 6.92 E l 9.64 E l 3 Pass Co-60 1.46 - 2.58 E2 1.94 E2 2.10 E2 3 Pass 2n 65 2.01 - 3.57 E2 2.68 E2 2.98 E2 3 Pass Cs-134 137 - 2.44 E2 1.83 E2 1.98 E2 3 Pass Cs-137 2.80 - 4.97 E2 3.74 E2 3.95 E2 3 Pass Ce-141 2.48 - 4.40 E I 3.31 E I 0.00 EI 3/3 Low 8/lEhh Q9830W I L Cr 51 4.83 H.56 E4 6.43 E4 6.54 E4 3 Pass Mn 54 0.85 1.50 E4 1.13 E4 1.18 E4 3 Pass Fe 59 1.16 - 2.05 E4 1.54 E4 1.62 E4 3 Pass Co-60 158 2.81 E4 2.11 E4 2.13 E4 3 Pass Zn 65 2 27 4.03 E4 3.03 E4 3.21 E4 3 Pass Cs-134 0.89 1.57 E4 1.18 E4 1.10 E4 3 Pass Cs-137 1.41 - 2.50 E4 1.88 E4 1.80 E4 3 Pass Cc-141 3.30 - 5.85 E4 4.40 E4 4.43 E4 3 Pass 12/7/98 Q9840WR Cr-S i 0.67 - 1.18 E3 8 86 E2 1.04 E3 3 Pass Mn 54 1.43 - 2.54 E3 1.91 E3 1.97 E3 3 Pass Fe-59 4.52 8.02 E2 6.03 E2 6.67 E2 3 Pass Co-60 3.28 - 5 82 E3 4 38 E3 4.45 E3 3 Pass Zn 65 3.60 6.38 E3 4 80 E3 4.98 E3 3 Pass Cs-134 1.73 - 3.06 E3 2.30 E3 2.18 E3 3 Pass i

h 837 3.u3 5.37 E3 4.04 E3 3.90 E3 3 Pass Cc-141 0.68 - 1.21 E3 )

9.10 E2 9.17 E2 3 Pass secuon 5 Page 6

)

I

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 3/2/98 Q981GWS Cr 51 4.03 - 7.14 E4 5.37 E4 5.08 E4 3 Pass Mn 54 2.12 - 3.77 E4 2.83 14 2.81 E4 3 Pass Fe-59 1.73 - 3.07 E4 2.31 E4 2.38 E4 3 Pass Co-60 1.34 2.37 E4 1.78 E4 1.73 E4 3 Pass Zn-65 2.28 - 4.04 E4 3.04 E4 3.13 E4 3 Pass Cs-134 1.32 - 2.34 E4 1.76 E4 1.58 E4 3 Pass Cs-137 2.51 4.45 E4 3.34 E4 3.15 E4 3 Pass Cc 141 1.35 - 2.40 E4 1.80 E4 1.75 E4 3 Pass 8/19/98 Q9830W I L Cr S I 4.83 - 8.56 E4 6.43 E4 6.54 E4 3 Pass Mn 54 0.85 - 1.50 E4 1.13 E4 1.19 E4 3 Pass

_ Fe-59 1.16 2.05 E4 1.54 E4 1.68 E4 3 Pass Co-60 1.58 2.81 E4 2.11 E4 2.15 E4 3 Pass Zn-65 2.27 4.03 E4 3.03 E4 3.23 E4 3 Pass Us 134 0 89 - 1.57 E4 1.18 E4 1.11 E4 3 Pass Cs-137 1.41 2.50 E4 1.88 E4 f.82 E4 3 Pass Cc-141 3.30 5.85 E4 4.40 E4 4.46 E4 3 Pass 12/7/98 Q9840WR Cr-S I U.67 - 1.18 E3 8.86 E2 9.70 E2 3 Pass M n-54 1.43 2.54 E3 1.91 E3 1.94 E3 3 Pass Fe 59 4.52 8.02 E2 6.03 E2 6.36 E2 3 Pass Co-60 3.28 - 5.82 E3 4.38 E3 4.34 E3 3 Pass Zn-65 3.60 - 6.38 E3 4.80 E3 4.96 E3 3 Pass Cs-134 1.73 - 3.06 E3 2.30 E3 2.12 E3 3 Pass Cs 137 3.03 - 5.37 E3 4 04 E3 3.80 E3 3 Pass Ce-141 0.68 - 1.21 E3 9.10 E2 8.83 E2 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 3/2/98 Q981GWS Cr 51 4.03 - 7.14 E4 5.37 E4 5.07 E4 3 Pass Mn-54 2.12 - 3.77 E4 2.83 E4 2.84 E4 3 Pass Fe-59 1.73 - 3.07 E4 2.31 E4 2.39 E4 3 Pass Co-60 1.34 - 2.37 E4 1.78 E4 1.73 E4 3 Pass Zn-65 2.28 4.04 E4 3.04 E4 3.12 E4 3 Pass Cs-134 1.32 - 2.34 E4 1.76 E4 1.54 E4 3 Pass Cs-137 2.51 4.45 E4 3.34 E4 3.13 E4 3 Pass Cc 141 1.35 - 2 40 E4 1.80 E4 1.73 E4 3 Pass 8/19/98 Q9830W I L Cr-51 4.83 8.56 E4 6.43 E4 6.54 E4 3 Pass Mn-54 0 85 1.50 E4 1.13 E4 1.19 E4 3 Pass Fe 59 1.16 2.05 E4 1.54 E4 1.68 E4 3 Pass Co-60 1.58 2.8I E4

2. I I E4 2.15 E4 3 Pass Zn 65 2.27 - 4.03 E4 3.03 E4 3.23 E4 3 Pass Cs-134 0.89 - 1.57 E4 1.18 E4 1.11 E4 3 Pass Cs 137 1.41 - 2.50 E4 1.88 E4 1.82 E4 3 Pass Ce-l41 3.30 5.85 E4 4.40 E4 4.46 E4 3 Pass

)

Sechon $ Page 7

).

Gamma in Water 0.5 liter continued 12/7/98 Q9840% R Cr 51 0.67 - 1.18 E3 8.86 E2 1.06 E3 3 Pass Mn 54 1.43 2.54 E3 1.91 E3 2.06 E3 3 Pass Fe 59 4.52 - 8.02 E2 6.03 E2 6.66 E2 3 Pass Co-60 3.28 - 5 82 E3 4.38 E3 4.47 E3 3 Pass Zn 65 3.60 - 6.38 E3 4 80 E3 5.26 E3 3 Pass Cs-134 1.73 - 3.06 E3 2.30 E3 2.08 E3 3 Pass Cs-137 3.03 - 5.37 E3 4.04 E3 3.81 E3 3 Pass Cc-141 0.68 - 1.21 E3 9.10 E2 9.25 E2 3 Pass Gamma in Filter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/ total pCi/ total pCi/ total 2/20/98 Al0347 Cr-51 4.72 - 8.37 E4 6.29 E4 6.55 E4 3 Pass Mn 54 f.98 - 3.51 E4 2.64 E4 2.91 E4 3 Pass Fe-59 185 - 3.27 E4 2.46 E4 2.84 E4 3 Pass Co-60 1.22 2.17 E4 1.63 E4 1.72 E4 3 Pass Zn-65 2.15 3.80 E4 2.86 E4 3.29 E4 3 Pass Cs 134 1.22 2.15 E4 1.62 E4 1.47 E4 3 Pass Cs 137 2.30 - 4.07 E4 3.06 E4 3.10 E4 3 Pass Ce141 1.52 2.70 E4 2.05 E4 2.20 E4 3 Pass 6/11/98 E l443 37 Cr 51 0.96 1.70 E2 1.28 E2 1.42 E2 3 Pass Mn-54 0.77 1.37 E2 1.03 E2 1.18 E2 3 Pass Fe 59 3.30 - 5.85 El 4.40 El 5.42 El 3 Pass Co-60 1.05 1.86 E2 1.40 E2 1.53 E2 3 Pass Zn-65 0.89 - 1.58 E2 1.19 E2 1.47 E2 3 Pass Cs-134 0.69 - 1.22 E2 9.20 El 8.02 El 3 Pass Cs-137 5.18 - 9.18 El 6.90 El 7.14 E l 3 Pass Ce-141 0.73 - 1.29 E2 9.70 El 1.03 E2 3 Pass 12/10/98 E 162137 Cr-51 3.90 6 92 E2 5.20 E2 5.44 E2 3 Pass Mn 54 0.57 1.01 E2 7.60 El 9.05 El 3 Pass Fe-59 0.59 - 1.05 E2 7.90 E l 9.53 El I/3 liigh Co-60 0.71 - 1.26 E2 9.50 El 1.04 E2 3 Pass Zn-65 5.55 - 9.84 El 7.40 El 9.86 El I/3 High Cs-134 0.88 1.56 E2 1.17 E2 1.03 E2 3 Pass Cs-137 0.73 - 1.29 E2 9.70 El I.03 E2 3 Pass Cc-141 2.97 5.27 E2 3.96 E2 4.40 E2 3 Pass s_,. e,o

)

).

lodine In Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status WM KM WM 3/2/98 Q981LIW 1 1 131 5.50 9.75 El 7.33 El 9.06 E l i Pass 3/2/98

} 0981LlW 2 l l 131 l 0.00 - 0.00 EO l 0.00 EU l 0.00 EU l

l Pass 3/2/98 l Q981LlW-3 l l 131 l 0.98.l.73 El l 1.30 El l 1.78 El

)

l/ l liigh 8/19/98 l V983LIW1 l l-131 l

4.00 - 7.19 El l 5.41 El l 5.68 El l

1 Pass 8/19/98 l Q983LlW2 l l-131 l 0 84 - l.49 El l 1.12 El l 1.09 El l

1 Pass 8/19/98 l Q983LlW3 l l 131 l 2.40 - 4.26 El l 3.20 El l 3.10 E l l

1 Pass lodine In Milk Reference Sample I.D.

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

$/26/98 V982LIMI l 131 5.22 - 9.25 El 6.96 El 6.44 E l 3 Pass 5/26/98 l Q982 LIM 2 l 1 131 l 2.80 4.97 El l 3.74 El l 3.49 El l

3 Pass 5/2t/98 l 0982 LIM 3 l l 131 l 0.00 - 0.00 EO l 0.00 E0 l 0.00 LO l

3 Pass lodine Cartridge Reference Sample i.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 2/20/98 A10348 04 l 131 2.25 - 3.99 ES 3.00 E5 3.04 ES 3 Pass 6/ l l/98 l E 1444 37 l l 131 l 4.65 - 8.25 El l 6.20 El }

6.69 E l l

3 Pass 8/14/98 l All038 04 l l-131 l

1.47 2.61 E5 l 1.96 E5 l 2.10 E5 l

3 Pass 12/10/98 l E 1622-37 l l 131 l 0.60 - 1.06 E2 l 8.00 E l l 8.30 El l

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/I2/98 E1334 47 lieta 2.02 3.58 L2 2.69 E2 2.47 E2 3 Pass 9/24/98 l El547 37 l Beta l 1.49 - 2.63 E2 l 1.98 E2 l 2.07 E2 l

3 Pass i

Sechon 5 Page 9

)

Beta Smear Reference Sample 1.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/ total pCi/ total pCi/ total 2/20/98 A 4035 l-04 Beta 2.94 5.23 E3 3.92 E3 4.5 l E4 3 Pass 2/20/98 l A10352 04 l Beta l 3.30 - 5.85 E3 l 4.40 E3 l 4.22 E3 l

3 Pass Beta Smear Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status uCi/ total uCi/ total uCi/ total 8/l4/98 A l l041-04 Beta 4.92 - MJ2 E 3 6.56 E 3 6.05 E 3 3 Pass 8/14/98 l All042 04 l Beta l 0.60 - 1.06 E-2 l 7.93 E-3 l

6.87 E-3 l

3 Pass 8/14/98 l A11044 37 l Beta l 5.12 - 9.08 E-3 l 6.83 E-3 l

5.84 E 3 l

3 Pass 1

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 3/2/98 V98 t l WS-2 H3 1.04 - 1.85 E4 1.39 E4 1.59 E4 3 Pass 3/2/98 l 098 t i'WS-3 l H-3 l

0.00 - 0.00 EO l 0.00 EU l 0.00 EO l

3 Pass 5/26/98 l V9821WR2 l H-3

{

0.81 1.43 E3 l 1.08 E3 l 0.94 E3 l

3 Pass 5/26/98 l 09821'% R3 l H3 l

2.51 - 4.45 E3 l 3.35 E3 l 3.05 E3 l

3 Pass 8/19/98 l 0983I WRI l 11-3 l

2.85 5.05 E3 l 3.80 E3 l 3.36 E3 l

l Pass 8/l9/98

} 0983 i W R2 l 11-3 l

1.4 4 - 2.50 E3 l 1.88 E3 l 1.76 E3 l

1 Pass 8/19/98 l U983 i W R3 l 11 3 l

0.00 - 0.00 EU l 0.00 EO l 0.00 EO l

l Pass 12n/98 l V9841 WR 1 l ll-3 l

3.91 - 6.94 E3 l 5.22 E3 l 5.55 E3 l

3 Pass

)

Secnon 5 Page 10

)

TABLE 5.0-C STATE OF NORTil CAROLINA DEPARTMENT OF ENVIRONMENTAL IIEALTil AND NATURAL RESOURCES 1998 ENVillONSIENTAL DOSlalTElt CitOSS-CilECK ltESULTS State of Acceptance Cross-Check North Carolina Radiation Dosimetry & Records Criteria Date Delivered Value Reported Value (mR)

(mR)

+/- 10%

June 1998 6.00 El 5.64 E l

-5.93 December 1998 l

6.00 El l

5.71 El l

-4.82

)

Section 5 - Page iI

)

T i

6.0 REFERENCES

6.1 McGuire Selected License Commitments 6.2 McGuire Technical Specifications 6.3 McGuire Final Safety Analysis Review 6.4 McGuire Offsite Dose Calculation Manual l

6.5 McGuire Annual Environmental Operating Report 1979 - 1997 6.6 McGuire Annual Radioactive Effluent Release Report 1998 6.7 Probability and Statistics in Engineering and Management Science, Ilines 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 l

Evaluating Compliance with 10CFR50, Appendix I.

6.10 Radiological and Environmental Services Operating Procedures 1

6.11 RETDAS, Radiological Eftluent Tracking and Dose Assessment Software, Vertechs Version 3.4.1, Duke Power Revision # 2.0 Sechon 6 - Page i

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page I

(

)

i l

APPENDIX A

)

ENVIRONMENTAL SAMPLING AND

)

j 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.

)

Section A.1 of this appendix describes the environmental sampling frequencies and analysis

)

procedures by media type.

)

1. Cil ANGE OF SAMPI,1NG PitOCEDllitES

)

No sampling changes were made to the sampling procedure during 1998.

)

In the environmental program, the air deposition parameters (D/Q) are used to decennine air, broadleaf vegetation and milk sampling locations. McGuire's sectors with the three highest values did not change in 1998.

)

II. DESCIllPTION OF ANAINSIS PitOCEDtillES

)

I

)

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, silled to remove foreign objects (rocks, clams,

)

glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples

)

receiving gamma analysis are analyzed as duplicate analyses.

)

j Low-level iodine analyses are performed by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous l

sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses ate performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium Appenda A - Page 2

)

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

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

Ill. CilANGE OF ANALYSIS PROCEI)URES No analysis procedures were changed during 1998.

I V.

SAMPI.ING AND ANALYSIS PROCEDURES A,1 AIRHORNE PARTICULATE AND RADIOIODINE i

Airbome 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 radiciodines were collected in a charcoal cartridge situated 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 weekly gross beta analysis was perfomled on each filter and a weekly gamma analysis was performed on each charcoal cartridge. Filters were segregated by location and a quarterly gamma analysis was performed on the filter composite. The filter and charcoal cartridge were analyzed independently. The continuous composite samples were collected from the locations listed below.

Location 120 Site Boundary (0.5 mi. NNE)

=

Location 121 Site Boundary (0.5 mi. NE)

=

Location 125 Site Boundary (0.4 mi. SW)

=

Location 133 Comelius, NC (6.2 mi. NE)

=

Location 134 East Lincoln Junior High School (8.8 mi. WNW)

=

Location 192 Peninsula development (2.8 mi. NNE)

=

Location 195 Fishing Access Road (0.2 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 119 Mt. Holly Municipal Water Supply (7.4 mi. SSW)

=

Appenda A - Page 3

)

Location 132 Charlotte Municipal Water Supply (11.2 mi. SSE)

=

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

=

Location 194 East Lincoln Water Supply (6.7 mi. NNW)

=

A.3 StiltFACE WATEll 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 (0.4 mi. NE)

=

Location 131 Cowans Ford Dam (0.6 mi. WNW)

=

Location 135 Plant Marshall Intake Canal (11.9 mi. N)

=

A.4 Mll K 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 138 Henry Cook Dairy - COWS (3.1 mi. ESE)

=

Location 139 William Cook Dairy - COWS (2.5 mi. E)

=

Location 140 Kidd Dairy - COWS (2.8 mi. SSE)

=

Location 141 Lynch Dairy - COWS (14.8 mi. WNW)

=

A.5 IlitOAI)LE A F VEG ETATION Monthly samples were collected as available and a gamma analysio %

performed on each sample. The samples were collected from tLe locations !!sted below.

Location 120 Site Boundary (0.5 mi. NNE)

=

Location 125 Site Boundary (0.4 mi. SW)

=

Location 134 East Lincoln Junior High School (8.8 mi. WNW)

=

' Location 193 Site Boundary (0.2 mi. N)

=

A.6 FOOI) PPOI)tiCTS 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 Garden (2.8 mi N)

=

)

Appendix A. Page 4

)

A.7 FISil 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.

Location 129 Discharge Canal Entrance to Lake Norman (0.5 mi.ENE)

=

Location 137 Pinnacle Access Area (12.0 mi. N)

=

A.8 SilORELINE 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 (0.5 mi. ENE)

=

Location 130 Highway 73 Bridge Downstream (0.5 mi. SW)

=

Location 137 Pinnacle Access Area (12.0 mi. N)

=

A.9 DIRECT GAMMA RADIATION (TLD)

Thennoluminescent dosimeters (TLD) were collected quarterly at forty-nine locations. A gamma exposure rate was determined for each TLD. 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.

TLD locations are listed in Table 2.1-B.

Appendix A - Page 5

)

A.10 ANNilAI, l.ANI) iISE CENSilS 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 Meat Animal The Nearest Garden greater than 50 square meters or 500 square feet S

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

This census was initiated on June 15,1998 and completed on June 16,1998.

Results are shown in Table 3.10.

dj A

G

)

Appendix A - Page 6

)

J APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 1998 Appendix B - Page 1

Environmental Radiological Monitoring Program Summary Facility: $1cGuire Nuclear Station Docket No. 50-369,370 1.ocation: Slecklenburg County, North Carolina Report Period: Ol JAN-1998 to 31-DEC-1998 Medium or Type and lotal Lower Location with Highest

^ " ' " " '

Pathway Number Limit of Annual Mean "5

can ns Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses

"}

"#I "}

"#" ")

(LLD)

Measurement Performed Range Code Range Range Air Particulate 134 (pCi/m3)

(8.8 mi WNW)

DETA 36_4 1.00E-02 1.77E-2 (312/312) 133

._ l.86E-2 (52/52) 2.6_6E-2 (52/52_)

0 4.66E 4.1 l E-2 (6.2 mi NE) 7.54E 3.3 t E 2 5.84E 6.4 7E-2 CS 134__28 5.00E-02 0.00(0/24) 0.00 (0/4) 0_00 (0/4)

_ _ _,0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS 137 28 6 00E-02 0 00 (0/24) 0.00 (0/4) 0.00 (0/4) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 1-131 28 7.00E-02 0.00(0/24) 0.00 (0/4) 0.00 (0/4) 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 @ 3/22/99 810 AM Appendix 0 Page 2

)

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

50-369,370 Location: Mecklenburg County, North Carolina Report Period: Ol-JAN-1998 to 31 DEC-1998 yPe and Medium or Lower Location with Highest

"~

^ " ' " " '

"I'"'

Pathway Limit of Annual Mean

"'5 '

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

Unit of Analyses

"" ( ## "

"(

")

"(

")

(LLD)

Measurement Performed Range Code Range Range Air Radiciodine 134 (pCi/m3)

(8 8 mi WNW)

CS-134 364_ 5.00E-02 0.00 (0/3,12) 0.00 (0_/52) 0.00 (0_/52) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 364 6 00E-02 0 00(0/312) 0.00(0/52) 0.00(0/52) 0 0.00 - 0,00 0.00 - 0.00

_ 0.00 - 0.00 1-131 364 7.00E-0_2 0.00,(0/312) _

0.00 (0/52).._

0.00 (0/52)

.O 0.00 -j).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 @ 3/22/99 810 AM Appendix B - Page.1

)

)..

Environniental Radiological Monitoring Prograni Sumniary Facility: SicGuire Nuclear Station Docket No.

50-369,370 Location: Slecklenburg County, North Carolina lleport Period: Ol-JAN-1998 to 31-DEC-1998 Medium or Type and Total Lower Location with Highest Pathway Number Limit of Annual Mean "E "

Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses can ( mc n) c n

an ( aedon)

Mean (& action)

(LLD)

Measurement Performed Range Code Range Range Drinking Water 136 (pCi/ liter)

(12.7 mi NNE)

DALA 140 52 15 0.00 (0/39) 0.00(0/l3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 52 4

2.54(34/39) 132 2.75(10/13) 2.33 (13/13) 0 0.8 - 5.88 (11.2 mi SSE) 1.24-5.88 0.93 -3.84 CO-58 52 15 0.00 (0/39) 0.00(0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 -0.00 CO-60 52 15 0.00(0/39) 0 00(0/13) 0.00(0/I3) 0 0.00 0.00 0.00 - 0.00

_ 0.00 - 0.00 CS 134 52 15 0.00 (0/39) 0.00 (0/13) 0.00(0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 CS.I 37 52 I8 0.00(0/39) 0.00 (0/I3) 0.00(0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 52 30 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 11 3

_ 16 2000 248(3/12)

. _ 132

_ 268 (l/4) 0 00 (0/4) _

0 206 - 270 (l1.2 mi SSE) 268 - 268 0.00 - 0.00 1 131 52 i5 0.00 (0/39) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN 54 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 N B-95 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00_ _

0 00 - 0.00 _

ZN-65 52 30_, __, _0.00 (0 39) 0.00 (0/13) 0 00(0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 52 15 0.00(0/39) 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 specilled locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/22/99 810 AM Appendix B Page 4

)

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

50-369,370 Location: Alecklenburg County, North Caro lina Report Period: Ol-JAN 1998 to 31-DEC-1998 Location with Highest Medium or Type and Total Lower I

"'I"'

Pathway Number Limit of Annual Mean L cation Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses an a

n) e n

an ( acd n) ean racdon)

(LLD)

Measurement Performed Range Code Range Range Surface Water 135 (pCi/ liter)

(11.9 mi N)

BALA.I40_ _ 39 I 5_.

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/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 i5 0.00 (0/26) 0.00(0/13) 0.00 (0/I3) 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/I3) 0.00 (0/I3) 0 0.00 - 0.00

_ _ _ 0.00 - 0.00 _ _

0.00,_0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/I3) 0.00 (0/I3) 0 0.00 - 0.00 0.00 000 0.00 0.00 H-3 12 2000 285 (6/8) 128 340(3/4) 0.00 (0/4) 0 212 -385 (0.4 mi NE) 310 - 385 0.00 - 0.00 1_l31 39 _

15 0.00_(0/26) 0.00_(0/13)

_ 0.00 (0/l_3) 0 0.00 - 0.00 MN 54 39 15 0.00 (0/26) 0.00 - 0.00 0.00 - 0.00 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 0.00 000 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 specilled locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements

)

Report Generated @ 3/22/99 8.10 AM Appendn 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-1998 to 31 DEC 1998 No. of Non-Medium or Type and Total Lower Location with liighest g g; Control Routine Pathway Number Limit of Annual Mean

'E 'I cations Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses ean ( mt n) cation Mean (Raction)

Mean (Fmtion)

(LLD)

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

(14.8 mi WNW)

BALA-140 104 15

_ 0.00 (0/78) 0.00_ _(0/26) 0.00(0/26) 0 0.00 0.00 0.00 - 0.00 0.00 0.00 CE13_4 _

104 15 0.0_0(0/78).

0.00_(0/2_6_) _ __ _ 0.,0_0 (0/26) 0 0.00 -0.00 0.00 0.00 0.00 - 0.00 CS-l 37 104 I8 0.00 (0/78) 0.00 (0/26) 0.00(0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 l-13I I04 15 0.00_(0/78)__

0.00 (0/2_6).

0.00(0/26)

O_

0.00 - 0.00 0.00 - 0.00 0.00 0.00 LLI131 104 I

__0 00 (0/78) 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 Genered @ 3/22/99 8.10 AM Appenda B - Page 6

)

i 1

Environmental nausological Monitoring Program Summary l

Facility: McGuire Nuclear Station Docket No.

50-369,.370 Location: Mecklenburg County, North Carolina lleport Period: Ol-JAN 1998 to Ji-DEC 1998 Medium or Type and Total Lower Location with Highest AllIndicator Pathway Number Limit of Annual Mean

"*5 '

c tions Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses e n ( met n) c tion Mean (Fmetion)

Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Broadleaf 134 Vegetation (8.8 mi WNW)

(pCi/kg-wet)

CS-134 40 60 0.00 (0/30) 0.00 (0/10) 0.00 (0/10) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 40 80 0.00 (0/30) 0.00 (0/10) 26.9 (l/I0) 0 0.00 _000 0.00 _0.0_0

_. _ _2_6.9 - E 9 _

I13l_ _ _ _ 40 6_0__

0.00 (0/3_0)

O_00 (0/l0) 0.00 (0/10) 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 @ 3/22/99 8 09 AM Appenda B Page 7

)

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

50-369,370 1,0 cation: Mecklenburg County, North Carolina Report Period: OI-JAN-1998 to 31-DEC-1998 Medium or Type and Total Lower Location with Highest All Indicator Control Routme Pathway Number Limit of g

cations L cation Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses

'"" ' "}

"}

(LLD)

Measurement Performed Range Code Range Range Food Products No Control (pCi/kg-wet)

Location CS 134_

12 _ 60 0.00 (0/12)_

0.00_(0/12_)_.__0.00(0(0)___

0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-l37 12 80 0.00 (0/I2) 0.00(0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1 131 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements

't

)

Report Generated @ 3/22/99 810 AM Appendix B - Page 8

)

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

50 369,370 Location: Stecklenburg County, North Carolina Report Period: Ol-JAN 1998 to 31 DEC-1998 Medium or Type and Total Lower Location with Highest

^" " " '

"U"'

""5 Pathway Number Limit of Annual Mean

E "

Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses

")

"** ")

(LLD)

Measurement Performed Range Code Range Range Fish 137 (pCi/kg-wet)

(12.0 mi N)

CO-58 l2 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 32.1(1/6) 129 32.1(1/6) 0.00 (0.'6) 0 32.1-32.1 (0.5 mi ENE) 32.1 - 32.1 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 specined locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements

)

Report Generated @ 3/22/99 810 AM i

Appendix B Page 9

).

Environmental Radiological Monitoring Program Sumniary Facility: SicGuire Nuclear Station Docket No.

50-369,370 Location: Stecklenburg County, North Carolina Report Period: 01-JAN 1998 to 31 DEC-1998 Medium or Type and Total Lower Location with Ilighest

"~

All Indicator Pathway Number Limit of Annual Mean U" 5 c tions L cation Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses can rac n) ca n ean mc n) ean( raction)

(LLD)

Measurement Performed Range Code Range Range Shoreline 137 Sediment (12.0 mi N)

(pCi/kg-dry)

CO-60 6

0 52.I3(2/4) 129 52.I(2/2) 0.00 (0/2) 0 40.3 - 63.9 (0.5 mi ENE) 40.3 - 63.9 0.00 - 0.00 CS-l 34 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-l 37 6

I80 67.2(4/4) 130 99.7(2/2) 0.00 (0/2) 0 32.6 - 1 I I (0.5 mi SW) 89.0 - 1 I I O 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 4

)

Report Generated @ 3/22/99 810 AM Appendix B - Page 10

)

Environniental Radiological Monitoring Program Surninary Facility: SicGuire Nuclear Station Docket No.

50-369,370 Location: Stecklenburg County, North Carolina Report Period: Ol-JAN 1998 to 31 DEC-1998 Medium or rotal k.#

All Indicator Control ikoutin Limit of Annual Mean Pathway Sampled Number

" ' "8 cati n ep rt Detection Name, Distance, Direction of Meas.

^""'I

e n ( rac n) ca n e n ( rac n) ean( raction)

Unit of Measurement (LLD)

Performed Range Code Range Range Direct Radiation 175 TLD (15.5 mi WNW)

(mR/ standard quarter) 18_7 0.00E + 00 16.9 (l83/I83)

. _1_80

_26.9_(4/4)_ _ _.

21.7_(4/4)_

_0 8.2 32.2 (12.7 mi NNE) 23.7 - 32.2 18.7 - 23.6 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 Genera -. ' r. /22/99 810 AM Appendit e Wge 11

)

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C Page 1

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 C.1 SAMPLING DEVIATIONS Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power outage to sampling equipment due

_ 135 6/2 - 6/16/98 6/10 - 6/16/98 PI to downed power line.

Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power outage to sampling equipment due to construction. Power line was damaged and power to sampling equipment was 125 11/24 - 12/1/98 11/24 - l 1/29/98 PO lost.

Power outage to sampling equipment due to construction. Power line was damaged and power to sampling equipment was lost. Sampling resumed when line was 125 12/l - 12/8/98 12/2 - 12/8/98 PO restored.

)

Appenda C - Page 2

)

E C.2 UNAVAILAlll>E ANAL >YSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 16l 12/29/97 - 3/30/98 OT TLD missing. 2"4 Quarter TLD placed in tield.

TLD missing due to construction.

158 3/30 - 6/29/98 OT 3'd Quarter TLD placed in field.

TLD missing due to construction.

178 3/30 - 6/29'98 OT 3'd Quarter TLD placed in tield.

159 6/29 - 9/28/98 VN TLD missing. 4'" Quarter TLD placed in field.

179 6/29 - 9/28/98 VN TLD missing. 4'" Quarter TLD placed in field.

l Appendix C - Page 3

APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 1998 Radiological Environmental Monitoring Program ApppJix D. Page 1 1

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 1998. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

Appendix E - Page i

_ - _ _ _ _ - _ _ _ ___

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