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Annual Radiological Environ Operating Rept 1991
	ML20095K015
Person / Time
Site:	Oconee
Issue date:	12/31/1991
From:	Hampton J; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9205040271
	Download: ML20095K015 (122)
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O ' Annual Radiological Environmental Operating Report 7

Dear-Sir:

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, Pursuant. to_LTechnical:' Specification 6.6.1.5, please find

< Jenclosed the' Oconee Nuclecr Site Annual Radiological IEnvironmental'LOperating Report for the calendar year.1991.

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I. OCONEE NUCLEAR STATION I

ENVIRONMENTAL RADIOLOGICAL MONITORING . . ' DAM I

ANNUAL OPERATING REPORT

'I Janus.ry 1,1991 - December 31, 1991 I.

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TABLE OF CONTENTS I mr -

List of Figures. . . . . . . . . . . . . . . . . . . . . . . . . . iii List of Tables . . . . . . . . . . . . . . . . . . . . . . . . . . iv

1. Executive Summary . . . . . . . ....... . . . . . 1-Page 1

2. Introduction. . . . . . . . . . . . . . . . . . . . . . . 2-Page 3 2.1 Site Description and Sample Locations . . . . . . . . 2-Page 3 I 2.2 Scope and Requirements of Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . 2-Fage 3 2.3 Statistical and Calculetional Methodology . . . . . . 2-Page 5 2.3.1 Estimation of the Mean Value. . . . . . . . . . 2-Page 5 2.3.2 Lower Level of Detection and Minimum 1 Detectable Activity . . . . . . . . . . 2-Page 6 2.3.3 Trend Identification. . . . . . . . . . . . . . 2-Page 7

3. Radiological Environmental Monitoring Program Discussion, Interpretation and Trending of Results. . . . . 3-Page 20 3.1 Airborne Radiciodines and Particulates. . . . . . . . 3-Page 22 3.2 Drinking Water. . . . . . . . . . . . . . . . . . . . 3-Page 26 3.3 Surface Water . . . . . . . . . . . . . . . . . . . . 3-Page 31 3.4 Milk. . . . . . . . . . . . . . . . . . . . . . . . . 3-Page 35 3.5 Broadleaf Vegetation. . . . . . . .. . . . . . . . . 3-Page 37 3.6- Shoreline Sediment. . . . . . . . . . . . . . . . . 3-Page 39 3.7 Fish. . . . . . . . . . . . . . . . . . . . . . . . 3-Page 45 3.8 Direct Gamma Radiation. . . . . . . . . . . . . . . . 3-Page 51 3.9 Land Use Census . . . . . . . . . . . . . . . . . . . 3-Page 55

-4.

Evaluation of Doses From Environmental Measurements Versus Estimated Dose From Releases. . . . . . . . . . . . . . . . 4-Page 57 4.1 - Dose From Environmental Measurements. . . . . . . . . 4-Page 57 tI I 4 J

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TABLE OF CONTENTS I TITLE (continued)

PAGE 4.2. Estimated Dose From Releases. . 4-Page 57 I

4.3 Comparison af Doses . . . . . . . . . . . . . . . . . 4-Page 5?

5. Quality Assurance. . . . . .. . . . . . . . . . . . . . . 5-Page 82 l 5.1 Duke Power Company's Environmental Laboratory 5.1.1 Sample Collection. . 5-Page 82 5.1.2 Sample Analysis. . 5-Page 82 I

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5.1.3 Dosimetry Analysis . . . . . . . . . . . . . . 5-Page 82 l 5.1.4 Intralaboratory Quality Assurance. . . . . . . 5-Page 82 5.1.5 Interlaboratory Quality Assurance. . . . . . . 5-Page 83 5.2 Contractor Laboratory . . . . . . . . . . . . . . . 5-Page 88

6. References . . . . . . . . . . . . . . . . . . . . . . . . 6-Page 92 Appendices:

A. Environmental Sample and Analysis Procedures . . .. . . . A-Page 93 B. Radiological Environmental Honitoring Program Summary of Results . . . . . . . . . . . . . . . . . . . . B-Page 97 C. Sampling Deviations and Unavailable Analyses . . .... . C-Page 108 D. Analytical Deviations. . . .......... . .... . D-Page 111 I

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LIST OP PIGURES .

E1Ct1IEg TirLE EAGE 2.1-1 Oconee Nuclear Stat. ion Radiological Monitoring Program Locations . . . . . . . . . . . . . . 2-Page 13 2.1-2 TLD Monitoring Locations at the Site Boundary. . . . . . 2-Page 14 3.2-1 H-3 in Drinking Water Samples. . . . . . . . . . . . . . 3-Page 30 3.6-1 Shoreline Sediment Co-60 and Ag-110m Activity. . . . . 3-Page 42 3.6-2 Shoreline Sediment Antimony Activity . . . . . . . . . . 3-Page 43 3.6-3 Shoreline Sediment Cesium Activity . . . . . . . . . . 3-Page 44 3.7-1 Cs-134 and Cs-137 in Bass Samples. . . . . . . . . . . . 3-Page 49 3.7-2 Cs-134 and es-137 in Catfish samples . . . . . . . . . . 3-Page 50 3.8-1 Environmental TLD Doserates. . . . . . . . . . . . . . . 3-Page 54 1

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LIST OF TABLES I TABLE TITLE PAGE 2.1-1 Radiological Environmental Menitoring Program Sampling Locations. . . . . . . . . . . . . . . . . . . . . 2-Page 15 I' 2.1-2 Radiological Environmental Monitoring Program TLD Locations . . ... . . . . . . . . . . . . . . . . . . 2-Page 16 2.2-1 Radiological Environmental Monitoring Program I- Analyses. ... . .... . . . . . . . . . . . . . . . . . 2-Page 17 2.2-2 Maximum Values for the Lower Limits of Detection (LLD). . 2-Page 18 2.2-3 Reporting Levels for Radioactivity Concentrations In Environmental Samples. . . . . . . . . . . . . . . . . . 2-Page 19 3.1-1 Airborne Particulates Filters Mean Annual Concentrations. ...... . . . . . . . . . . . . . . . . -lage 22 3.1-2 Airborne Radiciodine Cartridges Mean Annual Concentrations. .. ... . . . . . . . . . . . . . . . . . 3-Page 23 3.1-3 Airborne Particulates Trend Analysis of Mean Annual Concentrations. . . . . . . . . .. . . . . . . . . . . . . 3-Page 24 3.1-4 Airborne Radiciodine Trend Analysis of Mean Annual Concentrations. ...... . . . . . . . . . . . . . . . . 3-Page 25 3.2-1 Drinking Water Mean Annual Concentrations . . . . . . . . . 3-Page 26

_I 3.2-2 Drinking Water Trend Analysis of Mean Annual Concentrations. . . . . . . . . . . . . . . . . . . . . . . 3-Page 28 3.3-1 Surface Water Mean Annual Concentrations. . . . . . . . . . 3-Page 32 3.3-2 Surface Water Trend Analysis of Mean Annual Concentrations. . . . . ... . . . . . . . . . . . . . . . 3-Page 33 3.4-1 Milk Mean Annual Concentrations . . . . . . . . . . . . . . 3-Pege-35 3.4-2 Milk Trend Analysh of Mean Annual Concentrations . . . . . 3-Page 36 3.5-1 Broadleaf Vegetation Mean Annual Concentrations . . . . . . 3-Page 37 3.5-2 Broadleaf Vegetation Trend Analysis of Mean Annual Concentrations. . ..... . . . .. . . . . . . . . . . . 3-Page 38 I_ 3.6-1 Shoreline Sediment Mean Annual Concentrations . . . . . . . 3-Page 40 I

iv I

LIST OF TABLES

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E-TABLE TITLE PAQI 3.6-2 Shoreline Sediment Trend Analysis of Mean Annual Concentrations. . . . . . . . . . . . . . . . . . . . . . . 3-Page 41 3.7-1 Fish Mean Annual Concentrations . . . . . . . . . . . . . . 3-Page 45

-3.7-2 Fish Trend Analysis of Mean Annual Concentrations . . . . . 3-Page 47 3.8-1 Comparison of Inner Ring / Outer Ring TLD Results . . . . . . 3-Page 52 3.8-2 Direct Radiation as Measured by TLDs Mean Annual Dose Rates. . . . . . . . . . . . . . . . . . . . . . . . . _-Page 53 3.9-1 Land Use Census Data Sheet. . . . . . . . . . . . . . . . . 3-Page 56 4.1 1991 Environmental and Effluent Doses . 4-Page 59 I

4.2 Doses from 1991 Environmental Measurements. . . . . . . . . 4-Page 61 I 5.1 U.S. Environmental Protection Agency Interlaboratory Comparison Program 1991 Cross-Check Results for the ERL . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-Page 89 l- 5.2 North Carolina Department of Human Resources Enviroranental Dosimeter Cross-Check 1991. . . . . . . . . . 5-Page 91 I

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I SECTION 1.

EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Oconee Nuclear Station Radiological Environmental Program and the results of the program for the calendar year 1991.

Included in the report are identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of doses calculated from environmental measurements and doses calculated from effluent data, a summary of :he results of the 1991 program, discussion of the results, and discussion of the quality assurance activities associated with the program. Deviations from program requirements and changes made to the program are also included.

Sampling activities were conducted as prescribed by Selected Licensee Committents (SLC). Required analyses were performed and detection

-capabilities met SLC. In addition, supplemental samples were taken and additional analyses performed to better assess radioactivity in the environment.

Concentrations observed in the environment in 1991 for station related ,

radionuclides were generally within the ranges of concentrations observed in the past. Compared to 1990, there was very little difference in the radionuclides detected and their concentrations. All positive indications of radioactivity due to plant operations were well below the reporting levels specified by the Nuclear Regulatory Commission (NRC) as given in Selected Licensee Commitments. Visual inspection of data indicated that radionuclide concentrations in drinking water, surface water, shoreline sediment, and fish have increased since the operation of Oconee Nuclear Station began. Statistical analysis of the historical data showed the existence of any continuing increase to have moderate to no probability.

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I comparisons of doses calculated from environmental measurements and doses calculated from effluent data demonstrated that levels of radioactivity were not higher than expected and were within the Selected Licensee Commitments limits. In conclusion, Oconee Nuclear Station's contribution to environmental radioactivity is small and has had no significant radiological impact upon the health and safety of the general public.

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I SECTICN 2.

INTRODUCTION 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the there of Lake Keowee. This lake was formed by damming the Keovee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydro-electric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north the Jocassee Hydro-electric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant.

ONS consists of three pressurized water reactor units with a combined generating capacity of 2658 megawatts. Unit 1 began commercial operation 07/15/73. Unit 2 began commercial operation 09/09/74, and Unit 3 began on 12/16/74.

Site specific locations for the Radiological Environmental Monitoring Program are defined in the Duke Power Company Offsite Dose Calculation Manual (ODCM). Figure 2.1-1 is a map depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The samples obtained from the locations include Airborne Radioiodine and Particulates, Drinking Water, Surface Water, Milk, Broadleaf Vegetation. Shoreline Sediment and Fish. Table 2.1-1 lists the specific samples required for each location. Figure 2.1-2 is a map showing the TLD locations within a 1 mile radius of the site. Table 2.1-2 lists the locations of all the TLDs.

I 2.2 SCOPE AND REG'JIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM An environmental surveillance program has been continuously conducted i

at ONS since 1969, four years prior to operation of Unit 1. The 2-Page 3

I purpoce of the preoperational program was to document the existing environmental radioactivity levels and their variability during sampling in order to develop a baseline to which operational levels may be compared. The current operational program was established to detect changes in radioactivity levels in the environs of the plant and to supplement the radiological effluent monitoring program by verifying that the measurable activity and radiation levels are not higher than those expected based on effluent measurements and modeling of the environmental exposure pathways. In addition, measured concentrations and dose rates are compared to the levels and limits specified in Selected Licensee Commitments. Trends are identified so thct corrective actions may be taken prior to levels and limits being exceeded.

I The sample media used, the sampling locations, and the sampling frequencies are selected to monitor significant dose pathways as well as the anticipated types and quantities of radionuclides released from i the plant. Locations and media are utilized that would demonstrate physical and biological sites of activity accumulation. Control locations are utilized to distinguish between activity of plant origin and environmental background levels. Frequencies of sampling and sample quantities utilized are based on the release rate of plant effluents, the half lives of the radionuclides, and the required detection capabilities of the analyses. In turn, the concentrations specified for the detection capabilities correspond to environmental concentrations that could result in doses that are fractions of the allowable dose limits.

I The specific locations and sample frequencies given in Table 2.1-1 and 2.1-2 meet the program conditions of ONS Selected Licensee Commitments 16.11-6. The Selected Licensee Commitments also defines the analysis type, frequency and detection capabilities for each sample. These are repeated in Tables 2.2-1 and 2.2-2. Non-routine reporting levels for activity found in environmental samples are listed in Table 2.2-3.

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lI l These reporting levols are based on the activity in the pathway resulting in potential doses corresponding to the 10CFR50 Appendix I calendar-year dose objectives for effluents for one reactor.

I An additional surveillance requirement is that an annual Land Use Census be conducted. The census assures that changes in the use of the plant environs are identified. The census results are used to make appropri, ate modifications to the monitoring program and the parameters utilized to calculate doses from plant effluents.

I 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY I

2.3.1 ESTIMATION OF THE MEAN VALUE I There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determir_ation of the mean value fo' 'he indicator and the control samples for each sample medium. The mean (R) 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 N

- n.h K 1 N (eg. 2-1) where,x = estimate of the mean I i = individual sample N = total number of samples with a net activity (or concentration),

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

NOTE: "fiet activity (or concentration)" is the activity (cr I concentration) determined to be present in the sample.

No " Minimum Detectable Activity", " Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of I the mean. Prior to 1987 Minimum Detectable Activities (MDA) were included in the calculation of the mean when no detectable activity was found. Both positive and j negative MDA values were used in the mean calculctions.

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2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY I l l

The Lower Level of Detection (LLD) and Minimum Detectable i- Activity (MDA) are used throughout the Environmental Monitoring Program, both in the selected Licensee I Commitments and in the implementation of the committnent.

I The LLD, as defined in the Selected Licensee Commitment, is the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower

.I- limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The " required" LLD's for each sample medium and selected radionuclides are

given in the Selected Licensee commitments and are listed in Table 2.2-2.

I The MDA may be thought of as an " actual" LLD for a particular san.ple measurement remembering that the MDA is calculated using a sample background instead of a system background. In gamma spectroscopy analyses, the sample background may be elevated above the system background due to the continuum produced by higher energy gammas from other radionuclides (eit'ner man-made or naturally produced). The continuum increases the smallest concentration of a particular radionuclide that could be positively identified in the samp7e. Therefore, to insure that the " required" LLD is not exceeded for any radionuclide 4n a sample medium, the 2-Page 6 i

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I MDA is calculated based on the actual background in the area of the identifying gamma energy and is compared to the

" required" LLD. If the MDA exceeds the " required" LLD, the sample is counted for a longer time period so that the i

standard deviation of the sample background is minimized.

If the " required" LLD exceeds the MDA, then the analysis of the sample meets the requirements for the detection capebility for environmental sample analysis.

l For " gross" counters (such as alpha / beta proportional

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counters and liquid scintillation counters), the HDA is calculated using a batch background ::ount. This MDA is then compared to the " required" LLD. If the MDA exceeds the

" required" LLD, the sample is counted for a longer time period so that the standard deviation of the batch background is minimited. If the " required" LLD exceeds the MDA, then the analysis of the sample meets the requirements for the detection capability for environmental nample analysis.

I 2.3.3 TREN 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 either positive or negative. Since nuclear reactor operations do not normally 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 2-Page 7

I to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

In some cases, visual inspection of tabular or graphical presentations of data may be sufficient to determine if a trend exists. In other cases, it may not be so obvious.

Therefore, it is desirable to obtain a single numerical value from the data which will permit a meaningful intes sretation of the relationship existing between the variations in the data. If it 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 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:

r= NIXY - IXIY (eq.2-2)

{ (NIX 2 .

(IX)2) (NEY2 . (ty)2) )

I where, 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 ras.ge of values as calculated by the correlation I_ coeflicient lies between positive one (+1) and negative one

(-1). The absolute value of the correlation coefficient represents the probability of a trend. Zero (0) represents no indication of either a positive or negative trend. A positive (+) correlation coefficient indicates an increasing I

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I trend, and, conversely, a negative (-) correlation I coefficient indicates a decreasing trend. The ranges of a a -

correlation coefficient are summarized below: l 1 2 lrl > 0.7 High to moderate probability of a trend.

3 0.7 2 lrl > 0.3 Moderate to poor probability of a trend.

0.3 2 lrl 2 0 Poor to no probability of a trend.

Identifying a trend by using the correlation coefficient is on ly 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 l decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Other factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought or heavier than normal precipitation),

construction in or around either the nuclear plant or 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.

I The change in 1987 in the method of calculating the mean (using enly net positive results) will also affect the apparent trends. ,

I Because of these considerations, how trends are identified will depend not only on the least squares regression method, but will include some judgement by plant pe; sonnel on the factors affecting environmental levels.

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I-In some cases, we would not expect to observe a buildup of radionuelides in the 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 reactor discharges are having an impact on the environment, since there is no bioaccumulation. Another test is needed to give us a meaningful interpre,ation of the data. If we sssume that the naturally occurring radiation levels around the plant are normally distributed, and that the reactor discharges are not affecting the environment outside of this normal distribution, then we can compare the values of two sets of measurements taken at different nimes around the plant. The comparison involves one when we are certain no effect is occurring and one when an effect may be occurring and determine if they are statistically different from one another.

The statistic that compares the means from two sets of measurements to determine if there is a statistically significant difference is called the test statistic, or t-statistic, and is calculated as follows:

t= xi _2, s, V'1/ni + 1/n, where,

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x, = the mean value of the first set of measurements x, = the mean value of the second set of measurements

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s, = the average standard deviation of the two sets of

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s. = 2 where, s,' = fD, - 1 ) s , + ( n, - l i s, n, ~ t n, - 2 ni = the number of measurements in the first set n, = the number of measurements in the second set The calculated value of the test statistic is then compared to expected values of the test statistic tabulated based on the numbe: of measurements taken and the degree of confidence required for the results. For our purposes, the expected value of the test statistic will always be cho,+ .

te give us a 95% confidence level that a positive result is truly positive with only a 5% probability that a positive result is truly negative. This conficance level is chosen since it is consistent with the standard confidence levels specified for similar measurements.

I Due to the existence of naturally occurring differences in backgmund 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 of individual measurements. By using ratios, the errors associated with the measurement process then cancel each other out 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 another I. year.

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I -As with other environmental samples, outside factors may affect tiie results observed and the resulting trends identified. Therefore, the significance of trends will be based 'n part on judgement of plant personnel familiar with the factors affecting environmental levels, as well as the statistical results.

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BOUNDARY 045 026 5.0 MILES SSW TERMINUS OF HWY. 588 AT CROOKED CREED' 0.3 MILES SE SITE BOUNDARY 046 4.5 MILES SW HWI. 188 AT CROOKED CREEK ERIDGE

, 027 0.3 MILES SSE SITE BOUNDARY 028 047 ' 4.0 MILES WSW NEW HOPE CHURCH. HWI. 188 0.5 MILES S SITE BOUNDARY 048 4.0 MILES W JCT. EM. 175 & 188 029 0.6 MILES SSW SITE BOUNDARY 049 4.0 MILES WIN JCT. HWY. 201 & 92 030 0.4 MILES SW SITE BOUNDARY 050 4.0 MILES FM 031 STAMP CREEK LANDING-END OF EM. 92 0.2 MILES WSW SITE BOUNDARY 051 032 0.2 MILES W 4.5 MILES NfM FM. 128. 1 MILE N OF FM. 130 SITE BOUNDARY 052 12.0 MILES _ENE DPC BRANCH OFFICE-PICKENS E3 0.2 MILES WNW SITE BOUNDARY 053 11.0 MILES E DPC BRANCH OFFICE-LIBERTY 034 0.2 MILES NW SITE BOUNDARY 054 9.5 MILES ESE POST OFFICE-HWY.93 NORRIS 035 0.1 MILES NIN SITE BOUNDARY 055 9.5 MILES SSE CLEMSON htitOROLOGY PLOT 036 4.0 MILES N MILE CREEK LANDING 056 8.4 MILES SSW WATER TOWER-SENECA 037 4.5 MILES NNE KEDWEE CHURCH. HWY. 327 057 9.0 MILES SW OCONEE MEMORIAL HOSPITAL 038 4.0 MILES NE DURHAM CO?NENIENCE MART, JCT.

HWI . 183 & 133 058 10.0 MILES WSW BRANCH ROAD SUBSTATION-WALHALLA (CCNTROL) 039 4.0 MILES ENE WT. 133, 1 MILE EAST OF JCT. 059

, HWY. 183 & 133 9.0 MILES NW TAMASSEE DAR SCHOOL 2-Page 16

- g - g. g' g . g g M. M M -M .M .M M' 'M M M M M~ M-TABLE 2.2-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANALYSES ANALYSES SAMPLE MEDIUM ANALYSIS SCHEDULE GAMMA ISOTOPIC TRITIUM LOW LEVEL GEQLS ILQ

1. Air Radioiodine and 1-131 BETA Particulates Weekly X ,

2. Direct Radiation Quarterly X

3. Surface Water Monthly X Quarterly Composite X

.4. Drinking Water Monthly X X Quarterly Composite X

5. Shoreline Sediment Semiannually X

6. Milk Semimonthly X X

7. Fish Semiannually X

8. Broadleaf Vegetation Monthly X 2-Page 17

m W W W m M M M M M M m '.. m m M .m TABLE 2.2-2 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (Tfn) i sier Airborne Analysis Particulate Broadleaf Water or Gas Fish Milk Vegetation Sediment (pci/1) (pci/m') (pci/kg, wet) (pci/1) (pci/kg, vet) (pci/kg, dry) gross beta 4 H-3 2000 Mn-54 15 130 Fe-59 30 260 co-58,60 15 130 Zn-65 30 260 l Zr-95 30 Nb-95 15 I-131 15 7 x 10 ,

1 60 Cs-134,137 15,18 5,6 x 10-# 130,150 15,18 60,80 150,180 Ba-140 60 60 La-140 15 15 2-Page 18 i'

., . r- , -

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. Analysis Water Air Particulates Fish Milk Vegetation (pci/1) or cases (pci/m') (pci/Kg, wet) (pci/1) '

(pci/Kg, wet)

H-3 2 x 10**

l Mn-54 1 x 10' 3 x 10' Fe-59 4 x 10' 1 x 10' Co-58 1 x 10' 3 x 10' Co 3 x 10* 1 x 10' Zn-65 3 x 10' , 2 x 10' Zr-Nb-95 4 x 10' I-131 2" 1 'a 1 x 10' Cs-134 30 10 1 x 10' 60 1 x 10' cs-137 50 20 2 x 10' 70 2 x 10' Ba-La-140 2 x 10' 3 x 10'

'For drinking water samples. This is 40CFR Part 141 value.

- If lov level I-131 analyses are performed.

2-Page 19

I SECTION 3.

RADIOLOGICAL ENV2RONMENTAL NON!TORING PROGRAM DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS I Data trom the,1991 environmental ronitoring program was compared to preoperational and historical data whenever comparable. Comparisons from preoperatirnal through the present were possible for fish samples and direct gamma radiation as measured by TLD. Analysis results for other sample media were not directly comparable to preoperational and earlier ops. rational sample resulte because of either significant changes in the analysis methods or changes in the reporting

the results.

I Trend analyuis was performed for the radionuclides listed in Selected Licensee Commitment 16.11-6. These radionuclides are cellectively referred to os " Selected Licensee Commitments radionuclides" and include H-3, Mn-54, Fe-59, Co-50, Co-60, Zn-65, Zr-95, Nb-95, I-131, Cs-134, Cs-137, Ba-140, La-140, and gross beta for drinking water. In addition to these, trending was performed for other radionuclides that were detected and could have been the result of station effluents. For 1991, this included Ag-110m and Sb-125 in shoreline, sediment and Ag-110m in surface water.

Trending was performed using visual inspection and statistieni analysis of data. Trend methods included comparina annual mee.n concentrations of any ,

plant related detected radionuclide to the previous year's concentration.

Factors' evaluated included the frequency of detection and the concentration in terms of the percent of the radionuclido s reportirg level. The highest

. I- cnnual mean concentration of each Selected Licensee Commitments radionuclide and an? aber detected effluent related radionuclide was use' for the estimation u *.he linear regression correlation coefficient. Any negative annual mean values given as a result of previous reporting practices (described in section 2.3.3) were replaced with zero to properly represent environmental conditions.

3-Page 20

I Graphs of individual complo rosults were plotted for any datocted radionuclide that was a major dose contributor for the sample media's pathway according to dose calculations based on effluents. A radionuclide is considered a major dose contributor when 5% or more of the pathway dose is ciue to the radionuclide. Graphs are also drawn for a radionuclide whenever lucar regression analysis shows high probability of a positive trend. There were no high positive trends in 1991.

I peta presented in Sections 3.1 - 3.8 support the conclusion that there was

no significant increase in radionuclides in the environment around ONS due ,

to station operations in 1991. Similarly, there was no significant <

increase in ambient background radiation levels in the surrounding areas.

Section 2 and Appendix A provide additional information regarding sampling locations, sampling and analysis requirements. trend identification methods, and a description of the sampling and analysis procedures.

Appendix D contains tables summarizing sample results. These tables include detectable results of Selected Licensee commitments radionuelides only. Other radionuclides that were detected, as well as Selected Licensee Commitments radionuclides, are summarized in this section. Section 4 contains dose calculations based on the radionuclides and concentrations observed during 1991. Section 5 summarizes the quality assuranae activities for the year associated with radiological environmental mos.itoring. Appendices C and D list deviations from Selected Licensee Comnitments sampling and analysis requirements fcr environmental monitoring.

I I

I 3-Page 21 LI

I 3.1 AIRBORNE RAD 1010 DINE AND PARTICULATES I Gamma spectroscopy was performed on 258 fiber filters and 258 chatcoal cartridges collected during 1991. Tables 3.1-1 and 3.1-2 summarite the radionuclides that were detected. Comparison of the data in the tables shows that no radionuclides were detected at the indicator or control locations. No increases in radioactivity have occurred at the indicator locations.

I l TABLE 3.1-1 AIRBORNE PARTICULATES FILTERS 1 HEAN ANNUAL CONCENTRATIONS (Pei/m')

1990 1991 1991 Isotope Highest Mean Highest Deporting control Deporting Hean Level Hean Level None i Detected i

E I

I I

!I I 3-Page 22 I

5 TABLE 3.1-2 I AIRBORNE RADI0 IODINE CARTRIDGES MEAN ANNUAL CONCENTRATIONS (pCi/m')

1990 1991 1991 Isotope Highest Mean Highest % Reporting Control % Reporting I -

te .,,e

Mean Level Mean Level Detected I As reported in the 1989 and 1990 Annual Radiological Environmental operating Report, Cs-137 was observed as being present in air cartridges but not the corresponding particulate filter. However, this did not occur in 1991. An extensive investigat!on, performed by I the Radioanalysis Laboratory, lead to the conclusion that the ts-137 activity detected was not attributed by station effluents but is an I active constituent of the charcoal.

Visual 1.spection of tabular data taken from previous environmental report summaries and the 1991 summary did not reveal any increasing I- trends. Linear regression analysis results give a low probability of a trend for the majority of the radionuclides. None of the I radionuclides that had indications of increasing trends (positive correlation coefficient) were detected in any of the indicator I location samples taken during 1991. Table 3.1-3 and 3.1-4 summarizes I the data used and the results of the lineaj pregression analysis.

ly K-40 and Be-7 were observed in air samples in addition to the radionuclides listed in the tables.

I I

I 3-Page 23 I J

W W W WM M M M MM M M M M M M M M W

+

TABIE 3,I-3 AIRBORNE PARTKULATES -

TREND ANALYSIS OF MEAN ANNUAL CONCEN~IRAITONS CONCENTRATION (pCi mi) i I I I I I I i YEAR Ma-54 I I I i 1 I I I Ce 58 i Fe-59 I CoJo I 7:45 i NEOS I 7r 95 l I-l JI l Cs-134 i CSI 3? I I4ata-I m l l

l INDICATOR I INIMCATOR l INDICATOR i !ND!CATOR I INDICATOP, I IND'CATOR ! INDICATOR I INDICATOR l WIMCATOR l INDICATOR I INDICATOR l I l i i I I I 1 1 ! I I I _ l i I i I I I I I I I -

I 1 l 1979 I 5 52E44 I 536E44 1 1.85E-03 1 7.22E44 1 0 0 rid 10 1 73'E-04 1 7.57E44 1 7.54E43 1 $ M 44 1 5 60E43 l 1.5',E 44 I 1 1 i i i 1 1 I I I I I I i 1080 l 3.83E44 I 4 4 tE44 1 1.02E43 1 6 48E44 1 1.70E44 1 3.f EE43 I 3.ISE43 1 307-03 l O GT+<n i 1 1 I I 2.EE43 l 142E43 1 1 I I ( l i I I 10Rt I I I 7.14E44 1 2.76E-04 I t .83E41 i 1.I IE-03 1 0.00E +00 1 639E42 1 3.03E42 1 63 tE41 !

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l i Makrsse ! l Woerme ! Mh I Wimse ! Pw I li.sh l P= l 1 1 1 I I I I I t I I I I Tn= 1 1 I I I I i 1 I I !

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i -I I l I i l I I I YEAR ! Ms-54 i C+5a ! Ee-59 1 Co-60 I Ze45 ' 4 95 I I i _ 1 i l I Is 95 I t-lit i Cs-114 i Cs-117 s e'N

I Ii MACATORI I_.INDICATOR I_ I WD?CATOR I I INDfCATOR I INDICATOR l WDtCATOR I INDICATOR I INDICATOR I INDICATOR I INDf 1 I I i 1 I i I !

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I I l 722E44 1 000E*M i 75744 1 737E-o4 1 734E41 1 3ME44 1 5 69E43 I IN* ;

! ! I i 1080 1 3.8?E44 1 1 1 I I l i 4.4 t E44 1 192E43 1 6.4*E44 l 1.7nE44 1 t I I 3.t sE41 l 3. I BE4) i 10*E41 1 0.mE+00 1 2%E43 l 14f 5 I i 1 1 1 1 l 8081 1 7.14E44

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i l i i tem ==se i Dammeg ! Demews I I i i i ! I I Note: I ! I An negative mess values men replacas eth 'serW for calculauaani purpo es.

LPaqre 25

l 3.2 DRINK!CG WATER Gross beta analysis and gamma spectroscopy were performed on 39 monthly drinhing water samples. These samples were composited to form 15 quarterly period samples for Tritium analysis.

I Radioactivity was detected in the gross beta analyses. Table 3.2-1 i summarizes the results. The detection frequency increased in 1991 but the mean concentration decreased. The frequency of detettion may have been affected by the change in determining the critical level dascribed in Appendix A. There is also little difference between the indicator and control concentrations for 1991. Tritium was detected in one of the quarterly composites. Table 3.2-1 and 3.2-2 summarizes the results. All concentrations were well below any reporting levels.

I TABLE 3.2-1 DRINKING WATER MEAN ANNUAL CONCENT' ATIONS (pCi/ liter) l 1990 1991 1991 Isotope Highest Mean Highest % Reporting Control % Reporting Mean Level Mean Level H-3 ---(0/5)--- 5.58E2(1/5) 2.79% --- (0/5) ---

I Gross Beta 3.0E0(3/13) 1.81EO(10/13) HS 1.41(10/13) NS Value in parenthesis is the fraction of detectable measurements. NS = none specified by Selected Licensee Commitments.

Visual inspection of tabular data summarizing activity observed from tha preoperational period through 1991 did not show any siginifl cant increasing trends. Only one of the radionuclides evaluated by511near regression analysis had a high probablity of a trend. That I radionuclids was I-131 with a high probability of a decreasing trend.

I 3-Page 26

I Total Bata results had modarste probability of an increceing trend.

Linear regression analysis data and results are contained in Table 3.2-2.

I A previous drinking water location, Clemson Water Plant, location number 065, is still monitored though not required by Selected Licensee Commitments. The plant was closed 7/01/89, The raw water that supplied the plant continues to be sampled and results trended.

Only H-3 and K-40 have been detected in the raw water samples since the plant closure. The H-3 concentration averages to 7.96E2 pCi/ liter for the 1991 period, and is similar to the finished drinking water H-3 levels that had been obtained from the plant.

F17 Jre 3.2-1 shows the H-3 levels at the Clemson site and drinking water sites. Sample analysis results from location 065 raw water are I not included in the tables summarizing drinkirig water results.

I K-40 was observed in drinking water samples in addition to the Total Beta and tritium radioactivity listed in the tables.

I I

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I Gamma spectroscopy was performed on 26 monthly surface water samples.

These samples were composited to form 10 quarterly samples for Tritium analysis.

I Table 3.3-1 summarizes the radionuclides that were detected. The I

indicator locatien is near the liquid effluent release point and differences between the indicator and control samples are expected.

Cott.parison of 1990 and 1991 highest mean annual concentrations show there is no significant change in concentrations. For the majority of the radionuclides, the concentrations are low and the number of samples with detectable activity is small (with the exception of Tritium). Observed surface water concentrations were below any reporting levels.

1 Visual inspection of tabular data covering the preoperational period through 1991 did not reveal any significant increasing trendo.

Linear regression analysis was applied to the highest indicator location mean for Tritium from the preoperational period through 1991, and for the past thirteen years for the remaining radionuclides. The data used and the results are in Table 3.3-2.

Co-58, co-60, Ag-110m, and Sb-125 had positive correlation coefficients, which indicates an increasing trend. However, none of the radionuclides show a high probability of a trend. Only Co-58, Ag-110m and H-3 were detected in 1991 samples.

K-40 was observed in surface water samples in addition to the radionuclides listed in the tables, i

I 3

3...ge 31 5

.I TABLE 3.3-1 i SURFACE WATER HEAN ANNUAL CONCEliTRATIONS (pCi/ liter) 1990 1991 1991 Isotope Highest Mean Highest % Reporting Control % Reporting l Hean Level Mean Level 5 -

Co-58 127E0(1/13) 5.37E0(1/13) 0.54% ---(0/13) ---

1 Ag-110m 3.04E0(1/13) 7.04E0(1/13) NS ---(0/13) ---

H-3 1.03E4(5/5) 5.76E3(4/5) 28.9%* ---(0/5) ---

Value in parenthesis is the fraction of detectable measurements. NS = none specified by Selecteed Licensee Commitments.

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I 3.4 MILK Gamma spectroscopy and low level iodine analysis was performed on 78 milk samples collected in 1991. Table 3.4-1 summarizes the radionuclides that were detected. Cs-137 was the only radionuclide (Sserved in indicator location milk samples (besides naturally occurring ones). Although the detection frequency for Cs-137 increased in 1991, the mean concentration decreased. Cs-137 had a poor probability of an increasing trend. No concentrations above reporting levels were identified.

TABLE 3.4-1 HILM MEAN ANNUAL CONCENTRATIONS (pCi/ liter) 1990 1991 1991 Isotope Highest Mean Highest % Reporting Control % Reporting Mean Level Mean Level Cs-137 6.4E0(1/26) 4.99EO(4/26) 7.13% ~-(0/26) ---

I Value in parenthesis is the fraction of detectable meast.rements.

Visus 1 inspections of tabular data taken from pa evious environmer.tal report summaries and the 1991 summary did not reveal any significant increasing trends. Linear regression analysis data and results are found in Table 3.4-0. None of the radionuclides had a high probability of a positive trend. Trend analysis for I-131, which is the main contributor to doses calculated from gaseous particulate and iodine effluent data, indicates with moderate probability that iodine concentrations are decreasing.

K-40 was observed in milk samples in addition to the radionuclides listed in the tables.

I 3-Page 35

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3.5 BROADLEAT VECETATION I Gamma spectroscopy was performed on 39 broadleaf vegetation sarples during 1991. Cs-137 was detected one time and was the only radionuclida, other than those occurring naturally, that was observed in indicator location samples. Cs-137 was also detected in control location samples and at a higher frequency. The sample results are summarized in Table 3.5-1. Concentrations that were detected are below reporting levels.

I TABLE 3.5-1 BROADLEAF VEGETATIO!!

HEM 1 AfDIUAL C0!iCEllTRATIO!45 (pci/kg, wet) 1990 1991 1991 1sotope Highest Mean Highest % Reporting Control % Reporting 8 Mean Level Mean Level Cs-137 7.73E2(1/13) 2.22El(1/13) 1.11% 1.45E2(7/13) 7.3%

I Valls in parenGes1Ns the f raction of detectable measurements.

i

~

I visual inspection of tabular data taken from previous environmental repert summaries and the 1991 summary did not reveal any increasing trends. Linear regression analysis data and results are given in Table 3.5-2. Only one radionuclide. Cs-137. had a probability of an increasing trend and it was a moderate probability.

I K-40 and Be-7 were observed in broadleaf vegetation samples in addition to those listed in the table.

E 5

'I 3-Page 37 I

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I 3.6 SH:RELI!(d SEDIMENT 2

Gamma spectroscopy was performed on twelve sedirnent samples.

Selected Licensee Conwittnents equires samples to be collected from two locations semiannually. Three locations are sampled quarterly in order to better assess the concentrations being observed in sediment samples. The results of the additional samples are included in the shor eline sedin'ent tables and graphs.

Table 3.6-1 summarizes the radionuclides that were detected. The l')90 a*d 1991 highest annual rneans are very similar in the radionucliaer detected and their concentrations.

Visual inspection of tabular data from previous environmental report summaries and the 1991 summary indicated some increases in shoreline sediment concentrations. Linear regression analysis data and results are found in Table 3.6-2. Moderate positive trends resulted for Hn-54, Co-60, Cs-137, Ag-110m, and Sb-125.

Graphs of individual sample results can be found in Figures 3.6-1 through 3.6-3. The period plotted begins when shoreline aediment sampling was initiated in 1984. Cs-137, co-60, Ag-110m, and Sb-125 were graphed because of the moderate probability of increasing trend and because they are major dose contributors in effluent calculations. The graphs show an increasing trend is possible, but fluctuations in the results are large. The 1991 doses from shoreline sediments vere low and well within any dose limits.

E-40 and Be-7 were observed in shoreline sediment samples in addition g to the radionuclides listed in the tables.

IB I 3-Page 39 8

1

I TABLE 3.6-1 I Sil0 RELINE SED 1HENT HEAN ANNUAL CONCENTRATIONS (pCi/kg, dry) ti 1990 1991 1991 Isotope Highest Hean Highest % Reporting Control % Reporting Hean Level Mean Level Hn-54 3.40El(3/4) 3.26El(1/4) NS ---(0/4)---

Co-58 8.00El(2/4) 5.60El(1/4) NS ---(0/4)---

Co-60 2.59E2(2/4) 8.57El(1/4) NS ---(0/4)---

Cs-134 4.50El(2/4) 6.91El(1/4) NS ---(0/4)---

Cs-137 5.36E2(3/4) 1.24E2(3/4) NS ---(0/4)---

Ag-110m 1.71E2(2/4) 1.10E2(1/4) NS ---(0/4)---

Sb-125 9.00El(1/4) 1.78E2(1/4) NS ---(0/4)---

valve in parenthesis is the fraction of detectable measurements. NS = none

specified by Selected Licensee Commitments.

8 I

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l1 3.7 FISH Gamma spectroscopy was performed on 12 fish samples. Table 3.7 1 I summarizes the radionuclides that were detected. Comparison of data to previous years does not indicate any significant increases in concentrations. There were no 1991 fish sample resul' ., deiermined to have concentrations of radionuclides that exceeded reporting levels.

I TABLE 3.7-1 FISil MEAN ANNUAL CONCENTRATIONS (pC1/kg, wet) 1990 1991 1991 Isotope Highest Mean Highest % Reporting Control tReporting Mean Level Mean ieve1 Co-58 1.50El(2/4) 4.59El(1/4) 0.15% ---(0/4)---

Cs-134 4.80El(3/4) 1.25E2(2/4) 12.5% ---(0/4)---

Cs-137 1.19E2(4/4) 1.94E2(4/4) 9.7% 1.47El(2/4) 0.74%

Value in parenthesis is the fraction of detectable measurements.

Visual inspection of tabular data from previous environmental report summaries and the 1991 summary did not reveal any increasing trends.

Linear regression analysis was applied to radionuclides routinely evaluated for in fish samples. Table 3.7-2 lists the data used.

None of the radionuclides indicated a high probability of an increasing trend. Cs-134, Cs-137, and Co-58 results indicated moderate probabilities of an increasing trends. One factor affecting the trend analysis is a change in sampling locations. In 1984, a second downstream fish location was added. Location 063 is closer to the liquid effluent discharge point and has been the highest mean indicator since it was added.

I 3-Page 45 l5 I

I Grephs showing Cesium levels in both bass ar.J 1stfish were prepared since Cs-134 and Cs-137 are major effluent dose contributors through f the fish pathway. Figures 3.7-1 and 3.7-2 contain the graphs displaying individus1 sample results. Based on these graphs, the levels at the two downstream locations do not apt to be !

increasing.

K-40 was observed in fish samples in addition to the radionuclides linted in the tables.

I I

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I 3-Page 46

I

mae M mm ae M M M M m M M M . W .M M TAllLE 3 7-2 peseIor2 FISil TREND ANALYSIS OF MEAN ANNUAL CONCENTRAllONS CONCENTRATION (gGkg) i I I i i i l 1 1 1 1 l YEAR I Ma-54 e Co-58 i Fe-59 i Co40 l Zs45 i Nb-95 7r.95 1 1 1 131 1 Ba12-140 I I I INDICATOR I INDICATOR I INDICATOR l !NDICATOR I INDICATOR I INDICATOR I INDICATOR.I INDICATOR ' INICATOR 1 1 1 I i _I I i i l i i i l i 1 I 1 1 I L i i 1979 1 0.00E+00 l 1.91E+00 1 2.RIE+00 1 136E+01 1 0.00E+00 1 9 63Ed10 1 9 63EdM i- L72Fd)1 1 0 0nEd>0 l l 1 1 I i i i i i ! l l 1980 l 331E41 1 1.45E+01 1 0. ore +00 1 1.90E+01 1 0.00E +00 1 7.78E+00 1 7.78EdM i 1.2Vl +01 1 1.ASEMM 1 i i i i l i ! l I I I l IMI i 0.Or>E +00 l 2.25E+01 1 0.00E+00 1 1.49E+Cl i 1.93E*01 1 6.97E +00 1 0 0r4+00 1 2.54Ed)! ! I .44Ed)0 l l l 1 ! ! ! I i ! i i l 1%2 1 0.00E +00 l 9.83E41 ! 1.29E+01 1 8.03Ed)0 1 0 00E+00 1 1.69E+00 1 0 00E+00 1 166Ed)1 1 1.17E dil i I I I I I i 1 1 1 I I l 1981 1 0 00E+00 1 335F+01 1 7.ESE-of I 4.53E d>0 ; 0.00E+<M i 0.00E+03 1 7.01EWO 1 1.49Edn 1 5.73D01 l 1 I i 1 I I I I I i I l 1984 1 436E+00 1 1.2tE+0? I 230E+0i ! 6.23EM)1 1 427E+00 l 1.03E+01 1 7.76E+00 1 3.56F +01 1 0 00E+00 1 1 1 ; I I I I I I I I i 1985 1 2 SIE+00 1 1.62E+01 1 1.11E+01 1 1.10E+01 1 OD I+00 1 1.01E+01 1 1.92E+3) I l.41r d>l 1 316E-01 1 1 I i i i I I I I I I i 19R6 1 0.00E +00 l 9.56E+0i 1 0.00F 40 l 2.59E+0! l 0.00E+00 ! 4 CE@ l 0.00Ed30 I O m F+00 1 4.75E*M i i i i i ! I i l I I i 1 1987 1 2.20E +01 1 1.63E+02 1 0 00E+00 1 630E+0i 1 0 00E+00 i U.00fXm i 0 0r?F+00 1 0.cor+oo j 0000 0o g i l 1 I i 1 1 I I I I

! 1988 1 0 00E+00 1 960E+01 1 00uE+00 1 0 00E+00 i OVf +00 ! CNEdn 1 0 00E+00 1 0 0"E+00 1 0.00E d)0 l l I I i l I 1 i i i i i 1999 1 0.00E +00 1 430E+01 1 0.00E+00 l 1.50L+0! 1 0. ore +00 1 0 00E+00 1 0 00Ed#1 1 O M E+00 1 0 00Edn i l l 1 l i i l l I I I i 1990 1 0 0ff +00 l 130E+01 1 0.00E+00 1 0.00E+00 1 OCCE+00 I C D K d)0 1 0 00E+00 t CVX ) i OnoE+00 1 1 1 1 1 I I I I I I I i 1991 1 0.OnE+00 1 439E+01 1 0 00E+00 1 0.00E+00 1 000E+00 1 0.00Emo 1 0 00E+00 1 0.00E +00 l 0 VK+00 l l Correlatine i i l l l 1 1 1 1 I l Coefficie v l 134E-01 1 3.630-01 l -237E41 1 -131E41 1 -324E41 1 -3.19E41 1 4 60E-01 1 -6 46E of 1 -2.17E.01 I l i l '

l I l . . . _ . ! ! ._ 1_ i l Tmnd i I I I l l l t 1 !

! Prnhatahry 1 Pwr i Moderate j Poor ! Poor i Moderate 1 Moderate i Materate i M.derste i Pme 1 i i I_ i i i ! I _i ! l

! Tn= l l l 1 I I I 1 I I I Trend ] lacreasing I leerensing i Decreasing i Decreasing i Decmsmg 1 Daventing i Decresneg i Mreasing i Dacreaseg i i i l I i i l I ! ! I Note: All neganvc uneam values were replaced with reros' f<x cakulatmaall upmes.

3-Page 47

g g g: $ $ E IE' E E E E E N E E' E E '

TAf1LE 3.7-2 . page 2 of 2 FISil TREND ANALYSIS OF MEAN ANNUAL CONCENTRAllONS 1 I .I l l YEAR l Cs-!)4 l C&l17 l ,

1 I INDICATOR l INDICATOR 1 l - i i i l' I .

-l 8 -

! 1969 1 0.00E+00 l Il9E42 ,

l 1970 1 0&>F*00 l 1.66E+02 I l 1971 l ODT+00 1 1.00EW)2 l-1 7 l . 0. ore +00 ? 1.dlE+02 l i 1973 l OM)E*W) l 1.89E4)2 l l 1974 1 0 00E410 l 1.It4E +01 l l 1975 1 216E+0i ! 1.87E42 l l 1976 l ?l3E+01 l 1.66E+02 l l 1977 l 1.17E+02 l 322E+02 l l 1978 1 2.76E+02 1 6.00E +02 l l 1979 1 7.56E+01 1 4 09F+02 l l 19R0 1 8.14E+0! l 3.93E +02 l l 1991 l 9.19E+01 1 3,3AE+02 l l 1982 l I.l*E+02 l 2.04E +02 l l 1933 1 Il4Ed)2 l 3ME+02 l l 1934 [ 3.79E+02 l 1.04E+03 1 l 1985 l R.95E+0i l 2.93E+02 l l 1986 l 2.42E+02 1 7.36E+02 l l 1987 l 9.80E+01 l 3.93Ew12 I l 1988 1 7.20E+01 l 2 N)E+02 l l 1989 ) 8 60E+01 1 3.36Ed)2 1

-l 1990 l 4 80E+01 l 1.19E+02 l l 1991 l Il5E+02 l 1.94E+02 l l Com4a: ion ] l l l Coefficient l 4.72E41 1 3 30E41 l l 1 i i I Trend 1 I l l PriteN!*y l Moder.te i Moderate l

! I i _l i Type l l l l Treed I lacreasreg l' Increasing t i I i 1 3-Page 48

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v I 3.8 DIRECT GAMMA RADIATION I Thermoluminescent Dosimeter (TLD) measurements for direct gamma radiation were made each quarter at forty locations. Many of the TLDs are placed at the same site used by the NRC in their TLD Direct Radiation Monitoring Network. One hundred and fifty-five of the TLDs were recovered and processed. Tne highest annual mean for an indicator location was 26 millirem per quarter. This TLD was located at indicator location 059, Tamassee DAR School. The annual mean for the control location was 22 millirem per quarter. A graph showing the average quarterly TLD doserate is found in Figure 3.8-1 I The test statistic, or t-test, was used to compare the TLD measurements taken during preoperation to those taken during 1991.

In this case, the ratios of results from the 1-2 mile radius and the 4-5 mile radius were compared from one year to the next. Since the inner ring of TLD's are most likely to be affected by plant operations, the hypothesis was used that a significant change in the ratio from one year to another would be indicative of an environmental affect, or at least some phenomena requiring further investigation. A statistically significant change in ratio was determined by comparing the calculated t-value to expected values of the t-statistic based on the number of measurements and the desired accuracy of the results.

The value of t-statistic was calculated by comparing preoperational results to 1991. As shown in Table 3.8-1 the t-value was -1.781.

This corepared well to the expected value of the t-statistic, -2.030, based on 35 measurements and 95% confidence in the result.

Therefore, it can be concluded that the doserates measured around Oconee during 1991 do not differ significantly with those existing during preoperation ( Table 3.8-2 ).

E 3-Page 51 B

. . _ _ _. -.= -- - - - - .

1 I -

Table 3.0-1 Comparison of Inner Ring / Outer Ring TLD results 1991 (mR/qtr) Preop (mR/qtr)

Inner Ring 15.29 28.27 Outer Ring 16.24 30.98 Ratio . 0.94 0.91 I t-value -1.781 t-statistic -2.030 I-I I

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I 3-Page 52

c-M M M M M M M M M M M M M M M M M M M TABLE 3.8-2 DmECT RADIATION AS MEASURED BY TLDS MEAN ANNUAL DOSE RATES DOSE RATE MREMOTR l YEAR I MREMOTR l l l INDICATOR l 1 1 I I l l l 1970 1 3 94E+01 1 1 1971 1 3 50E+01 I l 1972 1 35,oE+01 i l 1973 l 3 07E+01 1 l 1974 l 2.8SE+01 l l 1975 1 318E+0 t l l 1976 1 3 00E+01 l l 1977 1 4 82E+01 l l 1978 1 31 t E+01 l 1 1979 l 329E+01 l

! 1980 l 3.33E41 l l 1981 l 3 72E41 l l 1982 1 4 97E+01 I

[ 1983 l 4 64E+01 l l 1984 l 3 68E+01 l l 1985 1 4.7 t E+01 1 1 19e6 1 4.7 t E+01 l l 1987 l 318E+01 l l 1988 1 3 35E+01 l f l 1989 1 2 4eE+01 l l l 1990 ( 2.80E+01 l l 1991 l 2 60E+01 l 1 i i I I i l I i i I 3-Page 53

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The Land Use Census was conducted during August in 1991. The census results are contained in Table 3.9-1. Milk animals vece identified

'.n sectors other than the one where milk samples were being collected, however the milk was not being used for human ecneumption.

No changes to the program were made during 1991.

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I 3-Page 55 I

TABLE 3.9-1 LAND USE CENSUS DATA SHEET Dates (s) Performed: 8-7-91 throuah 8-13-91 Sector Distance (Miles) Sector Distance (Miles)

I Hearest Residence 3.5 Nearest Residence 1.75 Nearest Mest Animal Nearest Meat Animal I

N S Nearest Cow -

Nearest Cow -

Nearest Goat -

Nearest Residence 2.25 Nearest Residence 1.0 Nearest Heat Animal -

Nearest Heat Animal -

NNE SSW I Nearest Cow Nearest Goat 3.25*

Nearest Cow Nearest Goat Nearest Residence 1.25 Nearest Residence 1.5 Nearest Heat Animal -

Nearest Heat Animal -

NE SW Nearest Cow 3.5* Hearest Cow -

! Nearest Goat 3.5* Nearest Goat -

Nearest Residence 1.0 Nearest Residence 1.5 ~

I ENE Nearest Heat Animal Nearest Cow 3.5 3.5*

WSW Hearest Heat Animal Nearest Cow 2.5 2.5*

Nearest Goat -

Nearest Residence 1.0 Nearest Residence 1.75 Nearest Heat Animal 2.75 " Nearest Meat Animal -

I E Nearest Cow Nearest Goat 2.75*

W Nearest Cow Nearest Goat Nearest Residence 1.0 Nearest Residence 1.75 Hearest Heat Animal 2.25 Hearest Meat Animal 3.5 ESE WNW L3 Nearest Cow 2.25* Nearest Cow 4.5 g Nearest Goat 4.75* Nearest Goat -

I SE Nearest Residence Nearest Meat Animal Nearest Cow 1.75 4.75 4.75*

NW Nearest Residence Nearest Heat Animal Nearest Cow 1.5 Nearest Goat -

Nearest Goat -

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I 3-Page 56 I

I SECTION 4.

EVALUATION OF DOSE FROM ENVIRONMENTAL HEASUREMENTS VERSUS ESTIMATED DOSE TROM RELEAST.S 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimated for measured cor.centrations of radionuclides in direct pathways to man using NRC Regulatory Guida 1.109 methodology and factors. NUREG/CR-1276 Appendix C dose factors were used when a radionuclide was not listed in Regulatory Guide 1.109. A dose factor of zero was used when the Guides listed "NO DATA" for a factor. The highest annual mean values for each sample type and radionuclide as I given in Section 3 and Appendix B were used after the background concentrations, as measured at the control location, had been subtracted. The high mean and control mean are conservatively based

.I on detectable measurements only. The maximum exposed individual j doses are summarized in Table 4.1. The individual population and l pathway dose calculations are contained in Table 4.2.

4.2 ESTIMATED DOSE FROM RELEASES Doses were estimated for released concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology. .

W The doses were calculated using GASPAR and LADTAP computer programs.

I The maximum exposed individual doses are summarized in Table 4.1.

4.3 COMPARISON OF DOSES The environmental and release data doses given in Table 4.1 agree reasonably well. The similarity of the doses indicate that the radiaactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposura pathways.

4-Page 57 I

Upon further review of the 1990 and 1991 doses from environmental measurement and estimated doses from ingestion, it was noted that in 1991 the environmental doses were more frequently the slightly higher of the two values. After examining the individual pathway doses it was determined that this difference in 1991 was due to the fish pathway. Out of all locations and all the fish sampled, the bottom feeder.(catfish) at location 063 would be expected to have the higher activity. (This was noted in section 3.7). This is the case in 1991 with location 063 being the fish high mean indicator location. It is recognized that the Co-58, Cs-134, and Cs-137 radionuclides in fish demonstrate a moderate increasing trend by linear regression ane. lysis (Table 3.7-2). These trends are also supported by the trends noted for shoreline st.diment. In Table 4.1, the doses from environmental measurements are higher than the estimated effluent doses when fish is the critical pathway. Considering the above noted trends, the sample type and the location where the sample was collected, this was an expected result and it will continue to be closely monitored.

I Drinking vater, shoreline sediment, and fish sample results were summed to determine the maximum total doses for all sampled liquid release pathways. Likewise, airborne radioiodine, airborne I particulate, milk, and broadleaf vegetation sample results were summed to determine the maximum total doses for all sampled gaseous release pathways.

I The doses calculated do not exceed

2 40 CFR 190 annual dose commitment limits for members of the public.

I I

I B

4-Page 58 I

I

( TABLE 4.1 page 1 of 2 1991 ENVIRONMENTAL AND EFFLUENT DOSES Liould Release Pathway Organ Environmental Critical Critical Pathway Maximum er Effluent Age Dose Data (mrem /yr)

Skin Environ. Teen Shoreline sediment 3.70E-3 Skin Effluent Teen Shoreline Sediment 9.68E-3 Bone Environ. Child Fish 6.08E-1 Bone Effluent Child Fish 3.39E-1 i Liver Liver Environ.

Effluent Teen Teen Fish Fish 8.33E-1 4.74E-1 1 T. Body Environ. Adult Fish 6.01E-1 T. Body Effluent Adult Fish 3.57E-1 Thyroid Environ. Child Drinking 5.78E-2 Thyroid Effluent Infant Drinking 2.02E-1 I Kidney Environ. Teen Fish 2.80E-1 Kidney Effluent Child Fish 1.96E-1 Lung Environ. Teen 71sh 1.13E-1 Lung Effluent Child Drinking 1.16E-1 GI-LLI Environ. Child Drinking 5.78E-2 GI-LLI Effluent Adult Fish 2.33E-1 I

I 5 4-Page 59

l-TABLE 4.1 (cont.) page 2 of 2 1991 ENVIRONMENTAL AND EFFLUENT DOSES Gaseous Release Pathway Roble Gas Efoosure Organ Environmental Critical Critical Pathway Maximum or Effluent Age Dose B.i Data (mrem /yr)

Skin Environ. - -

Noble Gas Not Sampled Skin Effluent N/A Noble Gas Exposure 4.29E-2 _

~

I T. Body Environ. - -

Noble Gas Not Sampled T. Body Effluent N/A Noble Gas Exposure 1.58E-2 Iodine. Particulate. and Tritium Exoolurg Organ Environmental Critical Critical Pathway Maximum or Effluent Age Dose Data (mrem /yr)

Bone Environ. Infant Milk 8.60E-1 '

Liver Environ. Infant Milk 1.01E0 -

T. Body Environ. Adult Milk 1.10E-1 g Thyroid Environ. - -

0.00E0 B Thyroid Effluent Infant Goat Milk 2.26E-1 Kidney Environ. Infant Milk 2.70E-1 Lung Environ. -Infant Milk 1.09E-1 GI-LLI Environ. Teen Milk 4.23E-3 I 4-Page 60 1

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inhalation Ibse Factor fecation in (mrem per pCiinhaled) D st/ Air ihr (inrem'yr)

Radionucthic lboe Iiser T. IbJy Thymid Kidacy Iung GI-LLI Directics (pCUm ) Ibne Iiwr T. IWy nynsd KAney Lung GI-LLI Ma-54 NO DA TA 4.95 E M 7.R7E47 NO DATA 1.23EJE I .75 E-04 9 67E4 ALL OmEdM 0.00Edw) 0 00Eufo 0#)EnW) ' OM E+m) O frE 44 0 00E+00 OmEdW)

Particulate Co-58 NO DATA L98E4)7 2.59F47 NO DATA NO DATA 1.16E44 13)E45 ALL 01N>Edn OJWJEd)0 0.00F+a) 0.00E +(n 0 0nE+00 0.00F+00 OJhE+00 o fwfE+4w) i l

Paniculate Fe-59 1.47E 45 3.47E46 132E46 NO DATA NO DATA I .27E-04 235E45 ALL 0 000+00 OIM>E dw) OmEdo 0 00E+m 0 00E+0') 0,00E+00 0.00E '00

< OI)cEdn Pankulate Co.60 NO DATA 1.44E44 1.85E 4 NO DATA NO DATA 7.46E44 3.56E-05 ALL 0.00E+00 03+ Mw) 0 00EH/) 0.00E MM 0 0f'E+9J 0 00Ed)n of>)Ed)0 010F+(n Particulate Zn-65 4 05Edw 1.29F-05 5.82EM NO DA TA 8 62E4 i F8E44 6LREM All 000F#4 OMEdn 0#)EWn OME +00 0 00E+00 OfWE +00 o.00E+00 Ot#fE+00 Particulate l Nb 95 1.76E4A 9.77E47 526E-07 NO DATA 9 67E47 631E4)$ 130E45 All 000E+00 0 000 +00 OtCEMM 0 00E+4)0 O ME

30 0 00EdM G#t+tM 0 00E+(0 Particulate 7r.95 134F45 436E46 2.91EE NO DAT A 6.77E46 2.21E-04 1.88E-OS ALL 0.OJE+00 0 00E+00 0 00E+00 0#>Evo 0#)F +'O O uC+00 O m E+00 OME +00 Particulme I-111 3.15 E46 4 47E4% 256E4m 1.49F 03 7.66EM NO DATA 7 8tSE 07 ALL 0 00E d)0 03)oE+00 0 00Fuio OMEdo 000E+W O!WJE +'M OF'E+00 0&>EdM Partrculate I-1 )I 315E 06 4 47EM 2.56E4M 1.49E41 7.66E45 NO DATA 7 85E 07 All OfoFH;0 OfkJEdm 000E+00 0 ')oEd)0 OME +00 0. toe d)f) ()/*)Edn OrnEde Charcoal i Cs-134 4 66E45 IJ)6E-04 9.10E-05 NO DATA 3.5cE45 122E-05 130E46 ALL OMEd)0 OME*W 0 00E+04 0 00E+00 0 00E 40 OroE+00 0 000dM 0 00Evo l Paniculate Cs-117 5.9sE-05 7.76E45 535E45 NO D ATA 2.78E45 9.40E-06 105EM ALL o mE+00 OD>E+00 0 0nI +00 0mEdo 0.00E +00 0.00E+N 0#>E +m 0.00E +00 Particulme lla!.a-140 4 RRE 06 2.17E 08 321E47 NO DATA 2.09E49 1.59E-04 5.73E-05 AI L 0 00Edo O tW5E+00 O tW)E+oo OmE+u) 0 09E uw) OtWF+00 O u)EdM 0 00Ed)f)

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4-Page 61

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Dose from Inhalation Pathway for 1991 Data Maximum Eyssed Teenager Breathing rate = 8000 m3 'yr Ilighest Ann. Mese Teenager C inc.

Inhalation Dose f actor Incation in (mrem per pCi inhaled) thsv Air Ibse (mrem yr)

Radionuciale Done Liver T. thly 1hymid Kidacy Imag GI-LIJ Direction (pC0m ) Ibne Liver T. Ihly Thyn,id Kidney Luns Gi-Lil Ma-54 NO DATA 639E4)6 1.05E 4 NO DATA 1.59E 4 2.4RE-04 835F 4 ALL 6.00E+00 0.00E+00 0.00E *) OurE+00 0.00E dX) 0.00E+00 O N>E+00 0.00EWM Particulate Co-58 NO DATA 239E-07 3.47E47 NO DATA NO DATA 1.68E-04 1.19F-05 ALL 0.00E+00 OJmE+00 0.00Ed)0 OJUEdm 0 00E+00 0 00Ed)0 0 00F+(4 0.00E dn l

Particulate l'e-59 1.99E-06 4 62E4 1.79E 4 NO DATA NO DATA 1.9 tE44 223E-05 ALL 0.00E+00 0 00E+00 0.00Enn 0.00E+00 OW +00 OfXfMW f).00E+00 r,.00E+00 j Particulate Co-60 NO DATA I.R9E 4 2.4*E4 NO DATA NO DATA 1.09E43 3.24E4 ALL 0 00E+00 0 00E* OJoE+00 O R E d)0 0 0r$+00 0.or$40 0.00E +00 0 00E+00 PartictJane 2n-65 4.82E4 1.67E-05 7.80E4 NO DATA 1.08E-05 1.55E44 5 83E4 alt. 0.00EMio Owf+00 OMEd)0 00rW+#) 0 00Edm 0 00Edo 0.00E+00 OMEdo i Particulate l Nh45 232E-06 1.29EJ)6 7.03E-07 NO DATA 1.25E-06 039E-05 1.2 t E-05 ALL OfiOE+00 ON#+00 ODEMrJ 0.00Edn ODEMO 0 0f +00 ODidW) 0.00E +&)

Particulate Zr 95 1.82E-05 5.73E 06 3.94E4 NO DATA 8.42E 4 336E44 1.86E45 AIL OME@ 0.0rN+00 0 00E+00 0 0fE+00 0.00E un Ov$4Y) 0 0r)E+4) 0.Orguy)

Particulare 1 131 4.43E4 6.14E46 330F-06 1.83E-03 1.05 E-05 NO DATA RIIE47 /LL 0 00E+00 000E+00 0 0E+00 cmEM)0 OZDFKe OW&dA 0 0rk+00 ODE +00 Par.iculare I-131 4.43E 06 6.14E4 330E4 I ale-03 1.05E-05 NO DATA 8.llE47 AIL 0 00E+00 0 00E +09 0 0rS+00 0.06E+00 0 00E +00 o ry Edy) O rygdn Ogguy)

Chwcoal Cs-134 6.28E-05 1.41E44 6 p E-05 NO DATA 4 60E-05 1.83E-05 1.22E 4 AIL 0.00E+00 0.00E d10 O thEdo OJWE+00 0 0r$+00 0.00E +(M OD f+00 OmEdn Particulare Cs-137 8 38F-05 1.06E44 3.89E.05 NO DATA 3.80E45 1.5tE-05 1.06E 4 ALL 0 09Edy) OJ)oE+00 0 00E+00 D N E+00 0.00E+00 r) 0fE+00 0.orK +00 0 00Ed t Particulase Bab 140 6 84E4 2.95E-04 4.40E-07 NO DATA 2.85E46 2.54E-04 6 09E 05 ALL 0.09E+00 OmFd)0 OME+00 0#Kde O rwE+00 0 00Edio 0#E+00 0 0nE+00 l

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Tota! Ibse (mreriyr) = 0 00E +00 0 0rE+4) 0.00E+00 O M E+00 oaf +O) 0.00E44 0 00E+00 1

4-Page 62

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Dose fmm Inhalation Patowsy for 1991 Data Maximum Expwd Infant Breathii g rete = l400 m39 liighest Ann. Mean Infnet Conc ,

Inhalation Dose Factor Location in (mrem per pCi ir.hsled) Dist! Air Dose (mreWyr)

Rulionuclide Done Iiver T. Ikxfy Byrcid - Kidney Lung GI-LLI Direction '(A m) Dane Liver T. Ikxty Hym'd . Kidsey Lang GI-Lil M3-54 NO DATA 1.81E-05 3.56E4 ~ NO DAT A 3.56En 7.14E-C4 5 04E4 ALL OfxE+00 0 0fE+00 - O fnE4W) afiOE+00 0.00E +00 0 00E +00 0.00Ed)0 0.044m Partwulee Co-53 . NO DATA 8.71E-07 130E416 NO DATA NO DATA 5.55E44 7.95E4 ALL 0.00F+00 0#E+00 0 0nE+00 0.00F+00 01:0E +W Of)0E+00 0.00F dn kbOE*Jo Parncula:e Fe-59 9.60E-06 1.68E-05 6.77E4 NO DATA NO DATA 7.25 E-04 f.77E45 ALL' O.00E+00 0 0'E+09 0 00Ed>0 O!ME+00 0.toEdC . OmE+00 0.00EHA ODE 40 Pusisulare

.Cc40 NC DATA 5.73E46 8.4 t E 06 NO DATA NO DATA 3 22E-03 228E-05 ALL Of>0Ed10 0#E+00 0 00E+00 0.00F +00 0<30E90 OVIE+00 O!nE+00 ' 0 00E+00 Particu'ee In45 13*E-05 4A7E-05 2.22E-05 NO DATA 232E 05 4.62E-04 3.67E-05 ALL 0.00Ed)0 Out#9 0.00E dy) 0 00E+00 0.00Edo onE+0S OwFd4 ODEW Particulate h%95 1.12E-05 4.59E4 2.70E4 NO DATA 337E46 3A2E-04 9.05E4 AIL 0.0tE d)0 09E d>0 0 00E+00 0 00Edo OD:E+00 O fy$ +00 0 00E t 00 0.00Edo Particulae Zr-95 8.24E-05 1.90E-05 1.45E-05 NO DATA 222E-05 125E-03 1.55E45 ALL O tti+00 OfnE+00 0 00Edo 0.00F +00 O fwE+00 OAE+t4 0#Edo OMEdwi Pasticulae I-131 2.7 t E45 ll7E.05 1.40E-05 1.06E42 3.70E-05 NO DATA 7.56E47 ALL OD)E+00 0. ore +no 0 00E49 0 000+00 00rK +00 ODW4M ODAdo O t#dM Pr.rticulate I-131 2.71E-05 317E45 1.40E 05 LO6E42 3.70E-05 NO DATA 7.56E-07 ALL 0 00E+0n ODEMM OhK+00 0.00E+00 0.00i'd4 CD)Ed)0 0 00E+00 00:540 Charcool Cs 134 2.81E-04 5,02E-04 532E-05 NO DATA 136E44 5.69E-05 9.53E-07 All 0.00E*00 0 9 5 +0n 0.00E+0n 0.00E+00 0 00E +00 0.fME 4M OfiOE+(n O W +0e Particulate Cs-137 3 92E44 437E-04 3.25E-05 NO DATA 1.23E-04 ' 5.09E-05 9.53E-07 ALL 000Ee n O D E d)0 0.00E +00 OW)E+00 0 00Edh 0.t. 40 OVE+00 0.0eEdM Particuwe Balm-140 4.09E-05 1.43E-07 2.07E-06 NO DATA 9.59E-09 1.14E-03 6.06E-05 AIL O M E+00 0 0fE+00 ONEdio Osm+00 OgE+et O y>E+00 Oum+0c 03WiE +00 Particulate Total Dose (mreriyr) = 0 00E+00 0.00E+00 0#E+00 0 00E+00 0.00E+00 0 00E+00 ot0E+00 4-Page 64

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Ibse from Dnnkinx Warer Pathway for 1901 Data Manimum Fy.ned Cluid

$10 k g>yr

(' Us se (intake rste) =

Ifighew Ann. Mees Chdd Conc. ,

Ingestion Dose Factor loc ation in (mrem per TCi ingemed) Dise Water Dase (trwem'yr) liver Kkiney lung GI-LLI threction (pCib) ibne liver T. Ibdy hymid Kidney Img Gl.LU Radsonuchte Ibne T. llody B)Wd 3.00E46 NO DATA 8.98E46 AIL 0.00EMM 0 00E4m 0.00Eun O AW +00 OroE4x) 0.00Edo ONEMC 0.00E4*)

Ma-54 NO DATA ?.J7E-05 2.85E4M NO DATA Co-58 NO DA1 A 1.80E46 5 5]E46 NO DATA NO DAT A NO DATA f 05E-05 AIL 000F+00 OMF +<M 0.00Edw) 0.00Fdo o w E+00 O rmFeio OfoEdo 0. ore +00 NO DATA NO D ATA 7.74E 06 2.7EE45 AIL OR*E+00 OMEdio 0.ortE +00 0.00E+00 UEEwn 0. ore 410 ONE4M OfME +00 Fe-59 1.h5E-05 2.67E45 1.33E-05 l

1 CM3 NO DATA 5.29E46 1.56E 05 NO DATA NO DATA NO DATA 2.93EJ)5 ALL 0 00E dio 0.00EH10 OfoE+00 OmEuw OME*) ODEun OMEvn 0.00Een 3.55E45 2.27E-05 NO DATA 2.30E-05 NO DATA 6.4 t EJ6 ALL O M E+00 0 00E+00 0.00E+00 OD E+00 0 00Ed)0 0#Ede omren 0#EdM Zn45 137E-05 8.23E49 NO DATA 1.62E45 ALL 0.00E+00 O M E d)0 0f100 +00 OMEW1 00rf uM 01:0Ed>0 0 00F+0'3 0 00Edo Nb-95 22sv48 8 76E-09 d26E-09 NO DATA I

2.55E4)3 2 27E-08 NO DATA 165E48 NO DATA 2.66E-05 ALL 0.00E+00 0 00E+M 0 00F+00 0.00L'00 0.4(4n ONW+00 OMEve ofEEds ;

Zs 95 1.16F-07 I 5.72E 43 2.84E45 NO DATA 1.54E fM ALL 0&E +00 0.00E M)0 o fxE +(W) 0 00E-00 Ovf+00 0 00Eun O NE+00 0 0rEvM I-131 1.72F-05 1.73E45 0 M3E-06 l

8.10E-05 NO DATA 1.19E-04 4.2753 05 2.07EJ36 All 000E+00 OAIDFdx) 0 00E 410 0.00E *00 0 00EMO Oh>EdM 0#1Fdn OVE +00 Cs-134 234E-04 3.84E 04 162F-05 NO DATA 102E44 3.67F45 1.%E-06 ALL 0 00E+00 OwfMM 0#3E+00 0.toEdM 0. ore +40 OfoF4A ~3 c90 +00 Ouf4M l Cs-137 3.27E4M 3.13E 04 1

l 4.85E46 NO DATA 2.47EJ18 4.34E 08 9.84E45 All 000E+00 0 0rE +00 6 0ff um OMEdM 09;Ed10 twoEMW) OME+N) ()REW)

Ilat a-140 8 3 f E-05 7 28E OR 2.0;E47 2.01E-07 0% 5.58F+a2 ONE+00 $3ME.02 $1xE4G 3nE42 53FE-02 538F-02 SJ8E-02 11-3 NO D/iTA 2.03E-07 2 03E47 2.03E-07 2 030-07 19 0niSSE Toul Dnse (mrem yry- 0 00E+00 5.7BE42 57dE-02 57FE42 5JaE42 538F42 5.78E-02 4-Page 67 l

l

-.L m = AT/u%,i& " " " " " "* * "

l en w == ipe == um I

l Dose from Dnaking Water Pathway for 1991 Data Maxinum Expneed Infest Usage (intske rute) = 330 1/p liighem Ana. Mens

!afact Conc.

l Ingenion Dme factor locatme in (mrem per pCiingewed) thst! Water Ibe (mrem'p)

Radionuclide Ibn Liver T. thly Thymid Kidney Imag GI-LLI Ihrestion (pGL) Ibne Liver T.Ndy Thyndo Kidney Imag GI-LIJ Me-54 NO DATA 1.99E45 4.51F46 NO DATA 4.41E4 NO DATA 73tE 4 ALL 0 00Ed)0 0 0rEdn 000Ed)0 O N E+co CRE+00 0.r*E <h 0.00E+00 0.00Ed)0 Co-58 NO DATA 3dE-06 8.r346 NO DATA NO DATA NO DATA R.97E 4 ALL O_00E+00 0.00E MC 0.00E430 0.00E +00 0 00Eus0 0.7446 0#)Edo OfMEdo Fe-59 3,08E45 531 E45 2.12E-05 NO DATA NO DATA 1.59E 0$ 2.57E-05 All 0.00Eds0 09)E we 0#1040 OJME+91 0 0"E4)0 0 0!E+00 0#JEdo O N E d)0 Co-60 NO DATA 1.osE-05 155E-05 NO DATA NO DATA NO DATA 2.57L 05 All Of/E +00 0.0rE4M 0 00E+00 0 00E+00 0 00Edy) 0!$FM)0 0 00E+00 0.00E44 Zn-f ' I.84E45 631E-05 2.91E 05 NO DATA 3 06E-05 NO DA1 A 533E-05 AIL O NE+00 0fnEd4 00rE+00 0 00Edjo 09E44 3.rsnEd)O 0/ME+00 0.00E+00 Nb 95 4.20E-08 1.73E 08 1.0^E-08 NO DATA 1.24E-OR NO DATA l.46E-05 ALL 0.00F 4W 0.00E+00 0 00E +00 O VF.Hi0 OMEWC 0.00Ed)0 0#)E+ M - 0 0rE+00 Zr 95 2.06E-07 5.02E 08 3.56E 04 NO DATA 5.4 t E48 NO DATA 2.50E-05 ALL OJME+00 ODE 44 ODOEMU O rOEd)0 0 0rE46 0.00Edo 0 0rEW) O 'yE 4M 1 131 3.59E 05 4.23E-05 1.86E 05 130E42 4.94E-05 NO DATA I.51E 4 All ONE+00 0.0 01:40 ODEdn 0 00 Ewe Ogrun Outun 0.0nEuy) 0*)E400 Cs-134 3.77E 04 7.03E-04 7.10E 05 NO DATA I.RIE.04 7.42E 05 1.9tE M ALL 0 00Ed)0 OWE.00 0 00E+00 O N E d;0 0 0r!E+00 ODrE d)0 ONEd10 C R E d)0 Cs-137 5.22E-04 6.IIE-04 433E 05 NO DATA 1.64E-04 6.64E-05 1.91E 06 ALL 0 00E+00 ODEun O r.(Ed)0 ODE +00 O D E dJo 09E +00 0 00E+00 00t{+00 1.71F47 8 8 tE 06 NO DATA 4 06E 08 1.05E47 9.7~E-05 ALL ODiE+00 0 00E+00 ODOE+00 ONE+00 0#Edn 0 0iE+00 0DE +00 0. ore 4n Bala-140 1.71E44 NO DATA 3 08E-07 3.08E-07 3D8E-07 3.08E-07 3 ORE 47 3.0RE47 066 5.53E+02 0 00Fdo 5 6'F-02 5.67E42 547E42 547E42 5 67E 02 5.67E-02 11-3 19 0mi'SSE Total lhe (mremit) = 0 00E+00 5.67E-02 5.67E-02 5 67E42 5.67E42 5 A7E 02 5.67642 4-Page 68

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Dose fem Milk Pethway for 1991 Data Maxirrem Extened Teenager "l Usage (Irdske rate) = 400 Uyr 16ghest Ann. Mean Teenager Conc. '

Ingestion Dose Factor locaties se (mrem per pCiingeced) Dial Mi!k Dose (mrem /yr) liver T Body HyvmJ Kidney Larsg Gl.LLI Direction (pG7t) Nae Lever T. Ndy hymd Kilney Iung GI-LU Rsdionuclide , Ik>ne 136E 4 NO DATA l 21E45 ALL 0 00E+00 O DnEdK1 ON>E+00 0 00F+00 OJ)oE+00 O m E+00 0.00E+00 0.00EWJO Mn-54 NO DATA 5.00E 06 1.17E 06 NO DATA 134E 05 AIL ebiE+00 0 0rE+00 0 00Ev>0 0.0(E+00 0 00E+00 0.00E+00 O N E 4)0 0.00E+00 Co-58 NO DATA 9.72E47 224E46 NO DAT A NO DATA NO DATA Fe-59 5.87E46 137E 05 5.29E-06 NO DATA NO DATA 432E M 3 24E-05 ALL 0.00E+00 0.00E+00 ONE+00 0 0(E+00 0.00E+00 Ois0Ede 0#EMW o frE+09 3.66E45 ALL 0.00E+00 ONE+00 c m E+00 0.onEve 0.00E+00 'O M E+00 0 00E+00 OVE+00 Co40 NO DATA 2.81E 06 633E n6 NO DATA NO DATA NO DATA 933E M NO DATA 128E-05 NO DATA 8.47EM ALL DJX)E+00 O V)E+00 0 00E+00 0.00Ev)0 O N)E+00 OMEvo OAK +00 0 00E+00 Za45 5? M6 2.00E-05 4.42E49 NO DATA 1.95E45 All 0.00E+00 0 00E400 0 00E+00 0.00E+00 0 0tE +00 0 0rE +00 o g E+00 0 00r+00 Nb-95 8.22EJ9 4 56E-09 2.51E-09 NO DATA 1.9 t E48 NO DATA 3 00E-05 All 0.00E+00 0.00E+00 O!xEdn o m E+00 0 0tE+(M 0 00E+00 0 #)E+00 0.09Euc Zr 95 412E-08 130E-08 8.94E49 NO DATA 230E-03 1.41E 05 NO DATA 1.62E M All 0 0tE+00 O M E+00 CWE+00 OME46 OME+00 0.OnE+00 OMEdo OMEuo I-131 5.85E4 8.19Em 4 40E46 9.14E45 NO DAT A 6.26E 05 230E-05 2.45E46 ALL 0.00E+00 0/ JOE +0') ODE +00 0.00E+00 OAE +00 0 00F+00 09E+no O M E+00 Cs-134 837E 05 1.97E44 5.07E 05 1.97E-05 2.12E46 069 4.99E +00 2.24E-01 2.97E-01 1.04E41 0.00r+00 1.01E41 193E42 4.23 E-03 Cs-137 I.12E44 1.49Eot 5.19E-05 NO DATA 4.$rn-WNW 3.48E-08 1.83E-06 NO DATA 1.18E 08 234E-08 9.82E-05 ALL 03)E+00 O M E+00 0.00E +00 ONE +00 ONE+00 ODE +00 ODE +IP) O M E+00 Ibla-140 2.84F-05 Tots! Dose (mrem)T) = 2.24E-01 2.97E-01 1.04E-01 OME 30 1.0lE-01 3 93E42 4.23E43 l

4-Page 70

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4-Page 77

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I SECTION 5.

QUALITY ASSURANCE 5.1 DUKE PONER COMPANY'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1.1 SNMPLE COLLECTION The ONS Chemistry Section performs the environmental sample collections as specified by approved sample collection procedures.

5.1.2 SAMPLE ANALYSIS The Wadiological and Environmental Services performs the environmental sample analyses as specified by approved analysis procedures.

5.1.3 DOSIMETRY ANALYSIS I

The Dosimetry Laboratory performs environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

I 5.1.4 INTRALABORATORY QUALITY ASSURANCE I

Radiological and Environmental Services has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working 7rder and these checks are used to monitor instrument performance. I I

I s-> e -

I l

I Additionally, National Institute af Standards and Technology !

(NIST) ctandarde thet represent counting geometries are analyzed as unkn6wns at various frequencies ranging from weekly 1

to annually to verify that efficiency calibrations are valid. l The frequency is dependent upon instrument use and performance.

Investigations are performed and documented should calibration verification data fall out of limits.

5.1.5 INTERLA30RATORt QUALITY ASSURANCE 5.1.5.1 DUKE PCWER'S AUDIT DIVISION Hadiological and Environmental Services, and the Dosimetry Laboratory were participants in a Quality Assurance audit in 1991, performed by Duke Power's Audit Division. No findings or recommendations concerning the Oconee Nuclear Station Padiological Environmental Monitoring Program were identified in the audit.

I The ONS Chemistry and Radiation Protection Sections responsible for environmental monitoring were evaluated by Quality Assurance in 1991. No findings were identified, but a recommendation was made to establish a consistent basis for environmental air sampler flow rates. Several regulatory guides and EPA guidelines were reviewed for applicability by the G.O. Radiation Protection. The guidance discussed several factors that influence volume requiretta.nts, such as LLD's, MPC's, radioactive decay characteristics, analysis method, filter media, etc.

Based upon this review, it was recommended that the air

sampler flow rates be lowered to 1.0 CFM to 3.0 CFM.

. I " " "'

I

I 5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM Radiological and Environmental Services participated in the Duke Power Nuclear Production Intercomparison Program during 1991. Interlaboratory cross-check body burden standards, marinelli beakers, air filters, air cartridges, gross alpha / bete on smears, and tritium in water samples were analyzed at *.*arious times of the year by the four counting laboruto-ies in Duke Power Company for this program.

I 5.1.5.3 U.S. NUCLtAR REGULATORY COMMISSION INSPECTIONS I Radiological and Environmental Services, ONS Chemistry and Radiation Protection Sectiont were audited by the NRC in 1991. No violations, deviations or follou-up items were identified by the inspector concerning the Oconee Nuclear Station Radiological Environmental Monitoring Program.

I 5.1.5.4 UNIYED STATES ENVIRONME14TfL PROTECTION AGENCY INTERCOMPARISON PRnffRAM Radiological and Environmental Services participates in

, the Environmental Protection Agency (EPA) Environmental Honitoring Systems Laboratory Intercomparison Program.

The EPA sample types include n.ixed gamma in water (3 times per year), mixed gamma in milk (2 times per year), gamma 9

in air filters (2 times per year), iodine in milk (2 times per year), tritium in water f.3 times per year), iodine in water (2 times per year), gross alpha / beta in air filters (2 ti.mes per year), and gross alpha / beta in water (2 times

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I per year). Radiological and Environmental Services prepares and analyzes each sample as quickly as pos=ible.

Should the data obtained be out of EPA limits, Radiological and Environmental Services performs and documents follow-up investigations. The Radiological and Enviror. mental services EPA Intercomparison Report code is "CP". A summary of the EPA Intercomparison Reports for i 1991 is documented in Tehle 5.1. Of the thirty-Seven (37) c analyses performed in 1991, one analysis (Gross Alpha / Beta in Air Filter cross-check, reference date 3/29/91) was out of EPA acceptance limits.

An investigation was performed to find out why the resulte wer- not within statistical limits. The following areas were investigated:

1. Sample geometry

2. Gas flow

3. Efficiency calibration files

4. Activity c,alculations

5. Cross-checks and verifications performed approximately the same time (April 1991) of the EPA analysis

6. Past trends of EPA Alpha / Beta Cross-checks

7. Recounting of the EPA Cross-Check Air Filters

8. Trending alpha / beta air filter sample results for 1991 E .

In the first area of investigation, geometry, it was noticed that the filter media the EPA uses is considerably thicker than that of our regular air samples, therefore the sample will be placed closer to the counting window during the time of analysis. This closer placement of the sample will then produce a higher alpha count rate than I '-""'"'

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I that of a sample that is more distant from the window.

This would in turn produce a higher activity reported for alpha, but the beta results would not necessarily change, because of the high energy of the C 137 beta.

I The results of the EPA cross-Checks for Air Filters and I Drinking Waters since 1984 were gathered and plotted to see if there was any trends in the results. The EPA 5 started using a new disk media to simulate an air filter in April of 1987. By studying these graphs it was seen that the alpha results, from 1988 on, start to trend high.

This trend can be related to either the change in filter media or change in calibration standards (new standards made in October 1987). By comparing the graphs it was seen that the change in results is due to the change in filter media, because the Drinking Water results did not trend in the same manner as those of the Air Filters.

The EPA Air Filters were analyzed again under the new calibration that was performed in June 1991. These results were acceptable for Beta activity, but were right at the warning limit for Alpha. The Air Filters were also counted with the Air Filters setting directly in the holders (i.e. not in planchets), and these results were

, within statistical limits. These results support the geometry investigation for Alpha, because the results were produced with the sample being further away from the counting window and closer to being the geometry used prior to April 1987. But on the other hand, this does not support the Beta, because even though the results are within statistical limits the activity had dropped.

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I In concluiion of this investigation, it appeared that just one reason for the poor results could be identified. The instruments will ccntinue to be checked on a quarterly basis to ensure they are within calibration limits.

Additional documentation of this investigation is available from Radiological and Environmental Services.

5.1.5.5 NRC/ STATE Or S.C. ENVIRONMENTAL HONITO't!NO PROGRAM I The ONS Chemistry Section and Radiological and Environmental Services routinely participate with the State of South Carolina in their NRC/ State Contract Environmental Monitoring Program. The ONS Chemistry Section splits water, milk, vegetation, sediment, ar.d fish samples with the Bureau of Psdiological Health of the State's Department of Health and Environmental Control (DEHC) for analysis. DPEC collects air ramples from two of the locations sampled for air by ONS. Results of the analyses performed on split and duplicate samples by Radiological and Environmental Services, and DHEC Laboratory are corr. piled by DHEC and provided to the NRC.

TLDs are also co-located with the State and NRC at various environmental sites.

5.1.5.6 NRC/ STATE Or N.C. INTERCOMPARISDN PROGRAM Radiological and' Environmental Services, and the Donimetry Laboratory routinely participate with the State of North Carolina Department of Environ:nental Health and Natural Resources (DEHNR) in an intercomparison program. Health and Radiological Projects sends air water, milk, I

I

lI vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis. TLDs are also co-located with the State and NRC at various environmental sites. Also, every six to eight months, the State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Dosimetry Laboratory for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 199.1 is documented in Table 5.2. The Dosimetry Laboratory results were within e.13% of the State of North MW Carolina results (excluding Standard Deviation values) for the March 1991 cross-check, and 3.79% (excluding Standard Deviation values) for the December 1991 cross-check.

5.1.5.7 U.S. DEPARTMENT OF ENERGY INTERCOMPARISON PROGRAM There was no DOE intercomparison program during calendar year 1991.

I 5.2 CONTRACTOR LABORATORY I No contractor laboratories were used during 1991.

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W M M M M M M M M M W W .M M M M TABLE 5.1 (Pace 1 of 2)

U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1991 CROSS-CHECK EESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY CONTROL LIMITS ANALYSIS DATE NUCLIDE(S) KND*iN VALUE (3 SIGMA: N=3) REPORTED VALUE Gamma in Hater 2/08/91 Ba-133 75 pCi/L 61.1 - 88.9 pCi/L 78.3 pCi/L Co-60 40 pCi/L 31.3 - 48.7 pCi/L 42.3 pCi/L Zn-65 149 pCi/L 123.0 - 175.0 pCi/L 158.0 pCi/L i Ru-106 186 pCi/L 153.0 - 219.0 pCi/L 212.3 pCi/L l Cs-134 8 pCi/L 0.0 - 16.7 pCi/L 8.3 pCi/L Cs-137 8 pCi/L 0.0 - 16.7 pCi/L 9.3 pCi/L l

6/07/91 Ba-133 62 pCi/L 51.6 - 72.4 pCi/L 65.0 pCi/L l Co-60 10 pCi/L 1.3 - 18.7 pCi/L 11.0 pCi/L '

Zn-6 5 108 pCi/L 88.9 - 127.1 pCi/L 112.7 pCi/L Ru-106 149 pCi/L 123.0 - 175.0 pCi/L 159.0 PCi/L Cs-134 15 pCi/L 6.3 - 23.7 pCi/L 15.0 pCi/L Cs-137 14 pCi/L 5.3 - 22.7 pCi/L 15.3 pCi/L 10/04/91 Ba-133 98 pCi/L 80.7 - 115.3 pCi/L 100.7 pCi/L Co-60 29 pCi/L 20.3 - 37.7 pCi/L 32.7 pCi/L Zn-6 5 73 pCi/L 60.9 - 85.1 pCi/L 83.3 pCi/L Ru-106 199 pCi/L 164.3 - 233.7 pCi/L 218.0 pCi/L l Cs-134 10 pCi/L 1.3 - 18.7 pCi/L 10.3 pCi/L

! Cs-137 10 pCi/L 1.3 - 18.7 pCi/L 11.0 pCi/L 1

l 2/15/91 I-131 75 pCi/L 61.1 - 88.9 pCi/L 78.7 pCi/L 1

l 8/09/91 I-131 20 pCi/L 9.6 - 30.4 pCi/L 2G.7 pCi/L l

r Air Filter 3/29/91 Cs-137 40 pCi/ Filter 34.2 - 45.8 pCi/ Filter 39.3 pCi/ Filter Gross Alpha 25 pCi/ Filter 18.1 - 31.9 pCi/ Filter 41.7 pCi/ Filter Gross Beta 124 pCi/ Filter 117.1 - 130.9 pCi/ Filter 108.0 pCi/ Filter 1

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M M M M M M M M M M M M M M M M M M TABLE 5.1 (PAGE 2 0F 2)

U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1991 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY CONTROL LIMITS ANALYSIS DATE HUCLIDE(S). KNOHN VALUF_ (3 SIGMA: Nr3) REPORTED VALUE Air Filter 8/30/91 Cs-137 30 pCi/ Filter 21.3 - 38.7 pCi/Filte- 31.7 pCi/ Filter Gross Alpha 25 pCi/ Filter 14.6 - 35.4 pCi/ Filter 35.0 pCi/ Filter Gross Beta 92 pCi/ Filter 74.7 - 109.3 pCi/ Filter 93.0 pCi/ Filter Tritium in Water 2/22/95 H-3 4418 pCi/L 3651.2 - 5184.8 pCi/L 4676.0 pCi/L 6/21/91 H-3 12480 pCi/L 10314.8 - 14645.2 pCi/L 12387.7 pCi/L 10/18/91 H-3 2454 pCi/L 1843.3 - 3064.7 pCi/L 2839.0 pCi/L Gemma in Milk 04/26/91 I-131 60 pCi/L 49.6 - 70.4 pCi/L 67.0 pCi/L Cs-137 49 pCi/L 40.3 - 57.7 pCi/L 49.7 pCi/L 9/27/91 I-131 108 pCi/L 88.9 - 127.1 pCi/L 110.7 pCi/L Cs-137 30 pCi/L 21.3 - 38.7 pCi/L 31.0 pCi/L Alpha-Beta 1/25/91 Gross Alpha 5 pCi/L 0.0 - 13.' pCi/L 7.7 pCi/L in Hater Gross Beta 5 pCC/L 0.0 - 13.7 pCi/L 9.3 pCi/L 9/20/91 Gross Alpha 10 pCi/L 1.3 - 18.7 pCi/L 10.7 pCi/L Gross Bete 20 pCi/L 11.3 - 28.7 pCi/L 21.3 pCi/L LS35.HPF 5-Page 90

g g- g g g g M M M M M s '. W W W W W TAEliE 5.2 STATE OF NDRTH CAROLINA DEPARTMENT 0:' ENVIRONMENTAL HEAL.TH AND NATURAL RESOURCES ENVIRONMENTAL DOSIMETER CROSS-CHECK 1991 s i e

l l State of H.C. I Dosimetry Laboratory i

l l Estimated Value Estimated Value i e l i e I I i I l I Cross-Check l Exposure l Estimated l Exposure l Estima ted l Date l (mR) l Uncertainty I (wR) Uncertainty l I l l (1 S.D. mR) l (1 S.D. mR) i l

i a e i l i i I 3/91 l l ! 49.6 l 1 1.2 l 47.72 l 1 1.91 1

! l ! l e i a 4 l t I l 12/91 l 49.8 0.7 i

l 1 45.75 l 1 1.19 i LS35.WPF 5-Page 91

SECT 16N 6.

REFERENCES

1. ONS Selected Licensee Commitments. 16.11-6 Radiological Environmental Monitoring

2. Duke Pcwer Company, Offsite Dose Calculation Manual, Section AS.O

3. ONS Chemistry Procedures for Sample Collection and Land Use Census {

4. Production Environmental Services, Radioanalysis Laboratory Procedures and Dosirretry Laboratory Procedures

5. ONS Final Safety Analysis Report

6. ONS Preoperational Environmental Radioactivity Monitoring Reports and Annual Radiological Environmental Operating Reports, 1969-1990

7. NRC Regulatory Guide 1.109, Calculation of Annual Doses To Han From Routine Releases Of Reactor Effluents For The Purposes Of Evaluating Compliance With 10 CFR Part 50, Appendix I B. N".C Regulatory Guide 4.15, Quality Assurance For Radiological Monitoring Programs (Normal Operations)-Effluent Streams And The Environment

9. NUREG/CR-1276, User's Manual for LADTAP II-A Computer Program for Calculating Radiation Exposure to Han from Routine Release of Nuclear Reactor Liquid Effluents

10. ONS 1991 Annual Liquid and Gaseous Effluent Report, 1/20/92,05-215.02

11. Probability and Statistics in Engineering and Management Science, Hines and Montogomery, 1969, Pages 287 - 293 I

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5 APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of environmental media is required to ensure compliance to the Radiological Environmental Monitoring Program as defined by ONS Selected Licensee Commitments and the ODCH. These procedures ensure that environmental media are sampled and analyzed according to the specific locations, frequencies, I

and types of analyses given in the ODCH (Tables 2.1-1, 2.1-2 and 2.2-1).

Analysis procedures ensure the detection capabilities given in Selected Licensee Commitments will be achieved (Table 2.2-2).

The required detection capabilities were met for the analyses performed in 1991. Deviations from analytical procedures are listed in Appendix D.

Collection requirements were also met with the exceptions Idsted in Appendix C. For some sample media, collection is performed at more locations than required by Selected Licensee Commitments. These includ!

Broadleaf vegetation, Shoreline Sediment and Fish. The additional samples make it possible to compare different sample med.ta collected from the same location.

Environmental sampling is performed by the ONS Chemistry Section. Sample analyses are performed by Duke Power Company's Radiological and I Environntntal Services. TLDs are processed by Duke Power Company's Dosimetry Laboratory. Sections A.1-A.9 describe the sampling and analysis I procedures by media type. The actual procedures which are applicable to the sampling and analysis are found in References 3-4.

CHANGE OF SAMPLING PROCEDURES There was a modification made in the starting flow rates for the environmental air samplers. The starting flow rates were lowered to 3.0 5 CFM to coincide with the 1991 QA audit recommendation (see section 5.1.5.1).

I A-Page 93 I

1, in addition to collecting fish with nets, electrofishing was performed in i

1991. Electrofishing will continue to be an option for fish collection.

CHANGE OF ANALYSIS PROCEDUKES During 1991, a change in the procedure was made for gross beta samples.

The samples are now counted in replicate, three times each, and a mean result is used h the calculation of activity.

I The value used to determine if the gross beta activity is less than the critical Itvel was re-evaluated and changed to be 50% of the HDA value, rather than 100%. This value is iridicated on the activity calculation printout for each sample.

SAMPLING AND ANALYSIS PROCEDURES A.1 AYRBORNE PARTICULATES AND RADIDIODINE Farticulate and Radiciodine activity in air is collected through use of fiber filters for particulate collection followed by charcoal cartridges for iodine absorption. Air samplers are operated continuously and samples are changed on a weekly frequency. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to semple approximately 3 cubic feet per minute. The volume of air usually sampled over the weekly period is approximately 8.5E2 cubic meters.

Gamma spectroscopy is performed on each fiber filter and each charcoal cartridge separately.

A.2 DRINKING WATER Drinking water samples are collected by operation of a composite I,

sampler. The sampler is operated to collect an aliquot at least once every two hours. The sample is collected monthly and utilized for gamma spectroscopy, gross beta analysis, and low-level I-131.

I The beta analysis is performed with a proportional counter. A separate portion is saved to form a quarterly composite with two other monthly period samples. Tritium analysis is performed on this A-Page 94 I

I quarterly composite using liquid scint!11ation. Low-level iodine analysis is performed in addition to the analyses required by Selected Licensee Commitments. An ion exchange recin is used to remove and concentrate any iodine in the drinking weter. The resin is then analyzed by gamma spectroscopy.

I A.3 SURPACE WATER Surface water samples are collected by operation of a composite sampler. The sampler is operated to colleet an aliquot at least every two hours. The sample is collected monthly and utilized for gamma spectroscopy. A separate portion is saved to forn a quarterly composite with two other monthly period samples. Tritium analysis is performed on the quarterly composite.

I A.4 MILK Milk samples are collected on a semimonthly frequency. The normal volume collected is twelve liters. A portion of the .nilk is utilized for gamma oper:troscopy. Part of the remaining portion is used for low-level iodine analysis. An ion exchange resin ic used to remove and concentrate any iodine in the milk. The resin is then analyzed by gamma spectroscopy.

A.5 BROADLEAF VEGETATION Broadleaf vegetation sampling is performed on a monthly frequency.

At least 1 kilogram of vegetation is collected. The most recent growth possible is sampled. Gamma spectroscopy is performed on each sample.

A.6 SHORELINE SEDIMENT I Shoreline sediment is collected quarterly, although Selected Licensee commitments requires semiannual collection. At least 500 grams of sample are collected from the top 7.5 centimetern of sediment at the edge of the water. Gamma spectroscopy analysis is 1

A-Page 95

I performed on each sample after drying and removal of rocks and clams.

g A.7 FISH sm Fish tre collected on a semiannual frequency. Gillnets and traps are put in place or electrof f shing is performed at the tnonitoring I locat. ions and fish are collected until the required sample size is met (~500 grams each species). Fish are prepared using just the fillets. Gamma Spectroscopy analysis is performed on each species of fish after they ."e prepared.

A.8 DIRECT CAMMA RADIATION Direct Radiation measurements are accomplistad by usinry caso,iny TLDs. The TLDs are changed out on a quarterly frequency. The gamma dose dett'rmined for each TLD after processing is converted to a dose rate for reporting purposes.

A.9 LAND USE GENSUS The Land Dae census is conducted to identify the location of the nearest milk animal, meat animal, and nearest residence in each of the sixteen meteorological sectors within a distance of 5 miles of the station. The census is accomplished by a vehicle search of each sector. Aerial surveys or consulting local authorities may also be utilized to collect information. The census is performed between April and August each year.

In lieu of a survey of gardens in the area, sempling of broadleaf veget v m is p rformed at the site boundary in the direction sector is 3 W ia- highest deposition parameter. This location ensures that

's ,.., st potential exposure from the vegetation pathway is monits ed.

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1 A-Page 96 1

I g A.,E 0,x .

RADIOLOGICAL ENVIRONMENTAL MONITORING ,R00 RAM

SUMMARY

OF RESULTS g s _ .,,.s.. . t.,..cs ..ei. s. . e.. 1 c1 e.e 1. <,1. ....me1..

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I Environeental Radiological nonitoring Progree $uenary Page : 1 Name of Facility : 04$ Dottet hseber i 50-269.270.207 Location of Facility : OC0 HEE C00tiiY. S.C. Rmrting Feriod 1 JAh 1991 through 31 MC 199) flee Report Generated 23-JAN-1992 08141119 Database hast ll!$11 (($$ER. ASC10NS91.5/J:1 I

: : : Location with Highest Near. :

he of g Medius or : isce 8 fotal : Loweri All Indicator - - - - " - - - - - ~ ~ ~ - ~ ~ - - - ~

hon-

'g Pathmat : Number of : Lleit of

Locations : hase. Distance and Direction l ControlLetations ' Routire Scooled : Analtses l.tetettien ' Mean (Frattsoni ! Location Mean (Fractioni Mean (fractioni

Recort (Units) : Performed l (LLD) : Range : Code Rangt Range

Meas.

IR PARilCULATE : l (PC1/Q31 l l l l :

: : : ' 073 (9.0 ni un l I Letations: Mit 257 l 0.0M*M 0.0M+00( 0/ 205) l 0.00D00( 0/ $21 : 0.00D001 0/ 52) : 0

0.00D00- 0.00D00 l 0.00D00- 0.00E *00 l 0.00D00-- 0.00E+00 :

I : '

l l C0-58 257 ! 0.00E+00 : 0.00D00( 0/ 205) : 0.0M*00( 0/ 521 : 0.00D001 0/ $2) : 0

. . . 0.MD00~ 0.00D00 : 0.MD00- 0.00E*00 : 0.00E+00- 0.00D 00

l l l !

l WI

FE49 257 : 0.00D 00 : 0.MD00( 0/ 205) : 0.MD00( 0/ 52) : 0.00D00( 0/ $2) ' 0

: 0.00E+00 - 0.00E+00 0.MD00-- 0.0M.00 : 0.ME *00- 0.00E *00

l l l l '

I : CD-60 l

257 l

0.00E+00 : 0.00E+00(

0.00E+00- 0.00E+00 l

0/ 205) :

l 0.MD00( of $2) : 0.00D00( CI 52) :

0.00D 00 - 0.00E+00 l 0.00E+00 - 0.00D 00 '

! l 0

l ik-65 257 l 0.0M +00 I

0.ME +00( 0/ 205) : 0.00D00( 0/ 52) : 0.00E+00( 0/ 52) l 0 l : : 0. ME+00 - 0.00E+00 : 0.00E*00- 0.00DM ' O.MD00- 0.0M*00 l l l ! ! l l NS-95 257 : 0.0X+M : 0.00D00( 0/ 205) : 0.0X+00( 0/ 52) : 0.00D00( 0/ 52) :

I 0

: : 0.00E*M-- 0.ME+00 : 0.00D00-- 0.00D 00 l 0.0M *00- 0.00E*00 l l l l l l l l IR 95 257 : 0.00D00 l 0.00D00I 0/ 2051 : 0.00E*00( 0/ 52) : 0.00D00I 0/ $21 : 0 I l l

1-131 l

l 0.ME +00 - 0. 00E *M :

257 : 7.00E-02 : 0.00E+00( 0/ 205) :

0.00E+00- 0. ME*00 : 0.00D 00 - 0.00E*00 l 0.00D00(

0/ 52) : 0.00E+00( 0/ 52) l 0

: : 0.00D00 - 0.MDM :

t l

CS 134 l !

257 : 5.00E-02 : 0.MD00( 0/ 205) :

0.00D00-- 0.00E+M : 0.00D00 - 0.ME*00 l 0.00D00( 0/ 52) : 0.00E *00( 01 52) :

0 0.00E+00-- 0.00D00 : 0.00D00- 0.00D00 0.00D 00 ~ 0.00E+00 :

I :

l CS-137 l

257 l 6.00E-02 : 0.00D00( 0/ 205) :

l l 0.0X +00 ~ 0.00D00 :

l 0.00000(

l 0/ 52) : 0.00D00( 0/ 57) :

0.00E*00 - 0.00E+00 ' O.00DM-- 0.00E+00 :

l 0

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l BALA 140 257 : 0.00E+00 : 0.0M+MI 0/ 205) : 0.00E*00( 0/ $2) : 0.00E +00( 0/ 52) : 0

: 0.00E+00- 0.ME*00 0.00E +00-- 0.ME *00 0.00D00-- 0,00D00 l hnandrangebasedcoondetectableseasuresentsonly W attien of detectable seasurements at specified locations is indicated in carentheses. (Frattioni fero range indicates no detectable activitt seasurerents LLC is esval to 0, then LLD is not reevired by Technical Soetifications Location 060

Greenville Water intate Rcad ation 0(,1 = Old Highear 193 atica 072 = Highway 130 ation 073 = laeassee DAR School location 074 = frover try Resort B-Pege 98

lI IMITU45titil fiA#iclegital Panitoring Progras Suesary Pant i 2 hast of facility DN5 Dottet hunber 50 269.270.267 Locatiot , facility : OCONEf COUNir. S.C. Reportir.g Period 1 J AN 1991 through 31-MC-1991 Tiet Ptoort Ernerated 23 JAN-1992 08:41:19 htabast kane : 5015tliluSER.ASC10NS91.$ Mil l l l l Location eith Highest Mean ! ha of Tyre 4 Total l Lo tr I

Medius or All Inditator :---- ---- - -~ ~ - ~ ~ - - - - -l l han-Pathsay l hoeber et l Lieit if : Locations : Naer. Distante and Direction l Control totations : Routint Sasoled l Analvses l..De t ti : Mean (Frtttion) : Location Mean tirattion)

Mean (Frattion) lStoort (Units) l Ferforeed (LLD) : Range : Code Rangt l Rangt l Meas.

IA!RRAD1010 DIN!$! l l l

l (PCl/Q3) l l l '

l l l l 073 (9.0 Mi NW) :

Locations : MN-54 257 : 0.MD00 0.00D001 0/ 205) : 0.MD001 0/ 52) : 0.00D001 0/ $2) l 0 l l l 0 MD00- 0.00DM l 0.00b90- 0.00D00 l 0.00D 00- 0. ME*00 I

l l ! : :

CD 58 257 l 0.00D 00 0.00D001 0/ 205) : 0.00Def 0/ 52) : 0.00D00f 0/ $2) l 0 l l ! 0.00D00- 0.MD00 ' O.00D00-- 0.0M *00 : 0.00E +00-- 0.00000 :

: : l l l l

ur l Ft 59 l

257 0.00D 00 : 0.00D001 ol 205) l 0.00t*001 0/ 52) l 0.00D00( O' $2) : 0 l l 0.00D00- 0.00D00 0.00D00- 0.00D00 l 0.00D00 - 0 ,JD00 l l l l l l l

CD-60 257 : 0.00D 00 : 0.00D00I 0/ 205) : 0.00D00( 0/ $2) l 0.00D00t 0/ 52) : 0 8 :

l

: 0.00D00- 0.00f *00 : 0.00DH - 0.00D00 : 0.00D00- 0.00D00 l l l l l

Ik-65 257 : 0.00f* M l 0.00f*001 0/ 20b) : 0.MD001 0/ $2) : 0.00D001 0/ 52) : 0

: : 0.00D00- 0.0M*00 5 l l l l 0.00f *00-- 0.00D00 l 0.00D00- 0.00D(0 :

l l l NS *5 257 l 0.00D00 l 0.00D001 0/ 205) : 0.00D001 0/ 52) : 0.00D00f 0/ 521 :

I 0

: ! 0.MD00- 0.00D00 l 0.00E 00- 0.00D 00 l 0.00D00- 0.00E*00 l l l l l l l IR 95 257 : 0.00D00 l 0.00E +001 0/ 205) : 0.00D001 0/ $2) l 0.00D00( 0/ $2) : 0 I :

l l l 131 l

0.00DM- 0.00D00 :

l 257 : 7.0M-02 : 0.00t+001 0/ 205) '

l 0.Mf+00-- 0.00D 00 l 0.00D00- 0.00D00 l O.00D001 l

0/ $2) : 0.00D00t 0/ 521 :

l 0

l l ! 6.MD00-- 0.MD00 l t l CS 134 l

257 l

5.00f 02 v.v0D00(

! 0.00D00 0.00D00 0/ 205) :

0.00000- 0.MD00 0.00D001 0/ 52) : 0.00D001 0.00D00-- 0.00D00 :

0/ $2) :

l 0

0.00D 00-- 0.00D 00 l 0.00D00-- 0.00E*00 :

I l CS-137 l

257 : 6.00[-02 l

l 0.00D001 l 0.00D00- 0.00D00 l l

0/ 205) :

l 0.00f*001 0/ 52) : 0.00t*001 0/ 52):

0.00E*00-- 0.00t+00 : 0.MD00-- 0.00D00 :

l 0

l l l l l l BALA-140 25i ! 0.00D00 : 0.00D001 0/ 205) : 0.00D001, 0/ 52) : 0.00D00( 0/ 52) : 0 l l 0.00D00- 0.00D00 l 0.00D00- 0.00E+00 l 0.00D00-- 0.00D00 l Banandrangebasedutondetectabirseasurteentsonly action of detettable seasurteents at sortified notations is indicated in parenthests. (Frattion) lero range indicates no detectable activity sensurteents LLD is toual to 0. then LLD is not reovired by itchnical Sortifications Location 060

Greenville Water Intake Road tation 061 : Old Highway 183 tation 072 Highway 130

. cation 073 Tan u tre CAR School location 074

teoste ter Resort B-Page 99

I levironetetal Radiological Monitoring Progras $$neart Page : 3 Nast of Fatality : 045 Dottet Nuttitr 30-269.270.287 Location of f acilite : OCDNEf COUN17. S.C. Rtoorting Period : 1 JAN-1991 through 31 MC 1991 41:19 Catabase kast i splSil:IUSER.ASC1DN591.5AF1 1....Tiet Recort

................ Generated

.............. ................................ : 23 JAN 1992.-...........................................................

09:

l l l l Location eith Highest Mran l l ho. of Typt & Total l Louer I All Indicator Medive or ! :---~~-------~~--~~-l l kon-Pathear l hunber of l Lielt of : Locations : hast. Distante and Direction : Control Letations l Routint Saneled ! Analysts :, Detection Mean (Frattioni l Location mean (Frattion) Mean IFrattion) l : Rtoort Illnits) l Performed l (LLtl l Range l Code Range : Rangt ' Mtas.

iBRDADLiAtVESti! ! ! l l l (PC1/WE1/t61 : l l l ! l l l l l l 073 19.0 Mi hW) l 53 Locations : M-54 39 l 0.0M*00 l 0.00E*00t 0/ 261 : 0.00E*001 0/ 13) : 0.00E*001 0/ 13) 0 l l l 0.00E*00~ 0.ME *00 : 0.00f+00-- 0.00E*00 : 0.00E*00~ 0.00E*00 :

l l l l l l l C0 58 39 : 0.00E*00 l 0.00E4001 0/ 261 l I l l l 0.00E *00-- 0.00E *00 l 0.00t *MI 0/ Jt) : o,gt.gg of 33) :

0.00(*00 ~ 0.00f*00 l 0.00E*00~ 0.00E*00 l o

l l l l l l l FE-59 39 0.00f*00 : 0.00f*00( 0/ 26) : 0.Mt *001 0/ 13) : 0.00E*00t 0/ 13) : 0 l l l 0.00E*00~ 0.M!*00 l 0.0M *00~ 0.Mf +00 0.Mf +00~ 0.00E *M l l l l l l

00-60 39 0.00f*00 l 0.ME *001 0/ 261 : 0.00f*MI 0/ 13) : 0.00f*001 0/ 131 : 0 5

~

l l

l l 0.00t*M~ 0.00!*00 0.00!*00 ~ 0. ME*00 l 0.00t*00 - 0.00E*00 l l l l l !

IN-65 39 l 0.00f*00l 0.0M*001 0/ 26) 0.00E *MI 0/ 131 l 0.0M *001 0/ 13) : 0 l l 0.0M *00~ 0.0M*00 0.00E*00 ~ 0.00E*00 : 0.00!*00 - 0.0M *00

: l l l l l WB 95 39 0.00E*00l 0.00E*001 0/ 261 l 0.00f*001 0/ 13) : 0.00E*001 0/ 13) : 0

! ! l 0,00E*00~ 0.00E*00 l 0.00t*00 ~ 0.ME*00 l 0.0M*00- 0.00E *00 l i l l l l l l

IR-95 39 : 0.00E*00l 0.00E+001 0/ 26) : 0.00f*001 0! 13) : 0.00E*001 0/ 13) : 0 l l 0.00E*00~ 0.00t*00 l 0.00E*00-- 0.00E*00 : 0.0@%-- 0.Mf +00 :

5 I l l-13.1 l l l l l 39 60. l 0.0M *001 0/ 26) : 0.00E*001 0/ 13) : 0.00E*001 0/ 131 l 0 I

l l 0.ME*00~ 0.00E*00 ! 0.00t*00 ~ 0.00E*00 : 0.00E*00-- 0.00E*00 l l l l ! l l CS-134 39 l 60. l 0.ME *001 0/ 26) : 0.00t*001 0/ 13) : 0.00E*001 0/ 13) : 0 l l 0.00t *00~ 0.0M *00 1 0.00(*00 ~ 0.00(+00 l 0. ME*00~ 0.00f*00 l

! l l 060 12.5 ni kNil l 5 l CS 137 39 90. l 22. ( 1/ 26) : 22. I 1/ 13) : 1.45E*021 7/ 13) : 0 l l 22. ~ 22. ! 22. ~

22. 36. -- 3.98E*02 l l l l l l l

BAL A-140 39 0.ME*00 l 0.00f*001 0/ 261 5 l l l 0.00E*0^~ 0.0M*00 0.00E*001 0/ 13) ' 0.00E*00( 0/ 13) :

0.00t *00-- 0.ME*00 l 0.00E*00- 0.00f*00 :

0 hana;drangebaseduoondetectableerasurteentsonly Wraction of detectable etasurteents at sottified locations is indicates in carentheses. (Frattion)

Jero rarige indicates no detettable attivity seaserteents LLD is temal to 0. ihen LLD is not reetired by Itchnical Settificatiens location 078 Site Bo nJrv station 060

Grettville Water latait Road

)tation 073 = lasaster CAR School 1

B-Page 100 l

_ . _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- ~ --- ---- - - - -

, I htirptierital Radiological Moritering Prograa Sennary Page 4 tree of Facilitt : ONS htlet hast;er 50 269.270.287 Letatica of Fatility : DC0kEE C00hTV. $ C. Rer.orting Period i 1 JAN 1991 through 31-DEE 19t!

I 11ae Report Generated 23 JAN-1992 09:41:19 l l htsbast kase : 015tlilDSER. ASC)0N591.5Ah!

l Locat an with Highest Besa l l ho, of nediva or l 1,pe 6 Total : Loser l All Indicator l- -- - - -- ~ ~ ~ ~ - " - -- -l l hon-Patheiv l N nber of Lisat et Locations : hut. httante and brettion l fontrolLocations Routine Sancied l Analtses l,.Deteciton ' Maan ifraction) !tocation Mean (Frattion) l Peport Mean tFrattion)

(Units) : Perf ormed l tilD) : sange Code Gange l Raritt l Meas.

IDRlulWB lWATER l l l ! l IPCl/LilER5) l l l l l l l l l l l 064 16.7 Mi SW) l Locations l AhAll-LL 39 l 1.0 l 0.0M+00( 0/ 26) : 0. 0M

00( 0/ 13) : 0.00E *001 0/ 13) : 0 l l l 0.00E*00- 0.0M+M l 0.00E*00 - 0.0M *00 l 0.00E *00- 0.00E+00 l

! l l l l l l MN-54 39 l 15. 0.00E*MI 0! 261 :

I l l l 0.0M*00- 0.00E*00 l 0.00E+00( 0/ 13) 0.00E *00f 0/ 13) : 0 0.00E *00-- 0.00E *00 l 0.ME*00- 0.0M *00 l l l l l l l l C0 58 39 l 15. l 0.0M

00( 0/ 26) :

5 l l 0.0M*00- 0.00E*00 l 0.0X*00( 0/ 131 l 0.00E

001 0/ lat l 0.0M*00- 0.00E *00 l 0.00E +00-- 0.ME *00 l 0

l l l l l l

FE 59 39 30. l 0.00E*00( 0/ 261 l 0.00E

001 0/ 13) : 0.ME

001 0/ 13) :

5 l l

l l 0.00E*M- 0.00E*00 l 0.00E *00- 0.00E *00 l 0.00E*00- 0.0M*00 l 0

l l l l l l CD 60 39 15. 0.00E*001 DI 261 :

0.00E*00( 0/ 13) : 0.00E*00( 0/ 131 l 0 5 :

l l l 0.00E600-- 0.00E* M l l l 0.00E*00- 0.00E*00 l 0.00E*00 - 0.00E+00 l l l l IW-65 39 : 30. 0.00E+00( 0/ 26) :

0.00E*001 0/ 13) : 0.00E+001 13) : 0 E : l l o ox *oo - 0 005*00 l o oot*oo- 0 oot*oo l 0 60t'o'- 2x*00 l 4 5 : : l l l l WB-95 39 l 15. l 0.008+001 0/ 26):

' 0.00E*001 0/ 13) l 0.00E*001 0/ 131l 0 g l l l 0.00E*00- 0.0DE*00 l 0.00E*00-- 0.00D00 g l l l l l 0.00E *00"- 0.0M *00 l l

l 1R-95 39 l 15. : 0.00E *001 0/ 261 l

0.00E*Mt 0/ 13) 0.00E*001 0/ 13) : 0 l l l 0.ME*00-- 0.00D00 l 0.00E+00 0.00E*00 0.00E *00 - 0.00E *00 l l l l 8 l l 131 39 l 15. l 0.0M

001 0/ 26) l l

0.0M*001 0/ 13) : 0.00E*001 0/ 131 l

! l 0

l l l 0.00D00-- 0.00E*00 l 0.00E*00 - 0.00D00 ! 0.00E+00 - 0.00E+00 l

, M l l l l l 5 : CS 134 l

3% l 15. 0.00E*00( 0/ 26: 0.00E*001 0/ 13) : 0.00E + 00( 0/ 13) :

l 0

l l 0.00U 00- 0.00E+00 l

0.0M *00-- 0.00E+00 l 0.00D 00 0.00E*00 l l l l l l l CS 137 39 l 18. l 0.000001 0/ 26) : 0.00E+001 0/ 131 l 0.00D00( 0/ 131 : 0 l l l 0.00E+00- 0.ME*00 l l

0.00D00- 0.00E+00 l 0.00E*00-- 0.MD00 l l l l I

l l SALA Ito ?9 15. l 0.00D00( 0/ 261 l l 0.00D00t 0/ 13) : 0.00D001 0/ 131 : 0 l l 0.00D 00-- 0.00E*00 l 0.00D00-- 0.0M*00 l 0.00E+M-- 0.00D00 l n and range based upon detettable seasuresents only

....... ....................................... ~......................................

ction of detectable seasurteents at sottsfied locatior's is it.ditated in carentheses. (Frattion) tre ran0r indicates no detectable attivitt stesurteents LLD is canal to 0. then LtD is not reouired t>t iethnical Sortificataans mation 060 = Greenville hier intake Location 064 = Seneca. $t lation 066 = AAderson. SC B-Page 101

l (avironarntal Radiological Monitoring Progras Susserv Page : 5 naar of facilitt : Ohl Dottet hunter i 50-269.?"0.287 Lotatfor of f acilitt DCONIf COUNif. S.C. Reporting Period 1-JAW 1991 through di 0f t 1991 11st Report 6erierated 23 JAN 1992 08:41:19 Catabase hase : lil5ti(L!51R.ASC10NS91.SVal l l Location with Highest Mean l l hs of Ptdfu or l Type 6 Ictal : Lo er All incitator : - - --- - - - - - - - - -- ~ ~ ~ - : : kon-I Pathus, l husber of l Lieit of : Locations :.ast. mistante and tirettien : ControlLocattor4 l Routier S.aoled ! Analvses : .tetection : Pean (Frattiont ' Letation Mean (Frattion) : Pean (Fraction) : Froort (Units) ! Frrierned (LLD) : Range : Code Rangt Range l Peas.

Erit;tlh5WAffR l l '

l l :

(FCl/LlilRS) l l l l l

l l l l l 064 (6.7 Pi Sul !

8 ! l l l 066 (19.0Mi $5E) l l

' BETA 39 : 4.0 l 1.5 i 19/ 261 l t.B i 10/ 13) : 1.4 ( 10/ 13) : 0 l l l 0.75 -

3.1 : ul --

3.1 : 0.60 -

1.9 19111D91 : l l l l Cl/LIIIRS) l l ! l l 064 (6.7 Mi SW) l l l l l 066 !!9.' u SSE) l l lH3 15 l 2.00t+03l 5.5BE+02( 1/ 10) l 5.581802l 1/ 5) 0.00E*001 0/ 5) :

Ilocation l l l 5.5BE+02 - 5.5BE+02 : 5.5BE*J7-- 5.5BE*02 : 0.00f+00- 0.00E+00 :

0 an and range based upon detettable seasurteents only action of detettable trasurteents at sortifiti locations is indicated in parentheses. (Frattical tre range indicates no detectable activity atasureernts f LLD is roual is 0. then LLD is not reevired bi Itchnical Sortifications

. cation 060 = Greenville Water Intale location 064

b eta. SC tation 066 = Anderson. SC I

I i

i I

.I I

B-Page 102

I EM ironacotal Radiological Monitoring Prograe Suesary Page : 6 8 ka ne of Facility : DNS Dettet Number- : 50-269.270.287 Location of Facility OCONEE CDUhTV. S.C. Reporting Period i 1*JAN-1991 through 31 DEC-1991 flee Report Benerated 23-JAN-1992 08:41:19 Database Nase DIS!!:! USER.ASC)0NS91.SAF:1 l l l Location with Nighest Mean l l No. of ivpe i Total ! Loaer l All Indicator '--- ---~ ~ ---------- - - --~ ~; l Non-s IMediveor Pathaar Sampled l Naaber of

Analyses Lisit of l

l. Detection !

Locations l Name. Distante and Direction l Control Locations l Routine Mean (Frattion) l Location Mean (fraction) l Mean ' Fraction) l Report (tinits) l Performed (LLD) l Range l fode Range ! Range l Meas.

IISH l l l l l l (PCl/ WET /tG) l' l l l g l l l l l

l 060 12.5 Mi NNE) l l

3 Locations l MN-54 17 ' 1.30E+02 ' O.00E+001 0/ 81 l 0.00E+001 0/ 4) l 0.00E*001 0/ 4) l 0

0.ME+00- 0.00E+00 l 0.00D00-- 0.00D00 l 0.00D 00- 0.00E+00 l l

l l l 063 (0.9 M. ;SE1 l l C0-58 12 l 1.30E+02 . 46. I 1/ Bl l 46. I 1/ 41 ! 0.00E+00( 0/ 4) l 0

. . 46. --

46.

l 46. --

46. l 0.00E+00-- 0.00E*00 l l l l *

.'lup l l l FE 59 12 l 2.60E+02 0.00D00( 0/ B) : 0.00D001 0/ 4) : 0.00E*00I 0/ 4) 0 l l l 0.00D00- 0.00D00 0.00E+00- 0.00E*00 l 0.00D 00-- 0.00D 00 l l l l l l !

l CD-60 12 l 1.30E*02 l 0.00E+00( 0/ B) : 0/ 41 l 0.00DMI 0/ 4) l

' 0.00D00( 0 l l l 0.00D00- 0.00D00 l 0.ME*00- 0.00E*00 0.00D00- 0.00D00 l l '

l l l l l IN 65 12 l 2.60D02 0.00E+00( 0/ 8) :

~.

0.00E+00( 0/ 4) l 0.00D00( 0/ 4) : 0 t

l 0.00E*00 - 0.00E+00 l 0.00E+00-- 0.00D 00 0.00000 - 0.00D00 l l l l l l l he-95 12 l 0.00E*00 l 0.00E*00f 0/ 01 :

0.ME +001 0/ 4) : 0.00E+00( 0/ 4) : 0 O.00E*00-- 0.00E+00 l 5 . . . .

0.00D00 - 0.00D00 0.00D00-- 0.00E+00 l 2R 95 12 0.00D00 l 0.00D00( 0/ 8) :

0.00D001 0/ 4) l 0.00E*00( 0/ 4) : 0 l l O.00E+00- 0.00E+00 l 0.000 00- 0.00E+00 0,00E+00-- 0.00E+00 l

~

1-131 12 l 0.ME*00 l 0.00E6Cc 0/ B) l 0.00E*001 of 4) l 0.00E400( 0/ 4) : 0 I

! ! 0.00E+00-- 0.00E*00 l 0.00D00- 0.00E+00 l 0.00E+00-- 0.00E*00 :

063 (0.8 Mi ESE) l l l CS-134 12 l 1.30D02 l 69. t */ O' 1.25E+02( 2/ 4) : 0.00E+001 0/ 4) : 0 l l l 9.9 -- 1.) W . 1.24E+02-- 1.26E+02 l 0.0nE+00-- 0.00D 00 g . . . . 00 10.9 Mi ESE) l l 3 : CS-137 12 l 1.50E+02l 1.29E+021 8/ 8) : 1.94E+02( 4/ 4) : 14. I 2/ 4) l 0 l- l ! 35. -- 3.49D 02 l 35. -- 3.49E+02 l 13. --

15. l l l l l l

'l'- l BALA-140 12 l 0.00E+00l 0.00E*001 0/ 8) l

. 0.00E+00-- 0.00E+00 0.00D00( 0/ 4) l 0.00E*00( 0/ 4) l 0 0.ME+00-- 0.00E+00 0.00E+00-- 0.00E+00 l hnandrangebasedupondetectableacasurementsonly suhttite ci detectable acasurescats at specified locations is indicated in carentheses. (Fraction)

Zero range indicates no detettable activitt seasureernts

3 LLD is roual to 0, then LLD is not required by lethnical Specifications 5

Locatior 060 = Greenville Water Intake Road ation 063 = Late Hartnell - Highway 183 Bridge aa en 067 = Highway 27 - Laurence Rasse7 Bridge B-Page 103

I Environmental Radiological Monitorine Progras Suenary Page : 7 I Nase of Facilit, 2 DNS Docket Number 50-269.270.287 Letation of Facility 1 DCONEE CDUNTY. $.C. Reporting Period : 1-JAN 1991 through 31-DEE-1991 Time Report Geerrated 23 JAN 1992 08:41:19 Database Naar : HIST 1:! USER. ASE10NS91.5M11

: : : Location with Highest Mean l l No. of j Medive or l Type 6 letal ! Lower : All Indicator ;---------------------~~~---l l Non.

l Pathsay l Nesber of l Limit of : Locations. Nase. Distante and Direction : Eontrol Locations l Routirie Saapled : Analyses l.. Detection l Mean (Frattion) : Location Mean IFraction! l Report l Mean (Traction)

(l'31ts) : Performed l (LLD) : Range : Lode Range Range l Meas.

" MILL : : l l :

(PCl/LliERSI : l l l l l l l : : l 066 (19.0 Mi SSE) l 53 Locations : MN 54 78 : 0.00E*00 ! 0.00E+00t 0/ 52) : 0.00E+00( 0/ 26) : 0.00E+001 0/ 26) l (

l l 0.00E+00~ 0.00E+00 l 0.00E *00-- 0.00E+00 0.00E+00-- 0.00E*00 :

I l l CD-58 l

78 l

l 0.00E+00 l

0.00E*001 0/ 52) l

! 0.00E+00-- 0.00E*00 :

l l 0.00E*001 0/ 261 : 0.00E*00( 0/ 26) :

0.00E+00~ 0.00E*00 l 0.00E*00-- 0.00E*00 "

l 0

l l l l l l l FE-59 18 l 0.00E+0C l 0.0C4001 0/ 52):

8 l l l 0.00E*00-- 0.00E*00 :

0.00E+00I 0/ 26) : 0.00E*00( 0/ 26) :

0.00E*00~ 0.00E*00 l 0.00E+00-- 0.00E+00 l 0

l l- l l l l

! CD-60 78 : 0.00E+00 : 0.00E*001 0/ 521 l 0.00!+00( 0/ 26) : 0.00E+00( 0/ 26) :

I5 : :

l

0.00E+00~ 0.00E+00 l l

0.00E*00-- 0.00E+00 : 0.00E*00- 0.00E*00 l 0

l l l JN-65 '9 0.00E+00 0.00E*001 0/ 52) : 0.00E*00( 0/ 261 : 0.00E+00( 0/ 261 l 0 5

l l 0.00E+00-- 0.00E*00 : 0.00E*00-- 0.00E*00 0.00E+00-- 0.00E+00 l

NB 95 fu 00E+00 0.00E+001 0/ 521 l 0.00E+001 0/ 26) 0.00E *001 0/ 26) l 0

: 0.00E*00-- 0.00E*00 l 0.00E+00 ~ 0.00E+00 l 0.00E*00-- 0.00E*00 :

I l l l l l 1R-95 /^ ' t ?0E*00 l 0.00E+00I 0/ 52) : 0.00E+001 0/ 26) : 0.00E+001 0/ 26) : 0 l 0.00E+00~ 0.00E*00 : 0.00t+00-- 0.00E*00 l 0.00E+00-- 0.00E+00 :

. ! l l l l l-131 78 : 15. : 0.00E*001 0/ 52) : 0.00E*00( 0/ 26) : 0.00E*001 0/ 26) : 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. l lLLI-131 78 l l

1.0 l

1 0.00E*001 0/ 521 :

l l 0.00E+001 0/ 26) : 0.00E*001 0/ 261 l l

0 l l l 0.00E+00-- 0.00E*00 1 0.00E+00 - 0.00 EGO : 0.00E*00-- 0.00E+00 :

l l l l l I l CS-134 78 l 15. : 0.00E+00f 0/ 52) l 0.00E+001 0/ 26) : 0.00E*00( 0! 26) l 0 l l l 0.00E400-- 0.00E+00 l 0.00E*00-- 0.00E+00 0.00E+00-- 0.00E+00

: : 069 (4.5 Mj NNW) l l l CS-137 78 : 18. 5.0 ( 4/ 52) : 5.0 1 4/ 26) : 0.00E+00( 0/ 26) l 0 l l l 1.9 -

9.6 l 1.9 --

9.6 l 0.00E+00~ 0.00E*00 :

! ! ! l l l lBALA-140 78 15. : 0.00E+001 0/ $21 l 0.00E+00( 0/ 261 l 0.00E*00f 0/ 26) : 0 au l l 0.00E+00-- 0.00E+00 l 0.00E+00-- 0.00E+00 l 0.00E+00-- 0.00E+00 !

an and range based upon detectable seasurteents only attim. of detettable seasurements at scerified locations is indicated in parentheses. (Fraction)

Jero range indicates no detectable attivity seasurements f LLD is roual te n, then LLC is not required by 1 ethnical Soetifications Totation J66 = Garrison Dairy

, cation 069 = Orr Dairy ration 071 = Cleeson Dairy B-Page 104

hvirorinental Radiological Monitoririg Program Susaary Page :

s I

Name of facility ONS Docket Number : 50-269.210.267 B Location of facility : OCONIE COUNif. S.C. Reporting Period 1-JAN-1991 through 31 DEC-1991 Tine Report Generated : 23 l Database Nase $tlSrls! USER.ASC)0NS91.SAFil

...........................................~..............................- ........................

8............................-JAN-199211:17:47 l Medius or l

l Type i Total :.. Loser :

All Jndicator l Location with Highest Mean

------ - ------~ ~-- - -------

No. of hon-i Pathmay l Nuat.cr of l Liait of l Locations : Naar. Distar.ce and Direction l Control Locations l Routine Saanled : Analyses : Detection l Mean (Fraction) : Location Mean (Fraction) l Hean (Frattion) l Report (Units) : Performed : (LLD) : hange l Code Rangt : Range : Meas.

gSEDIMENT l l l l l l g(PC1/ DRY /tG) l l l l l l l l l : : 067 (4.2 Mi SSE) : 068 (2.0 Mi W) :

Locations : MA-54 12 : 0.00E+00 l 33. I 1/ 8) : 33. I 1/ 4) : 0.00E+00( 0/ 4) : 0 l l ': 33. -- 33. 33. -- 33. l 0.0nE+00- 0.00E+00 :

l l l l 063 (0.8 Mi ESE) l l

! : C0-50 12 l 0.00E+00 l 56. ( 1/ B) : 56. I 1/ 4) : 0.00E+00( 0/ 4) l 0 l l 56. --

56. l 56. --

56. : 0.00E +00- 0.00E +00 '

8 l l l l l :

l lFE-59 12 0.00E*00 0.00F+00( 0/ 8) : 0.00E*00( 0/ 4) : 0.00E+00( 0/ 4) : 0

. . . 0.00E+00-- 0.00E+00 0.00E *00 . 0.00E+00 0.00E*00-- 0.00E+00 l

'5 : : : : 063 (0.8 Mi ESE1 : :

! : CD-60 12 l 0.00E+00 86. I 1/ B) : 86. ( 1/ 4) : 0.00E+00( 0/ 4) : 0 I

: 86. -- B6. l 86. -- 66. : 0.00E*00-- 0.00E +00 IN-65 12 l 0.00E+00 : 0.00E+00( 0/ 9) : 0.00E+0v( 0/ 41 l 0.00E+00( 0/ 4) : 0 l l l 0.00E+00-- 0.00E *00 0.00E+00-- 0.00E*00 0.00E+00-- 0.00E*00 l

W l

N8-95 l

12 : 0.00E+00 l l l l 0.00E+00( 0/ B) : 0.00E*00( 0/ 4) : 0.00E+001 0/ 4) : 0 I : l l 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E+00 0.00E*00-- 0.00E*00 l l l l l l l l IR 95 12 0.00E*00 0.00E+00( 0/ 8) : 0.00E+00( 0/ 4) : 0.00E+00( 0/ 41 l 0 j ! : : 0.00E+00-- 0.00C+00 0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 .'

1-131 12 h 0.00E+00 l 0.00E+00f 0/ B) h 0.00E*001 0/ 41!0.00E+00( 0/ 4) f 0 l l l 0.00E+00-- 0 A0E*00 :

0.00E+00-- 0.00E+00 l 0.00E+00-- 0.00E*00 :

' 063 (0.8 Mi ESE) l l

05-!?4 12 l 1.50E+02 l 69. ( 1/ B) : 69. I 1/ 4) : 0.00E+001 0/ 4) : 0 l l l 69. - 69. l 69. -

69 : 0.00E*00-- 0.00E+00 :

l l l l l 063 (0.8 Mi ESE) !

l CS-137 12 l 1.80E*02 l 08. I 6/ 9) l 1.24E+02( 3/ 4) : 0.00E+00( 0/ 4) : 0

: : 16. -- 2.71E*02 : 16. -- 2.71E+02 0.00E+00- 0.00E*C0 l l l l l l l l BR A-140 12 : 0.00E+00 : 0,00E*00( 0/ 6) : 0.00E*001 0/ 4) : 0.00E+00( 0/ 4) : 0 i l l : 0.00E+00- 0.00E+00 0.00E+00-- 0.00E*00 : 0.00E*00-- 0.00E*00 :

l Can ar.d range based upon detectable arasurements only I

action of detectable acasurearnts at specified locations is indicated in parentheses. (Fraction)

, to range indicates no detectab!e attivity erasurements Jf LLD is roual to 0, then LLD is not required by Technical Specifications cation 063 = late Hartnell- Highnar 183 Bridge ration 067 = Highway 27 - laurence Raasey Bridge Location 068 = High Falls County Park B-Page 105

l Environerntal Radislogical Monitoring Progras Susaary Page : 9 Waar of Facility : ONS Dette' haber 50-269.270.287 Location of Facilatt OC04EE COUNTY. S.C. Reporting Period : 1 JAN 1991 through 31 DEC-1991 Time Report Generated 23 JAN-1992 08:41:19 Databasr hane SDIS;i:[ USER.ASC10kS91.5AF 1 I Medive or

Type 6 Total l Leser All Indicator

. Location eith Highest Mean l l----------------------------l l No. of l Mon-Pathma, Number of : Limit of : Locations l Nase. Distance and Direction l Control Locations ! Routine 5-Sampled

Analyses l Detection l Mean (Fraction) : Location Mean (Frattion) : Mean (Fraction) l Report (Des ts) l Performed l, (LLD) l Range : Coe Range : Range l Meas.

URFACE WATER ! l l B(PCl/ LITERS) l l l l !

l l l

l l l l 00 (0.7 Mi ENE) :

MN-54 26 : lt. : 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) : 0.00E+00( 0/ 13)l 0 fLocations :; : : 0.00E+00 0.00E+00 l 0.00E*00-- 0.00E*00 ! 0.00E+00 0.00E+00 l : l 063 (0.9 Mi ESE) !

C0-52 26 ! 15. 5.4 ( ll 13) : 5.4 ( 1/ 13) : 0.00E+00( 0/ 13) l 0

! ! : 5.4 -

5.4 l 5.4 -- 5.4 : 0.00D00-- 0.00E+00 l l l l l l l l FE-59 26 : 30. : 0.00D00( 0/ 13; : 0.00D00( 0/ 13) l 0.00E+00( 01 13) : 0 I- l l

l 0.00D00- 0.00D00 0.00E+00-- 0.000 00 l 0.00D 00-- 0.00E*00 l

CD-60 26 : 15. : 0.00E+00( 0/ 13) : 0.00E +00( 0/ 13) : 0.00E+00( 0/ 13)

0 g : : l 0.00D00-- 0.00D00 0.00D00- 0.00E+00 0.00E+00- 0.00E+00 l

-5 '

l 2N-65 26 l 30. : 0.00E+00( 0/ 13) 3.00E+00( 0/ 13) l 0.00E*00( 01 13) : 0 l l l 0.00D00- 0.00E*00 0.00E+00- 0.00D00 0.00D00-- 0.00EiOO :

5 :

l WB-95 26 l l

15.

l

! 0.00D00( 0/ 13) l l

0.00E*00(

l 0/ 13) : 0.00D00( 0/ 13) :

l 0

: 0.00D00-- 0.00D00 l 0.00E+00-- 0.00D00 l 0.00D00-- 0.00D00 l l l I l 2R-95 26 l 15. l 0.00E+00( 0/ 13) : 0.00E*00( 0/ 13) : 0.00E+00t 0/ 131 l 0

l 0.00E+00- 0.00E*00 : 0.00E*00- 0.00i+00 1 0.00E+00- 0.00D00 l

l l l I- ; 1-131 l

26 l l

15. ! 0.vCD00( 0/ 13) :

l 0.00E+00-- 0.000 00 l 0.00E+00f 0/ 13) ' O 00D00( 0/ 131 l 0 0.00E+00- 0.00E+00 0.00D 00-- 0.00E*00 l l l l l l l

C5-134 26 l 5 l' l

15. l 0.00E*001 0/ 13) :

0.00E+00-- 0.00D 00 0,00E+00( 0/ 13) : 0.00D00(

0.00D 00-- 0.00E+00 0/ 13 ' l 0.00E+00-- 0.00D 00 l 0

l l ! l l

' g : C5-137 26 : 18. : 0.00D00( 0/ 13) : 0.00E+00( 0/ 13) l 0.00D00( 0/ 13) :

l 0

3 l l l 0.00D00-- 0.00E*00 l 0.00D00-- 0.00E*00 0.000 00 - 0.00E+00 l l l l l

l

BAL A-140 26 !$. l 0.00E+00( 0/ 13) 0.00D00( 0/ 13) : 0.00D001 0/ 13) : 0 l

tTRiflUM l l

l l 0.00D 00 - 0.00E+00 l

! l 0.00E+00-- 0.000 00 l

0.00E+00-- 0.00E+00 :

l (PCl/ LITERS) l l l '

l l l l 5 l H-3 10 l 2.00D 03 l 5.76D0H 4/ 5) !

l 063 (0.9 Mi ESE) 5.76D03( 4/ $1 l 0.00D00( 0/ 5) :

l 0

l : l 4.52D 03-- 6.289 03 l 4.520 03- 6.28E N3 l 0.00D00-- 0.00D00 l n and range based upon detectable seasurteents only Frattion of detectable seasurements at scerified locations is inditated in parentheses, iFraction) o range indicates no detectable attivity seasuresents LLD is toual to 0 theo LLA is det reaufred by Technical Sortifications Location 062 = Late teovee/ Hydro intatt

, gation 063 = Lake Hartwell . Highway 183 Bridge W B-Page 106

I Enrironeettel Radiological Monitoring Progree Suasary Page : 10 Nase of Facility : DNS Docket Number 50 269.210.287 Location of Facility : OCOMEt COUNTY, S.C. Reporting Period : 1 JAN 1991 through 314EC-1991

.$ " a Report Generated : 23 JAN 1992 00:40:09 Database Nase HISti [US(R. ASC)0NS91.SAFi l R.. ........................... ................................................................................................

l l l l Location eith Highest Mean l l No of

i tte i Total : Lower l All Indicator l------ - ------------------- --! l Non-IMediusorFathmar

$5epled l Nueber of l Limit of l Analyses :. Detection l Locations ! Nase Distante and Direction l Control Locatic,as l Routine l Mean (Fraction) l Location Mean (Fraction) Mean (Fraction) l Report flinits) l Performed l 'lLLD) l Range l Code Range l Range l Meas.

IRECT RAD-ILD l l l l l l (eR/DTR) l l l l l l l l l l 059f9.0 Mi NW) l 058 110.0 M kSW) l 50Litations! mR/DTR 155 0.00E+00 l 17. ( 151/ 151) l 26. ( 4/ 4) l 22. l 4/ 41 l 0

; 7.1 -- 29. l 22. --

28. l 19. --

25. l an and range based upon detectable seasuresents only rattien of detectable seasurteents at specified lotetions is indstated in parentheses. (Fraction) era range indicates no detectable activity seasurements i LLP is equal to 0, then LLD is not recuired by Technical Specifications location 059 : Tasassee DAR School i

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I APPENDIX C SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSES I. SAMPLING DEVIATIONS The deviations from sampling procedures that occurred during 1991 are listed bel'ow.

A. AIR FILTER / CARTRIDGE

1. Location #074, 7/9/91 to 7/16/91 Reason: Due to an apparent power failure, the sampler ran only 79.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months out of a normal 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months sempling.

Action: Replaced fuse and restarted sampler. Actual run time was 79.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. SVRTACE WATER

1. Location 4062, 12/26/90 to 1/22/91 Reason: Sampler was inadvertently left off on the last collection date. No composite sample was available.

Action: A " grab" sample was collected. Actual sampling period was 1/22/91.

2.

~

Location #063, 5/14/91 to 6/11/91 Reason: Due to composite pump being out of order from 5/14/91 to i 5/27/91, a full composite sample was unavailable.

Action: An abbreviated sample was collected. A work request was written when the problem was noticed and daily collections of " grab" samples were collected. Actual sampling period was 5/20/91 to 6/11/91.

3. Location #062, 9/5/91 to 10/1/91 I Reason: Due to the breaker to the pump tripping sometime between 9/9/91 to 9/12/91, a full composite sample was unavailable.

Action: Breaker was reset with no other problems. An abbreviated sample was collected. Ac' al sampling period was 9/5/91 C-Page 108 5

g.--

I to 9/9/91 and 9/12/91 to 10/1/91.

f II. UNAVAILABLE ANALYSES The following unavailable analyses occurred during 1991.

A. AIR FILTER / CARTRIDGE

1. Location #061, 2/19/91 to ?/26/91 RcArdm: -Due to the correct sample having been thrown away, no sample was available, Action: Replaced filter / cartridge and restarted sampler. Extra samples will be kept until the end of each week in case the mistake occurs again.

2. Location #072, 2/19/91 to 2/26/91 Reason: Due to the correct sample having been thrown away, no sample iras available.

Action: Replaced filter / cartridge and restarted sampler. Extra samples will be kept until the end of each week in case the mistake occurs again.

3. Location #072, 10/29/91 to 11/5/91 Reason: Due to a short in the power supply line, the sampler ran only 5 minutes out of a normal 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months sampling period.

Action: A-new power supply line was run to the sampling site.

Power was restored on 11/5/91 at 14:00.

B. DIRECT RADIATION (TLD'S)

1. Location #024, 12/12/90 to 3/13/91 Re s. son s - TLD was found to be missing on 3/13/91 due to unknown reasons.

Action: A new TLD was placed in the field on 3/13/91,

2. Location #051, 12/12/90 to 3/13/91 ~

Beason: TLD was found to be missing on 3/13/91 due unknown reascns.

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hi. tion: A new TLD was placed in a diff erent location in the field on 3/13/91.

3. Loestion #039, 6/12/91 to 9/18/91 Reason: TLD was found to be missing on 9/18/91 due unknown reasons.

Action: A new TLD was placed in the field on 9/18/91.

4. f,ocation #42, 9/12/91 to 12/12/91 4

Reason: TLD was found to be missing on 12/12/91 due to unknown reasons.

Action: A new TLD was placed in the field on 12/12/91.

5. Lt ::ation #39, 9/12/91 to 12/12/91

~

Reason: TLD was found to be missing on 12/12/91 due to unknown reasons.

M112D: A new TLD was placed in a different iocation in the field on 12/12/91.

The majority of samples scheduled were successfully collected and analyzed.

-Of those sample types having deviations, 98% of the air samples, 88% of the

l. surface water samples, and 96% of the TLDs were available without any deviations associated with them.

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{ C-Page 110 1

APPENDIX D ANALYT: CAL DEVIATIONS L

I. ANALYTICAL DEVIATICllS No analytical deviations occurred during the calendar year 1991.

_ Note: No lower limits of detection were exceeded for any analyses performed for 1991.

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