ML20138H411
| ML20138H411 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/31/1996 |
| From: | Barron H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9705070171 | |
| Download: ML20138H411 (125) | |
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DukeIbn er Company H IL Be:kn ~;
AkGuire Nackar Generation th partment lice haiknt. ;
k 127th1Hagers Ferry hbad(AIGollP) *
' (>l)854km Huntersriik, NC230MBIO (M1)M34809 Far c
- i. l l~ . DUKEPOWER I j
, April 29,'1997 i
U. S. Nuclear Regulatory Commission ,
i Attention: Document Control Desk '
Washington, D.C. 20555 ,
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Subject:
McGuire Nuclear' Station l 4 e Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report
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j Please find attached the .McGuire Nuclear Station Annual Radiological a Environmental Operating Report for 1996 pursuant to McGuire Unit 1 and Unit 2 ,
Technical Specification 6.9.1.6.
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.i Questions with respect to this report should be directed to Kay Crane, at (704)
- 875-4306. i Very truly yours, j f !
! .H. B. Barron, Vice President j McGuire Nuclear Station i
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l ANNUAL RADIOLOGICAL !
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ENVIRONMENTAL OPERATING REPORT :
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DUKE POWER COMPANY i
i MCGUIRE NUCLEAR STATION i Units 1 and 2 l
i l January 1 - December 31 l
t-l 1996 I
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b i TABLE OF CONTENTS i
TITI F. PAGE i
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4 List of Figures . . . . . . . . . . . . iv List of Tables . . . . . . . . . . . . . v i ;
4 List of Acronyms. . . . . . . . . . . . . vi 5 '
4
- 1. Executive Summary . . . . . . . . . . . . 1-1 1 2. Introduction . . . . . . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . . . . . 2-1 t
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- 2.2 Scope and Requirements of Environmental Monitoring Program . 2-1 2.3 Statistical and Calculational Methodology . . . . . . 2-2
- 2.3.1 Estimation of the Mean Value . . . . . . . 2-2
.' 2.3.2 Lower Level of Detection, Minimum Detectable Activity, 4
, and Critical Level . . . . . . . . 2-3 2.3.3 Trend Identification . . . . . . . . 2-3 1
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- 3. Radiological Environmental Monitoring Program - Discussion, l
Interpretation, and Trending of Results . . . . . . . 3-1 3-3 I 3.1 Airborne Radioiodines and Particulates . . . . . .
3.1.1 Radiciodines. . . . . . . . . . . 3-3 Particulates . 3-5 3.1.2 . . . . . . . . . .
! 3.2 Drinking Water . . . . . . . . . . . . 3-7 3-9 3.3 Surface Water . . . . . . . . . . . .
3-11 3.4 Milk . . . . . . . . . . . . . .
3.5 BroadleafVegetation. . . . . . . . . . . 3-13 3-15 3.6 Shoreline Sediment . . . . . . . . . . .
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3.7 Fish . . . . . . . . . . . . . 3-17
' i 3.8 Direct Gamma Radiation. . . . . . . . . . 3-19 '
3.9 Food Products . . . . . . . . . . . . 3-21 -
3.10 Land Use Census . . . . . . . . . . . 3-23 !
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. 4. Evaluation of Dose from Environmental Measurements Verses !
Estimated Dose from Releases . . . . . . . . . 4-1 4.1 Dose from Environmental Measurements 4-1 f
4.2 Estimated Dose from Releases . . . . . . . . . 4-1 ;
4.3 Comparison of Doses . . . . . . . . . . . 4-1 ,
1 4.4 Pathway Dose Calculations . . . . . . . . . 4-2 .
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- 5. Quality Assurance . . . . . . . . . . . 5-1 ;
5.1 Duke Power Company Environmental Laboratories . . . . 5-1 5.2 Contractor Laboratories . . . . . . . . . . 5-3 !
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- 6. References . . . . . . . . . . . . . . 6-1 Appendix A: Environmental Sample and Analysis Procedures - Summary . A-1 I. Change of Sampling Procedures . . . . . . . . A-1 II. Description of Analysis Procedures . . . . . . . . A-1 Ill. Change of Analysis Procedures. . . . . . . . . A-2 IV. Sampling and Analysis Procedures . . . . . . . . A-2 A.1 Airbome Paniculate and Radioiodines . . . . . . A-2 A.2 Drinking Water . . . . . . . . . . . A-3 A.3 Surface Water . . . . . . . . . . A-3 A.4 Milk . . . . . . . . . . . . A-3 A.5 BroadleafVegetation . . . . . . . . . A-3 A.6 Shoreline Sediment . . . . . . . . . . A-4 A.7 Fish . . . . . . . . . . . . . A-4 li
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l A.8 Direct Gamma Radiation (TLD) . . . . . . . A-4 l
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l A.9 Food Products . . . . . . . . . . . A-5 !
A.10 Annual Land Use Census . . . . . . . . A-5 l
.V. ProgramImprovements . . . . . . . . . . A-6 i
Appendix B: Radiological Environmental Monitoring Program - Results Summary j Air Particulate . . . . . . . . . . . . . B-1 !
i l Air Radioiodines . . . . . . . . . . . . . B-2 i l \
Broadleaf Vegetation . . . . . . . . . . . . B-3 '
t l Food Products . . . . . . . . . . . . . B-4 l l :
- Drinking Water . . . . . . . . . . . . . B-5 !
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! Fish. . . . . . . . . . . . . . . . B-6 L- !
! Milk . . . . . . . . . . . . . . . B-7 Shoreline Sediment B-8 1 l
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! l l Surface Water . . . . . . . . . . . . . B-9 l Direct Gamma Radiation (TLD) . . . . . . . . . B-10 l l ,
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Appendix C: Sampling Deviations and Unavailable Analyses l C.1 Sampling Deviations . . . . . . . . . . C-1 C.2 Unavailable Analyses . . . . . . . . . . . C-3 I
Appendix D: Analytical Deviations - Lower Limits of Detection . . . D-1 Appendix E: Radiological Environmental Monitoring Program Results . . E-1 i
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9 LIST OF FIGURES i
FIGUIE TITI.E PAGE 2.1-1 Sampling Locations Map (Site Boundary). . . . . . 2-7 2.1-2 Sampling Locations Map (Ten Mile Radius) . . . . . 2-8 :
3.1.1 Concentration ofI-131 in Airborne Radioiodines . . . . 3-3 :
i 3.1.2 Gross Beta Concentration Airborne Particulates . . . 3-5 3.2-1 Concentration of Tritium in Drinking Water . . . . . 3-7 3.2-2 Gross Beta Concentration in Drinking Water. . . . . 3-8 3.3 Concentration of Tritium in Surface Water . . . . . 3-9 3.4 Concentration of Cs-137 in Milk . . . . . . . 3-11 3.5 Concentration of Cs-137 in Broadleaf Vegetation. . . . 3-13 3.6-1 Concentration of Cs-137 in Shoreline Sediment . . . . 3-15 3.6-2 Concentration of Co-60 in Shoreline Sediment . . . . 3-16 3.7-1 Concentration of Cs-137 in Fish . . . . . . 3-17 3.7-2 Concentration of Co-60 in Fish. . . . . . . . 3-18 3.8 TLD Exposure from Direct Radiation . . . . . 3-19 3.9 Concentration of Cs-137 in Food Products . . . . . 3-21 3.10 Land Use Census Map . . . . . . . 3-26 IV
LIST OF TABLES
- TABLE TITLE PAGE j 2.1-A Radiological Monitoring Program Sampling Locations . . 2-5 2.1 -B Radiological Monitoring Program Sampling Locations (TLD) . 2-6 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . . . . . . . 2-9
. 2.2-B REMP Analysis Frequency . . . . . . . 2-10
) 2.2-C Lower Limit of Detection Capabilities for Environmental Sample Analysis . . . . . . . . . . 2-11 3.1.1 Concentration of Radionuclides in Airborne Radioiodines . . 3-4 3.1.2 Concentration of Radionuclides in Airborne Particulates . . 3-6 3.2 Concentration of Radionuclides in Drinking Water . . . 3-8 3.3 Concentration of Radionuclides in Surface Water. . . . 3-10 3.4 Concentration of Radionuclides in Milk . . . . . . 3-12 3.5 Concentration of Radionuclides in Broadleaf Vegetation . . 3-14 3.6 Concentration of Radionuclides in Shoreline Sediment . . 3-16 3.7 Concentration of Radionuclides in Fish . . . . . . 3-18 3.8 TLD Exposme from Direct Radiation . . . . . . 3-20 3.9 Concentration of Radionuclides in Food Products . . . 3-22 3.10 Land Use Census Results . . . . . . . . . 3-24 4.1-A 1996 Environmental and Effluent Dose Comparison for Liquid and Gaseous Waste Release Pathways . . . . 4-3 4.1 -B Maximum Individual Dose Summary for 1996 . . . . 4-5 5.0-A Duke Power Company Interlaboratory Comparison Program . 5-4 5.0-B State of North Carolins DEHNR 1996 Environmental Dosimeter Cross-Check Results . . . . . . . 5-7 C.1 Sampling Deviations . . . . . . . . . . C-1 C.2 Unavailable Analyses . . . . . . . . C-5 Y
LIST OF ACRONYMS .
Acronyms and their interpretations used in this report (displayed alphabetically)
ACRONYM DEFINITION BW BiWecidy C Control CL Critical Level DEHNR Depanment of Environmental Health and Natural Resources DHEC Depanment of Health and Environmental Control EPA Environmental Protection Agency
- LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual )
pCi/kg picocurie per kilogram pCill picoeurie per liter pCi/m3 picoeurie per cubic meter Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually l
SLCs Selected Licensee Commitments SM Semimonthly '
TECH SPECS Technical Specifications TLD Thermoluminescent Dosimeter pCi/mi microcurie per milliliter UFSAR Updated Final Safety Analysis Repon W Weekly vi
i 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 1996.
Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.
Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLC's). Required analyses were performed and detection capabilities were met for all samples as required by SLC's. Supplemental analyses were performed for some media for additional information. Twelve-hundred thirty-two samples were analyzed comprising 3778 test results in order to compile data for the 1996 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 1996 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 monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 7.10E-02 mrem for 1996. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.
section 1 - Page 1
2.0 INTRODUCTION
1 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of the highly industrialized l region on the Carolinas. The land is predominantly rural non-farm with a small amount of I land being used to support beef cattle and farming. Recreation in the area is confimed mostly to the lake and shores of Lake Norman and Mountain Island reservoir. The McGuire site is in noithwestern 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 ,
J north by 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Hydroelectric Station , which is located inunediately 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 Norman, 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 Monitoring Program. Figures 2.1-1 and 2.1-2 illustrate these locations as compared to McGuire Nuclear Station.
2.2 SCOPE AND REQUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM i An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to operation of Unit 1 in 1988. The preoperational program provides data on the existing emironmental 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" en ironmental 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 section 2 - Page i
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l surveillance of all appropriate critical exposure pathways to man and protects vital interests i of the company, public, and state ar.d federal agencies concemed with the environment. !
I Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A.
Table 2.2-B lists the REMP analysis and frequency schedule.
The Annual Land Use Census, required by Selected Licensee Commitments, is performed to i ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.10.
Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides fe-independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A sununary of the results obtained as part of this comparison program are in Section 5 of this annualreport.
2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):
N 51 F= <-
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.
Section 2 Page 2
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.
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 apriori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The " required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.
MDA - The MDA may be thought of as an " actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.
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. )
I 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 emironment due to the operation of the nuclear i station. Visual inspection of tabular or graphical presentations of data (including !
preoperational) is used to determine if a trend exists. Since nuclear reactor operations i do not remove radioactivity from the surrounding environment, a decrease in a l
particular radionuclide's concentration in an environmental medium does not indicate l that reactor operations are removing radioactivity from the environment but that l reactor operations are not adding that radionuclide to the emironment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.
section 2 - Page 3
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\ l l Substantial increases or decreases in the amount of a particular radionuclide's release i from the nuclear plant will greatly affect the resulting environmental levels; therefore,
- j. a knowledge of the release of a radionuclide from the nuclear plant is necessary to j completely interpret the trends, or lack of trends, determined from the environmental ,
j data. Some factors that may affect environmental levels of radionuclides include '
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prevailing weather conditions (periods of drought, solar cycles or heavier than normal l precipitation), construction in or around either the nuclear plant or the sampling j location, and addition or deletion of other sources of radioactive materials (such as the 2
Chernobyl accident). Some of these factors may be obvious while others are i sometimes unknown. Therefore, how trends are identified will include some 1 ~ judgment by plant personnel.
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TABLE 2.1-A MCGUIRE RADIOLOGICAL MONITORING PROGRAM ,
SAMPLING LOCATIONS TABLE 2.1-A CODES W Weekly SM Semimonthly l BW Biweekly j Q Quarterly M Monthly SA Semiannually )
C Control l Site ' '--
Location Description
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, "a r".*,t w.= ' w.w- ca-- en,"s tt vas 119 Mt. Holly Municipal Water Supply ( 7.4 mi SSW ) ,
BW i20 Site Boundary ( 0.5 mi NNE I W i 121 Site Boundary ( 0.5 mi NE ) W M(b) 125 Site Boundary ( 0.4 mi SW ) W 128 Discharge Canal Bridge ( 0.4 mi NE ) M(b)
BW 129 Discharge Canal Entrance to Lake Norman ( 0.5 mi ENE) SA SA I 130 Hwy 73 Bridge Downstream ( 0.5 mi SW )
SA 131 i Cowans Ford Dam ( 0.6 mi WN W ) BW !
132 Charlotte Municipal Water Supply ( l I .2 mi SSE ) BW 133 Cornelius ( 6,2 mi NE ) W 134 C East Lincoln Jr.High School ( 8.8 mi WNW ) W 135 C Plant Marshall intake Canal ( l I .9 mi N )
M(b)
BW 136 C Mooresville Municipal Water Supply ( 12.7 mi NNE ) BW 137 C Pinnacle Access Area ( 12.0 mi N ) SA SA 138 Henry Cook Dairy ( 3.1 mi ESE )
SM i39 William Cook Dairy ( 2.5 mi E )
SM 140 Kidd Dairv-Cows ( 2.7 mi SSE ) SM 141 C Lynch Dairy-Cows ( 14.8 mi WNW )
SM i88 5 mile radius Gardens ( 2.8 mi N ) M(a )
192 Peninsula ( 2.8 mi NNE ) W 193 Site Boundary ( 0.2 mi N )
194 East Lincoln County Water Supply ( 6.7 mi NNW )
M(b) l BW 195 Fishing Access Road ( 0.2 mi N ) W (a) During Harvest Season (b)When Available TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM Section 2 - Page 5
TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
S;'e Location Description : Sp Location Description
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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 145 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 rues E 171 4-5 MILE RADIUS 4.0 miles NW 148 SITE BOUNDARY 0.5 ud:s ESE 172 4-5 MILE RADIUS 5.7 miles NNW 149 SITE BOUNDARY 0.5 f.les SE 173 SPECIAL INTEREST 8.4 miles NNW 151 SITE BOUh0ARY 0.4 miles S 174 SPECIAL 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 SPECIAL INTEREST 11.0 miles SW 154 SITE BOUNDARY 0.5 miles W 177 SPECIAL INTEREST 8.8 miles S I' 156 SITE BOUNDARY 0.5 miles WNW 178 SPECIAL INTEREST 9.3 miles SE 189 SITE BOUNDARY 0.4 miles SSE 179 SPECIAL 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 SPECIAL INTEREST 7.0 miles NE 158 4-5 MILE RADIUS 4.3 miles NNE 182 SPECIAL INTEREST 6.2 miles NE 159 4-5 MILE RADIUS 5.0 miles NE 183 SPECIAL INTEREST 3 5.8 miles S
- 160 4-5 MILE RADIUS 4.9 miles ENE 186 SPECIAL INTEREST 0.2 miles NNW I 161 4-5 MILE RADIUS 4.7 miles E 187 SPECIAL 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 1% SPECIAL INTEREST 1.0 miles S i 164 4-5 MILE RADIUS 4.6 miles SSE 197 SPECIAL INTEREST 1.1 miles S
- 165 4-5 MILE RADIUS 5.1 miles S 198 SPECIAL INTEREST 1.3 miles S 166 4-5 MILE RADIUS 5.3 miles SSW 199 SPECIAL INTEREST 1.5 miles S i
- All TLDs are collected quarterly i
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.- I# de , . 56.25' c i7s .
172') ;pgq , ~ __ _
261 % 170 #
W . . Uncoln Co. 69 , d f e
^ 138 162 h
7 ,c,,.
- ^
1e g\.25*/
236 caenCa t
1es.
/'
g j
~
, 178
.m 123.7s*
\
_ [ 176 \ 339 i. s n me Q / -'
\
A L
, 1
} r }
213.wp 4 3 / 191.E
_ mo - / //
- 1 ( 188.b*""P' '
h
. nn - -
A M Other Locations N
L Sttan 2 . Py H
TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Ebalysis Water Air Particulates Fish Milk (pCi/ liter) Broadleaf orGases (pCi/kg-wet) (pCi/ liter) Vegetation (pCi/m')
113 20,000 (pCi/kg-wet)
Mn54 1,000 30,000 Fe59 400 10,000 CoS8 1,000 30,000 Co60 300 10,000 Zn65 300 20,000 Zr Nb-95 400 1131 2 1 3 100 Cs134 30 10 1.000 60 1,000 Cs137 50 20 2,000 70 2,000 Ba La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of30,000pCi/ liter may be used.
Section 2 Page 9
l TABLE 2.2-B REMP ANALYSIS FREQUENCY SAMPLE ANALYSIS GAMMA TRITIUM LOW GROSS TLD MEDIUM SCHEDULE ISOTOPIC LEVEL BETA I-131 Air Radioiodine Weekly X Air Weekly X Particulates Quarterly X 4
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 10
TABLE 2.2-C LOWER LIMIT OF DETECTION (LLD)
CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS
- Air-Analysis - Water Particulates Fish ' Milk BroadLeaf ) Sediment (pCi/ liter) or Gases (pCi/kg-wet) (pCi/ liter) Vegetation (pCi/kg-dry)-
- (pCi/m') (pCi/kg wet)
Gross Beta 4 H3 2000 "'
Mn54 15 130 Fe59 30 260 CoS8,60 15 130 Zn65 30 260 Zr Nb-95 15 II31 1"" 0.07 1 60 Csl34 15 0.05 130 15 60 150 Csl37 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) Ifno drinking waterpathway exists, a value of3000pCi/ liter may be used.
(b) Ifno drinking waterpathway exists, the LLD ofgamma isotopic analysis may be used.
3 Secuon 2. Page iI
3.0 RADIOLOGICAL 1 ENVIRONMENTAL MONITORING PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS This section pmvides a summary and review of all 1996 REMP analysis resuks to detect and identify changes in environmental levels as a resuh of station opemtion. The radionuclides with Selected Licensee Commitments reponing levels that indicate consistent detectable activity have been historically trended from preoperation to present. Analyses from 1977 -
1978 have been excluded since these resuhs were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses fmm 1981 were combined with the operational analyses fmm the latter pan of 1981 and avemged to give one concentration for each radionuclide for that year.
The highest annual mean concentmtion of applicable Selected Licensee Commitments radionuclkies fmm the indicator locations for each media type was used for trending purposes. Trending was performed by comparing annual mean concentrations to historical resuks. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the radionuclide's NRC reponing level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level. The highest value reached during 1996 was 8.65% for surface water tritium at the discharge canal (Location 128). Only Selected Licensee Commitments radionuclides were detected in 1996.
Changes in sample location, analytical technique, and presentation of resuks must be considered when reviewing for trends. Cakulation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net resuhs (sample minus background) positive and negative, were included in the calculation of the mean. Only positive net activity resuhs were used to calculate the mean for the other years.
All negative values were replaced with a zero for calculational and graphical purposes to pmperly represent environmental conditions. A change in gamma spectmscopy 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 metixxl the previous system used to estimate net activity may have been vulnerable to false-positive resuks.
Secton 3-Page ;
l l
1 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 kss 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 1996. Sinularly, there was no signifcant increase in ambient background radiation levels in the sunnunding areas. The 1996 land use census data, shown in Section 3.10, mdicates that no program changes are required as a resuk of the census.
k, 6
settson 3.Pagre2
3.1 AIRBORNE RADIOIODINES AND PARTICUlATES I 3.1.1 RADIOIODINES In 1996,364 radiciodine samples were analyzed,312 at six indicator locations and 52 at the contmllocation.
No detectable I-131 activity in environmental air samples was found in 1996. Cs-137 was found in three indicator samples, llowever, no Cs-137 was found on the contsponding particulate likers. An investigation perfonned in 1990 concluded that Cs-137 activity detected only on the caitridges was not attributed by station effluents but was an active constituent of the charcoal media (irference 6.5). Therefore, the Cs-137 activity was not used to calculate doses.
Figure 3.1.1 shows I-131 highest annual mean indicator and control location concentmtions with comparisons to 5% of the repoiting level. Table 3.1.1 gives indicator location highest annual means and control means since 1979 for I-131. Piroperational and seventeen year averages are also shown. No 1-131 activity has been detected since 1989. Since no mdionuclides were detected in 1996, no repoiting levels were appmached.
FIGURE 3.1.1 PCum CONCENTRATION OF l-131 IN AIRBORNE RADIOlODINES 6 00E@
6% CF REF ORTI40 LEVEL 6.00EW 4 00E@
3.00EM 2.00E-02 1.00E 02
/-
0.00E+00 1
\ - - - - - - - .
Year l*h1318ndicator *F131 Control l Secthm 3 -Page 3 l
l Table 3.1.1 Concentration of Radionuclidesin Airborne Radiolodians YEAR I 131 Indicator (pCihn') I-131 Control (pCi/m')
1979* 3.28E-3 1.04E-3 1980* 2.01 E-3 1.10E-3 1981* 4.17E-3 6.27E-4 1982* 1.42E-3 2.48E-3 1983* 1.99E-3 2.01 E-4 1984 3.17E-3 0.00E0 1985 3.15E-3 1.04E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.00E0 0.00E0 1989 2.18E-2 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 17 Year Average 3.79E-3 1.13E-3 1996 0.00E0 0.00E0
- Radiciodines and Particulates analyzed together.
I Scotum 3.Page 4
3.1.2 PARTICULATES In 1996,364 puticulate samples were analyzed for giuss beta,312 at the six indicator locations and 52 at the control location. Gamma analysis was perfonned on 28 samples,24 at the six indicator locations and four at the control location.
Per Selected Licensee Commitments, if giuss beta in air particulate samples is greater timn ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on individual samples. As in previous yeais, the location with the highest mean (3.1 lE-2 pCi/m') in 1996 was less than ten times the yearly mean of the control location (5.49E-2 pCi/m').
Therefore, gamma isotopic analysis was performed quatterly on composite paiticulate filteis. No detectable gamma emitting paiticulate activity has been found in enviiunmental air samples since 1987.
Figuie 3.1.2 shows gross beta highest annual mean indicator and control location concentmtions since 1985. 'Ihese is no reporting level for giuss beta. Table 3.1.2 shows indicator and contiul location highest annual means for Cs-137 and giuss beta. Picoperational data and previous yeais' avemges aie also shown. Since no gamma activity was detected in 1996, no reposting levels weie approached.
FIGURE 3.1.2 pol /mi GROSS BETA CONCENTRATION IN AIRBORNE PARTICULATES 1.00E 01 9.00E @
8.00E G 7.00E @
6.00E@ /\
6.00EW /A\ #
4 00E-02 # \\ /
3.00E@ 1 \\ /
.- Mk 2.00EM 1.00E @
0.00E+00 1985 1986 1957 1968 1989 1990 1991 1992 1 A33 1994 1995 1996 Year l *Oroes Beta Indicator *Oross Beta Controf l secten 3.Page5
Table 3.1.2 Concentmtion of Radionuclides in Airborne Particulates YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCi/m') (pCi/m') (pCi/m') (pCi/m')
1979* 4.40E-3 1.47E-3 ** **
1980* 6.70E-3 4.53E-3 ** **
1981* 6.I6E-3 5.32E-3 ** **
1982* 3.82E-3 2.29E-3 ** **
1983* 2.93E-3 3.21 E-3 ** **
1984 1.74E-3 8.29E-4 ** **
1985 1.86E-3 1.32E-3 2.44E-2 2.40E-2 1986 4.98E-3 3.03E-3 2.64E-2 2.52E-2 1987 1.07E-2 7.91 E-3 2.54E-2 2.59E-2 1988 0.00E0 0.00E0 7.49E-2 5.5 i E-2 1989 0.00E0 0.00E0 2.22E-2 2.14E-2 1990 0.00E0 0.00E0 2.58E-2 2.37E-2 1991 0.00E0 0.00E0 2.16E-2 2.15E-2 1992 0.00E0 0.00E0 1.92E-2 2.02E-2 1993 0.00E0 0.00E0 1.93E-2 2.04E-2 1994 0.00E0 0.00E0 2.28E-2 2.02E-2 1995 0.00E0 0.00E0 3.02E-2 5.17E-2 Average 2.55E-3 1.76E-3 2.84E-2 2.82E-2 1996 0.00E0 0.00E0 3.11E-2 5.49E-2
- Radiciodines and Paiticulates analyzed together.
- Gross Beta analysis not performed Sectum 3 Page6
l 3.2 DRINKING WATER In 19%,52 drinking water samples were analyzed for gross beta and gamma emitting radionuclides. Thirty-nine samples were from the three indicator locations and 13 fmm the contml location. Tritium (H-3) analyses were performed on 16 composite samples, 12 at indicator locations and four at the control location. Low-level iodine analysis was not petformed since the dose for consumption of water was less than one mrem per year, historically and for 1996.
No detectable gamma activity was found in drinking water samples in 1996 and has not been detected since 1987. Gross beta analyses indicated 2.75 pCi/l at the location with the highest annual mean and 2.11 pCUI at the control location. Tritium was detected in seven of the 1.2 indicator composite samples taken in 1996 with the highest annual mean resulting in only 1.80% of the repoiting level.
Figure 3.2-1 shows tritium highest annual mean indicator and control location concentrations with comparisons to 10% of the reporting level. Figum 3.2-2 shows gross beta highest annual mean indicator and control location concentrations. Them is no trponing level for gross beta. Table 3.2 gives indicator location highest annual means and control means since 1979 for tritium and gross beta. Preoperational and seventeen year averages are also shown.
FIGURE 3.21 pculiter CONCENTRATlON OF TRITlUM IN DRINKING WATER 2500 10% OF REPORTNG LEUEL 2000-1500 1000 ,
M AkA m f, -
0 . . ..
5 H E R R iE ! R H E aiH E i E E l*H-3 Indicator *H4 Control l s w . 3.nig
l I
FIGURE 3.2 2 peittiter GROSS BETA CONCENTRATION IN ,
DRINKING WATER e
6.5 4.5
. A n
,, Lt\ /\
, 7 \\ h(\
,, A A / T Ad7 \1
' 7T\
Mr yr
/ \ ww/ -
N//y
\
1.5 1
0.6 0
E 3
i H
E i
E I y, , , . .
E E
if E
i I
I-l .- a,. .. .. . . .. , -.- a ,... . o. . I Table 3.2 Concentration of Radionuclides in D inking Water YEAR II 3 Indicator 11-3 Control Beta Indicator Beta Control (pCIM) (pCIM) (pCiM) (pCIM) 1979 1.65E2 1.50E2 2.40E0 2.03E0 1980 1.63E2 2.05E2 2.34E0 1.87E0 1981 1.88E2 1.78E2 2.79E0 2.41E0 1982 2.43E2 1.45E2 2.62E0 2.43E0 1983 2.65E2 1.45E2 1.80E0 1.87E0 1984 5.77E2 2.45E2 2.78E0 1.81E0 1985 5.93E2 4.00E2 1.88E0 1.90E0 1986 1.14E3 4.37E2 2.13E0 2.15E0 1987 1.35E3 7.75E2 2.30E0 2.00E0 1988 9.92E2 7.I iE2 2.00E0 2.00E0 1989 5.62E2 0.00E0 2.80E0 2.70E0 1990 7.32E2 6.11E2 3.70E0 4.30E0 1991 5.22E2 0.00E0 2.40E0 2.50E0 1992 6.73E2 0.00E0 2.00E0 1.70E0 1993 0.00E0 0.00E0 2.80E0 2.40E0 1994 0.00E0 0.00E0 2.47E0 2.90E0 1995 3.58E2 0.00E0 4.20E0 3.30E0 17 Year Average 5.01E2 2.35E2 2.55E0 2.37E0 1996 3.60E2 0.00E0 2.75E0 2.1lE0 Sectum 3 Page8
3.3 SURFACE WATER in 1996,39 surface water samples were analyzed for gamma emitting radionuclides,26 at the two indicator locations and 13 at the contml location. Analyses for 11-3 were performed on 12 samples, eight at indicator locations and four at the control location.
No detectable gamma activity was found in surface water samples in 1996 and has not been detected since 1988. Tritium was detected in the eight indicator composite samples taken in 1996 with the highest annual mean resulting in only 4.04% of the repoiting level.
Figure 3.3 shows tritium highest annual mean indicator and control location concentrations with comparisons to 20% of the reponing level. Table 3.3 gives indicator and contml location highest annual means since 1979 for 11-3. Preoperational and seventeen year avemges are also shown.
FIGURE 3.3 polniter CONCENTRATION OF TRITlUM IN SURFACE WATER 4500 20%0F REPORTNO LUVEL 4000.
3500 3000 2500- ~
2000 t500 /\
t000 / \ gg
, , ) A % M /
, <**(/ \ \/
k 5
E k
k k
k 5
E k $ h k Year l+H4 Indlostor **"*H-3 Control l Secthm 3. rage 9
Table 3.3 Concentration of Radionuclides in Surface Water YEAR 113 Indicator (pCi/l) 113 Control (pCi/l) 1979 1.85E2 1.66E2 1980 2.13E2 1.93E2 1981 1.75E2 1.70E2 1982 3.30E2 1.23E2 1983 5.75E2 3.67E2 1984 4.10E2 2.65E2 1985 7.33E2 0.00E0 1986 2.33E3 6.13E2 1987 9.20E2 7.70E2 1988 9.40E2 0.00E0 1989 8.22E2 0.00E0 1990 6.77E2 0.00E0 1991 7.53E2 0.00E0 1992 8.13E2 0.00E0 ,
1993 6.85E2 0.00E0 1
1994 0.00E0 0.00E0 1995 3.15E2 0.00E0 17 Year Average 6.40E2 1.57E2 1996 8.08E2 0.00E0 l
I l
)
l Sectum 3.PaPe 10 E
3.4 MILK In 1996,104 milk samples weit analyzed for low level I-131 and other gamma emitting radionuclides,78 at the three indicator locations and 26 at the controllocation.
No detectable activity was found in milk samples in 1996. Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not been detected since 1987.
Figure 3.4 shows Cs-137 highest annual mean indicator and contml location concentrations with comparisons to the reponing level. Table 3.4 gives indicator location highest annual means and contml means since 1979 for Cs-137. Preoperational and seventeen year averages are also shown. Since no activity was detected in 1996, no reponing levels were approached.
l l
FIGURE 3.4 CONCENTRATION OF CS-137 r
IN MILK ;
80 REPCIRTING LFVEl. ,
l 10 60 s0 40 30 <
20 N/ "N m t ~ vx.-- ,- mg 0
k k k k k k k k k k Year l
l*Co 1371ndicator
- Co 137 Control l l
secuan 3.IV ii
l l
l Table 3.4 Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pCl/l) Cs-137 Control (pCi/I) 1979 2.48El 6.04E0 1980 1.72El 4.13E0 1981 2.04El 4.15E0 1982 1.21El 5.20E0 1983 2.01El 2.82E0 1984 1.48El 2.56E0 1985 1.42El 2.72E0 1986 3.74E0 3.45E0 1987 5.20E0 8.60E0 j 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 17 Year Average 8.66E0 2.99E0 1996 0.00E0 0.00E0 1
Sectum 3 1%ge 12
33 BROADLEAF VEGETATION In 1996, 36 broadleaf vegetation samples were analyzed, 27 at the thme indicator locations and nine at the control location.
No detectable activity was found in vegetation samples in 1996. Cs-137 has not been detected in vegetation samples since 1993 and all other radionuclides have not been detected since 1987.
Figure 3.5 shows Cs-137 highest annual mean indicator and control location concentrations with comparisons to 10% of the reporting level. Table 3.5 gives indicator and contini location highest annual neans since 1979 for Cs-137.
Preoperational and seventeen year averages are. also shown. Since no activity was detected in 1996, no mposting levels were approacled.
FIGURE 3.5 CONCENTRATION OF CS-137 IN Pol /kg-wet BROADLEAF VEGETATION ,
250 '
1C% OF ILEPORMNOLEVEL 200 160 100 I
-M%
x . .
h h
5 k
k k
k k- h h
h h
Year 1 l+Co-137 Indicator *Co-137 Controll I
l 1
i 1
l Section 3.Page 13
l 1
Table 3.5 Concentration of Radionuclides in Broadleaf Venetation YEAR Cs-137 Indicator (pCWg-wet) Cs-137 Control (pCl/kg-wet) 1979 2.19E1 1.93E1 1980 2.30EI 1.92EI 1981 3.04El 2.02El 1982 2.46El 1.22El 1983 9.07E0 7.85E0 1984 1.02El 1.05El 1985 8.05E0 2.37E-2 1986 4.03El 1.27El 1987 2.20EI 1.70El 1988 3.90El 3.40El 1989 9.60E1 0.00E0 1990 4.00El 0.00E0 1991 3.30EI 0.00E0 1992 4.90El 0.00E0 1993 1.60E1 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 17 Year Average 2.72El 9.00E0 1996 0.00E0 0.00E0 l
I l
Sectkm 3.Page 14 l 1
1 i
4 3.6 SilORELINE SEDIMENT 1
In 1996, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.
Figure 3.6-1 shows Cs-137 highest annual mean indicator and control location concentrations since 1979. Figure 3.6-2 shows Co-60 highest annual mean indicator i and contml location concentrations since 1979. These two mdionuclides represent the j highest dose contributors for shoreline sediment.
Table 3.6 gives indicator location highest annual means since 1979 for all radionuclides detected since the analysis change in 1988. Preoperational data and seventeen year averages are also shown. There is no irporting level for shoreline sediment.
FIGURE 3.6-1 CONCENTRATION OF CS-137 IN pc %
SHORELINE SCDIMENT 300 250 150 fIa i
- \ w ]
A /
/ )+ j .
l
- gg 0
[
I! ! ! ! ! !! !i i Yaar
- Co 137 Indlostor *Co-137 Control l
Secten 3 Page 15
FIGURE 3.6 2 CONCENTRATION OF CO-60 IN SHORELINE SEDIMENT 300 250 -
150
,00 N 60 l
. i i i Au/
i i i i i i i i
> > i i i
/i i I
Year I
- Co-00 indicator *Co 00 Control Table 3.6 Concentration of Radionuclides in Shoreline Sediment YEAR Mn 54 Co-58 Co-60 Cs-134 Cs-137 Indicator Indicator Indicator Indicator Indicator (pCIAg dry) (pCIAg-dry) (pCIAg dry) (pCIAg-dry) (pCIAg-dry) 1979 -1.07El 2.25El -6.50E0 0.00E0 1.20El 1980 1.06El -8.74E0 2.36El -3.53E0 1.44El 1981 2.13El 1.20El 8.21 E0 3.97El 3.36El 1982 5.38El 1.66El -1.69E0 7.67El 4.40El 1983 4.40E0 3.43El 2.12E l 7.65El 8.02El 1984 1.19El 7.1 lEl 3.04El 3.34El 9.13El 1985 4.77E0 1.46El 9.20E0 2.02El 1.61E2 '
1986 1.37El 1.02El 1.16El 6.35El 1.53E2 1987 0.00E0 1.06E2 2.10El 4.20El 1.65E2 1988 6.50E0 9.20El 1.20El 9.10E0 2.66E2 1989 2.90El 3.80El 2.90El 5.30El 6.50El 1990 3.80El 2.70El 1.68E2 0.00E0 6.10El 1991 2.80El 5.30El 1.31E2 0.00E0 1.03E2 1992 9.40E0 0.00E0 5.10El 9.20E0 8.60El 1993 0.00E0 2.20El 8.60El 0.00E0 9.30El 1994 4.10El 0.00E0 0.00E0 0.00E0 8.00El l 1995 1.70El 0.00E0 2.3 0111 0.00E0 1.38E2 l l
17 Year Average 1.70El 3.05El 3.68El 2.49El 9.69El 1996 2.90El 1.78El 3.50El 0.00E0 1.47E2
. All negative values have been replaced with zeros for calculational purposes Section 3.PaFe 16
3.7 FISil In 1996,12 fish samples were analyzed for gamma emitting radionuclides, six at the indicator location and six at the contmllocation.
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 13 cation concentmtions also with comparisons to 5% of the repolting 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. Piroperational data and sixteen year averages are also shown. No indicator samples weie analyzed in 1979. Only Cs-137 activity was detected in 1996 in three 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 1.39% of the irposting level.
FIGURE 3.7-1 pcilkg-wet CONCENTRATION OF CS-137 IN FISH 120 5 % 01:REPORTINGLEVE L 100.
80 )
60 l
A f
IN n \ "
\
/ VNW/ /
Year l**"Co 137 Indicator *Co-137 Control l Section 3 Page 17
FIGURE 3.7-2 pcl/kg. wet CONCENTRATION OF CO-60 l IN FISH
, ]
5% O'rREPORTINikLEVI:L 600.
400 300 200 m /
w' 0!
j ( '
Year l**"Co 40 Indicator *'-Co 00 Control l l
Table 3.7 Concentration of Radionuclides in Fish YEAR Mn 54 Co-58 Co-60 Cs-134 Cs-137 Indicator Indicator Indicator Indicator Indicator (pCl/kg-wet) (pCi/kg-wet) (pCl/kg-wet) (pCiAg-wet) (pCIAg wet) 1980 -1.97E l 8.36E0 -2.25El -2.70El -4.13E0 1981 -2.71 E0 -2.98E0 -2.65 E0 -1.99E0 1.80El 1982 -3.83E0 8.16E0 -4.34E-l -8.22E-l 2.69El 1983 -2.60E0 2.60El 1.l lEl - 1.32E0 6.03El 1984 3.61E0 1.45E2 2.82El 3.11E1 4.38El 1 1985 2.53E-1 7.19E0 1.72El -1.56E0 1.86El l 1986 1.03E0 3.17El 2.96El 1.67El 3.49El j 1987 0.00E0 2.71E2 1.25E2 2.60El 5.10El '
1988 1.20El 7.70El 0.00E0 2.70El 3.60El i 1989 9.00El 4.05E2 2.99E2 1.10El 3.50El 1 1990 0.00E0 5.60El 4.10El 0.00E0 3.30El l 1991 6.20E0 1.40El 6.50El 5.90E0 2.60El 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90El 1993 0.00E0 8.20El 1.30El 0.00E0 1.60El 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10El 1995 0.00E0 0.00E0 0.00E0 0.00E0 2.70El 16 Year Average 7.07E0 7.07El 3.93El 7.36E0 3.04El 1996 0.00E0 0.00E0 0.00E0 0.00E0 2.78El All negative values have been replaced with zeros for calculational purposes Sectkm 3.Page 18
3.8 DIRECT GAMMA RADIATION In 1996,187 TLD's were analyzed,183 at indicator locations and four at the contiul location.
Figure 3.8 and Table 3.8 show TLD inner ring, outer ring, and control location annual averages in milliroentgen (mR) per year. Preoperational data and seventeen year l averages are also given. As shown in the gmph, inner and outer ring averages !
historically compare closely, with control data somewhat higher, Inner and outer ring l avemges comprise a number of data points with control avemges repmsenting only one I location.
The calculated total body dose from gaseous effluents for 1996 was 3.66E-2 millirem, I which is 0.05% of the mean of all indicator TLD locations. Therefore, it can be concluded that discharges from the plant had veiy little impact on the measured TLD values.
FIGURE 3.8 TLD EXPOSURE mR/yr FROM DIRECT RADIATION 115 160 h a A \ >~
S, *e
%\ , y
- /N ,
60 25 i
0 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1998 Year l-e-Inner nin9
- outer ning =*-controil i l
l l
l Secten 3-Page 19
Table 3.8 TLD Exposure from Direct Radiation i
YEAR Inner Ring Average Outer Ring Average Control (mR/yr) (mR/yr) (mR/yr) 1979 7.9IE1 8.82E1 8.32EI 1980 7.54E l
- 8.29E !
- 1.05E2 1981 1.01E2 9.3IEI 1.05E2 1982 8.95El 8.97El 1.10E2 1983 1.16E2 1.14E2 1.30E2 3 1984 7.85El 7.83El 9.02El l 1985 9.54El 9.69El 1.27E2 1986 8.91El 9.35El 1.10E2 1987 7.58El 7.71El 1.23E2 1988 6.03El 6.42El 5.48El 1989 5.37El 5.30El 7.55El 1990 4.34E l 4.78El 6.25El 1991 5.14El 5.59El 6.80El 1992 5.65El 5.55El 7.60El 1993 5.61E1 5.71 El 7.20E1 1994 6.40El 6.93El 9.55El 1995 8.36El 8.25EI 1.08E2 17 Year Average 7.46El 7.64El 9.39El 1996 7.18El 7.02El 9.88El
- Values are based on two quaners due to change in TLD locations.
NOTE: The expected backgmund for North Carolina is 120 mrem per year (Refemnce 6.3).
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l Socikm 3 - Page 20
3.9 FOOD PRODUCTS In 1996,12 food products (crops) samples were analyzed, all at one indicator location. ,
Their is no control location for this media, l No detectable activity has been detected in this media since 1987. Figure 3.9 shows Cs-137 indicator highest annual means since 1979 with comparisons to 5% of the reporting level for binadleaf vegetation. Table 3.9 shows Cs-137 indicator highest annual means with preoperational data and seventeen year avemges. Since no activity was detected in 1996, no repoiting levels were approached.
FIGURE 3.9 CONCENTRATION OF CS-137 IN PC % mi FOOD PRODUCTS 120 SY OF RliPORTNG LE/EL 100 80 60 40 g qH k J
\ /
0' .. .. .. -_ .. .. .. .. ..
Year l-*-ce-137 ndicato]r Secthm 3-PnFe21 l
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Table 3.9 Concentration of Radionuclides in Fomi Products YEAR Cs 137 Indicator (pCi/kg-wet) 1979 2.19El 1980 2.30El 1981 3.04El 1982 2.46E l 1983 9.07E0 1984 8.45E0 1985 7.99E0 1986 2.15El
.1987 2.90El 1988 0.00E0 1989 0.00E0 1990 0.00E0 1991 0.00E0 1992 0.00E0 1993 0.00E0 1994 0.00E0 1995 0.00E0 17 Year Average 1.04El 1996 0.00E0 l
1 l
Secum 3-Page22
-,e,n 3.10 LAND USE CENSUS The land use census was completed June 14,1996 and the resuhs are shown in Table 3.10 and Figure 3.10. During the 1996 census, no new or closer irrigated gardens were identified. The census revealed eight milk animal locations that were i not included in the 1996 sampling pmgram. However, seven of the locations I (goats) do not produce sufficient volume to be added to the pmgram and the eighth (
(cow) is outside the five kilometer area of participation. The nearest residence is located in the East sector at 0.46 miles. No program changes were required as a resuk of the 1996 land use census.
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- ieconn 3 Page23
Table 310 land Use Census Resuhs SECI'OR I)lSTANCf.
4 N Nearest Residence 2.5 rnlles Nearest Meat Animal None in 5 miles Nearest Garden 2.56 miles
]
Nearest Cow None in 5 miles I Nearest Goat None in 5 miles f
NNE Nearest Residence 1.29 miles Nearest Meat Animal Norw in 5 miles Nearest Garden 2.37 miles Nearest Cow None in 5 miles
, Nearest Goat None in 5 miles 3
l NE Nearest Residence 1.2 rniles Nearest Meat Ammal Note in 5 miles
. Nearent Garden 2.10 miles Nearest Cow None in 5 miles l Nearest Goat 4.95 miles 1
ENE Nearest Residence 0.56 niles I
i Nearest Meat Animal 3.81 miles l
Nearest Garden 2.55 miles Nearest Cow 3.51 miles Nearest Goat Norw in 5 miles I
.a 1 E Nearest Residerre 0.46 udies I i
Nearest Meat Animal @8 miles j i
Nearest Garden 0.47 miles '
I Nearest Cow 2.46 miles l Nearcut Goat None in 5 mik s ESE Nearest Residence 0.67 rniles Nearest Meat Animal 1.30 miles Nearent Garden 0.85 m&s Nearest Cow 3.07 miles Nearest Goat 1.40 miles
}
i SE Nearest Residerre 1.17 rniles
' Nearest Meat Animal 2.79 miles I Nearest Garden 1.2I miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles SSE Nearest Residence 1.06 miles 1
Nearest Meat Animal 1.4R miles l
Nearest Garden 1.26 miles
- Nearest Cow 2.76 miles f Nearest Goat 2.09 miles i
s i Section 3.Page 24
Table 3.I0 Land Use Census Results
$fX. TOR DISTANCI?
5 Nearest Residerre 1.62 ndles Nearest Meat Ammal 3.01 miles Nearest Garden 3.04 miles Nearest Cow None in 5 miles Nearest Goat 4.30 miles SSW Nearest Residerre 2J7 ndles Nearest Meat Arimal 2.75 miles Nearest Gard 3n 2.95 miles Nearest Cr,w None in 5 miles Nearest Goat 3.06 miles SW Nearest Residerre I A0 niles i
Nearest Meat Animal None in 5 miles Nearest Gaiden i .80 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles WSW Nearest Residerre thi ndles Nearest Meat Animal 3.97 miles Nearest Garden 1.01 miles 4
Nearest Cow None in 5 miles Nearest Goat 3.97 miles W Nearest Residerre OA2 niles Nearest Meat Animal 3.07 miles Nearest Garden 0.90 miles Nearest Cow Noir in 5 miles Nearest Goat 3.R3 miles WNW Nearest Residerre 0.91 niles Nearest Meat Animal None in 5 mih, Nearest Garden 2.15 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NW Nearest Realdence 0.93 neles Nearest Meat Animal 3.49 miles Nearest Garden 1.37 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles f NNW Nearest Residerre 133 neles Nearest Meat Animal 347 miles Nearest Garden 1.69 miles Nearest Cow Nore in 5 miles Nearest Goat None in 5 miles Section 3 Page 25
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4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS VERSUS ESTIMATED DOSE FROM RELEASES 4.1 DOSE FROM ENVIR% (" ENTAL 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 values for each sample type and radionuclide as given in Appendix B were used after the background concentrations, as measured at the control location, had been subtracted. The maximum exposed individual doses are summarized in Tables 4.1-A and 4.1-B.
4.2 ESTIMATED DOSE FROM RELEASES Doses were estimated for release concentrations of radionuclides in direct pathways to I man using NRC Regulatory Guide 1.109 methodology. The doses were calculated using i GASPAR and LADTAP computer programs as reponed in the 1996 McGuire Annual j Radioactive Effluent Release Report (reference 6.6). The effluent liquid release doses are i summations of the dose contributions from the liquid pathways. Noble gas exposure and )
iodine, particulate, and tritium exposure gaseous release doses are reponed separately.
For noble gas exposure, there is no critical age group, as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, paniculate, and tritium exposure, the maximum total organ dose for the highest dose location is given for the maximum organ (thyroid) for the critical age group (child).
The maximum exposed individual doses are summarized in Table 4.1-A with the critical age and critical pathway listed.
4.3 COMPARISON OF DOSES l
' I The environmental and effluent doses given in Table 4.1-A agree reasonably well. The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways.
In calculations based on liquid release effluent pathways, drinking water consumption was the predominant dose path based on effluent data for 1996. For 1996 environmental 1
samples, drinking water also was the predominant dose path followed by fish. The only secuon 4.Page 1
..~ .- - -.. - . .. .- -. . - . - . . . . - . . _ _ _
t
. radionuclide detected in drinking water in 1996 was tritium. The only radionuclide '
i detected in fish in 1996 was Cs-137. Tritium from surface water samples also was i included in the fish pathway.
No environmental doses resulted from the gaseous pathway in 1996. Broadleaf j vegetation, milk, and airbome radiciodines and particulates indicated no activity in 1996.
The effluent data dose for iodine, particulate, and tritium is based on the vegetation pathway to the child with the majority of the dose contributed by tntium. ,
- %e doses, as calculated using the environmental sample results, are well below the limits
- specified in Selected Licensee Commitments Manual Section 16.11-12 and do not exceed 4
the 40CFR190 dose commitment limits for members of the public.
4 1
3 4.4 PATHWAY DOSE CALCULATIONS
'i 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. i a
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, TABLE 4.1-A
, Page 1 of 2 i
1996 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON FOR LIQUID AND GASEOUS WASTE RELEASE PATHWAYS LIOUID RELEASE PATHWAY 4
Environmental or Critical Critical Maximum Dose
- Organ Emuent Data Age Pathway (mrem)
Skin Environmental Teen Shoreline Sediment 9.48E-04 Skin Emuent Teen Shoreline Sediment 7.18E-04 i
Bone Environmental Child Fish 6.28E-02 Bone Emuent Child Fish 3.38E-02 i
Liver Environmental Child Fish 9.85E-02 Liver Effluent Child Drinking Water 8.46E-02 ;
i i
j T. Body Environmental Adult Fish 7.10E-02 !
j T. Body Effluent Adult Drinking Water 6.30E-02 j Thyroid Environmental Child Drinking Water 3.84E-02 Thyroid Emuent Child Drinking Water 4.90E-02
, Kidney Environmental Child Drinking Water 5.80E-02 ;
j Kidney Effluent Child Drinking Water 6.04E-02 Lung Environmental Child Drinking Water 4.54E-02 )
Lung Effluent Child Drinking Water 5.30E-02 GI-LLI Environmental Child Drinking Water 3.88E-02 GI-LLI Effluent Child Drinking Water 5.16E-02
- Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
1 I
2 ,
i Section 4. Page 3 i
]
j l
a l Page 2 of 2 GASEOUS RELEASE PATHWAY j
! Environmental or Critical Critical Maximum Dose Organ
! Effluent Data Age Pathway (mrem)
NOBLE GAS EXPOSURE 1
! Skin Environmental - -
Not Sampled l Skin Effluent N/A Noble Gas 6.56E-02 1 .
- T. Body Environmental - -
Not Sampled j T. Body Effluent N/A Noble Gas 3.66E-02 1
}
i
! Environmental or Critical Critical Maximum Dose *
. Organ Effluent Data Age Pathway (mrem)
. IODINE, PARTICULATE, and TRITIUM
- Bone Environmental - - 0.00E+00 Liver Environmental - - 0.00E+00 l
T. Body Environmental - -
0.00E+00 I Thyroid Environmental - - 0.00E+00 j Thyroid Effluent Child Vegetation 1.66E-01 i
Kidney Environmental - -
0.00E+00 l
l Lung Environmental - - 0.00E+00 i
GI-LLI Environmental - - 0.00E+00 i
- Maximum dose is a summation of the inhalation, milk and vegetation pathways.
Section 4 - Page 4 1
1
TABLE 4.1-B Maxim m Individ=1 Dosefor 1996 based on Environment:1 Me:surements (mrem)for McGrire Ncclear St: tion Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin lufant Airbome 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 3.66E-02 3.66E-02 3.66E-02 3.66E-02 3.66E-02 3.66E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 3.66E-02 3.66E-02 3.66E-02 3.66E-02 3.66E-02 3.66E-02 0.00E+00 Child . Airbome 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 3.73E-02 3.73E-02 3.73E-02 3.73 E-02 3.73E-02 3.73E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 6.27E-02 6.llE-02 9.88E-03 1.02 E-03 2.06E-02 8.06E-03 1.39E-03 0.00E+00 Shoreline Sediment 8.78E-05 8.78E-05 8.78E 05 8.78E-05 8.78E-05 8.78E-05 8.78E-05 1.03 E-04 TOTAL 6.28E-02 9.85E-02 4.73 E-L 3.84E-02 5.80E-02 4.54 E-02 3.88E-02 1.03 E-04 Teen Airbome 0.00E+00 0.00E+00 0.00E+00 0. 'E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 1.95E-02 1.95E-02 1.95E-02 1.95 E-02 1.95E-02 1.95 E-02 0.00E+00 Milk. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 llroadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 4.98E-02 6.75E-02 2.43 E-02 1.23 E-03 2.38 E-02 1.00E-02 2.18E-03 0.00E+00 Shoreline Sediment 4.20E-04 4.20E-04 4.20E-04 4.20E-04 4.20E-04 4.20E-04 4.20E-04 4.94E-04 TOTAL 5.02E-02 8.74E-02 4.42 E-02 2.12 E-02 4.37E-02 2.99E-02 2.21 E-02 4.94E-04 Adult Airbome 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.76E-02 2.76E-02 2.76E-02 2.76E-02 2.76E-02 2.76E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BroadleafVegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 4.65E-02 6.52E-02 4.33E-02 1.60E-03 2.32E-02 8.78E-03 2.83E-03 0.00E+00 Shoreline Sediment 7.52E-05 7.52E-05 7.52E-05 7.52E-05 7.52E-05 7.52E-05 7.52E-05 8.84 E-05 TOTAL 4.66E-02 9.29E-02 7.10E-02 2.93 E-02 5.09E-02 3.65E-02 3.05E-02 8.84E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.
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Dosefrom Shoreline Sediment Pathwayfor 1996 Data Maximum Exposed Child Shoreline Recreation = I4 hr (in one year)
Shore Width Factor = 0.3 (lake shore -location 129)
Shore Width Factor = 0.2 (river shoreline -location 130)
Sediment Surface Mass = 40 kg/m2 Child Dose from Shorline Sediment Pathway (mrem)- Shorline Recreation (hr) x External Dese Factor (mrem /hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentralion (pCL%g)
External Dose Factor Standing Highest Annual Net Euc on Contaminated Ground Mean Concentration (mrem /hr per pCl/m2) Indicator Sediment (mrem)
Radionuclide T. Body Skin Loestion (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 130 0.30 1.95 E-07 2.28E-07 Co-58 7.00E-09 8.20E49 129 17.80 2.09E-05 2.45 E-05 Co-60 1.70E-08 2.00E-08 130 35.00 6.66E-05 7J4E-05 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 ALL 0.00 0.00E+00 0.00E+00 Dose Commitment (mrem) = 8.78E-05 1.03E-04
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Dosefrom Shoreline Sediment Pathwayfor i996 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)
Shore Width Factor = 03 (lake shore-location 129)
Shore Width Factor = 0.2 (ri,er shoreline-location 130)
Sediment Surface Mass = 40 kg/m2 Teen Dose from Shorline Sediment Pathway (mrem) = Sherline Recreation (br) x External Dose Factor (mrem /hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pLMg)
External Dose Factor Standing Highest Annual Net Dng on Contaminated Cronad Mran Concentralien (mrem /hr per pCi/m2) Indicator Sediment (mrem)
Radionuclide T.Rody Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 130 030 933E-07 1.09E-06 00-58 7.00E-09 8.20E-09 129 17.80 1.00E-04 1.17E44 Co-60 1.70E-08 2.00E-08 130 35.00 3.19E-04 3.75E-04 Cs-134 1.20E-08 I.40E-08 ALL 0.00 0.00E+00 0.00E+ 00 Cs-137 4.20E-09 4.90E-09 ALL 0.00 0.00E+00 0.00E+00 Dose Commitment (mrem) = 4.20E-04 4.94 E-04
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U R A 1
Dosefrom Shoreline Sediment Path wayfor 1996 Data Maximum ExposedAdult Shoreline Recreation = 12 hr (in one year)
Shore Width Factor = 0.3 (lake shore -location 129)
Shore Width Factor = 0.2 (river shoreline -location 130)
Sediment Surface Mass = 40 kg/m2 Adult Dose from Shorline Sediment Pathway (mrem) = Shorline Recreation (br) x External Dose Factor (mrem /hr per pCl/ne2) x Shore width Factor x Sediment Surface Mass (kg/m2) x ,
Sediment Concentration (pCi/kg)
External Dose Factor Standing Ifighest Annual Net Done on Contaminated Groning Mean Concentration (mrem)
(mrem /hr per pCl/m2) Indicator Sediment Radiennelide T. Body Skin Location (pC1/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 130 0.30 1.67E-07 I.% E-07 Co-58 7.00E-09 8.20E-09 129 17.80 1.79E-05 2.10E-05 Co-60 1.70E-08 2.00E-08 130 35.00 S.7t E-05 6.72E-05 Cs-134 I.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 ALL 0.00 0.00E+00 0.00E+00 Dose Commitment (mrem) = 7.52E-05 8.84E-05
5.0 QUALITY ASSURANCE l
5.1 DUKE POWER COMPANY'S RADIOLOGICAL ,
ENVIRONMENTAL MONITORING PROGRAM I
5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology l
performed the environmental sample collections as specified by approved sample collection procedures.
5.1.2 SAMPLE ANALYSIS
, The Radiological and Environmental Services Group performed the environmental sample analyses as specified by approved analysis procedures.
l 5.1.3 DOSIMETRY ANALYSIS The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.
5.1.4 INTRALABORATORY QUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type ofinstrumentation 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.
Additionally, National Institute of Standards and Technology (NIST) standards that l represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid.
The frequency is dependent upon instrument use and performance. Investigations
, are performed and documented should calibration verification data fall out of limits.
section 5 - Page 1
Radiological and Environmental Sersices (R&ES) did not participate in the Environmental Protection Agency (EPA) cross check program during 1996 due to the EPA power plant cross-check program being discontinued by EPA. R&ES contracted a similar cross-check program using North American Scientific as the supplier of the cross-checks. Results of these cross-checks are displayed in Table 5.0-A.
5.1.5 INTERLABORATORY QUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISION The McGuire Nuclear Station Radiation Protection Section participated in a Quality Assurance audit in April 1995. This audit was conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group.
No recommendations pertaining to the McGuire Radiological Environmental Monitoring Program were identified in the audit. No audit was conducted in 1996. !
l 1
5.1.5.2 DUKE POWER'S INTERCOMPARISON PROGRAM The Radiological and Environmental Services group participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1996. Interlaboratory cross-check standards, including marinelli beakers, air filters, air cartridges, gross alpha / 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 stunmary of these Intercomparison Reports for 1996 is' !
documented in Table 5.0-A. I I
5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Radiological Environmental Monitoring Program was not audited by the NRC in 1996. The McGuire Nuclear Station Radiation Protection section participated in two NRC audits in 1996. There were no recommendations for the environmental monitoring program as a result of these audits.
section 5 - Page 2
5.1.5.4 NRC/ STATE OF N.C. SAMPLING INTERCOMPARISON PROGRAM Radiological and Environmental Services routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. Radiological and Environmental Services 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.
5.1.5.5 STATE OF N.C. TLD INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. Every six to eight months, 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 unknovm estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 1996 is documented in Table 5.0-B.
5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1996. l l
l l
l 1
i section 5. Page 3 I
TA.BLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 1996 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gammain CharcoalCartridge:
Collection Geometry Nuclide Acceptance Range Reference Value Reported Date (pCi/ total) (pCi/ total) Value (pCi/ total) 4/9/96 Cartridge Co-57 1.30E 2.30E-2 1.73E-02 1.93 E-02 Co-60 2.65E 4.69E-02 3.53E-02 3.87E-02 Y-88 5.60E 9.94E-02 7.47E-02 8.93 E-02 Cd-109 5.36E 9.51 E-01 7.15E-01 7.57E-01 Sn-113 3.41E-02 -i' 0$E-02 4.55E-02 4.92E-02 Cs-137 1.64E 2.91 E-02 2.19E-02 2.30E-02 6/1/96 Cartridge Ba-133 1.94E+04 - 3.48E+04 2.62E+04 2.45E+04 Gamma in MarinelliBeaker:
Collection Geometry Nuclide Acceptance Range Reference Value Reported Value Date (pCi/ total) (pCi/ total) (pCi/ total) 6/1/96 3.5 liter Cr-51 1.34E+04 - 2.38E+04 1.79E+04 1.88E+04 Co-57 8.9E+02 - 1.58E+03 1.19E+03 1.32E+03 Co-60 2.06E+03 - 3.64E+03 2.74 E+03 2.94E+03 Y-88 7.87E+03 - 1.40E+04 1.05E+04 1.07E+04 Sn-l l3 3.73 E+03 - 6.61 E+03 4.97E+03 5.15E+03 Te 123m 7.83E4 02 - 1.39E+03 1.04E+03 1.0lE+03 12/17/96 3.5 liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.43 E+05 Co-60 4.83 E+04 - 8.57E+04 6.44 E+04 6.24 E+04 I-131 5.02E+04 - 8.90E+04 6.69E+04 6.35 E+04 Cs-134 7.14E+04 - 1.27E+05 9.52E+04 8.03 E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.06E+04 Section 5 - Page 4
Collection Geometry Nuclide Acceptance Range Reference Value Reported Value Date (pCi/ total) (pCi/ total) (pCi/ total) 6/1/96 1.0 liter Cr-51 3.59+04 - 6.37E+04 4.79E+04 4.71 E+04 Co-57 2.39E+03 - 4.23 E+03 3.18E+03 3.18E+03 Co-60 5.50E+03 - 9.75E+03 7.33E+03 7.50E+03 Y-88 2.11 E+04 - 3.74E+04 2.8IE+04 2.68E+04 Sn-113 9.98E+03 - 1.77E+04 1.33E+04 1.31E+04 Te-123m 2.1OE+03 - 3.72E+03 2.80E+03 2.58E+03 Cs-137 1.04E+04 - 1.84E+04 1.38E+04 1.30E+04 12/I7/96 1.0 liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.58E+05 Co-60 4.83 E+04 - 8.57E+04 6.44E+04 6.45E+04 1-131 5.02E+04 - 8.90E+04 6.69E+04 6.68E+04 Cs-134 7.14E+04 - 1.27E+05 9.52E+04 8.69E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.18E+04 12/17/96 0.5 liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.43E+05 Co-60 4.83 E+04 - 8.57E+04 6.44E+04 6.24E+04 1-131 5.02 E+04 - 8.90E+04 6.69E+04 6.35E+04 Cs-134 7.I4E+04 - 1.27E+05 9.52E+04 8.03 E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.06E+04 7/1I/96 Gamma in Cs-137 1.25E+02 - 2.22E+02 1.67E+02 1.47E+02 Water 7/lI/96 Gamma in Cs-137 1.71 E+02 - 3.03 E+02 2.28E+02 1.96E+02 Milk 12/17/96 lodine in 1-131 1.24E+01 - 2.19E+0i 1.65E+0! 1.80E+01 Water Section 5 - Page 5
Gross Beta in Air Particulate:
Collection Geometry Nuclide Acceptance Range Reference Value Reported Date (DPM) (DPM) Value (DPM) 4/9/96 Gross Beta Cs-137 1.55E+04 - 2.74E+04 2.06E+04 2.05 E+04 in Air Filter 6/1/96 Gross Beta Cs-137 5.84E+04 - 1.04E+05 7.79E+04 7.21 E+04 in Air Filter Tritiunt:
Collection Geometry Nuclide Acceptance Range Reference Value Reported Date (pCi/ liter) (pCi/ liter) Value (pCi/ liter) 3/25/96 Tritium in H-3 1.31 E+05 - 2.33 E+05 1.75E+05 2.23 E+05 Water H-3 3.03E+06 - 5.37E+06 4.04E+06 4.33 E+06 7/9/96 Tritium Water H-3 5.92E+03 - 1.05E+04 7.89E+03 8.22E+03 Section 5 - Page 6 l
l
TABLE 5.0-B STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1996 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Radiation Cross-Check State of N.C. Dosimetry & Acceptance Date Delivered Value Records Criteria Reported Value (mR) +/- 10 %
(mR)
Jun-96 55 51.6 Pass Dec-96 40 38.4 Pass Section 5 Page 7
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 6.5 McGuire Annual Environmental Operating Report 1979 - 1995 6.6 McGuire Annual Radioactive Effluent Release Report 1996 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery,1969, pages 287-293.
6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain,1988, pages 83-93.
6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix 1.
6.10 Radiological and Environmental Services Operating Procedures 6.11 NUREG/CR-1276, Users Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
I section 6. Page i
T e
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments.
Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.
Environmental sampling and analyses were performed by Radiological and Environmental Services, 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.
L CHANGE OF SAMPLING PROCEDURES No sampling changes were made to the sampling procedure during 1996.
In the environmental program, the air deposition parameters (D/Q) are used to determine air, broadleaf vegetation and milk sampling locations. McGuire's sectors with the three highest values have not changed in 1996.
Some sampling location sectors were updated due to increased accuracy of the Global Positioning System (GPS) used to determine meteorological sectors. Surface water locations site #128, located in the NE sector (formerly ENE) and site #131, located in the WNW sector (formerly W) were affected.
II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.
Appendix A-Page i
Low-level iodine analyses are performed by passing a designated sample aliqcot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.
Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable.
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.
III. CHANGE OF ANALYSIS PROCEDURES Weekly gamma spectroscopy analysis of air particulate filters was discontinued for all air sampling sites in 1996. Air particulate filters continue to receive weekly gross beta analysis as required by Selected Licensee Commi*ments. Gross beta results on a per site basis have historically been less than 10 times the annual mean of the control location. Air particulate filters are segregated by site and composited quarterly for gamma spectroscopy analysis.
Low-Level Iodine 131 (LLI-131) for drinking water was discontinued. This analysis is not required if demonstrated that annual dose from the consumption of water is not greater than 1 mrem. Historical data from 1991 through 1996 indicated that the annual dose from consumption of dnnking water was less than 1 mrem.
IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airbome particulate and radiciodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order j 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 performed 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.
Appendix A - Page 2
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! Location 120 = Site Boundary (0.5 mi. NNE) j Location 121 = Site Boundary (0.5 mi. NE) l
- Location 125 = Site Boundary (0.4 mi. SW) j
- Location 133 = Comelius, NC (6.2 mi. NE) !
Location 134 =
i East Lincoln Junior High School (8.8 mi. WNW) ;
Location 192 = Peninsula development (2.8 mi.NNE) l Location 195 = Fishing Access Road (0.2 mi.N) i :
j A.2 DRINKING WATER l t
1 i Biweekly composite samples were collected. A gross beta and gamma analysis was l
performed on monthly composites. Tritium analysis was perfonned on the quarterly
. composites. The composites were collected biweekly from the locations listed below. {
l Location 119 = Mt. Holly Municipal Water Supply (7.4 mi. SSW) j 4 Location 132 = Charlotte Municipal Water Supply (11.2 mi. SSE) i Location 136 = Mooresville Municipal Water Supply (12.7 mi. NNE) l 3 =
Location 194 East Lincoln Water Supply (6.7 mi. NNW) ;
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] AJ SURFACE WATER l
- Biweekly composite samples were collected. A gamma analysis was performed on the j monthly composites. Tritium analysis was performed on the quarterly composites sample. i i The composites were collected biweekly from the locations listed below. ;
i i I Location 128 = Discharge Canal Bridge (0.4 mi.NE) 1 Location 131 =
- Cowans Ford Dam (0.6 mi. WNW) ,
Location 135 =
{ Plant Marshall Intake Canal (11.9 mi. N)
! A.4 MILK i
{ 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 i
- the locations listed below.
l Location 138 = Henry Cook Dairy - COWS (3.1 mi. ESE) ;
}' Location 139 = William Cook Dairy-COWS (2.5 mi. E) l Location 140 = Kidd Dairy- COWS (2.7 mi. SSE) !
Location 141 - Lynch Dairy- COWS (14.8 mi. WNW) ,
,i i A.5 BROADLEAF VEGETATION i
Monthly samples were collected as available and s gamma analysis was performed on j each sample. The samples were collected from the locations listed below.
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- Appendix A.Page 3 !
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! i j Location 120 =
Site Boundary (0.5 mi.NNE) l j Location 125 =~ Site Boundary (0.4 mi. SW) l j Locetion 134 = '
East Lincoln Junior High School (8.8 mi. WNW) i Location 193 = Site Boundary (0.2 mi. N) i l A.6 SHORELINE SEDIMENT '
j~ Semiannual samples were collected and a gamma analysis was performed on each j
{ following the drying and removal of rocks and clams. The samples were collected ;
l from the locations listed below. !
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Location 129 =
Discharge Canal Entrance to Lake Norman (0.5 mi. ENE) f Location 130 =
Highway 73 Bridge Downstream (0.5 mi. SW) !
l Location 137 =
Pinnacle Access Area (12.0 mi.N) !
- i A.7 EISH i
- . Semiannual samples were collected and a gamma analysis was performed on the edible l j portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the j l head and tail portions. The samples were collected from the locations listed below.
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Location 129 =
Discharge Canal Entrance to Lake Norman (0.5 mi.ENE) l
- Location 137 =
Pinnacle Access Area (12 0 mi.N) f l A.8 DIRECT GAMMA RADIATION frLD)
!' Thermoluminescent 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.
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- 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 j over water; however, two special interest TLD's were placed in these sectors inside 3 the site boundaryin March,1991.
a j
- An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 j kilometerrange.
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- The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and control locations.
E TLD locations are listed in Table 2.1-B.
i i l Appendix A Page 4 i
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A.9 FOOD PRODUCTS I
Samples were collected monthly when available during the harvest season and a
' l gammaanalysis was performed on each. The samples were collected at the location listed below, i Location 188 =
Garden (2.8 mi N)
A.10 ANNUAL LAND USE CENSUS j 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 i sixteen meteorological sectors, the following:
j
- The Nearest Residence ;
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- The Nearest Meat Animal
- The Nearest Garden greater than 50 square meters or 500 square feet t
} The Nearest Milk-giving Anunal (cow, goat, etc.)
i I This census was initiated on June 10,1996 and completed on June 14,1996. Results are shown in Table 3.10 on pages 3-24 and 3-25.
V. PROGRAM IMPROVEMENTS i ;
i In 1996, McGuire Plan MG-95-0449, Environmental Sampling Deviation Reduction Plan, was
, completed to reduce sampling equipment deviations. This plan included the following actions:
- Installation of dual air samplers at each air sampling site ;
- Modification of air sampling houses to allow sufficient heat removal during the summer months
- Modification of electrical equipment / circuitry at air sampling sites l
- Installation of heat tracing and/or insulation as needed at surface water snes j Purchase and set-up ofISCO composite water samplers as back-ups for surface water sites
- Initiadon ofpreventive maintenance schedule for surface water sites
, The majority of the work was completed by May 1996. Most of the ten 1996 deviations occurred
! prior to the completion of this plan and over half can be attributed to dual air sampler start-up problems which were quickly recognized and resolved. Only one deviation occurred during the l 1
latter half of the year and was promptly corrected. Therefore, the actions outlined in this plan have l been effective in reducing emironmental sampling deviations due to equipment problems See
. Appendix C for details on all 1996 sampling deviations. -
1 Appendix A-Page 5
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- APPENDIX B i
l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 1996
Environmental Rcdiological Monitoring Program Summary Fccility: McGuire Nuclear Station Docket No. 50-369,370 Loc:tioz: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31-DEC 1996 I
M:dium or Type and Total Lower Location with liighest "* ""'
Pathway Number Limit of
^" *** ' 1 utine Annual Mean "$
Sampled of **"* catt n Detection Name, Distance, Direction ePod Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code i
' Air P1rticulate 134 (pCi/m3)
(8.8 mi WNW)
BETA 364 1.00E-02 2.59E-02 (312/312) 125 3.I IE-02 (52/52) 5.49E-2 (52/52) 0 6.IE 7.61E-02 (0.4 mi SW) 1.11 E 7.6E-02 [1 5 - 0.23 CS134 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 CSl37 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 j 1131 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 i
~
Mean and range based upon detectable measurements only i Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction) l Zero range indicates no detectable activity measurements i If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments
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Report Generated @ 3/19/97 4:50 PM Appendix B Page I
Environmental Radiological Monitoring Program Summary 1
Ftcility: McGuire Nuclear Station Docket No. 50-369,370
. Loc:tio::: Mecklenburg County, North Carolina Report Period: Ol-JAN-1996 to 31 DEC-1996 P thway Total k **'
Limit of All Indicator Location with Highest Annual Mean g
N8h. n
"{ "
Simpled Detection Name, Distance, Direction cPod of Meas.
Unit of Analyses '" " " #" "
! Meisurement Performed (LLD) Mean Range Mean Range Range Code Air Radiciodine 134 4 (pCi/m3)
(8.8 mi WNW)
CS134 364 5.00E-02 0.00 (0/312) 0.00(0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 t CS137 364 6.00E-02 7.58E-03 (3/312) 192 8.78E-03 (1/52) 0 0.00 (0/52) 5.99E-03 8.78E-03 (2.8 mi NNE) 8.78E 8.78E-03 0.00 - 0.00 1131 364 7.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 a
Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) j Zero range indicates no detectable activity measurements
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I Repon Generated @ 3/1997 4:51PM Appendix B Page 2 2
Environmental Radiological Monitoring Program Summary Freility: McGuire Nuclear Station Docket No. 50-369,370 1
I tecstlox: Mecklenburg County, North Carolina Report Period: Ol-J AN-1996 to 31 DEC-1996 i
Medium or Type and Total Lower Location with liighest
+
P:thway
. . All Indicator Control Routine Number Limit of Annual Mean Locations Location Report -
of Sampled Detection Name, Distance, Direction Meas.
i i Unit of Analyses Mean (Fraction) Location M asurement Performed (LLD) Mean Range Mean Range Range Code i
Broadleaf 134 Vegetation (8.8 mi WNW)
(pCi/kg-wet)
CS134 36 60 0.00(0/27) 0.00 (0/9) 0.00(0/9) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 j CS137 36 80 0.00 (0/27) 0.00 (0/9) 0.00(0/9) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 1131 36 60 0.00 (0/27) 0.00 (0/9) 0 0.00 (0/9)
- 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00
- Mean and range based upon detectable measurements only Frtction of detectable measurements at specified locations is indicated in parentheses, (Fraction) i Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments i
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i Repon Generated @ 3/19/97 4:5.5 PM Appendix B - Page 3
Environmental Radiological Monitoring Program Summary Fccility: McGuire Nuclear Station Docket No. 50-369,370 1
J
! Loc: tion: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31-DEC-1996 1
Medium or Type and Total Lower Location with liighest AH Indicator Pathway Number Limit of Annual Mean "5' anon Report Sampled of Detection Name, Distance, Direction Meas.
Unit of Analyr.cs Mean (Fraction) Location Measurement (LLD) Mean Range Mean Range Performed Range Code
] ,
4 Crops No Control (pCi/Lg-wet) Locations CS134 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00
, CSI37 12 80 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 O.00 0.00 0.00 - 0.00 0.00 - 0.00 1131 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 0.00 0.00 - 0.00 0.00 0.00 4
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 l
] If LLD is equal t0 0.00, then the LLD is not required by Selected Licensee Commitments
}
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Report Generated @ 3/19/97 4:54 PM Appendix B Page 4
Environmental Radiological Monitoring Program Summary Ftcility: McGuire Nuclear Station Docket No. 50-369.370 Locttiox: Mecklenburg County, North Carolina Report Period: Ol-JAN-1996 to 31 DEC-1996 Medium or Type and Total Lower Location with Highest nq l
- utme 9"'-
Pathway Number Limit of Annual Mean cau ns Cab n Sampled of Detection Name, Distance, Direction cPort Meas.
Unit of Analyses Mean (Fraction) Location M:asurement Performed Range Code
"" ""E "" ""E' Drinking Water 136 (pCi/ liter) (12.7 mi NNE)
BALA140 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 BETA 52 4 2.52 (37/39) 119 2.75 (13/13) 2.11 (12/13) 0 0.78- 6.45 (7.4 mi SSW) 0.85 - 6.45 0.86 - 4.11 CO58 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 CO60 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 CSI34 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 CS137 52 18 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 FE59 52 30 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 000 0.00 - 0.00 113 16 2000 353 (7/12) I19 360(4/4) 0.00 (0/4) 0 161 565 (7.4 mi SSW) 250- 565 0.00 - 0.00 1131 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 MN54 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 NB95 52 15 0.00(0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 O.00 - 0.00 0.00 - 0.00
_ZN65 52 30 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 ZR95 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 j
Mean and range based upon detectable measurements only j Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) i Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments ,
Report Generated @ 3/19'97 4.55 PM l Appendix B Page 5 1
Environmental Radiological Monitoring Program Sumniary Facility: McGuire Nuclear Station 50-369,370 Docket No.
' Location: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31 DEC-1996 Medium or Type and Total Lower "' "'
Location with Highest Pathway Limit of All Indicator Control Number ,, Routme Sampled of Detection Name, Distance, Direction catmn Repod J
Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed Range Code
"" ""E "" ""8' l
! Fish 137 l
(pCi/kg-wet)
(12.0 mi N)
)
{
C058 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
- CO60 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 CS134 12 130 0.00 (0/6) 0.00(0/6) 0.00 (0/6) 0 j
0.00 - 0.00 0.00 0.00 0.00 - 0.00
, CSl37 12 150 27.R (3/6) 129
! 27.8(3/6) 0.00(0/6) 0 17.4 - 37.5 (0.5 mi ENE) 17.4 37.5 0.00 - 0.00
- FE59 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
. MN54 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 ZN65 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 1 a
Mean and range based upon detectable measurements only j 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 i
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- Report Generated @ 3/1997 4
- 56 PM Appendix B Page 6
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I Environmental Radiological Monitoring Program Summary '
Freility: McGuire Nuclear Station l Docket No. 50-369,370 Bacitiox: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31-DEC-1996 Medium or Type and Total Lower Location with liighest ' I "'
Pathway Number Limit of
^" .
" .cator utine ations Annual Mean "5 Sampled of Detection Name, Distance, Direction a1 n epod Meas.
Unit of Analyses Mean (Fraction) Location 1
- "" ""E# "" ""E#
Measurement Performed Range Code Milk 141 (pCi/ liter)
(14.8 mi WNW)
BALA140 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 CS134 104 15 0.00 (0/78) 0.00 (0/26) 0 0.00 (0/26) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 104 18 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 1131 104 15 0.00 (0/78) 0.00 (0/26) 0 0.00 (0/26) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLII31 104 1 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 i
l 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 l
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f Repon Generated @ 3/19/97 4:57 PM Appendix B - Page 7 j
Environmental Radiologicci Monitoring Progrcm Summary Ftcility: McGuire Nuclear Station Docket No. 50-369,370 Loc:tior: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31 DEC-1996 Medium or Type and Total Lower Location with Highest All Indicator Control Routme Pathway Number Limit of ,
of Detection catm ns L catmn Repmt S mpled Name, Distance, Direction Meas.
Unit of Analyses "" "" " " "
(LLD) Mean Range Mean Range Measurement Performed Range Code Shoreline 137 Sediment (12.0 mi N)
(pCi/kg-dry)
C058 6 0 17.8 (2/4) 129 17.8(2/2) 0.00(0/2) 0 11.2 - 24.5 (0.5 mi ENE) i1.2 - 24.5 0.00 - 0.00 CO60 6 0 31.9(4/4) 130 35 (2/2) 0.00(0/2) 0 22.8 - 47 (0.5 mi SW) 23 - 47 0.00 - 0.00 CS134 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 CS137 6 180 96 (4/4) 130 147 (2/2) 198 (1/2) 0 24.8 156 (0.5 mi SW) 137 - 156 198 - 198 MN54 6 0 28.7(2/4) 130 29(2/2) 28.7(1/2) 0 26.2 - 31.2 (0.5 mi SW) 26.2 - 31.2 28.7 - 28.7 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)
Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3!!9W 4:58 PM l Appendix B Page 8
4 Environmental Radiological Monitoring Program Summary
- Facility
- McCulre Nuclear Station Docket No. 50-369,370 Loc:tio2: Mecklenburg County, North Carolina Report Period: 01-JAN-1996 to 31 DEC-1996 d M-Medium or Type and Total Lower No. of Non-g;, Location with Highest Pathway Number Limit of Control Routine Annual Mean "D "* ca n Sampled of Detection Name, Distance, Direction ePo Unit of Analyses Mean (Fraction) Location Measurement Performed Range
- " ""E* **" ""E*
Code I
j Surface Water 135
- (pCi/ liter)
(l1.9 mi N) n BEA140 39 15 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0 j 0.00 - 0.00 0.00 0.00 0.00 - 0.00 CO58 39 15 0.00 (0/26) 0.00 (0/13) 0 0.00 (0/13) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO60 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 !
- CS134 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
)
CS137 39 18 0.00 (0/26) 0.00 (0/13) 0
]
0.00 (0/13) _
O.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE59 39 30 0.00 (0/26) 0$00 (0/13) 0.00 (0/13) 0 4
0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H3 12 2000 638 (8/8) 128 808 (4/4) TOO (0/4) 0 i
277- 1730 (0.4 mi ENE) 336 - 1730 0.00 - 0.00 1I31 39 15 0.00(0/26) 0.00 (0/13) 0.00(0/I3) 0 1
0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 i MN54 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 j NB95 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 ZN65 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 ZR95 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 i
Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero r:nge indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments i
Report Generated @ 3/19 97 4:59 PM Appendix B Page 9 a
Environmental Radiological Monitoring Program Summary Freility: McGuire Nuclear Station Docket No. 50-369,370
, Locrtion: Mecklenburg County, North Carolina Report Period: Ol-JAN-1996 to 31-DEC-1996 1
Medium or Type and Total Lower Location with Highest No. of Non-gg g Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance. Direction
. Location Report Mm >
Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Direct Radiation 175 TLD j (15.5 mi WNW)
(mR/ Quarter) mR/Qtt 187 0.00E+00 18.1(183/183) 173 27.3(4/4) 24.7 (4/4) 0 10.2 - 32.8 (8.4 mi NNW) 23.9 - 30.7 22.2 - 26.3 Mean and range based upon detectable measurements only
! Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction) 1 Zero range indicates no detectable activity measurements f If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 1 l i
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APPENDIX C j
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SAMPLING DEVIATIONS i: UNAVAILABLE ANALYSES J
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APPENDIX C l 1
1 MCGUIRE NUCLEAR STATION l l SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES :
I l
DEVIATION & UNAVAILAHLE REASON CODES
! BF Blown Fuse K) l Power Outage FZ Sampic Frozen PS Pump out of service / Undergoing Repair iW inclement Weather SL Sample Loss / Lost due to Laboratory Accident LC Line Clog to Sampler SM Motor / Rotor Seized l OT Other TF Torn Filter l ' Pi Power interrupt VN Vandalism 1
1 PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radiciodines i Location Scheduled Actual Reason Corrective Action Collection Dates Collection Dates !
120 4/16 - 4/23/96 4/16 - 4/23/96 PI Dual samplers were operating at collection time. Both clocks indicated I the power was interrupted during l composite period.
l 134 2/27 - 3/5/96 2/27 - 2/29/96 Pl Breaker trip occurred. Deviation was associated with addition of second sampler which caused breaker trip due l to additional power requirements.
i 3/5 - 3/12/96 3/5 - 3/6/96 BF Replaced fuse and restarted sampler.
Main fuse to air sampler complex was blown. Deviation associated with addition of second sampler which caused breaker trip due to additional power reqdirements.
3/26 - 4/2/96 3/26-3/27/96 Pl Breaker box inside fence was tripped.
Backup air sampler turned off to reduce power consumption until l maintenance can upgrade electrical system. Work request submitted for electrical system upgrade to handle additional power requirements.
4/2 - 4/9/96 4/2 - 4/4/96 BF Breaker box inside fence was tripped.
Related to deviation of 3/26 - 4/2/96.
Electrical system was upgraded to handle increased air sampler power requirements. Work request was completed.
Appendix C- Page I
192 2/20 - 2/27/96 2/20 - 2/24/96 BF Fuse replaced - sampler #LVASl4 was tagged.
195 4/23 - 4/30/96 4/23 - 4/29/96 PO Breaker to air samplers was tripped.
Severe thunderstorms were suspected cause of breaker trip. The breaker was reset.
Drinking Water Location Scheduled Actual Reason Corrective Action Collection Dates Collection Dates 136 1/16 - 1/30/96 1/30/96 VN Grab sample collected. Sampling equipment was disconnected by construction workers without any prior notification. Personnel were asked to refrain from tampering with sampling equipment. A sign was placed above the sampling equipment requesting the Environmental Center personnel be contacted prior to any actions taken with the sampling equipment.
3/26- 4/9/96 4/9/96 VN Grab sample collected. Sampling equipment was again disconnected by construction personnel at the water treatment facility. Work request 96-MC5537 was written to modify the overflow drain to prevent possible sample vessel overflow. The work request was completed. Constniction at water treatment facility was completed and personnel tampering with water supply valve no longer present.
Surface Water Location Scheduled Actual Reason Corrective Action Collection Dates Collection Dates 131 8/13 - 8/27/96 8/27/96 OT No sample flow to sampler station at time of collection. Purnp was not operational. Work request was written to replace the pump. An "lSCO" portable water sampling pump was placed into operation to avoid any j additional sample loss. Work request completed and the pump was repaired.
Note: See Appendix A,Section V, Program Improvements, for a discussion on deviation reductions.
4 Appendix C- Page 2 1
1 C.2 UNAVAILABLE ANALYSES 1 The following unavailable analyses from sampling requirements occurred during 1996:
TLD Locaties Scheduled Reason Corrective Action CeMeetion Dates .
163 3/25-6/24/96 VN TLD missing. 3rd Quarter TLD was placed in field.
168 3/25-6/24/96 VN TLD missing. 3rd Quarter TLD was placed in f eld. ,
180 3/25 6/24/96 VN TLD missing. 3rd Quarter TLD was placed in field..
163 6/24 - 9/23/96 OT TLD missing. Structure the TLD was placed on had been l, removed. 4th Quarter TLD was placed in field. l 190 6/24 - 9/23/96 OT TLD missing. Tree limb TLD was placed on was missing due to weather or vandalism. TLD was moved to metal stake. 4th Quarter TLD was placed in field. I i
l l
l Appendix C- Page 3
APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 1996 Radiological Environmental Monitoring Program.
Appendix D - Page I
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS 1996 This appendix includes all of the sample analysis reports generated from each sample mediam for 1996. 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 1
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