ML20107M015
| ML20107M015 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 12/31/1995 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9604300135 | |
| Download: ML20107M015 (105) | |
Text
ll I DukeMgr Company T. C M6ftsm McGuire Nudear Generation Deparonent Vice President 12700HagersferryRoad(MG01\P) (704)8754800 Huntersome, NC280788985 (104)8754809 Fat DUKEPOWER April 24, 1996 U. S. Nucletr Regulatory Commission Attention: Document Control Desk washington, D.C. 20555
Subject:
McGuire Nuclear Stat Docket Nos. 50-369 ai. ;0-370 Annual Radiological Environmental Operating Report Pir;ase find attached the McGuire Nuclear Station Annual Radiological Environmental Operating Report for 1995 pursuant to McGuire Unit 1 and Unit 2 Technical Specification 6.9.1.6.
Questions or problems with respect to this report should be directed to Kay Crane, at (704) 875-4306.
Very truly yours,
</fk T. C. McMeekin, Vice President McGuire Nuclear Station Mr. Victor Nerses, Project Manager Mr. Dayne Brown Office of Nuclear Reactor Regulation Division of Radiation Protection U. S. Nuclear Regulatory Commission P.O. Box 27687 Washington, D.C. 20555 Raleigh, N.C. 27611-7687 i
Mr. S. D. Ebneter ANI Library U. S. Nuclear Regulatory Commission Town Center, Suite 300S Region II 29 South Pain Street 101 Marietta Street, NW - Suite 2900 West HartLord, CT Atlanta, Georgia 30323 06107-2445 Mr. George Maxwell Senior Resident Inspector !<
McGuire Nuclear Site )
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4 Annual l Radiological Environmental i
Operating Report 1995 1 i
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- ANNUAL RADIOLOGICAL i
ENVIRONMENTAL OPERATING REPORT 4
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i for i
i l DUKE POWER COMPANY j MCGUIRE NUCLEAR STATION
! Units 1 and 2 January 1 - December 31 i
I 1995 1
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TABLE OF CONTENTS TITLE PAGE List of Figures iv List of Tables . v List of Acronyms . vii
- 1. Executive Summary 1-1
- 2. Introduction . . 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of Environmental Monitoring Program 2-1 2.3 Statistical and Calculational Methodology 2-2 2.3.1 Estimation of the Mean Value . 2-2 1 1
2.3.2 Lower Level of Detection, Minimum Detectable Activity, and Critical Level 2-3 i 1
2.3.3 Trend Identification 2-3 2.3.4 Test Statistic . 2-5
- 3. Radiological Environmental Monitoring Program - Discussion, Interpretation, and Trending of Results 3-1 3.1 Airborne Radiciodines and Particulates. 3-2 l 3.1.1 Radiciodines . 3-2 1
3.1.2 Particulates 3-4 3.2 Drinking Water 3-6 3.3 Surface Water 3-8 3.4 Milk 3-10 :
3.5 BroadleafVegetation. 3-12 i
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l 3.6 Shoreline Sediment . . . . 3-14 I l
3.7 Fish . . . 3-16 I 3.8 Direct Gamma Radiation 3-18 I 3.9 Food Products 3-21 3.10 Land Use Census . . 3-23 l
- 4. Evaluation of Dose from Environmental Measurements Verses Estimated Dose from Releases . . . 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases . . 4-1 4.3 Comparison ofDoses 4-1 l 4.4 Pathway Dose Calculations 4-2
- 5. Quality Assurance . . . 5-1 5.1 Duke Power Company Environmental Laboratories 5-1 5.2 ContractorLaboratories . . . 5-4
- 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-2 III. Change of Analysis Procedures . A-2 IV. Sampling and Analysis Procedures A-2 A.1 Airborne Particulate and Radiciodines 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 ii
A.7 Fish . . . . , . A-4 A.8 Direct Gamma Radiation (TLD) . . . A-4 A.9 Food Products .
. . A-5 A.10 Annual Land Use Census A-5 V. ProgramImprovements . . A-6 Appendix B: Radiological Environmental Monitoring Program - Results Summary Air Particulate . .
. . B-1 Air Radioiodines B-2 BroadleafVegetation . . B-3 Food Products B-4 1 Drinking Water . . . . . . B-5 Fish. . .
. B-7 Milk . . .
. . B-8 l
Shoreline Sediment . . . B-9 Surface Water . . . . B-10 Direct Gamma Radiation (TLD) . . . B-11 Appendix C: Sampling Deviations and Unavailable Analyses C.1 Sampling Deviations . . . . C-1 C.2 Unavailable Analyses . . . C-4 C.3 Sample Deviation and Unavailable Reduction Plan . . C-4 Appendix D: Analytical Deviations - Lower Limits of Detection D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 iii i
LIST OF FIGURES FIGURE TITLE PAGE i
2.1-1 Sampling Locations Map (Site Boundary). . 2-9 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-10 3.1.1 Concentration ofRadionuclides in Airborne Radiciodines 3-2 3.1.2 Concentration of Radionuclides in Airborne Particulates . 3-4 3.2 Concentration of Radionuclides in Drinking Water 3-6 3.3 Concentration of Radionuclides in Surface Water . 3-8 3.4 Concentration of Radionuclides in Milk 3-10 3.5 Concentration of Radionuclides in Broadleaf Vegetation . 3-12 3.6 Concentration of Radionuclides in Shoreline Sediment. . 3-14 3.7 Concentration ofRadionuclides in Fish . . 3-16 3.8 TLD Exposure from Direct Radiation . . 3-18 3.9 Concentration of Radionuclides in Food Products. 3-21 3.10 Land Use Census Map . 3-26 iV
- _ . . - - . - - _ . . ~ . -. . . . -. . . -. .-
! LIST OF TABLES TABLE TITLE PAGE I l
l 2.1-A Radiological Monitoring Program Sampling Locations . 2-7 2.1-B Radiological Monitoring Program Sampling Locations (TLD) 2-8 i 2.2-A Reporting Levels for Radioactivity Concentrations in
! Environmental Samples . . 2-11 3
2.2-B REMP Analysis Frequency . . . 2-12 l 2.2-C Lower Limit of Detection Capabilities for Environmental Sample Analysis . . 2-13 l
3.1.1-A Concentration of Radionuclides in Airborne Radiciodines 3-3 3.1.1-B Percentages of Reporting Levels for Radiciodines . . 3-3 3.1.2 Percentages of Reporting Levels for Particulates 3-5 3.2-A Concentration of Radionuclides in Drinking Water 3-7 3.2-B Percentages of Reporting Levels for Drinking Water 3-7 3.3-A Concentration of Radionuclides in Surface Water . . . . 3-9 3.3-B Percentages of Reporting Levels for Surface Water 3-9 3.4-A Concentration of Radionuclides in Milk . . . 3-11 ;
3.4-B Percentages of Reporting Levels for Milk . . . . 3-11 i 3.5-A Concentration of Radionuclides in Broadleaf Vegetation 3-13 3.5-B Percentages of Reponing Levels for Broadleaf Vegetation . . 3-13 3.6-A Concentration of Radionuclides in Shoreline Sediment. . 3-15 3.6-B Comparison ofIndicator and Control Means for Shoreline Sediment . 3-15 3.7-A Concentration of Radionuclides in Fish . . 3-17 3.7-B Percentages of Reporting Levels for Fish . . 3-17 3.8-A TLD Exposure from Direct Radiation . 3-19 3.8-B Comparison ofInner Ring / Outer Ring TLD Results . 3-20 3.9 Percentages of Reporting Levels for Food Products 3-22 v
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3.10 Land Use Census Results . . . 3-24 4.1-A 1995 Environmental and Effluent Dose Comparison for Liquid and Gaseous Waste Release Pathways 4-3 4.1-B Maximum Individual Dose Summary for 1995 . 4-5 5.0-A Duke Power Company Interlaboratory Comparison Program . 5-5 5.0-B 'U.S. Environmental Protection Agency Interlaboratory ;
Comparison Program . 5-7 5.0-C State of Nonh Carolina DEHNR 1995 Environmental I Dosimeter Crost-Check Results 5-9 C.3-A Deviation Reduction Plan Overview. . . . C-4 C.3-B Deviation Reduction Plan Equipment Purchases . . C-5 l C.3-C Deviation Reduction Plan Air Site Upgrade Equipment Purchases . . C-6 ,
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LIST OF ACRONYMS :
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l Acronyms and their interpretations used in this report (displayed alphabetically) l 1
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l ACRONYM DEFINITION BW Biweekly I C Control CL Critical Level DEHNR Department of Emironmental Health and Natural Resources DHEC Department of Health and Emironmental Control l EPA Environmental Protection Agency l FSAR Final Safety Analysis Report l LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Actisity MNS McGuire Nuclear Station mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picoeurie per liter pCi/m3 picocurie per cubic meter Q Quarterly REMP Radiological Emironmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECS Technical Specifications TLD Thermoluminescent Dosimeter uCi/ml microcurie per milliliter
! W Weekly 4
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l 1.0 EXECUTIVE
SUMMARY
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This Annual Radiological Environmental Operating Report describes the McGuire Nuclear 1 Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 1995.
J 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 samples were analyzed comprising 9000 test l
- l results in order to compile data for the 1995 report. Based on the annual land use census, i the current number of sampling sites for McGuire Nuclear Station is sufficient. !
l Concentrations observed in the environment in 1995 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, ddnking 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 j i
results, was 6.86E-02 mrem for 1995. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.
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section 1 - Page 1
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of the highly industrialized region on the Carolinas. The land is predominantly rural non-farm with a small amount of land being used to support beef cattle and farming. Recreation in the area is confined mostly to the lake and shores ofLake Norman and Mountain Island reservoir. The McGuire site is in northwestern Mecklenburg County, North Carolina,17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the nonh by 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Hydroelectric Station , which is located immediately west of the site and on the Catawba River channel. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals Hydroelectric Station is at the upper reaches of Lake Norman. Marshall Steam Station is located on the western shore of Lake 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 REOUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM 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 environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.
The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation. .
l This monitoring program is based on NRC guidance as reflected in 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- j made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from McGuire Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides Section 2 - Page 1 J
surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the environment.
Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A.
Table 2.2-B lists the REMP analysis and frequency schedule. 1
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The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by )
changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to l 10CFR50. Results are shown in Table 3.10. !
Participation in an approved Interlaboratory Comparison Program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed l as part of the quality assurance program for environmental monitoring in order to demonstrate I that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A l
summary of the results obtained as part of this comparison program are in Section 5 of this l annual report.
2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):
N Ix, x =
N Where:
~
x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) xi = net activity (or concentration) for sample i.
Section 2 - Page 2
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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 concentration.s 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. I 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, j above the system background, that will be detected with 95% probability with only 5% l probability of falsely concluding that a blank observation represents a "real" signal. l The LLD is an apriori lower limit of detection. The actual LLD is dependent upon l the standard deviation of the background counting rate, the counting efficiency, the l sample size (mass or volume), the radiochemical yield, and the radioactive decay of the j sample between sample collection and counting. The " required" LLD's for each ;
sample medium and selected radionuclides are given in the Selected Licensee l 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.
1 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.
1 2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup ~of radionuclides in the environment due to the operation of the nuclear station. This is traditionally done by looking at historical data (including ,
preoperational data) and determining if a trend exists. Trends, if they exist, may be l either positive or negative. Since nuclear reactor operations do not remove radioactivity from the surrounding environment, a negative trend in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the l preoperational level and that the normal removal processes (radioactive decay, l deposition, resuspension, etc.) are influencing concentration.
I Section 2 - Page 3
J In many cases, visual inspection of tabular or graphical presentations of data may be sufficient to deterniine if a trend exists. In other cases, it may not be so obvious.
4 Therefore, it is desirable to obtain a single numerical value from the data which will permit a meanmgful interpretation of the relationship existing between the variations in I the data. Ifit is assumed that a linear relationship exists between the time after startup ;
of the reactor and the amount of radionuclides in a particular environmental medium, !
the least squares regression method may be used to define the linear relationship. To ;
determine if the data actually correlate to the straight line assumption, the theoretical I l variance is compared to the actual variance. The numerical value that summarizes this '
comparison is known as the correlation coefficient.
This correlation coefficient, symbolized by "r", is a determination of how closely the
- data fit a straight line and may be calculated from the following equation (reference 6.8)- .l i I
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NEXY- EXEY r= , i
[(NEX _(gg):yg37 _(37)2)p 2 2 l
l Where:
e i r = correlation coefficient for the data set of X and Y, X = the year or point in time, Y = the radionuclide concentration associated with X, N = number of observations.
The range of values as calculated by the correlation coefficient lies between positive l
- one (+1) and negative one (-1). Zero (0) represents no indication of either a positive i or negative trend. A positive (+) correlation coefficient indicates an increasing trend, 1 l and conversely, a negative (-) correlation coefficient indicates a decreasing trend. The ,
j ' absolute value of the correlation coefficient indicates the strength of the relationship or
' l probability of a trend.
i Identifying a trend by using the correlation coefficient is only useful for the time
- periods where the discharge from the nuclear plant is relatively stable and no other
- sources of radioactivity are present. Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the
, resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, i determined from the environmental data. Other factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought or
. heavier than normal precipitation), constmetion in or around either the nuclear plant or J. the sampling location, addition or deletion of other sources of radioactive materials (such as the Chernobyl accident), etc.. Some of these factors may be obvious while others are sometimes unknown to the plant personnel. Specific discussion of i
I Section 2 - Page 4
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correlation coefficient results are discussed in Section 3, " Radiological Environmental )
Monitoring Program - Discussion, Interpretation, and Trending of Results".
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The change in the method of calculating the mean (using only net positive results incorporated in 1987) will also affect the apparent trends.
Because of the above considerations, how trends are identified will depend not only on the least squares regression method, but will include some judgment by plant personnel on the factors affecting environmental levels.
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2.3.4 TEST STATISTIC i i
In some cases, we would not expect to observe a buildup of radionuclides in the j environment, but instead would expect to see a measurable increase in levels over a short duration. This is the case for direct radiation measurements, where the radiation level is measured over a finite period and is dependent upon whether plant discharges were occurring at that time or not. In this case, the correlation coefficient is not a sufficient indicator of whether effluents are having an impact on the eiwironment, since there is no bioaccumulation. Another test is needed to give us a meaningful interpretation of the data.
1 The statistic that compares the means from two sets of measurements to determine if l there is a statistically significant difference is called the test statistic, or t-statistic, and j is calculated as follows (reference 6.7):
,, Xi - X2 3 S, 1
+1 n, n2 Where:
. K =
the mean value of the first set of measurements K = the mean value of the second set of measurements
=
S, the common variance of the two sets of measurements l
S, =
f Where:
2 (n, - 1)s,2 + (y _ 3),2 S# =
1 n+n-2 i 2 n3 = the number of measurements in the first data set Section 2 - Page $
n2 =
the number of measurements in the second data set
= the sample variance of the first data set si I
s2 = the sample variance of the second data set The calculated value of the test statistic is then compared to expected values of the test statistic tabulated based on the number ofmeasurements taken and the degree of confidence required for the results. The calculated value of the test statistic will be i
compared to the expected value at the 95% and 99% confidence levels. A positive i value occurs (the two sets of data are significantly different) when the absolute value
- of the calculated test statistic exceeds the absolute value of the expected tabulated i value.
i Due to the existence of naturally occurring differences in background radiation levels over time (as a result of solar cycles and other meteorological phenomena) and systematic errors due to instrument variability, ratios of measurements can be used to
- calculate the t-statistic instead ofindividual measurements. By using ratios, biases associated with the measurement process are minimized and allow us to more accurately compare results from one year to the next. Specifically, in the case of TLD measurements, the inner ring of TLD results'is ratioed with the outer ring of TLD measurements in a given year and the ratio for one year is compared to the ratio for i an ther year.
As with other environmental samples, outside factors may affect the results observed
. and the resulting trends identified. Therefore, the significance of trends will be based in part on judgment of plant personnel familiar with the factors affecting environmental
- levels, as well as the statistical results i
n j
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Section 2 - Page 6 j
TABLE 2.1-A I
MCGUIRE RADIOLOGICAL MONITORING PROGRAM l SAMPLING LOCATIONS l
I TABLE 2.1-A CODES W Weekly SM Semimonthly l BW Biweekly Q Quarterly M Monthly SA Semiannually C Control Site h6On DeScripdOn ""8 8'"""' '* "d" 8" '
, "ar"an 'w""'
aw w""aw seh m'"' uitv"es.
I19 Mt. Holly Murucipal Water Supply ( 7.4 nu SSW ) BW 120 Site Boundary ( 0.5 mi hWE ) W M(b) 12i Site Boundary ( 0.5 mi NE ) W 125 Site Boundary ( 0.4 mi SW ) W M(b) 128 Durcharge Canal Bridge ( 0 4 mi ENE ) BW 129 Discharge Canal Entrance to IAe Norman ( 0.5 mi ENE) SA SA 130 Hwy 73 Bridge Downstream ( 0.5 mi SW ) SA 131 Cowans Ford Dam ( 0 6 mi W ) BW l32 Charlotte Murucipal Water Supply ( l1.2 mi SSE ) BW I33 Comelius ( 6.2 mi NE ) W 134 C East Lincoln Jr.High School ( 8.8 mi WNW ) W M(b) 135 C Plant Marshall Intake Canal ( l 1.9 mi N ) BW 136 C Mooresville Murucipal Water Supply ( 12.7 mi NNE ) BW 137 C Pmnacle Access Area ( l2.0 mi N ) SA SA 138 Henry Cook Dairy ( 3.1 mi ESE ) SM 139 Wilham Cook Dairy ( 2.5 mi E ) SM i40 Kidd Daarv4ows ( 2.7 mi SSE ) SM 14i C Lwch Dairy-Cows ( l4.8 mi WNW ) SM i88 5 mile radius Gardens ( 2.8 mi N ) M (a )
192 Peninsula ( 2.8 mi NNE ) W 193 Site Boundarv ( 0.2 mi N ) M(b) 194 East Lincoln County Water Supply ( 6.7 mi NNW ) BW 195 Fishmg Access Road ( 0.2 mi N ) W (a) During Han'eSt Season (b) When Available Section 2 - Page 7
TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
Location Description 87 Location Description 87 143 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 miles E 171 4-5 MILE RADIUS 4.0 miles NW 148 SITE BOUNDARY 0.5 miles ESE 172 4-5 MILE RADIUS 5.7 miles NNW 149 SITE BOUNDARY 0.5 miles SE 173 SPECIALINTEREST 8.4 miles NNW 151 SITE BOUNDARY 0.4 miles S 174 PECIAL INTEREST 8.8 miles WNW 152 SITE BOUNDARY 0.4 miles SSW 175 CONTROL 12.7 miles WNW 153 SITE BOUNDARY 0.5 miles SW 176 SPECLAL INTEREST 11.0 miles SW 154 SITE BOUNDARY 0.5 miles W 177 SPECIALINTEREST 8.8 miles S 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 SPECIALINTEREST 7.0 miles NE 158 4-5 MILE RADIUS 4.3 miles NNE 182 SPECIALINTEREST 6.2 miles NE 159 4-5 MILE RADIUS 5.0 miles NE 183 SPECIALINTEREST 5.8 miles S 160 4-5 MILE RADIUS 4.9 miles ENE 186 SPECIALINTEREST 0.2 miles NNW 161 4-5 MILE RADIUS 4.7 miles E 187 SPECIALINTEREST 0.2 miles N 162 4-5 MILE RADIUS 4.5 miles ESE 191 SITE BOUNDARY 2.8 miles SSE 163 4-5 MILE RADIUS 4.9 miles SE 196 SPECIAL INTEREST 1.0 miles S 164 4-5 MILE RADIUS 4.6 miles SSE 197 SPECIALINTEREST 1.1 miles S 165 4-5 MILE RADIUS 5.1 miles S 198 SPECIALINTEREST 1.3 miles S 166 4-5 MILE RADIUS 5.3 miles SSW 199 SPECIALINTEREST 1.5 miles S
- AllTLDs are collected quarterly 1
J 4
w Secuan 2 - Page 8
Figure 2.1-1 sampling Locations Map (SitC U""
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?( I A ALL OTHER SAMPLING LOCATIONS MCGUIRE NUCLEAR STATION f FIGURE 2.1-2 SAMPIlNG LOCATIONS MAP (TEN MILE RADIUS)
LOTTE WATER WORKS Section 2. Page 10 c
fo 00 r 300135 -01 "
__ J
TABLE 2.2-A 1
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES l
Analysis Water Air Particulates Fish Milk BroadLeaf l (pCi/ liter) or Gases (pCi/kg-wet) (pCi/ liter) Vegetation 1 (pCi/m8) (pCi/kg-wet)
H3 20,000)
Mn54 1,000 30,000 j Fe59 400 10,000 CoS8 1,000 30,000 l l Co60 300 10,000 I
Zn65 300 20,000 Zr-Nb-95 400 I131 2 1 3 100 Csl34 30 10 1,000 60 1,000 Csl37 50 20 2,000 70 2,000 l Ba-La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of30,000pCi/ liter may be used.
l
[
Section 2 - Page 11 l
l
! l l
1 i l TABLE 2.2-B i
REMP ANALYSIS FREQUENCY a
. SAMPLE ANALYSIS GAMMA TRITIUM LOW GROSS TLD MEDIUM SCHEDULE ISOTOPIC LEVEL BETA i
! Air Radioiodine j and Particulates Weekly X X j Direct Radiation Quarterly X
< Monthly
- Surface Composite X j Water Quarterly l
Composite X
- Biweekly X
! Monthly i 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 12 s
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 I131 1*> 0.07 1 60 Csl34 15 0.05 130 15 60 150 Cs137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) Ifno drinking waterpathway exists, a value of3000 pCi/ liter may be used.
(b) Ifno drinking waterpathway exists, the IlD ofgamma isotopic analysis may be used.
1 l
l Section 2 - Page 13
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS i The radionuclides with Selected Licensee Commitments reponing levels in the environmental media samples that indicated detectable activity since the change of analysis techniques in 1988 have been historically trended over a seventeen-year period from 1979 - '
1995. Fish media have been trended over a sixteen year period since indicator samples were i not available in 1979. Analyses from 1977 - 1978 have been excluded since these results l were much higher than the other preoperational years due to outside influence such as ;
weapons testing. Including these results would have produced correlation coefficients and averages that were not representative. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year. The highest annual mean concentration of applicable Selected Licensee Commitments radionuclides from the indicator locations for each media type was used for the estimation of the mean value and correlation coefficient.
Highest annual means were used to determine trends and occasionally the average I
concentrations reported were negative. Negative values were obtained using reported activities that were less than the assumed background. All negative values (concentrations) were replaced with a zero to properly represent environmental conditions. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels. Figures 3.1.1 through 3.9 provide a graphical presentation of the indicator highest l means, control means, and reporting levels (if applicable) for each media type. Control I means for food products were not graphed since there is no food products control location.
In addition, the percentages of Selected Licensee Commitments reporting levels were calculated for each reportable radionuclide in each media type.
No Selected Licensee Commitments reporting levels were exccaled or approached in 1995 due to plant effluents.
Only the radionuclides with Selected Licensee Commitments reponing levels that have shown consistent activity since 1989 were historically trended and compared with the sixteen-year average. All other radionuclides demonstrated no detectable activity for the past seven years and have shown decreasing or no trends. It is important to note that while historical trends are helpful in determmmg radioactivity buildup, environmental radionuclide levels could be affected without exhibiting increasing or decreasing trends.
section 3 - Page 1
3.1 AIRBORNE RADIOIODINES AND PARTICULATES 3.1.1 RADIOIODINES I
In 1995,364 radiciodine samples were analyzed,312 at six indicator locations and 52 at the controllocation.
l No detectable 1-131 activity in environnental air samples was found in 1995. Cs-137 was i found in one indicator sample and two control samples. However, no Cs-137 was found on the corresponding particulate filters. An investigation performed in 1990 concluded that Cs-137 activity detected only on the cartridges was not attributed by station effluents but was an j active constituent of the charcoal media (reference 6.5). Therefore, the Cs-137 activity was not used to calculate correlation coefficients or doses.
Figure 3.1.1 shows I-131 indicator and control location concentrations with cornparisons to 10% of the reporting level. Table 3.1.1-A gives indicator location higlest annual means since 1979 for I-131. Preoperational and sixteen year averages are also shown. The correlation coefficient indicated a decreasing trend for I-131. No I-131 activity has been ,
detected since 1989. Table 3.1.1-B shows control location means and the percentages of l l
environmental concentrations to the Selected Licensee Commitments reporting levels for the l indicators at the locations with the highest annual mean for 1995. No activity was detected l and therefore no reporting levels were approached.
1 FIGURE 3.1.1 pcum. CONCENTRATION OF RADIONUCLlDES IN AIRBORNE RADIOlODINES 1.20E41 i 10%OFREPoRnNGl.EVEL
! 1.00E41.
8.00E42 6.00E42 -- - -
4.00E42 2.00E42 - - -- - - -'
m .
0.00E+00 '
Year l*"#"k131 Indicator ""*"*k131 Control ""*"10% of Reporting Level l settinn 3 Page 2
Tahle 3.1.1,A C nneantrafinn of Rndinnnelidac in Alrhorne RndinIndinec R I 131 Indicator (pCi/m')
J 1980* 2.01E-3 1981* 4.17E-3 1982* 1.42E-3 1983* 1.99E-3
! 1984 3.17E-3 1985 3.15E-3 l 1986 1.27E-2 i
1987 1.07E-2 I
1988 0.00E0 1 1989 2.18E-2 1990 0.00E0
} 1991 0.00E0
! 1992 0.00E0 1993 0.00E0 1994 0.00E0 16 Year Average 4.03E-3 1995' O.00E0 Correlation Coefficient -0.14
- Ra.lioiodines and Paniculates analyzed together, l
Tahle 3.1.1 R Percentages of Reporting Imek for Radinindines Radionuclide Indicator Reporting Level Percentage of Control Mean Highest Mean (pCi/m') Reporting Level (pCi/m')
(pCi/m3) 1-131 0.00E0 1.00E0 0.00 % 0.00EC Secnon 3 Page3
3.1.2 PARTICULATES l
In 1995,364 particulate samples were analyzed,312 at the six indicator locations and 52 at the controllocation.
Per Selected Licensee Commitments, if gross beta in air particulate samples is gmater than ten times the yearly mean of controi samples, gamma isotopic analysis shall be performed on individual samples. Although the location with the highest mean (3.02E-2 pCi/m') was less than ten times the yearly mean of the controllocation (5.17E-2 pCi/m'), gamma isotopic analysis was performed on all paniculate filters. No detectable gamma emitting particulate activity was found in environmental air samples in 1995. Figure 3.1.2 shows Cs-137 indicator and control location concentrations with comparisons to 1% of the reporting level. Since no activity has been detected since 1987, all radionuclides have indicated decreasing or no trends.
Table 3.1.2 shows control location means and the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicator locations with the highest annual mean for 1995. No activity was detected and therefore no reporting levels were approached.
l i
FIGURE 3.1.2 g CONCENTRATION OF RADIONUCLIDES IN AIRBORNE PARTICULATES 1% OF REPORTING Ll! VEL l
1.50E41 l
l 1.00E41 l 5.00E42 -
JL 0.00E+00 Year l
l*C&137 Indicator *CD137 Control *1% of Reporting Level l I
l l
l sat % 3 -Page 4
Tahle 3.1.2 Percentmoes of Dennatino Imrels.for Particulates i
1 4
Radionuclide Indicator Reporting Level Percentage of Control Mean Highest Mean (pCi/m3) Reporting Level (pCi/m')
j (pCi/m3) i I-131 0.00E0 1.00E0 0.00 % 0.00E0
)i Cs-134 0.00E0 1.00E1 0.00 % 0.00E0 Cs-137 0.00E0 2.00E1 0.00 % 0.00E0 1
l i
1 5
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4 I
section 3 Page5
3.2 DRINKING WATER In 1995,52 drinking water samples were analyzed for beta, I-131/LL, and other gamma emitting radionuclides. Thirty-nine samples were from the tlure indicator locations and 13 from the control location. Tritium (H-3) analyses were performed on 16 composite samples,12 at indicator locations and four at the controllocation.
No detectable gamma activity was found in drinking water samples in 1995 and has not been detected since 1987. Beta analyses indicated 4.2 pCill at the location with the highest annual mean and 3.3 pCi/l at the control location. Tritium was detected in one of the 12 indicator composite samples taken in 1995. Figure 3.2 shows tritium indicator and control location concentrations with comparisons to 10% of the reporting level.
Table 3.2-A gives indicator location highest annual means since 1979 for H-3.
Preoperational and sixteen year averages are also shown. The cormlation coefficient, '
which was slightly above zero, indicated an increasing trend for H-3. All other radionuclides have decreasing or no trends.
Table 3.2-B shows control location means and the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the lccations with the highest annual mean for 1995. The one 1995 sample that indicated tritium activity resulted in only 1.79% of the reporting level and was less than the sixteen year average.
FIGURE 3.2 pc W ter CONCENTRATION OF RADIONUCLIDES IN DRINKING WATER es00 10%oF RIEPORT NG lE/EL 2000.
1500 l 1000
) .
y ) Y
/> f 0 -
Year l*H-3 Indecator *10% of Reporting '.evel *H-3 Control l Scoion 3 Page6
Tahle 3.2-A Concentration of Radionuclides in Drinking Water YEAR H-3 Indicator (pCl/l) 1979 1.65E2 1980 1.63E2 1981 1.88E2 1982 2.43E2 1983 2.65E2 1984 5.77E2 1985 5.93E2 l
1986 1.14E3 l
1987 1.35E3 1988 9.92E2 ,
l 1989 5.62E2 l 1990 7.32E2 l 1991 5.22E2 i 1992 6.73E2 l l 1993 0.00E0 1994 0.00E0 l 16 Year Average 5.10E2 1995 ? 3.58E2 -
Correlation Coefficient 0.09 l
Tnhle 3.2-B Pawoninoes of Dennr41no I#vels for Drinkino Water Radionuclide Indicator Reporting Level Percentage of Control Mean Highest Mean (pCill) Reporting Level (pCi/1)
(pCi/1)
H-3 i 3.58E2 2.00E4 1.79 % 0.00E0 Mn-54 0.00E0 1.00E3 0.00 % 0.00E0 Fe-59 0.00E0 4.00E2 0.00 % 0.00E0 Co-58 0.00E0 1.00E3 0.00 % 0.00E0 Co-60 0.00E0 3.00E2 0.00 % 0.00E0 Zn-65 0.00E0 3.00E2 0.00 % 0.00E0 Nb-95 0.00E0 4.00E2 0.00 % 0.00E0 Zr-95 0.00E0 4.00E2 0.00 % 0.90E0 I-131/LL 0.00E0 2.00E0 0.00 % 0.00E0 Cs-134 0.00E0 3.00E1 0.00 % 0.00E0
! Cs-137 0.00E0 5.00E1 0.00 % 0.00E0 Ba/La-140 0.00E0 2.00E2 0.00 % 0.00E0 Section 3-Page7
I 3.3 SURFACE WATER In 1995,39 surface water samples were analyzed for I-131/LL and other gamma emitting radionuclides,26 at the two indicator locations and 13 at the controllocation. Analyses for H 3 were performed on 12 samples, eight at indicator locations and four at the control location.
No detectable gamma activity was found in surface water samples in 1995 and has not been detected since 1988. Tritium was detected in three of the eight indicator composite samples taken in 1995. Figure 3.3 shows tritium indicator and control location concentrations with comparisons to 20% of the reporting level. Table 3.3-A gives indicator location highest annual means since 1979 for H-3, Preoperational and sixteen year averages are also shown.
The correlation coefficient indicated an increasing trend for H 3. All other radionuclides have decreasing or no trends.
Table 3.3-B shows control location means and the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1995. He samples that indicated H-3 activity in 1995 resulted in only 1.58% of the reporting level and was less than the sixteen year average.
FIGURE 3.3 Amer CONCENTRATION OF RADIONUCLIDES IN SURFACE WATER 2(% OF REPOlm NGLEVEl.
4000.
3500 l
3000 2500 2000 1500 --
/ nh w~/%
sw
- j Year l*H 3 Indicator *H-3 Control *20% of Reporting Leve4 l section 3 Page8
l l
Tahle 3 LA Cancentralian of Radiarmelariac fn Surface Water YEAR H-3 Indicator (pCi/l) 1979 1.85E2 1980 2.13E2 1981 1.75E2 1982 3.30E2 1983 5.75E2 1984 4.10E2 1985 7.33E2 1986 2.33E3 1987 9.20E2 1988 9.40E2 1989 8.22E2 1990 6.77E2 1991 7.53E2 1992 8.13E2 1993 6.85E2 1994 0.00E0 16 Year Average 6.60E2 1995 >
3.15E2 Correlation Coefficient 0.13 I I
Tahle 3_%H Percentmees of Ronni4ina Isvels for Surface Water i
Radionuclide Indicator Reporting Level Percentage of Control Mean l Highest Mean (pCi/l) Reporting Level (pC1/l)
(pCi/l)
H-3 3.15E2 2.00E4 1.58%: . 0.00E0 -
Mn-54 0.00E0 1.00E3 0.00 % 0.00E0 Fe-59 0.00E0 4.00E2 0.00 % 0.00E0 Co-58 0.00E0 1.00E3 0.00 % 0.00E0 Co-60 0.00E0 3.00E2 0.00 % 0.00E0 Zn-65 0.00E0 3.00E2 0.00 % 0.00E0 l Nb-95 0.00E0 4.00E2 0.00 % 0.00E0 Zr-95 0.00E0 4.00E2 0.00 % 0.00E0 1-131/LL 0.00E0 2.00E0 0.00 % 0.00E0 Cs-134 0.00E0 3.00E1 0.00 % 0.00E0 Cs-137 0.00E0 5.00E1 0.00 % 0.00E0 Ba/La-140 0.00E0 2.00E2 0.00 % 0.00E0 Section 3.Page9 l
I I
3.4 MILK I In 1995,104 milk samples were analyzed for I-131/LL 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 1995. Cs-137 has not been detected in milk samples since 1990 and all other radionuclides have not been detected since 1987. l Figure 3.4 shows Cs-137 indicator and control location concentrations with comparisons to the reporting level. Table 3.4-A gives indicator location highest annual means since 1979 for
)
Cs-137. Preoperational and sixteen year averages are also shown. The correlation coefficient indicated a decreasing trend for Cs-137. All other radionuclides have decreasing or no trends.
Table 3.4-B shows control location means and the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual means for 1995. No activity was detected and therefore no reporting levels were approached.
FIGURE 3.4
,, CONCENTRATION OF RADIONUCLIDES IN j MILK 1 80 REPORTNG LE'fEL 70 -
l 80 50 1
40 30 i
20 - -
10 -
Year l*Co-137 Indicator *10% of Reporting Level *Co 137 Controll satinn 3 Page 16
]
Tahle 3.7-A Cancentratian of Radiannelides in Fish YEAR Mn 54 Co-58 Co-60 Cs-134 Cs 137 Indicator ' Indicator Indicator Indicator Indicator I
(pCi/kg-wet) (pCi/kg-wet) (pCi/kg wet) (pCl/kg-wet) (pCi/kg-wet) l 1980 -1.97El 8.36E0 -2.25El -2.70E1 -4.13E0 1981 -2.71E0 -2.98E0 -2.65E0 -1.99E0 1.80E1
- 1982 -3.83E0 8.16E0 -4.34E-1 -8.22E-1 2.69El 1983 -2.60E0 2.60E1 1.11El -1.32E0 6.03E1 1984 3.61E0 1.45E2 2.82E1 3.11El 4.38E1 1985 2.53E-1 7.19E0 1.72E1 -1.56E0 1.86El 4 1986 1.03E0 3.17El 2.96El 1.67El 3.49El 1 3
1987 0.00E0 2.71E2 1.25E2 2.60E1 5.10E1 1988 1.20E1 7.70E1 0.00E0 2.70E1 3.60E1 1989 9.00E1 4.05E2 2.99E2 1.10E1 3.50E1 1
1990 0.00E0 5.60E1 4.10E1 0.00E0 3.30E1 l 4
1991 6.20E0 1.40E1 6.50E1 5.90E0 2.60E1
- 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90E1 1993 0.00E0 8.20E1 1.30E1 0.00E0 1.60E1 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10E1
- 15 Year 7.54E0 7.54E1 4.19El 7.85E0 3.06El ,
4 Average 1
-1995' - 0.00E0 - 0.00E0 : 0.00E0 0.00E0 2.70E1 -
~
Correlation 0.09 0.04 0.10 -0.12 0.05 Coefficient j NOTE: All negative values were replaced with "zero's" for calculational purposes.
2 I
Table 3.7-B Percentnoes of Rennetino Isvels for Fish Radionuclide Indicator Reporting Level Percentage of Control Mean Highest Mean (pCi/kg) Reporting Level (pCi/kg) l
! (pCi/kg) l
[ Mn-54 0.00E0 3.00E4 0.00 % 0.00E0 4
Fe-59 0.00E0 1.00E4 0.00 % 0.00E0 l Co-58 0.00E0 3.00E4 0.00 % 0.00E0 i Co-60 0.00E0 1.00E4 0.00 % 0.00E0 Zn-65 0.00E0 2.00E4 0.00 % 0.00E0 Cs-134 0.00E0 1.00E3 0.00 % 0.00E0
. Cs-137 ' 2.70E1 2.00E3 1.35 % 0.00E0 l
Section 3.Page 17 l
3.8 DIRECT GAMMA RADIATION In 1995,188 TLD's were analyzed,184 at indicator locations and four at the control location.
Figure 3.8 shows TLD highest nean indicator and control location exposure rates in j millirem per year. Table 3.8-A gives indicator and control location highest annual means since 1979. Preoperational data and sixteen year averages are also given.
i I l i
I FIGURE 3.8 TLD EXPOSURE
"'" FROM DIRECT RADIATION
- 200 l
1 l 100 -
i 120-- - -- - -- -
i
- s N
N/ /N// /
) 40
/Nd 1
0 j 1979 1980 '1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1933 1994 1995 Year f *TLDIndcator *TLD Contred l l
I section 3 Page 18 J
l l
Tahla 3AA TI D Fvnnem fmm Direct DarlintIan l
YEAR Indicator (mrem /yr) Control (mrem /yr) '
1979 8.76El 8.32E1 1980 1.16E2 1.05E2 1981 1.45E2 1.05E2 1982 1.36E2 1.10E2 1983 1.75E2 1.30E2 1984 1.20E2 9.02E1 1985 1.52E2 1.27E2 1986 1.40E2 1.10E2 1987 1.43E2 1.23E2 1988 1.08E2 5.48E1 1989 9.77El 7.55El 1990 8.30E1 6.23E1 1991 9.60E1 6.80E1 1992 1.12E2 7.60E1 1993 1.00E2 7.20E1 1994 1.09E2 9.55El i 16 Year Average 1.20E2 9.30E1 1995- -
1.32E2 1.08E2 NOTE: The expected background for North Carolina is 120 mrem per year from FSAR 11.6.1.
l l
l l
Season 3.Page19
1 l The test statistic, or t-test, was used to corr. pare the TLD measurements during preoperation i to those taken during 1995.
l 1
The value of the t-statistic was cakulated by companng preoperational results to 1995. As l 4
shown in Table 3.8-B, the t-value was -2.115. This is slightly higher than the expected value of12.056, based on 26 degrees of freedom and 95% confidence level (n = 0.025, n = 26),
but is well within the acceptable value ofi 2.779 (a = 0.005, n = 26) for the 99%
conSdence level. Also, because the cakulated whole body dose from gaseous efDuents for 1995 was 0.14 rruem (0.1% of total TLD dose), it can be concluded that discharges from ;
the plant had very little impact on the measured TLD values.
Table 3.8-B Comparison of Inner Ring / Outer Ring TLD Results 1995 (mr/yr) Preop (mr/yr)
Inner Ring 83.6 79.14 Outer Ring 82.5 88.16 Ratio 1.03 0.91 Variance 0.02 0.02 t-value -2.115 ,
i t-table (95%) 2.056 I t-table (99%) 2.779 saman 3.Page20
3.9 FOOD PRODUCTS J
i In 1995,10 food products (crops) samples were analyzed, all at one indicator location. Them is no controllocation for this media.
1 No detectable activity was found in food products samples in 1995. Since no activity has been
- detected in this media since 1987, any possible trends are decreasing or nonexistent. Figum 3.9 shows Cs-137 indicator highest annual means since 1979 with comparisons to 10% of the j reporting level. Table 3.9 shows percentages of environmental concentrations to the SLCS reporting levels for the indicator highest annual mean for 1995. No activity was detected and therefore no reporting levels were approached.
i l
A FIGURE 3.9
- *I CONCENTRATION OF RADIONUCLIDES IN j FOOD PRODUCTS 4
,50 l
10% DFRE00RTIN3LEVliL 200 f
i 150 1
100 l
i 50 l
0 Year l *Co 137 indicator *10% of Reporting Level l section 3 Page21
.- ._. .- _ _ - . . . = .
l Tahle 3.9 Perrentnoes of Renadino Isvels for Fnarl Pnvincec Radionuclide Indicator Highest Reporting Level Perrentage of Mean (pCi/kg) (pCi/kg) Reporting Level I-131 0.00E0 1.00E2 0.00%
Cs-134 0.00E0 1.00E3 0.00%
Cs-137 0.00E0 2.00E3 0.00 %
1 Secoon 3.Page22
3.10 LAND USE CENSUS
- The land use census was completed July 6,1995 and the results are shown in Table i
3.10 and Figure 3.10. During the 1995 census,19 irrigated gardens were identi6ed.
These gardens were reviewed with respect to amount ofinigation, size, willingness to participate, crop types, and location. The Davenport garden (location 184, 2.5 miles ENE) was not planted in 1995 due to the age of the residents. Therefore, the Davenport garden was deleted from the program after the growing season. The
- Austin garden (Location 188,2.8 miles N) was determined to be the best overall garden with respect to sample reliability, crop variety, and size. The census also revealed eight milk animal locations that were not included in the 1995 sampling program. However, seven of the locations do not produce sufficient volume to be added to the program and the eighth is outside the five kilometer area of participation. The nearest residence is located in the East sector at 0.46 miles.
1 1
1 l
l i
I section 3-Page23
Table 3.10 Land Use Census Rea*c l
SECTOR DISTANCE )
l N Nearest Residence 2.5 miles 1 Nearest Meat Animal None in 5 miles Nearest Garden 2.56 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NNE Nearest Residence 1.29 miles '
4 Nearest Meat Animal None in 5 miles Nearest Garden 2.37 miles 1
Nearest Cow None in 5 miles Nearest Goat None in 5 miles NE Nearest Residence 1.2 miles Nearest Meat Animal 4.95 miles Nearest Garden 2.1 miles Nearest Cow None in 5 miles Nearest Goat 4.95 miles ENE Nearest Resulence 0.56 miles Nearest Meat Animal 3.81 miles l
Nearest Garden 2.55 miles Nearest Cow 3.51 miles Nearest Goat None in 5 miles E Nearest Residence 0.46 miles Nearest Meat Animal 4.08 miles Nearest Garden 0.47 miles Nearest Cow 2.46 miles Nearest Goat None in 5 miles ESE Nearest Residence 0.67 miles Nearest Meat Animal 1.3 miles Nearest Garden 0.85 miles Nearest Cow 3.07 miles Nearest Goat 1.4 miles SE Nearest Residence 1.17 miles Nearest Meat Animal 2.79 miles Nearest Garden 1.21 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles SSE Nearest Residence 1.06 miles Nearest Meat Animal 1.48 miles Nearest Garden 1.26 miles Nearest Cow 2.76 miles Nearest Goat 2.09 miles Seaion 3-Page24
Table 3.10 Land Use Census Results SECTOR DISTANCE S Nearest ResWoce 1.62 miles Nearest Meat Animal 3.01 rmles Nearest Garden 1.49 miles Nearest Cow None in 5 miles l
l Nearest Goat 4.30 miles SSW Nearest Residence 2.57 miles Nearest Meat Animal 2.75 miles Nearest Garden 2.95 miles Nearest Cow None in 5 miles Nearest Goat 3.06 miles SW Nearest ResWnce 1.8 miles NearestMeat Animal None in 5 miles Nearest Garden 1.8 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles WSW Nearest ResWnce 1.01 miles Nearest Meat Animal 3.97 miles Nearest Garden 1.16 miles Nearest Cow None in 5 miles Nearest Goat 3.97 miks W Nearest ResWace 0.82 miles Nearest Meat Animal 3.53 miles Nearest Garden 0.90 miles Nearest Cow None in 5 miles Nearest Goat 3.83 miles WNW Nearest ResWnce 0.91 miks Nearest Meat Animal None in 5 miles l Nearest Garden 2.15 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NW Nearest ResWnce 0.93 miles 1 1
Nearest Meat Animal None in 5 miles Nearen Garden 1.37 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NNW Nearest ResWnce 1.53 miles l
Nearest Meat Animal 3.67 miles Nearest Garden 1.69 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles Section 3 Age 25
l Figure 3.10 t
I " ~ ' ' ' -
1% V _
[ D . Q McGuire Nuclear Station 1994-1995 Land
- '. f N4p , 7 f jk'j #$ g h.5
, s Y Use Census Map
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July 1995 u.cawes Section 3 - Page 26
4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL '
MEASUREMENTS VERSUS ;
ESTIMATED DOSE FROM 1 RELEASES I
4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimated for measured concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology and factors. A dose factor of zero was used when the Reg. Guide listed "NO DATA" for a factor. The highest annual mean 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 maxunum exposed individual doses are summanzed 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 man l using NRC Regulatory Guide 1.109 methodology. The doses were calculated using !
GASPAR and LADTAP computer programs as reported in the 1995 McGuire Annual Radioactive Efiluent 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 reported separately. For noble gas exposure, there is no critical age group, as the maxunum exposed individuals are ,
assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure, the maxunum total organ dose for the highest dose location is given for the maxunum organ (thyroid) for the critical age group (child). The maximum exposed individual doses are summanzed in Table 4.1-A with the critical age and critical pathway listed.
4.3 COMPARISON OF DOSES The environmental and efHuent 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 modelling of the environmental exposure pathways.
Secuan 4 -Page 1
l In calculations based on liquid release effluent pathways, dnnkmg water consumption is the l
.predommant dose path based on effluent data and fish consumption is the predommant dose path based on environmental samples. The only radionuclide detected in fish in 1995 was from two samples indicating Cs-137. Tritium from surface water samples also was included i in the fish pathway. For the drinking water pathway, the only radionuclide detected in 1995 was one sampleindicating tritium.
No environmental doses resulted from the gaseous pathway in 1995. Broadleaf vegetation, i milk, and airborne radioiodines and particulates indicated no actisity in 1995. 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.
l l
The 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 the l
40CFR190 dose commitment limits for members of the public.
4.4 PATHWAY DOSE CALCULATIONS 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. l l
l Sectxn 4-Page 2
1
, TABLE 4.1-A
- Page 1 of 2 1995 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON i
FOR LIQUID AND GASEOUS WASTE RELEASE PATHWAYS LIOUID RELEASE PATHWAY
^
fjF3sisosmentilIAMi IditisslE iCSUi$is liMsilMbidDss53
- < J (PS$ksyl1 I llTAffeni)j
[EfiluediDhtAt M%hes
~ ~ '
~
5Idn ~ Environmental ~~ Teen Sitorel[ne 5ediment 6.71E-04 Skin Efiluent Teen Shoreline Sediment 4.22E-04 w
.z... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . . . . . . . .
. . . . Bone . . . . . . . . . Environmental.. Child Fish 6.09E-02 Bone Effluent Child Fish 8.47E-03 Liver Environmental Child Fish 9.58E-02 Liver Efiluent Child Drinking Water 5.41E-02 T. Body Environmental Adult Fish 6.86E-02
- T. Body Efiluent Child Drinking Water 4.67E-02 Thyroid Environmental Child Drinking Water 3'.75E-02 Thyroid Effluent Child Drinking Water 4.52E-02 l
K'idney Environmental' Child' Drinking Water 5.65E-02 Kidney Effluent Child Drinking Water 4.79E-02
" Lung Environmental Child Drinking Water 4.43E-02 Lung EfIluent Child Drinking Water 4.61E-02
~
GI-LLI Environmental Chil'd Drinking Water 3.795-02 GI LLI EfIluent Child Drinking Water 4.68E-02
- Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
Section 4. Page 3
I Page 2 of 2 GASEOUS RELEASE PATHWAY
....=....-...x EEnvironmental or? t.CriticalV : Critical-i 1 Maximum Dosei yrganc ~ EEfHeeniDaitb i ne : UPNhwayl 1snremN NOBLE GAS EXPOSURE l
Skin Environmental - -
Not Sampled .
Skin Efiluent N/A Noble Gas 3.18E-01 l l
T. Body Environmental - -
Not Sampled l l T. Body Efiluent N/A Noble Gas 1.40E-01
!! Environmental ~orti tCriticali ?Criticall ?Mhimmn Dose
- Organ. .y_ ~ g gggp- qq gg; 3-
^g gg IODINE,. PARTICULATE, and TRITIUM Bone Environmental - - 0.00E+00 Liver Environmental - -
0.00E+00 T. Body Environmental - -
0.00E+00 Thyroid Environmental - - 0.00E+00 Thyroid Efiluent Child Vegetation 1.34E-01 Kidney Environmental - - 0.00E+00 Lung Environmental - - 0.00E+00
' GI'-LLI ' Environmental' - - 0.00E+00
- Maximum dose is a summation of the inhalation, milk and vegetation pathways.
l t
Section 4 Page 4
TABLE 4.1-B Maximum Individu:1 Dosefor 1995 based on Environment:1 Measurements (mrem)for McGuire Nuclear St: tion Age Sample Medium Bone Liver T. Body _ Thyroid Kidney Lung . GI-LLI Skin Infant Airborne 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 3.64E-02 3.64E-02 3.64E-02 3.64E-02 3.64E-02 3.64E-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 3.64E-02 3.64E-02 3.64E-02 3.64E-02 3.64E-02 3.64E-02 0.00E+00 Child Airborne 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+0d 0.00E+00 0.00E+00 Drmking Water 0.00E+00 3.71E-02 3.71 E-02 3.71E-02 3.71E-02 3.71 E-02 3.71 E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BroadicarVegetation 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00EM0 0.00E+00 0.00E+00 0.00E+00 Fish 6.09E-02 5.87E-02 9.00E-03 3.98E-04 1.94E-02 7.24E-03 7.63E-04 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.20E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.40E-04 TOTAL 6.09E-02 9.58E-02 4.62E-02 3.75E-02 5.65E-02 4.43E-02 3.79E-02 1.40E-04 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 Drinking Water 0.00E+00 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BroadicafVegetation 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 4.84E-02 6.48E-02 2.29E-02 4.82E-04 2.24E-02 8.99E-03 1.40E-03 0.00E400 Shoreline Sediment 0.00E+00 0.00E+00 5.73E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.71E-04 TOTAL 4.84E-02 8.42E-02 4.29E-02 1.99E-02 4.18E-02 2.84E-02 2.08E-02 6.71E-04 Adult Airborne 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 2.74E-02 2.74E-02 2.74E-02 2.74E-02 2.74E-02 2.74E-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 4.52E-02 6.24E-02 4.llE-02 6.26E-04 2.16E-02 7.60E-03 1.82E-03 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.03E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.20E-04 ,
TOTAL 4.52E-02 8.98E-02 6.86E-02 2.80E-02 4.90E-02 3.50E-02 2.92E-02 1.20E-04 Note: Dose tables are provided for sampic media displaying positive nuclide occurrence.
Section 4 - Page 5 I
Dosefrom Drinking Water Pathwayfor 1995 Data Maximum ExposedInfant Infant Dose from Ddnking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem /pCI ingested) x Concentration (pCLT)
Usage petske an ese year) = 330 I ;
Highest Annual [
Net Mean i Inzestion Dose Factor Concentration Dose (mrem)
Indienter Wster Rad 6omaclide llene Liver T. Body Thyreed Kidney Long GI-LLI Leesties (pCUL) Bose Liver T. Body Thyroid Kidney i.neg GI.118 Mm-54 NO DATA 1.99E-05 4.51E 06 NO DATA 4.4tE 06 NO DATA 7 3IE46 All 8.00 9.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 3.60E46 8.99E46 NO D kTA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E400 8.00E+00 0.00E+00 0.00E+00 0.00E+0e Fe-59 3.00E-05 5.33E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E 95 ALL 8.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce40 NO DAT A 1.08E-05 2 55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.00E*00 0.00E*00 000E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.0 4E-05 6 3 tE-05 2.9tE45 NO DATA 3.06E-05 NO DATA 5J3E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E400 Nb-95 4.20E-08 1.73E-08 1.00E 00 NO DATA 1.24E-00 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E*00 Zr-95 2.06E47 5.02E-08 3.56E40 NO DATA 5.4tE-00 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 !
I-til 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E45 NO DATA 1.5 t E-06 All 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e.00E+00 C+134 3 77E44 7.03E44 7.10E45 NODATA 101E-04 7.42E-05 1.91 E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5 22E44 611E44 4.33E45 NO DATA 1.64E-04 6 64E-05 1.9tE-06 ALL 8.00 0.00E400 0.00E+00 0 00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bate.140 1.7t E-04 1.71E47 8.8tE-06 NO DATA 4.06E-00 1.05E-07 4.20E-45 ALL 0.00 0.00E+00 0.00E+00 0.00E*00 0.00F+00 0.00E+00 0.00E+00 0 00E+00 II-3 NO DATA 3.08E-07 3 0RE-87 3.08E47 3.09E47 3.08E-07 3.00E-07 119 358.00 0.00E+00 3.64E42 3.64E-02 3.64E-02 3.64E-02 3.64E42 3.64E42
[
Dese Cossentamient (norean) = 0.00E+00 3.64E42 3.64E-02 3.64E-02 3 64E-42 3.64E42 3.64E42 l
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Dosefrom Fish Pdthnwyfor1995 Data Maximum Exposed Child Child Dose from Fish Pathwmy (mrem) = Usage (kg) Dose Factor (arem/pCIingested) x Concentration (pCE/kg) 11-3 Concentration in Fish = Surface Water pCl/l n Bioaccumulation Factor 9.9 pCl/l = 315 pCill x 0,9 = 284 pC1/kg Us:ge (inteam in one year) = 6.9 kg Highest Annual Net Mean Innestion Dese Factor Concentration Doge (mrent)
Indicater Fish Redienectide Bene Liver 1. Body Thyroid Kidney Lung GI.LIJ Iacetion (pCiths) Bene Liver T. Body Thyrehl Kidney Lung Cl-L12 Mn-54 NO DATA 1.07E-05 2.052-06 NO DATA 3.00E-06 NO DATA 0.90EM ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00 Co-50 NO DATA 1.00E-06 5.5t E44 NO DATA NO DATA NO DATA 1.05E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe.59 1.65E-05 2.67E-05 IJ3E-f5 NODATA NO DATA 7.74E-06 2.70E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C040 NO DATA 5.29E 06 1.56E-03 NO DATA NO DATA NO DATA 2.93E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+&r 0.00E+00 0.00E+00 Zn 65 1.37E.05 3.65E-05 2.27E 05 NO DATA 2.30E.05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+06 , 0.00E+00 000E+00 0.00E+00 Nk95 2.25E-00 0.76E-09 6.26E-09 NO DATA 0.23E49 NO DATA 1.62E-OS ALL 0.00 0.00E400 0.00E+00 0.00E+00 0.00E100 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-00 2.27E-00 NO DATA 3.65E.00 NO DATA 2.66E-05 ALL 6.00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 1.72 E-05 1.73E-05 9.03E-06 5.72E43 2.04E-05 NO DATA 1.54EM ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.04 E-04 0.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 3.27E-04 3.13E-04 4 62E45 NO DATA 1.02 E44 3.67E45 1.96E46 129 27.00 6.09E42 5.03E-02 0.6t E43 0.00E+00 1.90E-02 6.04E-03 3.65E44 BiLa-ide 0J t E-05 7.20E-00 4.05E46 NO DATA 237E40 434E-00 4.21E-05 ' ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 . 0.00E+00 II-3 NO DATA 2.03E-07 2.03E47 2.03E47 2.03E47 2.03E47 2.03E-07 120 204.00 . 0.00E+00 3.90E44 3.90E44 3.90E44 3.90E-04 3.90E-04 3.90E44 Deme C_ " (arean) = 6.09E-02 5.07E-02 9.00E-03 3.90E.04 1.94E 02 7.24E-03 7.63E-04
_ - - - _ _ - _ - - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - . _ . _ _ _ _ _ - - _ _ . - _ - - _ _ . _ _ _ _ _ _ - - _ __ . ~-_ _ - _ _ . - - .- .
Dosefrom Shoreline Sediment Pathwayfor 1995 Data Maximum Exposed Child Shoreline Recreation = 14 hr(in one year)
Shore MMth Factor = 0.3 (lake shore location 129)
Shore Width Factor = 0.2 (dver shoreline -location 130) bedhnent Surface Mass = 40 kg/m2 Child Dose from Shodine Sedhnent Pathway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem /hr per pO/m2) Shore %Mth Factor x Sediment Surface Mass (kg/m2)
Sediment Concentration (pC1/kg)
External Dose Factor Standing Highest AnnualNet Dose on Contaminated Ground Mean Concentration (mrem /hr per pCl/m2) Indicator Sediment (mrem)
Radionuclide T. Body Sidn lastion (PCL%g) T. Body Sida Mn-54 5.80E-09 6.80E-09 130 17.00 1.10E-05 129E-05 Co.58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Fe-59 8.00E.09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00F 08 130 23.00 4.38E-05 115E-05 Zn-65 4.00E-09 4.60E-09 ALL 0.00 0.00E+00 0.00E+00 l
Nb-95 110FA9 6.00E-09 ALL 0.00 0.00E+00 0.00E+00 Zr-95 100E-09 180E-09 ALL 0.00 0.00E+00 0.00E+00 1-131 2.8PE-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 138.00 6.49E-05 7.57E-05 BaLa-140 2.10F 09 2.40F-09 ALL 0.00 0.00E+00 0.00E+00 Dose Commitment (mrem) = 1.20E-04 1.40E-04
Dosefrom Drinking Water PatArnwyfor 1995 Data Maximum Exposed Teen Teen Dose from Dninkhig Water Pathway (mrem)= Usage (I) x Dese Factor (mrem /pClingested) x Concentration (pCM)
Usage (i.e.tw in one year) = 510 I Highest Annnel Net Mean Insrestion Date Factor Concentration Date (ntresn)
Indienter Water Redtemodede Bene IJver T.Bedy Thyroid Kidney Lums GI-til Lecetten (yCl/L) Bene 1 Aver T.Bedy Thyroid Kidney Leme C1-LLI Mm44 NO DATA 5.90EM 1.17E46 NO DATA 1.76E-06 NO DATA 1.21E45 ALL 0.00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-50 NO DATA 9.72E.07 2.24E46 NO DATA NO DATA NODATA 1.34E.05 ALL 0.00 0.00E+00 0.00E+00 0.00E+ee 0.00E440 0.00E+49 0.00E+00 0.00E+00 Fe-59 6.07E-06 1.37E49 S.29E-06 NO DATA NO DATA 4.32E.06 3.24E45 All 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+ee 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2. ORE.06 6.33E-06 NO DATA NODATA NO DATA 3 66E45 ALL 4.00 0.00E+ee 0.00E+et 0.00E440 0.00E+00 0.00E+00 0.00E+ee 0.00E+et Zm 65 5.76E-M 2.00E45 9.33E-06 NO DATA 1.26E-05 NO DATA S.47E-06 All 5.00 0.00E+00 0.00E+00 0.00E+00 000E+00 0.00E+00 0.00E+ee 0.00K+es Nb 95 0.22E.09 4 56E49 2.5tE.09 NO DATA 4.42E.09 NODATA 19$E.05 AIL 0.00 0.00E+00 0.00F.4 0.00E+00 0.00E+ee 0.00E+00 0.00E+ee 0.00E*e0 Zr.95 4.12E-00 1.30E-00 0.94E49 ' NO DATA 1.9tE 00 NO DATA 3.00E-05 All 0.00 0.00E400 0.00E+00 000E400 0.00E+00 0.00E+00 0.00E+00 0.00E+49 1 131 S S5E-06 0.19E-06 4.40E-06 2.39E-03 1.4tE-06 NO DATA 1.62E-M All 0.00 0.00E+00 0.00E+00 0.00E+49 0.00E+00 0.00E400 0.00E+00 0.00E400 Cs.134 0.37E45 1.97E44 9.14E-05 NO DATA 6.26E45 2.39E.06 2.4SE-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+40 0.00E+49 0.00E+00 0.00E+60 0.00E+00 Cs-137 1.12E-04 1.49E44 il9E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.00E+49 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 BnLa.140 2.04E-05 3.40E-00 1.03E-06 NO DATA 1.10E40 2.34E40 4.30E45 ALL 0.00 0.00E+40 0.00E+00 0.00E440 0.00E+00 0.00E+00 0.00E+00 0.00E+00 11-3 NO DATA 1.06E47 1.06E-07 1.06E.07 1.06E47 1.06E47 1.06E-07 119 350.00 0.00E+60 1.94E-02 1.94E-02 1.94E-02 1.94E42 1.94E-02 1.94E-02 Done C _: (seream)= 0.00E+00 194E-01 1.94E-02 1.94E-02 1.94E42 1.94E-02 1.94E-82
Dosefrom Fish Pathnwyfor 1995 Data Maximum Exposed Teen Teen Dese from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem /pClingested) x Concentration (pC1/kg) 11-3 Concentration in Fish = Surface Water pCl/l x Bioeccumulation Factor 0.9 pC1/1 = 315 pCl/l x 0.9 = 284 pC1/kg Usage (intase su one year) = 16 kg liighest Annual Ineestion Dose Factor Net Mean Dose (mresn) ,
concentration Radiommetide Bene IJver T. Body Thyroid Kidney Long GI-11I Lecettom (her yr) Bene IJver T. Body Thyro 6d Kidney Lang CI411 ble-54 NO DATA 5.90E-06 1.17E46 NO DATA 1.76EM NO DATA 1.2 t E-05 AIL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 000E+00 0.00E+00 Co.58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA IJ4E-05 ALI, 0.00 0.00E+00 0.00E+00 0.00E+00 000E+00 0.00E+00 0.00E400 0.00E+00 Fe-59 5.27E-06 1.37E.05 5.29E-06 NO DATA NO DATA 4.32E 06 3.24E-05 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.8tE-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E.05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E +00 Za-45 5.76E-06 2.00E-05 9.33 E.06 NO DATA I.28E-05 NO DATA 3.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2.5tE49 NO DATA 4.42E49 NO DATA 1.95E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.WE+00 0 00E+00 Fr-95 4.12E-08 1.30E40 8.94E49 NO DATA 1.9tE-00 NO DATA 3.00E-05 All 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 f.131 5.05E-06 0.19E-06 4.40E-06 2J9E43 1.4tE45 NO DATA 1.62E46 ALL 0.00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 0.37E-05 97E44 9.14E-05 NO DATA 6.26E45 2J9E-05 2.45E46 ALL 0.00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.0PE+00 0.00E+00 0.00E+00 '
Co-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E45 2.12E-06 129 27.00 4.84E-02 6.44E-02 2.24E42 0.00E+00 2.19E42 0.StE 03 9.16E-04 Bata-140 2.94E 05 3.4SE-08 1.33E-06 NO DATA 1.10E45 2.34E40 4JSE 85 AIL 0.00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 11 3 NO DATA 1.06E-07 1.06E-07 1.06E -07 1.06E-07 1.06E-07 1.06E-07 128 204.00 0.00E+00 4.02E-04 4.02E44 4.32E-04 4.82E-04 4.02E-04 4.82E-04 Dese Commitswet (arem) = 404E42 6.40E42 2.29E-02 4.82E-04 2.24E42 B.99E-03 1.40E-03
i Dosefrom Shoreline Sediment Pathwayfor 1995 Data
! Maximum Exposed Teen l Shorehne Recreation = 67 hr(in one year)
Shore width Factor = 0.3 Gake shore . location 129)
Shore Width Factor = 0.2 (rivershoreline-location 130)
Sedienent Surface Mass = 40 kg/m2 Teen Dose from Shorline Sedunent Pathway (mrem) = Shorline Recreation (br) x External Dose Factor (mmni/hr per pO/m2) x Shore Midth Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pGig)
External Dose Factor Standing Highest Annual Net h on Contaminated Ground Mean Concentration (mrena/hr per pCVm2) Indicator Sediment (mrem)
Radionucude T. Body Skla Location (pOig) 7. Body Sida Mn-54 5.80E-09 6.80E-09 130 17.00 5.28E-05 6.20E-05
- 58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00
- 0.00E+00 Fe-59 8.00E-09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 130 23.00 2.10E-04 2.47E-04 Zn-65 4.00E-09 4.60E-09 ALL 0.00 0.00E+00 0.00E+00 Nb.95 5.10E-09 6.00E-09 ALL 0.00 0.00E+00 0.00E+00 Zr-95 5.00E-09 5.80E-09 ALL 0.00 0.00E+00 0.00E+00 I-131 2.80E-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E 08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 138.00 3.11E-04 3.62E-04 BaLa-140 1.50E-08 1.70E-08 ALL 0.00 0.00E+00 0.00E+00 Dose Commitment (mrem) = 5.73E-04 6.71E-04 l
l
Dosefrom Drinking Water Pathwayfor 1995 Data Maximum Exposed Adult Adult Dose from Ddnidng Water Pathway (mrem) = Usage (I) Dese Factor (mrem /pClingested) x Concentration (pCL1)
Usage time . e e per) = 730 1 Ilighest Annual Net Mean Inrestion Dose Factor Concentration Dose (mrem)
Ind6 cater Water Radioseende Bone IJvse T. Body Thyreld Kidney Lang GI-LLI Locaties (pCA/I) Bone IJwr T. Body Thyroid Kidney Long GI-LLI Stm.54 NO DATA 4.57E.06 0.72E-07 NO DATA 1.36E M NO DATA 1.40E.05 ALL 4.00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.5IE45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E*00 0.00E+00 0.00E+00 Fe-59 4.34E46 1.02E.05 3 9tE.06 NO DATA NO DATA 2.05E46 3.40E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+60 0.00E+00 0.00E+00 0.00E+00 000E+00 Ce 60 NO DATA 2.14E46 4.72E46 NODATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 Za-65 4.04E-06 1.54E45 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E46 ALL 0.00 0.00E+00 0.00E+0C 0.00E+00 0.00E*00 0.00E+00 0.00E+40 0.00E+ee Nk95 6.22E49 3.46E 09 1.06E49 NO DATA 3.42E49 NO DATA 2.10E.05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E40 9.75E.09 6.60E-09 NO DATA ' t.53E-00 NO DATA 3.09E45 ALL 4.00 0 00E+00 0.00E+00 0.09E+00 0.00E+40 0.00E+00 0.00E+00 0.00E+00 1 131 4.16E-06 5.95E46 3.4tE46 1.95E43 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+ee 0.00E+00 0.00E+00 0.00E+eo 0.00E+00 000E400 0.00E+49 Cs-134 6.22E45 1.40E44 1.2tE44 NO DATA 4.79E-05 1.59E-05 2.59E46 ALL 0.00 0.03E+60 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E45 1.09E-04 7.14E45 NO DATA 3.70E-05 1.23E-05 2.llE46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Eies BeLa-140 2.03E-05 2.55E40 1.33E46 NO DATA 0.67E-09 1.46E-00 4.10E45 ALL 0.00 0.00E440 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 11 3 NO DATA 1.0$E-07 1.0$E-07 1.05E-C7 1.05E-07 105E-07 1.0$E47 119 350 00 0.00E+00 2.74E.02 2.74E-01 2.74E-02 2.74E42 2.74E-02 2.74E-02 Dese C _ " (msrein) = 0.00E+40 2.74E42 2.74E-02 2.74E-02 2.74E-02 2.74E42 2.74E-02
Dosefrom Fish Pathwayfor D95 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem /pCl ingested) x Concentration (pCl/kg) 11-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCl/l = 315 pCI/I x 0.9 = 284 pCE/kg Usr ge (intake in ene year) = 21 kg liighest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)
Redienuclide Bone ther T. Body Thyroid Kidney Lung GI-Lil Imation (pCi/kg) Bene Iber T. Body Thyroid Kidney Lang GI-LIJ Mn-54 NO DATA 4.57E-06 0.72E 07 NO DATA 1.36E-06 NO DATA 1.40E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '0.00E+00 Co.50 NO DATA 7.45 E.07 L67E-06 NO DATA NO DATA NO DATA 1.5t E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E.06 1.0Z E-05 3.9t E-06 NO DATA NO DATA 2.05Em 3.40E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce40 NO DATA 2.14 E-06 4.72 EM NO DATA NO DATA NO DATA 4.02E45 ALL 0.00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+60 0.00E+00 0.00E+00 Zn-65 4.04E46 L54E45 6.96E46 NO DATA 1.03E-05 NO DATA 9.70E46 ALL 0.00 0.00E+00 9.00E+00 0.00E+00 0.00E+00 0.00E+00 000E+00 0.00E+00 Nb-95 6.22E.09 3.46E.09 1.06E49 NO DATA 3.42E49 NO DATA 2.10E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 3.04E40 9.75E.09 6.60E-09 NO DATA 1.53 E-06 NO DATA 3.09E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 131 4.16EM 5.95E46 3.4 t EM L95E43 1.02E45 NO DATA 1.57E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.134 6.22E45 1.40E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E.05 1.09E-04 7.14E45 NO DATA ? %F 05 1.23 E-05 2.llE.06 129 27.00 4.52E42 6.10L82 4.05E.02 0.00E+00 2.10E42 6.97E.J3 1.20E-03 Bate.140 2.03 E.05 2.55K-00 IJ3E M NO DATA 6.6TEP 1.46E.00 4.10E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 11 3 NO DATA 105E47 1.05E-07 1.0$E47 1.05E47 1.0$E-07 1.05E47 120 204.00 0.00E+00 6.26E44 6.26E44 6.26E44 6.26E-04 6.26E-04 6.26E44 Dese Commitnient (mrem) = 4.52 E-02 6.24E-02 4.It E 02 4.26E44 2.16E.02 7.60E.03 1.02E43
__m___ __.__.__._____.____._ __ _ __-_____ mmm --______ _ _ _ - _.___v __ .=
l l
l l
Dosefrom Shoreline Sediment Pathwayfor 1995 Data Maximum Exposed Adult i
Shoreline Recreation = 12 hr(in one year)
! Shore width Factor = 0.3 (lake shore -location 129)
Shore %1dth Factor = 0.2 (river shoreline -location 130)
- Sediment Surface Mass = 40 kg/m2 f Adult Dose from Shoriine Sediment Patnway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem /hr per pCl/m2) x Shore %1dth Factor x Sediment Surface Mass (kghn2) x Sedunent Concentration (pCng)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration l (mrem)
(mrenv%r per pCiha2) Indicator Sediment
- Radionuclide T. Body Sidn Location (pCWg) T. Body Sidn Mn-54 5.80E-09 6.80E-09 130 17.00 9.47E-06 1.11E-05 Co-58 7.00E-09 8.20E-09 ALL 0.00 0.00E+00 0.00E+00 Fe-59 8.00E-09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 l Co-60 1.70E-08 2.00E-08 130 23.00 3.75E.05 4.42E-05 l
I Zn45 4.00E-09 4.60E-09 ALL 0.00 0.00E+00 0.00E+00 l
Nb-95 5.10E-09 6.00609 ALL 0.00 0.00E+00 0.00E+00 I Zr-95 100E-09 5.80E-09 ALL 0.00 0.00E+00 0.00E+00 1131 2.80E-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40LO8 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 130 138.00 5.56E-05 6.49E-05 l BaLa-140 2.10E-09 2.40E-09 ALL 0.00 0.00E+00 0.00E+00 l
Dose Commitment (mrem)= 1.03FA4 1.20E-04 l
I
i 1
1 5.0 QUALITY ASSURANCE i
l 5.1 DUKE POWER COMPANY'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l 1
5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.
5.1.2 SAMPLE ANALYSIS l
The Radiological and Environmental Services Group performed the environmental sample analyses as specified by approved analysis procedures.
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 OUALITY 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. I Additionally, National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance.
Investigations are performed and documented should calibration verification data fall out oflimits.
Section 5 - Page 1
I 5.1.5 INTERLABORATORY OUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISION i 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.
i l
5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM The Radiological and Environmental Services group participated in the j Duke Power Nuclear Generation Department Intercomparison Program 1 during 1995. Interlaboratory cross-check standards, including marinelli !
beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium l in water samples were analyzed at various times of the year by the four I counting laboratories in Duke Power Company for this program. A l summary of these Intercomparison Reports for 1995 is documented in !
Table 5.0-A. l l
5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS l
The Radiological Environmental Monitoring Program was not audited by the NRC in 1995. The McGuire Nuclear Station Radiation Protection section participated in an NRC audit in 1995. Improvement of environmental monitoring equipment reliability was listed as a recommendation. A thorough description ofimprovements can be found in Appendix C, Section 3.0.
5.1.5.4 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM The Radiological and Environmental Services Group participated in the Environmental Protection Agency (EPA) Environmental Monitoring i Systems Laboratory Intercomparison Program. The EPA sample types I included mixed gamma in water, mixed gamma in milk, gamma in air l filters, iodine in milk, tritium in water, iodine in water, gross beta in air i filters and gross beta in water.
Section 5 - Page 2
l i
l j Radiological and Environmental Services prepared and analyzed each sample as quickly as possible. Data obtained greater than EPA limits is documented by follow-up investigations. The Radiological and Environmental Services EPA Intercomparison Report code is "CP". A ,
summary of the EPA Intercomparison Reports for 1995 is documented
{
in Table 5.0-B. 1 i
An investigation was made into failed Beta in Water and Gamma in l Water dated 4/18/95. Both tests conducted by Radiological and i Environmental Services failed high due to cross-contamination of the samples. The investigation reviewed preparation of samples, training of personnel, materials used for sample preparation, laboratory area used for preparation, and review of data. I One sample was analyzed but results were not reported by the required date. (See corrective action #1 below)
After careful review of preparation of samples, it was determined that all procedure steps were accurately followed. No deviation in preparation i procedures were found. Laboratory personnel that performed the analysis were sufficiently trained and had conducted similar analyses with acceptable results. The contamination of the cross-checks is believed to have resulted from analysis of primary reactor coolant samples by Radiological and Environmental Services. The potential existed for glassware and work surfaces to be contaminated with pnmary coolant in the preparation area. This is considered to be the root cause of the contamination.
Corrective actions are as follows:
- 1) The receipt and tracking ofEPA samples was refined in order to meet all future deadline:.
- 2) An entire process improvement initiative was implemented that 1 distinctly isolates all lab work by potential activity.
- 3) Specific glassware has been physically identified for all analyses types, e.g. environmental, effluent, primary reactor coolant, EPA, etc..
- 4) Cleaning procedures have been reviewed and improved for glassware and counter surfaces, minimizing the potential for contamination.
- 5) Data reviewers have been reminded to use historical information as
" benchmark" data to find potential anomalies.
Section 5 - Page 3
~
Mr -
1 l
l l !
l .
- 6) Procedures will be modified for 1996 samples to include a blank to be prepared with each set of samples. This will verify the presence of any interfering contaminants in sample matrices.
I 5.1.5.5 NRC/ STATE OF N.C. SAMPLING l INTERCOMPARISON PROGRAM l
Radiological and Environmental Services routinely participates with the l State ofNonh Carolina Department ofEnvironmental Health and i Natural Resources (DEHNR) in an intercomparison program l l Radiological and Environmental Services sends air, water, milk, l vegetation, sediment, and fish samples which have been collected to the 1 State ofNorth Carolina Radiation Protection Section for intercomparison analysis.
5.1.5.6 STATE OF N.C. TLD INTERCOMPARISON PROGRAM ,
1 Radiation Dosimetry and Records routinely panicipates m a TLD l intercomparison program Every six to eight months, f.he State ofNorth !
Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State ofNorth Carolina Environmental Dosimetry j Intercomparison Repon for 1995 is documented in Table 5.0-C.
l 5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1995.
l J
I Section 5 - Page 4
1 I
i TABLE 5.0-A ,
1 l
DUKE POWER COMPANY I l INTERLABORATORY COMPARISON PROGRAM 1995 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gamma:
> 'i g9 , 2 ,
ggy ' ,,
Colle'etion ' Geometry
^
Nuclide- ' Accy-RangeW Reference Value Reported <
PWalsh s Date > l (pCi/1) , (pCi/1) '
a g g jj; g 6/23/95 3.5 Liter Cr-51 1.93E4 - 3.42E4 2.57E4 2.60E4 Mn-54 1.30E4 - 2.30E4 1.73E4 1.77E4 Co-58 5.82E3 - 1.03E4 7.76E3 8.01E3 i
Fe-59 5.46E3 - 9.68E3 7.28E3 7.51E3 Co-60 1.31E4 - 2.33E4 1.75E4 1.78E4 Zn-65 1.31E4 - 2.33E4 1.75E4 1.84E4 Cs-134 7.95E3 - 1.41E4 1.06E4 9.8E3 1
Cs-137 7.36E3 - 1.31E4 9.81E3 9.97E3 l Ce-141 5.62E3 - 9.96E3 7.49E3 7.70E3
-- , m, ~ ~
y ~
c.d <
s
~
~
,' \
$611ectis",s%Cl:f$G&iinetri
! Nuclide A, _ Range Reference Value - Reported l
' l JDatyt. <
s 1 agg (pCi/ total) ,; ,(pCi/ total) '/
Value >' ,
m . . . .
6/23/95 1.0 Liter Cr-51 4.45E4 - 7.89E4 5.93E4 6.02E4 ,
1 Mn-54 3.02E4 - 5.35E4 4.02E4 4.16E4 Co-58 1.36E4 - 2.41E4 1.81E4 1.88E4 Fe-59 1.27E4 - 2.25E4 1.69E4 1.84E4 Co-60 3.04E4 - 5.39E4 4.05E4 4.20E4 Zn-65 3.03E4 - 5.37E4 4.04E4 4.34E4 Cs-134 1.83E4 - 3.25E4 2.44E4 2.26E4 Cs-137 1.70E4 - 3.02E4 2.27E4 2.28E4 Ce-141 1.31E4 - 2.31E4 1.74E4 1.85E4 I
Section 5 - Page 5
Gamma:
.,; - , , , . , . --....f. :--, , . ,....:..,:.,,,_,,
- ..., - ;-....;.7c.. .
g
- C6de-..sti6st i; D. . Ae6metryp!Nuclide1! 1Acse,_tande p Ransel 1ReferenceValdej , LRegiortedi 7Datelij- a [.(pCi/ total)j ' [(pCi/ total)j j.VajusjL.
4 iT6Ci/ total)?
8/18/95 Cartridge I-131 4.43E 7.86E-1 5.91E-1 6.07E-1 Tritium:
,; ..,.......... ..,.....3.,, . , . . . .
C611pioul ige 6 metry LNuclide;;l IX,. ..6EeptancpRangs; 1RefefericdNalds Rep &isd!
RDstej < ;;.(. . - +.1: ' .uCi/ml)i
?.:(.6Cihn!))!
~
.ep:'.
- ;::. .....:- . '-: - llNalue3..
-;.........e - - . --
~ .
?(uC' -ilinl)1 ;
8/l8/95 20ml vial H-3 1.22E 3.39E-3 2.04E-3 1.74E-3 l
l l
1
\
i l
I l
l l
l 4
Section 5 - Page 6 l
l
1 1
TABLE 5.0-B l
l l U.S. ENVIRONMENTAL PROTECTION AGENCY
! INTERLABORATORY COMPARISON PROGRAM l
1995 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY l
i Gammain Water:
i i
b' '
2 , ,^ ; ~ < ~k,, '> ) , l'
, C#* Date' 3 Nuclide(s) ',' Control Lunit's '
,Known Value: y Reported
' ' l'
i , s ;; ': ,
# 4. (3 Sigma;N?3) '!y(pCill) , ; Value, ^
l Ai '
cfa , ,
" (pCM) >
<> ' (pCM) "
2/3/95 I-131 82.7 - 117.3 100 98.7
! eg 39 s e sp a < , ;te , m gg , . m,, -
l 4/18/95 Co-60 20.3 -37.7 29 30.7 1
! Cs-134 11.3 - 28.7 20 213.7 ")
l l
Cs-137 2.3 - 19.7 11 276.30)
, , En g g >!O g y g.[ jijijg g.;z j @ *< s gyijyi.
- x igij;ih ( ^
-s l
6/9/95 Ba-133 65.1 - 92.9 79 81.0 Co-60 31.3 -48.7 40 41.7 Zn-65 62.1 - 89.9 76 81.0 Cs-134 41.3 -58.9 50 46.7 l Cs-137 26.3 - 43.7 35 34.7 i
shu a* - % ,' , s
, ss s *isi M M #
e
! 10/6/95 I-l31 122.0 - 174.0 148 158.7
,4
. ., en , w , s - yy ,
10/17/95 Co-60 40.3 -57.7 49 50.0 l Cs-134 31.3 -48.7 40 37.7 l Cs-137 21.3 -38.7 30 30.0 y ag !? , , , ,
+
, J gp ,
4 11/3/95 Ba-133 81.7 - 116.3 99 100 Co-60 51.3 - 68.7 60 55.7 Zn-65 102.5 - 147.5 125 132.7 31.3 -48.7
, Cs-134 40 35.3 Cs-137 40.3 - 57.7 49 51.3 i
i Section 5 - Page 7 l
t I
l
. l i
i Gamma in Milk:
. , ./ , , ' , a #
.;.:.:...q.y: .x xs- ; .y < ;.: p.
g .
,9
%CoBection Dagy ' Nuchde(s) Control Lim ~ns KnownVahs Reported- j
- ,q 4' , ~
,, : $ (3 Sigma; N=3)j+ .
(pCi/1)' - ' 3 Value :, l
,, c' (pCi/l) ' -
, ' '(pCM) l 9/29/95 I-131 81.7 - 116.3 99 106.3 Cs-137 41.3 - 58.7 50 49.3 Betain Water:
CollacMen 'e
' ' '*:' ' v h h ControlI nits ' ,
,(3 Sigma;N=3)
Known'V (pCill) ' -
^
Reported
,; Value '
- ~ - '
, g. s.[. ' '" (pCi/1) ~
is
' ' ^ '
- (DCi/l) ,'
^
1/27/95 Gross Beta 0.0 - 13.7 5.0 8.33 ( )
4/18/95 Gross Beta 69.3 - 103.9 86.6 405.0 W 7/21/95 Gross Beta 10.7 - 28.1 19.4 27.33
.10/27/95 Gross Beta 16.1 - 33.5 24.8 29.0 l Tritiumin Water:
gan * ,
- - s'
.c,~.
YEi!
w a cW:
,:*' s w 's
~s
'4
's,
~
s' '>'
CoBectionDate Nuclide(s)} Controlinnna 's Known Value ' y Reported -
> ay 1 (3 Sigma; N=3)- (pci/l) > o ms 'Value ' s sm ' l4% . . . f!a*
'; J'(pCM) ' ' 3
~ ' ' " '
L'-(DCMYb 3/10/95 H-3 6144.2 - 8725.8 7435 7132.3 8/4/95 H-3 4028.5 - 5715.5 4872 4626.7 Air Filter:
l l'
d, + s, s+
- 4. [yj$ ' ...~ ,
..c....
. . ~ .
CoBection Date' BNdclide(s)} ControlLimits ' Known Value' RReported
~$Vsi$Ejise
- g,g$1g[
' ' s ' ,, ' '
'- ,-(3 Sigma;N=3) ' ,
(pCi/I) tg:., ,,
-(
8/25/95 Cs-137 16.3 - 33.7 25.0 26.7 Gross Beta 69.3 - 103.9 86.6 86.7 (1) See Explanation in Section 5.1.5.4.
(2) This value was not reponed before the duc date and was not included in the reports Section 5 Page 8
-m. ._
TABLE 5.0-C STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1995 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS s - .
- su a~<.-
c . < ; ,. :.:.: s. . .. : . 3 .
- .... me -
s;.p:; , ,
I i y.: :. . ;,.; .,
..3
'l][Cf6 @ '
s jjia,@;gKQ & Records " Acceptance PiD.stsk.
j! Deli 0&edMalssi >
ReportedValue > ' Criteria ' ' '
's x' ..;.
.;ne '
\ v {'.j%[j' .::.:M:::'< . n<-: :;co j
edm f(mR}j, g3 (mRj '>
+/- 10*A
~, " <
w
.. , e.2 , ,.
, Q..; . .; .-:-.-
May-95 100 92.5 Pass ,
1 Nov-95 60 56.9 Pass i
Section 5 - Page 9
3 l
l I
l
6.0 REFERENCES
l 6.1 McGuire Selected License Commitments 6.2 McGuire Technical Specifications 6.3 McGuire Final Safety Analysis Review l
6.4 McGuire Offsite Dose Calculation Manual l
6.5 McGuire Annual Environmental Operating Report 1979 - 1994 6.6 McGuire Annual Radioactive Effluent Release Report 1995 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery,1969, pages 287-293.
l 6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain,1988, pages 83-93.
6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.
6.10 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.
section 6 - Page 1
i l
i i
l APPENDIX A l
l l
l ENVIRONMENTAL i
i SAMPLING AND l
ANALYSIS PROCEDURES l
l t
I
\
s e
l
l l
1 l APPENDIX A l 1
l l
ENVIRONMENTAL SAMPLING AND l ANALYSIS PROCEDURES I 1
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.
l l Environmental sampling and analyses were performed by Radiological and Environmental Services, Dosimetry and Records, and Fisheries and Aquatic Ecology.
l Starting at Section A.1, this appendix describes the environmental sampling frequencies and analysis
( procedures by media type.
l i I. CHANGE OF SAMPLING PROCEDURES 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 l have not changedin 1995.
1 Changes to the environmental program are listed below:
Deletions to the sampling program for 1995 are as follows:
Food product location #184 was deleted in September due to the discontinuation of l the garden bythe residents.
Drinkmg water location #142 was deleted at the end of 1994 due to the closing of tha water treatment facility.
l Additions to the sampling program for 1995 are as follows:
Drinkmg water site #119 was first collected in January of 1995.
TLD special interest #163 was added the begmnmg of the fomth quarter 1995 to investigate the differences between the NRC and the Duke Power co-located TLDs.
Descriptions of all above changes are given under applicable media headings.
1 i
Appendix A-Page I
q 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 sedunents are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.
l l
Low-level iodine analyses are performed by passing a designated sample aliquot through an ion :
, exchange resin to remove and concentrate any iodine in the aqueous sample (milk or water). The l l resin is then dded 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.
t 1 i Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and l analyzing by gas-flow proportional counters.
f i
III. CHANGE OF ANALYSIS PROCEDURES l
Low Level Iodine 131 (LLI-131) analysis was discontinued for all surface water sites on January 28,1995. This analysis was not required for surface water samples by Selected License Commitments.
l IV. SAMPLING AND ANALYSIS PROCEDURES j A.1 AIRBORNE PARTICULATE AND RADIOIODINE j Airbome particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radiciodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartddges were collected weekly. A weekly gamma analysis and gross beta analysis was performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. The filter and charcoal cartridge were analyzed independently. The
- continuous composite samples were collected from the locations listed below.
Location 120 = Site Boundary (0.459 mi. NNE)
Location 121 = Site Boundary (0.466 mi. NE)
Location 125 =
Site Boundary (0.390 mi. SW) l Appenchx A - Page 2
)
Location 133 = Cornelius, NC (6.228 mi. NE) l Location 134 =
East Lincoln Junior High School (8.762 mi. WNW)
Location 192 =
Peninsula development (2.810 mi. NNE)
Location 195 =
Fishing Access Road (0.200 mi. N) l A.2 DRINKING WATER i l
Biweeldy composite samples were collected. A low-level Iodine-131 analysis was performed ,
on each composite sample. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweeldy from the locations listed below.
Location 119 =
Mt. Holly M alicipal Water Supply (7.403 mi. SSW)
Location 132 =
Charlotte Muaicipal Water Supply (11.162 mi. SSE) l Location 136 =
Mooresville Municipal Water Supply (12.675 mi. NNE)
Location 194 =
East Lincoln Water Supply (6.7 mi. NNW)
A.3 SURFACE WATER Biweekly composite samples were collected. A low-level Iodme-131 analysis was performed on each composite sample until January 28,1995. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites sample. The composites were collected biweekly from the locationslisted below.
Location 128 =
Discharge Canal Bridge (0.442 a i ENE)
Location 131 =
Cowans Ford Dam (0.6 mi. W)
Location 135 =
Plant Marshall Intake Canal (11.929 mi. N)
A.4 MLK Biweekly grab samples were collected at each dairy. A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the locationslisted below.
Location 138 =
Henry Cook Dairy - COWS (3.078 mi. ESE)
Location 139 =
William Cook Dairy - COWS (2.494 mi. E)
Location 140 = Kidd Dairy- COWS (2.760 mi. SSE)
Location 141 =
Lynch Dairy- COWS (14.800 mi. WNW) l A.5 BROADLEAF VEGETATION 4
- Monthly samples were collected as available and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.
Appendix A.Page 3
I Location 120 =
Site Boundary (0.459 mi. NNE)
Location 125 =
Site Boundary (0.390 mi. SW) l Location 134 =
East Lincoln Junior High School (8.762 mi. WNW)
Location 193 = Site Boundary (0.2 mi. N) l l
A.6 SHORELINE SEDIMENT l
Semiannual samples were collected and a gamma analysis was performed on each I following the drying and removal of rocks and clams. The samples were collected I from thelocationslisted below. .
Location 129 =
Discharge Canal Entrance to Lake Norman (0.508 mi. ENE)
Location 130 =
, Highway 73 Bridge Downstream (0.535 mi. SW) l l Location 137 =
Pinnacle Access Area (11.988 mi. N) l l
A.7 FISH l
Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.
1 Location 129 =
Discharge Canal Entrance to Lake Norman (0.508 mi.ENE)
Location 137 =
Pinnacle Access Area (11.988 mi.N)
A.8 DIRECT GAMMA RADIATION (TLD)
Thermoluminescent dosimeters (TLD) were collected quarterly at forty-eight locations for the first three quarters of 1995. A new special interest TLD was placed in the field at location
- 163 at the begmnmg of the 4th quarter, makmg a total of forty-nine locations. A gamma dose rate was determmed for each TLD. The TLDs were placed as indicated below.
- An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in the N and NNW sectors are over water, however, two special interest TLD's were placed in these sectors inside the site boundaryin March,1991.
- An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.
- The remammg TLDs were placed in specialinterest areas such as population j centers, residential areas, schools, and control locations.
i TLD locations are listed in Table 2.1-B.
AppenAx A-Page 4
l 1
A.9 FOOD PRODUCTS 4
Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the locations listed below. Location 184 was discontinued in September 1995 due to the sparse availability ofcrops and indication of the residents to discontinue the quantity necessary for continued collection.
Location 184 =
5 Mile Radius (2.5 mi ENE) Gardens (Davenpon)
Location 188 =
5 Mile Radius (2.8 mi N) Gardens (Austin)
!. l A.10 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following: ,
1
- The Nearest Residence l
The Nearest Meat Ammal
- The Nearest Garden greater than 50 square meters or 500 square feet 1
The Nearest Milk-giving Ammal (cow, goat, etc.)
l This census was completed July 6,1995 and the results are shown in Table 3.10 on pages 3-24 i and 3-25.
Appendix A.Page 5
l l
l V. PROGRAM IMPROVEMENTS l Trending of both air sampler and site location is performed for continuous identification of trends l impacting the deviation rate in the Radiological Environmental Monitoring Program (REMP). Each air site has been evaluated for correct grounding, proper voltage range and the equipment requirement to install surge and lightning suppressers. A work request was submitted on 10/09/95 to have surge protectors, lightning arrestors, electrical conduit and water resistant quad outlets installed l in each of the environmental air sampler weather houses.
i A work request was submitted on 09/12/95 to have annual planned maintenance performed on each of the surface water sites. The work request encompasses screen cleaning, solenoid valve inspection, I and plumbing clog inspection. To improve winter reliability, heat trace element installation for smface water sites #131 and #128 has been completed.
Various equipment upgrades and purchases were made in 1995 to enhance the radiological environmental monitoring program for McGuire Nuclear Station. A thorough description of the
, purchases and upgrades to the environmental program may be found in the " Sampling Deviation Reduction Plan for 1995 and 1996" in Appendix C, Section C.3.
Appendix A- Page 6
4 i
i 1
4.
f 3
i i i
4 ,
, l t
APPENDIX B l
- l l
l RADIOLOGICAL !
ENVIRONMENTAL l i MONITORING PROGRAM l 4
i i
SUMMARY
OF RFsSULTS
- 1995 i
1 a
4 i
! Note: IAcations, respective sectors and distances are included in Section 2.1, Site Descriptions j
J
)
i i
}
1 i
}
f 4
Environmental Radiological Monitoring Program Stamary Name of Facility : MCOUIRE NUCLEAR STATION Oocket NLmiber : 50 369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1-JAN-1995 through 31-0EC 1995 Time Report Generated : 11-JAN-1996 10:57:57 Catabase Name : $ DISK 1:(USER.ASC)MCGUIRE NUCLEAR STATION 95.sAF;4 l l l l Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l All Indicator l"""-""""--------"----"l l Non-Pathway l NLmber of l Limitofl Locations l Name,OistanceandDirectionl Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLO) l Range l Code Range l Range l Meas.
AIR PARTICULATE l l l l l l (PC!/M3) l l l l l134(8.7MiWNW) l l l l 1 I I 7 LOCATIONS lMN54 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l 1 I I I I lCO-58 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l l l l 1 lFE-59 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) ] 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l l 1 l l I I lCD-60 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l 1 I I l lZN-65 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00 - 0.00E+00 l 0.00E+00--0.00E+00l 1 1 I I I I lNB-95 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l 1 l l I I l2R-95 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 1 I I I I lI-131 364 l 7.00E-02 l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l l l l l lCS-134 364l 5.00E02l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l I I l l I i lCS-137 364l 6.00E02l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l l l l I jBALA-140 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l l l125(0.4MiSW) l l l BETA 364l 1.00E-02l 2.71E-02( 312/ 312) l 3.02E-02( 52/ 52) l 5.17E 02( 52/ 52) l 0 l l l 1.24E 02- 8.06E-02 l 1.58E-02-7.12E-02l 1.66E-02" 0.26 l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero renge indicates no detecta m activity measurements if LLO is equal to 0, then LLD is not rea'.iired by Selected Licensee Commitments Appendix B - Page 1
Envirorynental Radiological Monitoring Program Stamary Name of Facility : MCCU!RE NUCLEAR STATION Docket NLnber + $0 369,370 Location of Facility : MECKLENBURO COUNTY, N.C. Reporting Period : 1 JAN-1995 through 31-DEC-1995 Tima Report Generated : 11.JAN-1996 10:57:57 Database Name ' S0!SK1:(USER.ASC)MCCUIRE NUCLEAR STATION 95.SAF;4
.........................................................................................................~......~................
l l l l Location with Highest Mean l l No. of Medlun or l Type & Total l Lower All Indicator l-~.~.--------~~".-~.~~.l l N on-Pathway l Number of l Limit of . Locations l Name, Distance and Direction l Control Locations l Routine Sayled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) Mean (Fraction) l l Report (Units) l Performed l (LLO) l Ranga l Code Range l Range l Meas.
.......................................................... ........~...............................................................
AIRRAD10100!NESl l l l l l (PCl/M3) l l l l l134(8.7MiWNW) l l l 1 1 I 7 LOCATIONS l
lMN54 364l 0.00E+00l 0.00E+00( 0/312)l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00~ U.00E+00 l 0.00E+00~ 0.00E+00 l l l 1 I I I lCO-58 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l 0.00E+00-.0.00E+00l l l 1 1 I i lFE-59 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 I l ! I I lCo-60 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00~ 0.00E+00 l l l 1 I I I l2N.65 364l 0.00E+00l 0,00E+00( 0/312)l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00-.0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l 1 I I I l lNB95 364l 0.00E+00l 0.00E+00( 0/312)l 0.00E+00( 0/ 52) l 0.00E+00( C/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l l l 1 1 I I lZR-95 364l 0.00E+00l 0.00E+00( 0/ 312) l 0.00E+00( C/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l 1 1 I l l lI-131 364l 7.00E-02l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00~ 0.00E+00 l 1 I I I I I lCS134 364l 5.00E02l 0.00E+00( 0/ 312) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00" 0.00E+00 l l l l l120(0.4MiNNE) l l lCS137 364l 6.00E-02l 5.89E 03( 3/ 312) l 9.78E 03( 1/ 52) l 7.55E 03( 2/ 52) [ 0 l l l 3.33E03--9.78E03l 9.78E 03~ 9.78E 03 l 7.49E03--7.60E-03l l l l l 1 I lBALA-140 364l 0.00E+00l 0.00E+00( 0/312)l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0
- l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00
............................................................................................................................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, then LLD is not required by Selected Licensee connitments Appendix B - Page 2 l
l
_ _ ___ _ _ _ _ _ - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~
Environmental Radiological Monitoring Program Samary Name of Facility MCGU!RE NUCLEAR STATION Docket Number : 50-369,370 Location of facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1 . TAN-1995 through 31-DEC 1995 Time Report Generated
- 11 JAN-1996 10:57:57 Database Name
- S0!SK1:(USER.ASC)MCGUIRE NUCLEAR STAtl0N95.SAF
...................................................................................................................................;4 .
l l l l Location with Highest Mean lNo.of Modiun or l Type & Total l Lower l Att Indicator l......-.---~.------.---------ll l Non-Pathway l Nunter of l Limitofl Locations l Name,OlstanceandDirectionl Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range j Code Range Range Mea
.....................................................................................................l.......................l....s. ....
BROADLEAFVEGETl l l l l (PCl/ WET /KG) l l l l134(8.7MiWNW) l l MN 54 36 l 0.00E+00l 0.00E+00( 0/ 27) 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 4 LOCATIONS l l 0.00E+00-. 0.00E+00 l
0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 1 I i i I lC0-58 36l 0.00E+00l 0.00E+00( 0/ 27) l l l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) [ 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l 1 I I I I lFE-59 36l 0.00E+00l 0.00E+00( 0/ 27) l l
0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l i I I I . I lCo-60 36l 0.00E+00l 0.00E+00( 0/ 27) l l l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l I 1 i i l l lZW65 36l 0.00E+00l 0.00E+00( 0/ 27) l l l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l 1 1 I I lN895 36l 0.00E+00l 0.00E+00( 0/ 27) l l l 0.00E*00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l 1 1 I I I l2R-95 36l 0.00E+00l 0.00E+00( 0/ 27) j 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l l 1 I I I 131 36l 60. l 0.00E+00( 0/ 27) l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9)l 0 l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 1 I I I I lCS134 36l 60. l 0.00E+00( 0/ 27) 0.00E+00( 0/ 9) [ 0.00E+00( 0/ 9) [ 0 l l l 0.00E+00-- 0.00E+00 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l I I I I I I l CS 137 36l 80. l 0.00E+00( 0/ 27) l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l l l 0.00E+00~ 0.00E+00 l 1
0.00E+00.-0.00E+00l 0.00E+00--0.00E+00l I I I I I lBALA-140 36l 0.00E+00l 0.00E+00( 0/ 27) l 0.00E+00( 0/ 9) l 0.00E+00( 0/ 9) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-. 0.0CE+00 0.00E+00-- 0.00E+00
.....................................................................................................l.......................l........
Maan and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 2ero range indicates no detectable activity reasurements If LLD is equal to 0, then LLD is not required by Selected Licensee Commitments Appendix 8 - Page 3
s Environmental Radiologic *s knnitoring Program Swmary Name of Facility : MCGUIRE NUCLEAR STATION 00cket Number : 50-369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1-JAN-1995 through 31-0EC-1995 Time Report Generated : 11 J m 1996 10:57:57 Database Name : 50!SK1:(USER.ASC)MCGUIRE NUCLEAR STATION 95.SAF;4
.................................................... ............................................................................... ~
l l l l Location with Highest Mean l lNo.of Meditsn or l Type & Total l Lower l All Indicator l------------------------------l l Non-Pathway l Number of l Limitofl Locations l Name, Olstance and Direction l Control Locations l Routine Sempted l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLO) l Range l Code Range l Range l Meas.
CRwS l l l l l l +
(PCl/ WET /KG) l l l l lNOCONTROLLOCATIONSl l l l l l 1 LOCATION HN-54 10 l 0.00F+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10)l 0.00E+00( 0/ 0) l 0 l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 l l l l I 1 l lCo-58 10l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10)l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l l l l l l l lFS-59 10l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I I I lCo-60 10 l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I I ZN-65 10 l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10)l 0.'s01 +00( 0/ 0) l 0 %-
l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l r.0f600--0.00E+00l l 1 I I I I lNS95 10 l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 0) l 0 ,
l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l 1 I I I lZR-95 10 l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I I j1-131 10l 60. l 0.00E+00( 0/ 10) ] 0.00E+00( 0/ 10)l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 1 I I I I lCS-134 10l 60. l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10)l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I i 1 l l CS-137 10 l 80. l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10)l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l I I I I I I lBALA-140 10 l 0.00E+00l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 10) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00-- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 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 LLO is equal to 0, then LLO is not required by selected Licensee Commitments Appendix B - Page 4 ,-
Envirorynental Radiological Monitoring Program Summary ,
Name of Facility : MCGUIRE NUCLEAR STATION Docket N mber -
50-369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1 JAN 1995 through 31 DEC 1995 Time Report Generated : 11 JAN 199610:57:57 Database Name : SOISK12(USER.ASC]MCGUIRE NUCLEAR STAtl0N95.SAF;4 l l l l Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l ALL Indicator l--..---""-"-"'""""""l l Non-Pathway l Number of l Limitofl Locations l Name,DistanceandOfrectionl Control Locations l Routine Saript ed j Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) ] Performed l (LLD) l Range l Code Range l Range l Meas.
DRINKING WATER l l l l l (PCl/ LITER) l l l l136(12.5MiNNE) l .
l ANAL 1LL 52 l 1.0 l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 4 LOCATIONS l l l 0.00E+00" 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l l l l l ANAL 2LL 52l 1.0 l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00-0.00E+00l l l l l l l lMN54 52l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 1 I I I I I lCO-58 52 l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l 1 I I I lFE59 52l 30. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l 0.00E+00 " 0.00E+00 l ,
I I I I I i lCO60 52l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 0.00E+00" 0.00E+00 l l l l l l l lZN-65 52l 30. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00-- 0.00E+00 l 1 I I I I I lNS95 52 l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l l I i ZR 95 52l 15. l 0.00E+00( 0/ 39) l 0.00G+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l 0.00E+00" 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00" 0.00E+00 l l l 1 I I ll131 52l 15. l 0.00E+00( 0/ 39)l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l l l I I I I lCS-134 52l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 0.00E+00" 0.00E+00 l 1 l l I I I lCS-137 52l 18. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 .
l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 I I I I I lBALA-140 52l 15. l 0.00E+00( 0/ 39) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00-.0.00E+00l 0.00E+00 0.00E+00l 0.00E+00" 0.00E+00 l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zoro range indicates no detectable activity measurements If LLD is equal to 0, then LLO is not required by Selected Licensee Comitments Appendix B - Page 5
I Envirorsnental Radiological Monitoring Program Smynary Name of Facility : MCGUIRE NUCLEAR STATION Docket Nmber : 50 369,370 Location o' facility : MECKLENBURG COUNTY, N.C. Reporting Period .1-JAN 1995 through 31-DEC 1995 Time P y Jrt Generated : 11-J AN-1996 10:57:57 Database Name : SDISK1 IUSER.ASC)MCGUIRE NUCLEAR STATION 95.SAF;4 l l l l Location with Highest Mean l lNo.of Meditsn or l Type & Total l Lower l All Indicator l--.------------------...-----l l Non-Pathway l Nunber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sagted l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
DRINKING WATER l l l l l l (PCI/ LITER) l l l l119(7.4MiSSW) l136(12.5MiNNE) l 4 LCCATIONS l BETA 52l 4.0 l 3.7 ( 36/ 39) l 4.2 ( 13/ 13) l 3.3 ( 12/ 13) l 0 l l l 0.84 -- 17. l 0.98 -- 17. l 1.6 -- 7.4 l l t l I I I DW TRITIUM l l l l119(7.4MiSSW) l l (PCl/ LITER) lH3 16 l 2.00E+03l 3.58E+02( 1/ 12) l 3.58E+02( 1/ 4) l 0.00E+00( 0/ 4) l 0 4 LOCATIONS l l l 3.58E+02--3.58E+02l 3.58E+02--3.58E+02l 0.00E+00--0.00E+00l Mean arid 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, then LLO is not required by selected Licensee Comitments e
4 Appendix 8 - Page 6
Environmental Radictogical Monitoring Program SLmnary Name of Facility : MCGUIRE NUCLEAR STATION Docket Number 50-369,370 Location of Facility 4 MECKLENBURG COUNTY, N.C. Reporting Period . 1 JAN 1995 through 31-DEC 1995 Time Report Generated : 11 JAN 1996 10:57e57 Database Name : SDISK1 (USER. ASC)MCGUIRE NUCLEAR STAtl0N95.SAF;4 l l l l Location with Highest Mean l lNo.of Medlun or l Type & Total l Lower l All Indicator l...-.---..-..-.......-...-.....l l Non.
Pathway Number of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sanpled Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) Mean (Fraction) l Report l
(Units) u Performed l (LLD) l Range l Code Range l Range l Meas.
FISn ! I I I I I (PCl/ WET /KG) l l l l l 137 (12.0 Mi N) l l l .I I I I 2 LOCATIONS lMN-54 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l i I I I I lCo.58 12l 1.30E+02l 0.00E+00( 0/ 6)l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00.-0.00E+00l 0.00E+00--0.00E+00l l 1 I I I I lFE59 12l 2.60E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l 1 lCo60 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) [ 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l l l l l l 1 lZN-65 12l 2.60E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l C l l l 0.00E+00. 0.00E+00 l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l 1 I I I I I lNS-95 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00.-0.00E+00l 0.00E+00--0.00E+00l l l l l l 1 l2R-95 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 I I I I I l I 131 12l 0.0')E+00 l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0
0 l l l 0.00E+00. 0.00r+00 l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l l l 1 1 I I lCS-134 12l 1.30E+02l 0.00E+00( 0/ 6)l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l129(0.9MiENE) l l lCS-137 12l 1.50E+02l 27. ( 2/ e.) l 27. ( 2/ 6) l 0.00E+00( 0/ 6) l 0 l l l 19. -- 34. l 19. -- 34 l 0.00E+00--0.00E+00l l 1 I I I I lBALA140 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l Mean and range based upon detectobhr measurements only Fraction of detectable measurements at specified locations is indicated in parentneses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLD is not required by Selected Licensee Comitments Appendix B . Page 7
Environmental Radiological Monitoring Program Sumary t$ame of Facility : MCCUIRE NUCLEAR STATION Docket Number : 50-369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period .
- JAN-1995 through 31-DEC-1995 Time Report Generated : 11. J AN-1996 10:57:57 Database Name : S0!SK1:[ USER.ASC)MCGUIRE NUCLEAR STAT
.......................................................................................................................... ION 95.SAF;4 ..........
l l l Location with Highest Nean l Medlun or l Type & Total l Lower l All Indicator l lNo.of l.-""---.~"-""~""----l l Non.
Pathway Sanpled l Nuter of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) Mean (Fraction)
(Units) l l Report l Performed l (LLD) l Range l Code Range
.....................................................................................................l............ge Ran l Meas.
MILK I I I I I (PCI/ LITER) I l l l l l141(14.8MiWNW) l l l 1 1 4 LOCATIONS I i lMN-54 104l 0.00E+00l 0.00E+00( 0/ 78)l 0.00E+00( 0/ 26) i 0.00E+00( 0/ 26) [ 0 l l l 0.00E+00~ 0.00E+00 l 1
0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 1 1 I I lCo-58 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00(
l l Of 26) l 0.00E+00( 0/ 26) [ 0 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 1 I I I I lFE.59 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.009+00( 0/ 26)l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00~ 0.00E+00 l 1
0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l I I i l l lCO-60 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) { 0.00E+00( 0/ 26) l 0 l l l 0.00E+00~ 0.00E+00 l l
0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l I I I l ZN-65 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00(
! 0/ 26) l 0.00E+00( 0/ 26) l 0
] ] 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 I I NS 95 i i 104l 0.00900l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l 0.00E+00-- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l I I I I
lZR95 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) ,
l l 0.00E+00( 0/ 26) [ 0 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l I I l i I lI-131 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00(
l 0/ 26) l 0.00E+00( 0/ 26) l 0 l l 0.00G+00--0.00E+00l l I 0.00E+00~ 0.00E+00 l 0.00E+00.-0.00E+00l I I I i lLLI.131 104l 1.0 l 0.00E+00( 0/ 78) l 0.00E+00(
l 0/ 26) l 0.00E+00( 0/ 26) [ 0 l l 0.00E+00.-0.00E+00l 1
0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 l I I I I I lCS-134 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) { 0 l l l 0.00E+00~ 0.00E+b0 l l
0.00E+00--0.00E+00l 0.00E+00.-0.00E+00l l I CS-137 i l 104l 18. l 0.00E+00( 0/ 78)l 0.00E+00( 0/ 26)l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l 0.00E+00~ 0.00E+00 l 1 1 I I I I lBALA-140 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00(
l l 0/ 26) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 0.00
.....................................................................................................l......E+00~0.00E+00l .........................
Mecn and range based upon dettetable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectacle activity measurements If LLO is equal to 0, then LLO is not required by Selected Licensee Comitments Appendix 8 - Page 8
Environmental Radiological Monitoring Program Sumary Nant2 of Facility : MCGUIRE NUCLEAR STATION Docket N mber : 50-369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1 JAN 1995 through 31 DEC 1995 Time Report Generated : 11-J AN-1996 10:57:57 Database Name : SD I SK1 : [USE R . ASC] MCGU I RE NUCLE AR ST A T I ON95. SAF ; 4 l l l l Location with Highest Mean l l No. of Medi m or l Type & Total l Lower l All Indicator l-----------...--.-----------l l Non-Pathway l Nunber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
SE0! MENT l l l l l l (PCI/ DRY /KG) l l l l l137(12.0 min) l
[ l l l130(0.6MiSW) l l 3 LOCATIONS lMN54 6l 0.00E+00l 17. ( 1/ 4) l. 17. ( 1/ 2) l 0.00E+00( 0/ 2) l 0 l l l 17.- -- 17. l 17. -
- 17. l 0.00E+00--0.00E+00l 1 I I I I I lCo58 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l '
l l l 1 I I lFE-59 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l l l l l130 l l lCO-60 6l 0.00E+00l 23. ( 1/ 4) l 23. ( 1/ 2) l 0.00E+00( 0/ 2) { 0 l l l 23. --
- 23. l 23. --
- 23. l 0.00E+00--0.00E+00l l l l 1 I i lZN65 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I I lNS-95 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l l 1 I I lZR-95 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l C.00E+00( 0/ 2) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l l l l l l 1 l I-131 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l l l l l lCS134 6l 1.50E+02l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 I I I130 l I lCS-137 6l 1.80E+02l 1.38E+02( 2/ 4) l 1.38E+02( 2/ 2) l 0.00E+00( 0/ 2) [ 0 l l l 50. -- 2.27E+02 l 50. - 2.27E+02 l 0.00E+00--0.00E+00l l l l l I i lBALA140 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range irdicates no detectable activity measurements lf LLD is equal to 0, then LLD is not required by Selected Licensee Commitments 4
Appendix B - Page 9
Environmental Radiological Monitoring Program Sumiary Name of Facility 4 MCCUlRE NUCLEAR STATION Docket Nwber : 50 369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period 1-JAN 1995 through 31 DEC-1995 Time Report Generated : 11 JAN.1996 10:57257 Database Name : S0!SX1 (USER. ASC)MCGulRE NUCLEAR STATION 95.SAF;4 l l l l Location with Highest Mean l lNo.of Meditra or l Type & Total l Lower l All Indicator l.. -- ---- -- - ------ --- -l l Non-Pathway l N mber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sarpled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l . Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
SURFACE WATER l l l l l l (PCl/ LITER) l l l l l135(12.0 min) l 1 I I I I I 3 LOCATIONS l MN 54 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l
l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l l l l l l l l CO 58 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l l l l l I I lFE-59 39 l 30. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l 1 1 I I i
CO-60 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13) l 0 l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I l ZN 65 39l 30. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 i l l I I lN8-95 39l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l l 1 I I I 2R-95 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l l l l l lI-131 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l l l l 1 lCS134 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 1 I I I I l lCS137 39 l 18. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00-.0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l l l l l lBALA140 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l SW TRITIUM l l l l l l (PC1/ LITER) l l l l l l l l l l128(0.4MiENE) l l 3 LOCATIONS lH-3 12 l 2.00E+03l 3.04E+02( 3/ 8) l 3.15E+02( 2/ 4) l 0.00E+00( 0/ 4) l 0 l l l 2.06E+02--4.23E+02l 2.06E+02-4.23E+02l 0.00E+00-0.00E+00l 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, then LLD is not required by Selected Licensee Commitments Appendix B - Page 10
Environmental Radiological Monitoring Program $tsnmary Name of Facility : MCGUIRE NUCLEAR STATION Docket Number : 50 369,370 Location of Facility : MECKLENBURG COUNTY, N.C. Reporting Period : 1.JAN 1995 through 31.DEC-1995 Time Report Generated : 17-JAN 1996 15:56:28 Database Name : $ DISC 1 (USER.ASC]MWs95.sAF;4 l l l l Location with Highest Mean l lNo.of Meditsn or l Type & Total l Lower l All Indicator l.............-........-........l l Non.
Pathway l Ntsrber of l Limitofl Locations l Name, Distance and Direction l Control Locations lRoutie Sampled Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) Performed l (LLD) l Range l Code Range l Range l Meas.
DIRECT RAD TLD l l l l l l (nR/ QUARTER) l l l l l 175 (12.7 Mi WNW) l l l l l180(11.5MiNNE) l l 48 LOCAY!ONS lmR/QTR 188l 0.00E+00l 21. ( 184/ 184) l 33. ( 3/ 3) l 27. ( 4/ 4) l 0 l l l 13. -- 34. l 31. -- 34. l 24. .-
- 29. 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, then LLD is not required by Selected Licensee Commitments Appendix 8 . Page 11
- - - - - - - - - - - , - , , - - - - - - ~ - - , - - - - - - - - - - - - - - - - - , - - - - - - - - - - - - - - - - - - - - - - - - - , - - - - - - - - - - - - - - , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , - - , - - - - - - -
9 0
e APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES
APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CX)DFJ UF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergomg Reparr IW Inclement Weather SL Sample Im' Lost due to Laboratory Accident if Line Clog to Sampler SM Motor / Rotor Setzed -
OT Other TF Torn Filter l PI Power Intetrupt VN Vandah m l PM Prevenuve Maintenance C.1 SAMPLING DEVIATIONS The following deviations from sampling requirements occurred during 1995:
Air Particulate and Air Radioiodines Location : Scheduled - Actual Collection . Reason - Corrective Action
- Collection Dates . Dates -
120 5/16-5/23/95 5/16-5/23/95 BF Replaced fuse and restarted sampler.
Tagged sampler #0691 for first BF during this period.
121 3/21-3/28/95 3/21-3/22/95 BF Replaced fuse and restarted sampler.
This sampler, #9, will be checked periodically during the next week.
134 7/11-7/18/95 7/11-7/13/95 BF Replaced fuse and restarted sampler.
Probable cause was due to ,
thunderstorms in the area.
192 7/25-8/1/95 7/25-8/1/95 P1 Reason unknown. Restarted sampler.
195 5/16-5/23/95 5/16-5/18/95 BF Replaced fuse and tagged sampler #19 for first blown fuse during this period.
6/13-6/20/95 6/13-6/18/95 SM Replaced sampler. Probable cause was due to mechanical failure. Sampler <
will be repaired.
Note: Blown fuses caused the majority of air sampling deviations for 1995. Samplers are trended for problems by tagging each sampler as problems occur. AAer two consecutive blown fuses, the air sampler is taken out of service to be checked for operability. See Appendix C, Section C.3, Sample Deviation and Unavailable Reduction Plan for resolutions and future preventative measures.
Appendix C - Page 1
Drinking Water
' Location Scheduled Actual Collection Reason Corrective Action Collection Dates Dates 194 8/29-9/12/95 9/12/95 PS Grab sample collected. Notified Commodities and Facilities and submitted work request 95-MC3662 to repair / replace cracked PVC on the supply line to the solenoid valve at the ,
Lincoln County Water Treatment plant.
9/12-9/26/95 9/26/95 PS Grab sample collected. Sampler not yet repaired. Work request 95-MC3662.
9/26-10/10/95 9/27-10/10/95 PS Abbreviated sample collected.
Sampler repaired on 9/27. Work request 95-MC3662 closed out.
Note: All 1995 drinking water deviations were due t.o this one supply line problem which was fixed within two weeks of discovery.
Surface Water Location Scheduled Actual Collection Reason Cornctive Action Collection Dates Dates 131 3/14-3/28/95 3/20-3/28/95 PS Abbreviated sample collected. Notified Commodities and Facilities. Submitted work request 95-MC2363 on 3/14 to repair the inoperable pump.
135 2/14-2/28/95 2/28/95 PS Grab sample collected. Notified Commodities and Facilities. Submitted ,
work request 95 MC2235 on 3/1 to replace / repair the solenoid switch.
Pump is operable, but no water in sample tank.
2/28-3/14/95 3/8-3/14/95 PS Abbreviated sample collected. Work request 95-MC2235 was completed on 3/8 and the sampler was returned to service.
6/20-7/3/95 7/3/95 PS Grab sample collected. Notified Commodities and Facilities. Submitted work request 95 3344 to unclog sample line. There is power to the pump, but sample line is clogged.
Appendix C - Page 2 l
Surface Water (cont'd)
Location Scheduled Actual Collection Reason Contctive Action Collection Dates Dates 135 7/3-7/18/95 7/5-7/18/95 PS Abbreviated sample collected.
Sampler was inoperable at beginning of sampling period. Work request 95-3344 completed on 7/5.
8/29-9/12/95 9/12/95 PS Grab sample collected. Solenoid valve clogged. Valve was cleaned and sampler placed back in senice.
Note: Location 135 had various mechanical problems in 1995. See Appendix C, Section C.3, Sample Deviation and Unavailable Reduction Plan for resolutions and future preventative measures.
Appendix C . Page 3 m
C.2 UNAVAILABLE ANALYSES The following unavailables from sampling requirements occurred during 1995:
TLD I4 cation Scheduled . Reason ~ Corrective Action .
Collection Dates ,
156 3/27-6/27/95 VN TLD was missing. 4th Quarter TLD uns placed in field.
166 3/27-6/27/95 VN TLD was missing. 4th Quarter TLD uns placed in field.
180 9/25-12/27/95 VN TLD was missing. Ist Quarter '96 TLD was placed in field..
181 3/27-6/27/95 VN TLD was missing. 4th Quarter TLD was placed in field.
C.3 SAMPLE DEVIATION AND UNAVAILABLE REDUCTION PLAN The sampling deviation and reduction plan was initiated by the REMP working group on 9/25/95.
Items were identified to be addressed and/or implemented to bring about a reduction in the number of sample deviations and unavailable samples. The information in Table C.3-A was the schedule for which the identified activities took place.
TABLE C.3-A Deviation Reduction Plan Overview A ctivity description information is sorted by ascending target date completion.
Activity Date Target Date STATUS Description Initiated Completion CODE
- Purchase additional air stunplers for dual air monitoring 10/5/95 10/5/95 C Purchase "lSCO" portable composite water samplers 10/5/95 10/5/95 C Consistent Deviation / Unavailable codes implemented 10/5/95 10/5/95 C Heat tracing of applicable water sites 9/12/95 10/30/95 C Deviation section of AEOR to include more detail 10/17/95 11/15/95 C Air site electrical modifications 10/9/95 12/1/95 1 Air site grounding 10/10/95 12/1/95 1
_ Preventive maintenance of water sites implemented 11/16/95 12/7/95 P Water site electrical modifications 10/26/95 12/31/95 P Modify air sampler housing to accommodate dual samplers 1/1/96 3/31/96 P
- Timeframe STA TUS CODES: P = Pending,1 = In Process, C = Completed, D = Deleted PURCHASE ITEMS Table C.3-B lists items for the environmental monitoring program that were purchased to improve and enhance the environmental sample collection program. Included are sampling equipment and supplemental sampling items.
Apperdx C . Page 4
C.2 UNAVAILABLE ANALYSES The following unavailables from sampling requirements occurred during 1995:
TLD <
~
IAcation Scheduled Reason Cornetive Action :
Collection Dates 156 3/27-6/2W95 VN TLD was missing. 4th Quarter TLD was placed in field.
166 3/27 4/27/95 VN TLD was missing. 4th Quarter TLD was placed in field.
180 9/25-12/27/95 VN TLD was missing. Ist Quarter '9mD was placed in field..
181 3/27-6/27/95 VN TLD was missing. 4th Quarter TLD was placed in field.
C.3 SAMPLE DEVIATION AND UNAVAILABLE REDUCTION PLAN The sampling deviation and reduction plan was initiated by the REMP working group on 9/25/95.
Items were identified to be addressed and/or implemented to bring about a reduction in the number of sample deviations and unavailable samples. The information in Table C.3-A was the schedule for which the identified activities took place.
TABLE C.3-A Deviation Reduction Plan Overview Activity description information is sorted by ascending target date completion.
Activity Date Target Date STATUS Description Initiated Completion CODE
- Purchase additional air samplers for dual air monitoring 10/5/95 10/5/95 C Purchase "ISCO" portable composite water samplers 10/5/95 10/5/95 C Consistent Deviation / Unavailable codes implemented 10/5/95 10/5/95 C Heat tracing of applicable water sites 9/12/95 10/30/95 C Deviation section of AEOR to include more detail 10/17/95 11/15/95 C Air site electrical modifications 10/9/95 12/1/95 1 Air site grounding 10/10/95 12/1/95 I Preventive maintenance of water sites implemented 11/16/95 12/7/95 P Water site electrical modifications 10/26/95 12/31/95 P Modify air sampler housing to accommodate dual samplers 1/1/% 3/31/96 P
~
- Timeframe STA TUS CODES: P = Pending,1 = In Process, C - Completed, D = Deleted PURCHASE ITEMS Table C.3-B lists items for the environmental monitoring program that were purchased to improve and enhance the environmental sample collection program. Included are sampling equipment and -
supplemental sampling items.
Appendix C . Page 4
TABLE C.3-B Deviation Reduction Plan Equipment Purchases Sample Stream ITEM DESCRIPTION ITEM QUANTITY AIR 1/3 HP low volume air sample pump 8 AIR elapsed time meter,0.0 - 999.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (may be reset) 8 AIR NEMA conduit box for elapsed time meter 8 WATER "lSCO" model 3710 portable composite sampler 2 WATER Model 913 power converter & battery charger,120/60 2 WA1tR 100' of 3/8" bulk vinyl suction tube 2 WA1ex 3/8" vinyl suction line accessory kit 2 WAIen Weighted 3/8" stainless steel strainer 2 WATER Silicone rubber pump tube. 50' roll 1 WATER Model 934 nickel-cadmium rechargeable battery pack 1 SITE MODIFICATIONS Air sampling electrical andgrounding equipment will be provided by Consolidated Electrical Distributors (CED).
AIR SITES - Air sampler modifications will include the following items:
1 - Purchase additional air samplers for dual air monitoring to be implemented at each environmental air monitoring site. The dual samplers will be houied in existing sample houses.
2 - Upgrade electrical equipment at each air sample site. This will include the installation oflightning arrestors, waterproof outlets, GFCI breakers, and surge protectors.
This work request was submitted on 108/95 and can be referenced by work order 95-MC3835.
3 - Grounding of air sample houses and air sample cages to < 0.025 oluns. 7his work request was submitted on 109/95 and can be referenced by work order 95-MC3835.
4 - Modify air sample houses to allow for sufficient heat removal during summer months.
Currently, each air sample house is cooled by a continuously operating electrical cooling fan. After electrical modifications and grounding are completed, the sample houses will be physically altered to allow for natural cross-ventilation to occur to supplement the electrical fan. Sample house door hinges on both sides of the house will be moved and reversed to allow for a small, free, open air space to be created. This modification will create additional heat removal capability during the summer months while still protecting the air samplers incide the house from the Appendix C . Page 5
environment (i.e. wind, rain, snow). This work request will be initiatedfollowing the completion ofwork order 93-MC3835.
Sample site visits and evaluations for all of McGuire air sampling sites was performed on October 16,1995. The purpose of the visit was to identify the exact electrical equipment upgrade needs for each individual site. Results of these site visits are displayed in Table C.3-C.
TABLE C.3-C Deviation Reduction Plan Air Site Upgrade Equipment Purchases SPECIFIC UPGRADE ITEM 120 121 125 133 134 192 195 Ground Rod w/ clamps 5/8 x 8 1 1 1 1 1 n/a n/a 2/0 Bare Copper ft 10' 10' 10' 10' 10' 3' 2' 20 AMP GFCI Breaker n/a 2 2 2 2 2 2 WP Male Plug Woodhead 4 4 4 4 4 4 4 Multioutlet Box (4) WP receptacles 1 1 1 1 1 1 1 Vertical Fence Grd clamp n/a n/a n/a 2'3" n/a l'2" 2'4" Horizontal Fence Grd. Clamp n/a n/a n/a n/a n/a n/a n/a Equip. Grd. Clamp 2/0 2 2 2 1 2 1 1 Single phase panel arrestor SDSAl175 n/a n/a n/a n/a n/a n/a 1 Surge suppresser 1 1 1 1 1 1 1 l Ground Clamp n/a n/a n/a n/a n/a n/a 1 WATER SITES - Water sampler modifications include the following items:
1 - Purchase portable water compositors (ISCO) for utilization when water sites are undergoing preventive maintenance or repair.
2 - Upgrade electrical supply at each surface water site to sufficiently accommodate the ISCO portable water composite samplers.
3 - Heat tracing of water site #131 (Cowan's Ford Dam) and site #128 G.icGuire Discharge Canal) is complete under work request 95-MC3660.
4 - 110 volt outlets needed include:
SITE # 128 - DISCHARGE CANAL (under bridge)
SITE # 135 - MARSHALL INTAKE (site being evaluated) 5 - Work Request 95-MC3661 was initiated on 9/12/95 with a requested completion date of 10/31/95. This work request was written to establish the preventive maintenance program for water sites for McGuire's three surface water sample sites.
y .
Appendix C . Page 6 l
l
APPENDIX D ANALYTICAL DEVIATIONS -
No analytical deviations were incurred for the 1995 Radiological Environmental Monitoring Program.
Appendix D Page 1
\ -
(
APPENDIX E RADIOLOGICAL -
ENVIRONMENTAL MONITORING PROGRAM .
RESULTS 1995 This appendix includes all of the sample analysis reports generated from each sample medium for 1995. 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 IIuntersville, North Carolina. .
Appendix E. Page I
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