Text

Annual Radiological Environ Operating Rept 1996
	ML20140F272
Person / Time
Site:	Catawba
Issue date:	12/31/1996
From:	Mccollum W; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9705020207
	Download: ML20140F272 (120)
	v • d • e

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Duke thour Company H1a mtR.AldnLLUM,JR Catauha Nudcar Generation Department Lice Preudent l

4SW ConcordRoad (8WJDI-EM 0ffire turk. SC29715 (803)331J116 Fax DUKEPOWER l

April 29, 1997 U.

S. Nuclear Regulatory Commission l

ATTN:

Document Control Desk Washington, DC 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 1996 Annual Radiological Environmental Operating Report i

i Pursuant to Technical Specification 6.9.1.6, find attached the 1996 Annual Radiological Environmental Operating Report.

This report covers the operation of Catawba Units 1 and 2 during the 1996 calendar year.

Sincerely, C

W.

R. McCollum, Jr.

KEN /96REOR Attachment xc:

(*w/o attachment) f L. A.

Reyes, Regional Administrator P.

S. Tam, ONRR

R.

J.

Freudenberger, SRI 020000 l

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT for j

DUKE POWER COMPANY CATAWBA NUCLEAR STATION Units 1 and 2 January 1 - December 31 1996 l

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t TABLE OF CONTENTS 1

j TITLE PAGE I

List of Figures iv List of Tables v

List of Acronyms.

vi 1.

Executive Summary.

1-1 2-1 2.

Introduction 2.1 Site Description and Sample Locations.

2-1 2.2 Scope and Requirements of Environmental Monitoring Program 2-1 2.3 Statistical and Calculational Methodology 2-2 2.3.1 Estimation of the Mean Value.

2-2 2.3.2 Lower Level of Detection, Minimum Detectable Activity, and Critical Level 2-3 2-4 2.3.3 Trend Identification 3.

Radiological Environmental Monitoring Program - Discussion, Interpretation, and Trending of Results.

3-1 3.1 Airbome Radiciodine and Particulates.

3-3 3-5 3.2 Ground Water 3.3 Drinking Water.

3-6 3.4 Surface Water 3-8 3.5 Milk 3-10 3.6 BroadleafVegetation 3-11 3.7 Shoreline Sediment.

3-13 3.8 Fish 3-16 i

l 3

3.9 Direct Gamma Radiation (TLD) 3-19 3.10 Food Products 3-21 l

i 3.11 Bottom Sediment 3-22 3.12 Land Use Census 3-25 4.

Evaluation of Dose from Environmental Measurements Verses

)

Estimated Dose from Releases 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-2 4.3 Comparison of Doses.

4-3 5.

Quality Assurance 5-1 5.1 Duke Power Company Environmental Laboratories 5-1 5.2 Contractor Laboratories 5-3 l

6.

References 6-1 i

Appendix A: Environmental Sample and Analysis Procedures - Summary A-1 1

I.

Change of Sampling Procedures A-1 II. Description of Analysis Procedures.

A-1 III. Change of Analysis Procedures.

A-2 IV. Sampling and Analysis Procedures.

A-2 A.1 Airborne Particulate and Radiciodine.

A-2 A.2 Drinking Water.

A-3 A.3 Surface Water A-3 A.4 Milk A-3 A.5 BroadleafVegetation A-3 A.6 Shoreline Sediment.

A-4 A.7 Fish A-4 A.8 Direct Gamma Radiation (TLD)

A-4 ii

A.9 Food Products A-4 A.10 Ground Water A-5 A.11 Annual Land Use Census A-5 V.

Program Improvements A-5 Appendix B: Radiological Environmental Monitoring Program - Results Summary Air Particulate B-1 Air Radiciodine.

B-2 BroadLeafVegetation B-3 i

Food Products B-4 j

Drinking Water.

B-5 Fish B-6 Ground Water B-7 Milk B-8 Shoreline Sediment.

B-9 Surface Water B-10 Direct Gamma Radiation (TLD)

B-11 Appendix C: Sampling Deviations and Unavailable Analyses C.1 Sampling Deviations.

C-1 C.2 Unavailable Analyses.

C-1 Appendix D: Analytical Deviations - Lower Limits of Detection D-1 Appendix E: Radiological Environmental Monitoring Program Results.

E-1 iii

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l LIST OF FIGURES FIGURE TITLE PAGE l

2.1-1 Sampling Locations Map (TLDs) 2-7 2.1-2 Sampling Locations Map (ten mile radius) 2-8 3.1 Air Particulate Gross Beta Concentrations 3-4 3.3 Drinking Water Tritium Concentrations.

3-7 3.4 Surface Water Tritium Concentrations 3-8 3.6 Broad Leaf Vegetation Cs-137 Concentrations 3-12 3.7-A Shoreline Sediment Co-58 Concentrations 3-14 3.7-B Shoreline Sediment Co-60 Concentrations 3-15 3.8-A Fish Co-58 Concentrations 3-17 3.8-B Fish Co-60 Concentrations 3-18 3.9 TLD Exposure from Direct Gamma Radiation 3-20 3.10 Food Products Annual Mean Concentrations.

3-21 3.11-A Bottom Sediment Sampling Locations in CNS Discharge Canal 3-22 3.11-B Bottom Sediment Annual Mean Concentrations.

3-24 3.12 Land Use Census Map 3-27 iv

LIST OF TABlLES TABLE TITLE PAGE 2.1 -A Radiological Monitoring Program Sampling Locations (TLD).

2-5 2.1 -B Radiological Monitoring Program Sampling Locations.

2-6 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-9 2.2-B REMP Analysis Frequency 2-10 2.2-C Lower Limit of Detection Capabilities for Environmental Sample Analysis.

2-11 3.1 Air Radiciodine Annual Mean Concentrations 3-3 3.3 Drinking Water Annual Mean Concentrations 3-6 3.4 Surface Water Annual Mean Concentrations.

39 3.5 Milk Annual Mean Concentrations.

3-10 4

3.6 Vegetation Annual Mean Concentrations 3-11 3.7 Shoreline Sediment Mean Annual Concentrations 3-13 3.8 Fish Annual Mean Concentrations 3-16 3.9 Exposure from Direct Gamma Radiation 3-19 3.11 Bottom Sediment Annual Mean Concentrations 3-23 3.12 Annual Land Use Census 3-26 4.1-A Environmental and Effluent Dose Comparison for Liquid and Gaseous Waste Release Pathways 4-5 4.1-B Maximum Individual Dose Summary for 1996 4-7 5.0-A Duke Power Company Interlaboratory Comparison Program 5-4 5: B State of North Carolina DEHNR 1995 Environmental Dosimeter Cross-Check Results 5-7 C.1 Sampling Deviations.

C-1 C.2 Unavailable Analyses.

C-1 Y

LIST OF ACRONYMS Acronyms and their interpretations used in this report (displayed alphabetically)

ACRONYM DEFINITION BW Biweekly C

Control CL Critical Level DEllNR Department of Environmental Health and Natural Resources DHEC Department of flealth and Environmental Control EPA Environmental Protection Agency LLD Lower Limit of Detection M

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

ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picoeurie per cubic meter Q

Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECliSPECs Technical Specifications TLD Thermoluminescent Dosimeter pCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W

Weekly Vi

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Catawba Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 1996.

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

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs). Required analyses were performed and detection capabilities were met for all samples as required by SLCs. Supplemental analyses were performed for some media for additional information. Nine-hundred fifty-eight samples were analyzed comprising 2900 test results in order to compile data for the 1996 report. Based on the annual land use census, the current number of sampling sites for Catawba Nuclear Station is sufficient.

Concentrations observed in the environment in 1996 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs.

Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 0.902 mrem for 1996. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

section 1 Page I

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Duke Power Company's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse Electric Corporation. Each generating unit is designed to produce a net electrical output of approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7,1985, and May 8,1986, respectively.

Condenser cooling is accomplished utilizing a closed system incorporating cooling towers, instead of using lake water directly. Liquid etfluents are released into Lake Wylie sia the station discharge canal and are not accompanied by the large additional dilution water flow associated with "once-through" condenser cooling. This design results in greater radionuclide concentrations in the discharge canal given comparable liquid effluent source terms.

The CNS Radiological Environmental Monitoring Program sampling locations are summarized in Tables 2.1-A and 2.1-B. Table 2.1-A lists the environmental Thennoluminescent Dosimeter locations. Table 2.1-B lists all other sampling locations. The REMP sampling and analysis procedures are summarized in Appendix A.

Figures 2.1-1 and 2.1-2 are maps depicting the specific positions of all REMP sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within one mile of CNS. Figure 2.1-2 comprises all remaining locations.

2.2 SCOPE AND REQUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM An environmental monitoring program has been in effcet at Catawba Nuclear Station since 1981, four years prior to operation of Unit 1 in 1985. The preoperational program provides data on the existing emironmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.

The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency section 2 - Page i

and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of ctelion origin from natural or other " man-made" environmental radioactivity. The environment 41 monitoring program also verifies projected and anticipated radionuclide concentrations 'n the environment and related exposures from releases of radionuclides from Catawb i Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Append x 1 to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public and state and federal agencies concerned with the environment.

Reporting levels for activity found in environmental sa.nples are listed in Table 2.2-A.

Table 2.2-B lists the REMP analysis and frequency senedule.

The Annual Land Use Census, required by Selected Licensee Commitments, ir, performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the REMP are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results e shown in Table 3.12.

Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision an.1 accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

1 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE 1

There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sarnpling and analysis of the various media in the REMP. The following equation was used to estimate the menn (reference 6.8):

N Ex,

[

o. I N

Where:

x = estimate of the mean, Section 2 - Page 2

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

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

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

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

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

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

2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. Since nuclear reactor operations do not remove radioactivity from the surrounding environment, a decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities section 2. Page 3 L

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

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

l section 2 - Page 4

TAHLE 2.1-A CATAWHA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location Distance Sector Site Location Distance Sector 200 SITE flOUblDARY 0.6 mi NNE 233 4-5 MILE RADIUS 3.9 mi ENE 201 SITE BOUNDARY 0.5 mi NE 234 4-5 MILE RADIUS 4.5 mi E

202' SITE BOUNDARY 0.6 mi E

235 4-5 MILE RADIUS 3.9 mi ESE 203 SITE 110UNDARY 0.4 mi ESli 236 4-5 MILE R ADIUS 4.3 mi SE 204 SITE ilOUNDARY 0.5 mi SSW 237 4-5 MILE RADIUS 4.8 mi SSE 205 SITE BOUNDARY 0.3 mi SW 238 4-5 MILE RADIUS 4.0 mi S

206 SITE BOUNDARY 0.7 mi WNW 239 4-5 MILE RADi'JS 4.5 mi SSW 207 SITE BOUNDARY 0.9 mi NNW 240 4-5 MILE RADIUS 4.1 mi SW 212 SPECIAL INTEREST 3.3 mi E

241 4-5 MILE RADIUS 4.6 mi WSW 217 CONTROL 10.3 mi SSli 242 4-5 Mll 'if.ADIUS 4.6 mi W

222 SITE BOUNDARY 0.7 mi N

243 4-5 Mit> gOlUS 4.4 mi WNW 223 SITE BOUNDARY 0.6 mi E

244 4-5 MILE RADIUS 4.0 mi NW 224*

SITE BOUNDARY 0.6 mi ESE 245 4-5 MILE RADIUS 4.1 mi NNW 225 SITE BOUNDARY 0.7 mi SE 246 SPECIAL INTI! REST 7.8 mi ENE 226 SITli BOUNDARY 0.5 mi S

247 CONTROL 7.3 mi ESE 227 SITE BOUNDARY 0.5 mi WSW 248 SPECIAL INTEREST 6.6 mi S

228 SITE BOUNDARY 0.6 mi W

249 SPECIAL INTEREST 8.1 mi S

229 SITE BOUNDARY 0.8 mi NW 250 SPECIAL INTEREST 10.4 mi WSW 230 4-5 MILE RADIUS 4.4 mi N

251 CONTROL 9.7 mi WNW 231 4 5 MILE RADIUS 4.2 mi NNE 255 "

SITE ilOUNDARY 0.6 mi ENE_

232 4-5 MILE RADIUS 4.1 mi NE 256 "

SITE BOUNDARY 0.6 mi SSE

Deleted 09/l4/89

" Added 09/14/89 l

Section 2 - Page 5

TABLE 2el-H CATAWHA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS TABLE 2.1 11 CODliS W

Weekly SM Semimonthly BW Biweekly Q

Quarterly M

Monthly SA Semiannually C

Control N8*

Location Descrintion

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Veg. (b) 200 Site Boundary (0.6 mi NNE)

W M

201 Site Doundary (0.5 mi NE)

W M

205 Site boundary (0.3 mi SW)

W 208 Discharge Canal (0.5 mi S)

BW SA SA 209 Dairy (6.0 mi SSW)

SM 210 Ebenezer Access (2.3 mi SE)

SA 21i Wylie Dam (4.0 mi ESE)

HW 212 Tega Cay (3.3 mi E)

W 214 Rock flill Water Supply (7.3 mi SE)

BW 215 River Pointe - ilwy 49 (4.2 mi NNE) CON I ROL llW SA 216 Hwy 4911 ridge (4.0 mi NNE) CONTROL SA 217 Rock Hill Substation (10.3 mi SSE) CONTROL W

218 Belmont Water Supply (13.4 mi NNE) CON'I ROL BW M

219 Dairy (5.7 mi SW)

SM 221 Dairy (14.5 mi NW) CONTROL SM 226 Site Boundary (0.5 mi S)

M 252 Residence (0.7 mi SW)

Q 253 Irrigated Gardens (Downstream within 5 mile radius)

M(a) 254 Residence (0.8 mi N)

Q (a) During liarvest Season (b) When Available i

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Section 2 Page 6

Catawba Nuclear Station Figure 2.1-1 Sarnpling Locations Map (Site Boundary) a 1

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'ntim 2 - Page 8

TAHLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Air Food Analysis Water Particulates Fish Milk Products (pCi/ liter) or Gases (pCi/kg-wet)

(pCi/ liter)

(pCi/kg-wet)

(pCi/m')

H3 20,000

Mn54 1,000 30,000 Fe59 400 10,000 CoS8 1,000 30,000 Co60 300 10,000 Zn65 300 20,000 Zr-Nb-95 400 1131 2

0.9 3

goo Cs134 30 10 1,000 60 1,000 Cs137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of30.000 pCi/ liter may be used.

l l

Section 2 - Page 9

TABLE 2.2-B REMP ANALYSIS FREQUENCY SAMPLE ANALYSIS GAMMA TRITIUM LOW GROSS TLD MEDIUM SCHEDULE ISOTOPIC LEVEL BETA 1-131 Air Radioiodine Weekly X

Air Weekly X

Particulates Quarterly X

Composite Direct Radiation X

Quarterly Monthly Surface Composite X

Water Quarterly Composite X

Biweekly X

Monthly Drinking Composite X

X Water Quarterly Composite X

Shoreline Sediment Semiannually X

Milk Semimonthly X

X Fish Semiannually X

Broadleaf Monthly Vegetation (when X

available)

Monthly Food Products (during X

harvest season)

Section 2. Page 10

i TABLE 2.2-C LOWER LIMIT OF DETECTION (LLD)

CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Air Analysis Water Particulates Fish Milk Food Sediment (pCi/ liter) or Gases (pCi/kg-wet)

(pCi/ liter)

Products (pCi/kg-dry) 3 (pCi/m )

(pCi/kg-wet)

Gross Beta 4

0.01 H3 2000(*)

Mn54 15 130 Fe59 30 260 CoS8,60 15 130 Zn65 30 260 Zr-Nb-95 15 1131 1*

0.07 1

60 Csl34 15 0.05 130 15 60 150 Cs137 18 0.06 150 18 80 180 Ba-La 140 15 15 (a) Ifno drinking waterpathway exists, a vahte of3000 pCi/ liter may be used.

(b) Ifno drinking waterpathway exists, the LLD ofgamma isotopic analysis may be used.

f l

Section 2. Page 11

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS In addition to the required sampling and analyses described in Selected Licensee Commitments Table 16.11-7, the following supplemental measures were taken in 1996.

These measures were first adopted in 1986 to improve assessment of the impact of CNS operations on the environment.

1) Shoreline sediment (required collection at one point along CNS discharge canal, Location 208) was collected at three points (Locations 208-1S,208-2S and 208-3S).

2) Shoreline sediment (required collection semiannually) was collected quarterly. The first and third quarter samples from Locations 208-IS,210 and 215 are considered requhed samples and all remaining samples are considered supplemental.

3) Fish (required collection from Location 208 and 216 semiannually) were collected quarterly. Second and fourth quarter samples are the required samples and the first and third quarter samples are supplemental.

4) Bottom sediment (not required to be collected) was collected quarterly at Locations 208-1M,208-2M and 208-3M. These are all supplemental samples.

Review of all 1996 REMP analysis results was performed to identify changes in environmental levels as a result of station operations. The following section depicts and explains the review of these results. Sample data for 1996 was compared to preoperational and historical data. Over the years of operation, analysis and collection changes have taken place that do not allow direct comparisons for some data collected from 1984 (preoperational) through 1996.

Summary tables containing 1996 information required by Technical Specification Administrative Control 6.9.1.6 are located in Appendix B. These tables contain data based upon required sample results and supplemental sample results.

Section 3 - Page i

Evaluation for significant trends was performed for radionuclides that are listed as required within Selected Licensee Commitments 16.11-8. The radionuclides include: H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, I-131, Cs-134, Cs-137, Ba-140 and La-140. Gross beta analysis results were trended for drinking water and gross beta trending for air particulates was initiated in 1996.

A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related to NRC reporting levels (Table 2.2) were used as criteria for trending conclusions. All 1996 maximum percentages of reporting levels were well below the 100% action level. The highest value noted during 1996 was 49% for surface water tritium collected during fourth quarter at discharge canal Location 208.

Selected Licensee Commitment section 16.11-13 addresses actions to be taken if radionuclides other than those required are detected in samples collected. The occurrences of these radionuclides are the result of CNS liquid effluents which contained the radionuclides.

Dunng 1979-1986, all net activity results (sample minus background), both positive and negative, were included in calculations of sample mean. A change in the RAES gamma spectroscopy system on September 1,1987, decreased the number of measurements y'.elding detectable low-level activity for indicator and control location samples. It was t wught that the method used by the previous system was vulnerable to false-positive results.

All 1996 sample analysis results were reviewed to detect and identify significant trends.

Tables and graphs are used throughout this section to display data from effluent-based radionuclides identified since the system change in late 1987. All negative concentration values were replaced with zero for calculation purposes. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels.

Review of all 1996 data presented in this section supports the conclusion that there were no significant changes in environmental radionuclide concentrations in samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.

(

i section 3 - Page 2

I 3.1 AIRBORNE RADIOIODINE AND PARTICULATES 1

During 1996,260 radioiodine samples were analyzed via gamma spectroscopy,52 from four indicator locations and 52 from one control location.

There was no detectable I-131 in air samples analyzed in 1996. Table 3.1 shows the highest indicator annual mean and control location annual mean for I-131 since 1984 (preoperational period).

Table 3.1 Air Radiolodine Annual Mean Concentrations Y ear Indicator Location C o n trol Location 1984 1.3 0 E -0 3 1.4 6 E -0 2 1985 4.7 5 E -0 3 2.3 8 E -0 3 1986 1.4 3 b -0 2 1.0 2 E -0 2 1987 I.3 8 E -0 2 0.0 0 E + 0 0 1988 0.0 0 E + 0 0 0.0 0 E + 0 0 1989 0.00E+00 0.0 0 E + 0 0 1990 0.0 0 E + 0 0 0.UUE+00 1991 0.0 0 E + 0 0 0.0 0 E + 0 0 1992 0.0 0 E + 0 0 0.0 0 E + 0 0 1993 0.00 E + 0 0 0.0 0 E + 0 0 1994 0.00E+00 0.0 0 b + 0 0 1995 0.0 0 E + 0 0 0.0 0 E + 0 0 1996 0.0 0 E + 0 0 0.0 0 E + 0 0 During 1996, K-40 and Be-7 which occur naturally, were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was detected on three of the cartridges, but not on any of the particulate filters. The detection of Cs-137 on the charcoal cartridges was determined in 1990 to be an active constituent of the charcoal (reference 6.5). Therefore, the Cs-137 activity was not used in any dose calculations in Section 4.0 of this report.

There were no detectable gamma emitters identified for particulate filters analyzed during 1996.

Gross beta analysis is performed on particulate filters. Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the

)

control location samples during 1996. The two sample locations' results are similar in concentration and have varied negligibly since preoperational periods.

section 3 - Page 3

Figure 3.1 Air Particulate Gross Heta Concentrations 1.30E-01.

9.00E-02 8.00E-02 i

l a{ 7.00E-02

=

l g 6.00E-02 5 5.00E-02 i

, 4.00E-02 H

8 g 3.00E-02 2.00E-02 {

e 1.00E-02 4

0.00E+00 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year

-+ indicator Location

-+ Control Location l

l I

l section 3. Page 4 l

L

3.2 GROUND WATER A total of four ground water samples were collected and analyzed for gamma emitters.

There are two indicator locations and no control locations. Naturally occurring K-40 was the only radionuclide identified during 1996.

There have been no radionuclides identified in ground water samples since 1988. Only naturally occurring K-40 and Be-7 were identified.

Section 3 - Page 5

3.3 DRINKING WATER During 1996, gross beta and gamma spectroscopy were performed on 26 drinking water samples. The samples were composited to create 8 quarterly samples that were analyzed for tritiwn. Two indicator locations were sampled, along with one control location.

Table 3.3 shows highest annual mean gross beta concentrations for the indicator location and control location since 1984. The indicator location (downstream of the plant effluent release point) average concentration was 3.08 pCi/l in 1996 and the control location concentration was 3.14 pCi/1. The 1995 indicator mean was 4.80 pCi/1. The table shows that 1996 gross beta levels are not statistically different from preoperational concentrations.

Table 3.3 Drinkine Water Annual Mean Concentrations Gross Beta Tritium Year Indicator Location Control Location Indicator Location Control Location 1984 4.72 1.83 3.10E-02 3.10E-02 1985 2.70 2.24 4.13E+02 4.00E+02 1986 3.11 2.26 7.23E+02 7.33E+02 1987 3.10 2.40 7.80E+02 4.80E+02 1988 3.60 2.60 6.64E+02 0.00E+00 1989 3.60 2.90 8.91 E+02 5.72E+02 1990 4.50 3.20 7.03E+02 0.00E+00 1991 3.70 2.20 7.04E+02 0.00E+00 1992 3.20 2.40 7.65E+02 5.38E+02 1993 3.50 2.50 7.06E+02 0.00E+00 1994 3.30 2.70 0.00E+00 0.00E+00 1995 4.80 4.50 4.28E+02 2.21 E+02 1996 3.08 3.14 3.71 E+02 3.27E+02 Average 3.61 2.68 5.50E+02 2.52E+02 0.00 = no detectable activity measurements 1984-1986 mean based on ALL net activity Tritium was detected at low levels in all samples during 1996. The mean concentration was 371 pCi/1,1.85% of reporting level. In 1995, only one sample from each location resulted in positive tritium activity. The 1995 mean concentration for the indicator location was 428 pCi/l and the mean for the control was 221 pCi/1. Table 3.3 and Figure section 3. Page 6

3.3 display the highest indicator and control location annual means for tritium since 1984. Comparison of the locations and results since 1988 show stable to decreasing concentrations.

Fleure 3.3 Drinkine Water Tritium Concentrations 3.00E+03. -

2.50E6 ------------------------------------------------.

2.00E+03 ------------------------------------------------.

s A.50E+03 1

9z 1.mE+03 - ------------------------ ----------------------.

0 5.00E+02- ----- ------ ------

--- ---.-- --------------j O me+m :.

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year

_+-Indcator Location

-e-Controllocahon No gamma emitting radionuclides were identified in 1996 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.

section 3 Page 7

3.4 SURFACE WATER During 1996,39 monthly surface water samples were analyzed for gamma emitting radionuclides. The samples were composited to create 12 quarterly samples for tritium analysis. Two indicator locations and one control location were sampled. One indicator location (208) is located near the liquid effluent discharge point.

Tritium was the only radionuclide identified in surface water samples collected during 1996. The highest annual mean tritium concentration for all indicator locations was 3921 pCi/1, which is 19.6% of the reporting limit. Indicator Location 208 (Discharge Canal) showed a range of reporting levels from 23.7% to 49% The control sample highest annual mean for 1996 was 261 pCi/l. The 1995 mean concentration for Location 208 was 4170 pCi/1.

Figure 3.4 displays the indicator and control annual means for tritium since 1984. Table 3.4 lists indicator annual means.

Figure 3.4 Surface Water Tritium Concentrations 1.00E+04 9.00E+03 - --_-------------.---.. ----__-----__-----____-------.

8.00E+03 ----------------------- ---------- ---_---- - __---__j 7.00E+03 6.00E+03

+-- H-3

n. 5.00E+03

-. 5.-Contml 2 4.00E+03 3.00E+03 2.00E+03 - ------

---__---_-_--------)

1.00E+03

--- -------- I 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year Section 3 - Page 8

Table 3.4 summarizes gamma spectroscopy results for surface water samples collected since 1984. In addition, tritium concentrations for Location 208 and control Location 715 are shown. Data shows a relatively stable to slightly increasing trend for tritium and small, sporadic indications of gamma emitting radionuclides routinely identified in plant effluents.

Table 3.4 Surface Water Annual Mean Concentrations Year Co-58 Co-60 Nb-95 Cs-137 H-3 (208)

H-3 (215) 1984 4.59E-01 5.71 E-01 6.48E-01 9.08E-01 3.35E+02 3.18E+02 1985 3.46E+00 4.83E-02 2.70E+00 8.19E-01 1.19E+03 5.05E+02 1986 3.10E-01

-4.12E-02 2.05E+00 4.85E-01 2.34E+03 5.05E+02 1987 0.00E+00 3.10E+00 4.30E+00 9.90E+00 4.17E+03 6.20E+02 1988 9.20E+00 0.00E+00 0.00E+00 0.00E+00 6.03E+03 6.07E+02 1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.27E+03 0.00E+00 1990 6.50E+00 0.00E+00 0.00E+00 0.00E+00 3.98E+03 7.73E+02 1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.87E+0f 0.00E+00 1992 0.00E+00 0.00E FOO 0.00E+00 0.00E+00 6.91E+03 6.64E+02 1993 4.70E+00 1.80E+00 0.00E+00 0.00E+00 5.98E+03 0.00E+00 1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.42E+03 0.00E+00 1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.13E+03 2.89E+02 1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.36E+03 2.61 E+02 0.00E0 = no detectable activity measurements 1984-1986 mean based on ALL net activity Section 3 - Page 9

P 3.5 MILK During 1996, a total of 78 milk samples was analyzed via gamma spectroscopy and low level iodine during 1996. Samples were collected from two indicator locations and one control location sampled.

One gamma emitting radionuclide was identified in one indicator sample during 1996.

Cs-137 was detected at a concentration of 6.05 pCi/1, which is 8.5% of the reporting level. The occurrence of Cs-137 in milk samples has been noted several times since 1984.

During 1995 there was also one sample analy. ed in which Cs-137 was identified with a concentration of 8.6 pCi/1. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.

Table 3.5 lists highest indicator location and control location annual mean for Cs-137 since 1984. Concentrations are similar for the two sample types. Cs-137 is the only l

radionuclide, other than K-40 and Be-7, reported in milk samples since 1988.

l Table 3.5 Milk Annual Mean Concentrations (Cs-137 oCi/l) i Year Indicator Location C ontrol Location 1984 2.95 2.98 1985 2.11 2.12 1986 3.76 4.54 l

1987 5.00 5.50 1988 3.20 3.80 1989 0.00 0.00 1990 8.00 6.70 1991 0.00 0.00 1992 3.40 5.00 1993 5.00 0.00 1994 2.80 0.00 1995 8.60 0.00 1996 6.05 0.00 A ve ra g e 3.91 2.36 0.00E0 = no detectable activity measurements 1984-1986 mean based on ALL net activity i

I l

section 3 - Page 10

i 3.6 BROADLEAF VEGETATION l

During 1996, gamma spectroscopy was performed on 47 broadleaf vegetation samples.

i Three indicator locations and one control location were sampled.

Cs-137 was detected in six of the twelve samples collected at Location 201 and the highest concentration was 112.30 pCi/kg. Eight of the thirty-five samples collected at all indicator locations contained detectable Cs-137 activity. The control location produced i

only one sample with Cs-137 activity, which was 62.19 pCi/kg (3.1% of reporting level). Cs-137 results for 1996 were slightly higher than 1995 results.

During 1996, Cs-137 was not detected in airborne effluents from Catawba. Although, Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.

Naturally occurring K-40 and Be-7 were observed in broadleaf vegetation samples.

Table 3.6 Venetation Annual Mean Concentrations (Cs-137 pCi/ke)

Year In dicator Location C o n trol Loca tion 1984 3.7 6 E + 01 1.3 0 E + 01 1985 5.48E+01 4.16 E + 01 1986 7.4 2 E + 01 2.2 2 E + 01 1987 6.10 E + 01 5.10E+01 1988 9.10 E + 01 7.4 0 E + 01 1989 1.0 0 E + 0 2 4.8 0 E + 01 1990 7.7 0 E + 01 5.80E+01 1991 1.9 8 E + 0 2 8.6 0 E + 01 1992 9.7 0 E + 01 0.0 0 E + 0 0 1993 1.13 E + 0 2 3.2 0 E + 01 1994 7.0 0 E + 01 0.0 0 E + 0 0 1995 3.6 0 E + 01 0.0 0 E + 0 0 1996 2.2 3 E + 0 2 6.2 2 E + 01 A ve ra g e 9.4 8 E + 01 3.7 S E + 01 1984-1986 mean based on ALL net activity results section 3 Page 11

4 1

i Figure 3.6 Hroad Leaf Venetation Cs_I37 Concentrations 1

5.00E+02

~ ~ _

)

4.50E+02 ___________________ ___.________.__________________

)

4.00E+02 -__________________________________________._______

3.50E+02.________________________________ _______._________

3.00E+02 e 2.50E+02 Q 2.00E+02 1.50E+02 j

1 1.00E+02

__t 5.00E+01 I

1 0.00E+00 3 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year l

+1ndicator Location g Control Location l

i l

Section 3 - Page 12 l

l

3.7 SHORELINE SEDIMENT l

During 1996, a total of 20 shoreline sediment samples was analyzed, four from indicator Location 210 and 12 from indicator Location 208 (subdivided into discharge canal sites 208-IS,208-2S and 208-3S). Co-58, Co-60, Cs-137 and Mn-54 were identified in l

samples collected from Location 208. Location 208 is closest to the plant's liquid effluent release point. Four samples were analyzed from control Location 215. The control sample analyses detected no radionuclides other than naturally occurring l

K-40.

The shoreline sediment location with the highest annual mean for all detectable radionuclides was Location 208-IS. Cs-137 was identified with an annual mean concentration of 82 pCi/ dry-kg. Other radionuclides identified during 1996 included Sb-125, K-40 and Be-7. Table 3.7 lists highest indicator location annual mean since 1984.

Included in the table are radionuclides that have been identified in shoreline sediment samples since 1988.

Table 3.7 Shordine Sediment Mean Annual Concentrations (nCi/kg-drv)

Ycar 14 54 Co-58 O>60 lW95 Zr-95 Q-1.M G 137 Co-57 bb.125 19&4 1.03E+00 4.40E+00

-234E+00 0.00E+00 0.00E+00 3.19E+01 1.07E+02 0.00E+00 0.00E+00 1985

-3.12E+00 1.16E+02 5.18EK)0 0.00E+00 0.00E+00 2.llE+02 2.97E+02 0.00E400 0.00E+00 1986 1.09E+02 3.79E402 2.05E+02 0.00E+00 3.96E+0) 6.50E+01 1.61E402 0.00E+00 0.00E400 1987 8.83E401 4.08E+02 1.61E+02 422E+01 0.00E+00 6.08E+01 126E+02 0.00E400 0.00E+00 1988 1.07E+02 3.29E+02 2.63E+02 228E+01 7.54E+00 2.59E+01 1.07E+02 7.65501 3.68E+00 1989 4.58E+01 1.94E+02 1.21E+02 5.02E40 0.00E+00 1.65E401 5.77E+01 0.00E400 1.57E+01 1990 539E+01 2.08E+02 1.77E402 0.00E+r0 0.00E+00 1.66E+01 8.18E+01 0.00E40C 7.15E400

~

1991 8.50E+01 3.70E+02 4.19E+02 530E+00 0.00Ed)0 1.82E+01 833E+01 1.20E+0C 1.50E+01 1992 1.17E+02 1.13E+03 5.80E+02 3.50E400 0.00E+00 1.69E+01 1.07E+02 3.00E+00

7 70E+01 1993 133E+02 1.07E+03 1.(ME+03 0.00E+00 0.00E+00 2.80E401 1.26E+02 2.47E+01 2.16E+02 1994 4.93E401 7.98E+02 5.73E+02 0.00E+00 0.00E+00 5.67E+00 1.07E+02 438E400 4.60E401 1995 1.02E+02 133E403 8.65E+02 1.13E+02 0.00E400 0.00E+00 8.50E+01 3.69E+01 1.49E+02 1996 8.73E+01 339E+02 5.81E+02 0.00E+00 0.00E+00 0.00E+00 830E401 0.00E400 1.96E402 0.00E0 = no detectable activity measurements 1984-1986 mean based on ALL net activity results Negative values are calculated as zeros I

secuon 3 - Page 13 l

I.

i Figure 3.7-A depicts Co-58 annual mean concentrations from 1984 through 1996.

Co-58 has been a major contributor to the calculated dose from shoreline sediment since 1986. From these graphs the trend for Co-58 is apparent. The accumulation of the radionuclides over time is significant based on radiological half-life and the direct correlation to actual concentrations released in liquid effluents. Concentrations of Co-58 were significantly lower during 1996 compared to 1995 (339 pCi/kg and 1330 pCi/kg).

Therefore, observations of these trends show that environmental removal processes have not overcome the accumulation of annual activity released via liquid effluents in shoreline sediment samples at least through 1995.

Finure 3.7-A Shoreline Sediment Co-58 Concentrations 2.00E+03 1.80E+03 1.60E+03 1.40E+03 D 1.20E+03 V

g 1.00E+03 g 8.00E+02 6.00E+02 4.00E+02 2.D e T

0.00E+00 L 0

e 0

e e

c e

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year

--$--- Control

--g---lrKICMOr diOn l

l l

l Section 3 Page 14

Figure 3.7_B depicts Co-60 annual mean concentrations. Co_60 has also been a major contributor to the calculated dose from shoreline sediment since 1986. Accumulation of the radionuclide over time is significant based on radiological half-life and the direct correlation to actual concentrations which have been released in liquid effluents.

Concentrations of Co-60 have increased since 1989 and since 1992 have been relatively stable.

Fleure 3.7_B Shoreline Sediment Co-60 Concentrations 2.E+03. - __._ __ __ - -_-- -

1.80E+03 1.60E+03 1.40E+03. - - - - - - -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.

b 1.20E+03

'P y 1.00E+03

=

Q 8.00E4Q 6.00E43.-_____________________________________________

4.00E402 2.00E+02 0.00E400 n 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year l

--+-- CanEel

] --G-IrdcatorLocatidi ~-]

section 3 - Page 15 l

-_ -=

3.8 FISH During 1996, gamma spectroscopy was performed on 24 fish samples collected from one downstream indicator location and one control location. Analyses identified Co-58, Co-60 and Cs-137 as the pcedominant radionuclides. Six of twelve indicator location samples contained Co-58 and Cs-137. The highest average concentration for Co-58 in l

indicator location samples was 59.5 pCi/kg (0.20% of reporting level). For Cs-137 in l

indicator location samples, the highest average concentration was 30.2 pCi/kg (1.5% of l

reporting level). The highest individual sample concentrations were as follows: Co-58, 49.06 pCi/kg (0.16 % of reporting level), Co-60, 94.62 pCi/kg (0.95% of reporting level) l and Cs-137, 55.28 pCi/kg (2.8% of reporting level). These values are lower than those reported in 1995.

Three of twelve control location samples contained Co-58 (highest annual mean concentration of 49.1 pCi/kg) and Cs-137 (highest annual mean concentration of 25.1 pCi/kg).

In addition,1996 sample results for fish collected at indicator Location 208 were trended by fish type. Results show that all radionuclide detection frequencies and concentrations are higher for forager fish than for predator and bottom feeding fish. Similar results have been noted from 1990 through 1995.

Table 3.8 depicts the highest indicator location annual mean for radionuclides detected.

l However, only radionuclides identified in fish samples since 1988 are ircluded in the table. Overall, radionuclides have not shown a significant trend or accumulation since 1988.

l Table 3.8 Fish Mean Annual Concentration (pCi/kd Year Wh44 CoS Co40 Os.134 C&137 Pbe5 Fe4iB S>122 S>125 1984 10?E+00 a00E+00 611E41

-5.32E+00 1.mE+00 00T+00 000E+00 00T+00 00E+00 1985 7.6 1-01 a40E+01 9.11E400 122E+00 1.28E+01 5.07E+00 0.00E+00 0.00E+00 000E+00 1986 201E+01 1.86E+02 4.01E+01 151E+01 9.29E+01 000E+00 7.13E+00 0.00E+00 0.00E+00 1987 724E+00 7.57E+01 4.81E+01 383E+00 427E+01 540E+00 0.00E+00 0.00E+00 000E+00 1988 2.85E+01 1.40E+G2 9.70E+01 1.67E+01 824E+01 000E+00 000E+00 000E+00 000E+00 19E a28E+00 1.33E+G2 183E+01 1.47E+01 4.37E+01 858E41 000E+00 000E+00 000E+00 l

1990 251E+01 1.75E+G2 7.77E+01 1.32E+01 4.66E+01 a TE+00 0.00E+00 7.00E+00 925E+00 1991 115E+01 1.4GE+02 1.29E+G2 1.CGE401 4.60E+01 7.90E-01 2.30E+00 000E+00 7.45E+00 1982 1.34E+01 9.02E+01

&20E+01 127E+01 4.61E+01 000E+(0 0.00E+00 0.00E+00 000E+00 1993 2.14E+01 158E+02 121E+02 2.73E+00 256E+01 QOOE400 000E+00 000E+00 000E+00 l

19EM 1.91E+00 4.75E+01 1.81E+01 000E+00 1.75E+01 000E+00 0.00E+00 0.00E+00 1.45E+01 1995 5.65E+01

&90E+02 2.66E402 000E+00 677E+01 1.38E+01 0.00E+00 000E+00 000E+00 1996 0.00E+00 595E+01 668E+01 000E400 aQ2E+01 000E+00 0.00E+00 0.00E+00 000E+00 0.00E0 = no detectable activity measurements t

section 3 - Page 16

Figures 3.8-A displays annual mean concentrations for Co-58 which has been major i

calculated dose contributors from ingestion of fish since 1988. Concentrations of l

Co-58 in fish have followed a direct pattern with Co-58 concentrations in liquid effluents I

released from the plant. The addition of supplemental samples in 1986, has provided additional data to assist in this continuing correlation between radionuclide concentration in indicator fish samples and radionuclide concentration released via the liquid effluent pathway.

Figure 3.8-A Fish Co-58 Concentrations 3.00E+03 2.75E+03 i

2.5E+03 2.25 E G...__________________-----__________________________________ _

2. E +03 a

5 1.75E+03

1. 1.50E+03 - --_______._______________________________________________ _

9 1.25E+03 oo 1.00E+03 7.50E+02 -...---------__---------______________________--_________ _.---

5.EG 2.5TG

_____1____________

i f

5 5

0.00E @ ::

19EM 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year l

- -+--Irdcator

--g-Contral l

)

Section 3 Page 17 l

i I

i Figures 3.8-B displays annual mean concentrations for Co-60, another major calculated dose contributor from ingestion of fish since 1988. Concentrations of Co-60 detected in fish samples have also followed a direct pattern with Co-60 concentrations in liquid effluents released from the plant. The addition of supplemental samples in 1986 has provided additional data to assist in this continuing correlation between radionuclide i

concentration in indicator fish samples and radionuclide concentration released via the liquid effluent pathway.

Naturally occurring K-40 was observed in fish samples collected during 1996.

Figure 3.8-H Fish Co-60 Concentrations 1.00E+03 ---

i 7.50E+02 -

I ms N.00E+02 5

4 2.50E+02 l

0.00E+00 ::

=

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year l

-+-Indicator

--G-. Control l

Section 3 - Page 18

3.9 DIRECT GAMMA RADIATION Forty thermoluminescent dosimeters (TLD's) are located in the vicinity of CNS to monitor direct gamma radiation. The TLD locations are divided into four subgroups:

control locations (3), site boundary ring locations (16),4-5 mile ring locations (16), and special interest locations (5). A total of 154 TLDs were recovered from the field and processed. During 1996, the highest annual mean exposure was 109 milliroentgen (mR), measured from indicator Location 203 (0.4 miles, ESE of the station). The annual mean exposure for a control location was 64 mR. Five TI Ss were not recovered due to damage or loss while in the field.

The calculated total body dose from gaseous effluents for 1996 was 0.0458 mrem, which is <0.03% of the measured TLD values. It can therefore be concluded that gaseous effluent discharges from CNS had very little impact upon the measured TLD values during 1996.

Table 3.9 shows TLD exposure from direct gamma radiation for the period 1984 through 1996. Inner ring average, outer ring average and control annual averages are showTi in mR per year.

Table 3.9 TLD Exposure from Direct Gamma Radiation Year Inner Ring

Oater Ring

Control Average Average (mR/yr)

(mR/yr)

_I_

(mR/yr) 1984 87.5 82.6 79.3 1985 116.9 108.7 108.9 1986 104.3 98.5 94.4 1987 97.0 87.4 84.7 1988 74.6 70.3 67.1 1989 67.1 60.8 60.0 1990 52.0 44.5 39.1 1991 62.0 54.1 46.7 1992 80.4 72.5 64.5 1993 70.3 60.9 53.6 1994 76.3 69.3 63.9 1995 99.6 89.7 80.8 1996 84.3 73.9 63.6 Average 82.5 74.9 69.7 Inner Ring = Site Boundary Outer Ring = 4-5 Mile Radius from station section 3 - Page 19 I

t l

Figure 3.9 shows TLD exposure from direct gamma radiation for the period 1984 l

through 1996. The graph indicates the highest annual mean for indicator locations and l

control Location 217.

Fleure 3.9 TLD Exposure fron Direct Gamma Radiation i

200.0 180.0 l

160.0 140.0 - ------ ----------------------------__------------ 3 120.0 4---__-----__

4%

I j 100.0 ---- ---

--G-Cartrd 80.0 l 1

60.0 ------__--------------

40.0 20.0 l

0.0 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 Year i

l a

Section 3 - Page 20

3.10 FOOD PRODUCTS Collection of food product samples (crops) from an irrigated garden located on Lake Wylie downstream from CNS (Location 253) began in 1989. During 1996, six samples were collected and analyzed for gamma radionuclides. There is no control location for this sample type.

Only one sample has shown detectable activity since 1989. Figure 3.10 shows Cs-137 indicator location highest annual mean concentrations since 1989.

Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels. This provides the most likely basis for the one occurrence of Cs-137 in food products analyzed since 1989.

Figure 3.10 Food Products Annual Mean Concentrations 1.40E+02 1.20E+02 g

[ 1.00E+02

.x g 8.00E+01 m.

s 6.00E+01 n

3 4.00E+01 o

2.00E+01 0.00E+00.

e 1989 1990 1991 1992 1993 1994 1995 1996 Year

+Cs-137 Indicator Section 3. Page 21

3.11 BOTTOM SEDIMENT Bottom sediment samples are not required to be collected. Samples were first collected during 1986 from three points in the discharge canal following review of shoreline sediment and fish samples collected there. The three points were designated 208-1M, 208-2M and 208-3M (Figure 3.ll-A). Bottom sediment control samples have never been collected.

The following radionuclides were identified in bottom sediment samples collected in

)

1996: Mn-54, Co-58, Co-60 and Cs-137. During 1996, the majority of samples collected contained these radionuclides, as have samples collected and analyzed since 1986. These four radionuclides along with Cs-134 have been predominant in shoreline sediment samples since 1986. In addition, Co-58 and Sb-125 were identified during 1996. All detected radionuclides were attributable to liquid effiuents from CNS during 1996.

l Figure 3.11-A Bottom Sediment Sampline Locations in CNS Discharge Canal i

RL C'5 CHARGE g

I WC 015 CHARGE 208 (35) 2b(LM) f 208 (25)

FLOW I

.Na

"o "'

noAo 1132 satoGt section 3 - Page 22 j

I 1

l l

Table 3.1I shows bottom sediment sample annual mean concentrations for the three sample points at indicator Location 208 (CNS discharge canal) for the period 1986 through 1996. Overall detection frequencies were high and relatively stable throughout this period. Shoreline sediment data also reflected similar concentrations and frequencies for this period.

l From 1986 through 1995, detectable concentrations for bottom sediment correlated well with concentrations released in liquid effluents. One exception was Co-60 which j

exhibited an increasing trend. Over the period of trending, indications show no sigmficant environmental " removal" processes for Co-60.

)

l l

Figure 3.11-B shows annual mean concentrations of the major radionuclide contributors j

identified in bottom sediment from 1986 through 1996: Mn-54, Co-58, Co-60, Cs-137 and Cs-134. In addition, Co-57 and Sb-125 have been identified in samples collected i

since 1988, i

Effluent concentrations from liquid releases during 1996 follow the same changes as the i

annual mean concentrations of radionuclides detected in bottom sediment. Therefore, the impact of plant operation on bottom sediment from Location 208 is at an expected level when considering liquid effluent data for 1996.

Table 3.11 Bottom Sediment Annual Mean Concentrations Year Mn44 Co 58 Co40 IG>95 Co-134 Cs-137 Cr 51 Co47 St>125 1986 3.60E+02 1.09E+03 9.64E+02 6.99E+01 1.71E+02 3.48E+02 0.00E+00 0.00E+00 0.00E+00 1987 5.63E+02 1.34E+03 2.18E+03 6.99E+01 1.10E+02 4.03E+02 0.00E400 0.00E+00 0.00E+00 1988 5.78E+02 9.52E+02 3.18E+03 1.78E+01 1.23E+02 5.70E+02 0.00E+00 5.64E+00 6.2SE+01 1989 3.98E+02 4.47E402 3.42E+03 4.49E+00 1.05E+02 5.04E+02 0.00E+00 4.48E+00 8.11E+01 1990 3.81E+02 5.22E+02 4.12E+03 7.06E+00 9.55E+01 5.06E+02 0.00E+00 4.56E+00 2.15E+02 1991 4.15E+02 5.76E+02 5.10E+03 1.63E+01 8.13E+01 5.02E+02 7.53E+01 8.20E+00 2.13E+02 1992 5.25E+02 1.34E+03 7.10E+03 7.20E+00 4.55E+01 4.94E+02 2.22E+01 1.97E+01 4.33E+02 1993 3.72E+02 1.33E+03 5.79E+03 0.00E+00 7.66E+01 5.38E+02 0.00E+00 1.58E+01 1.33E+03 1994 2.77E+02 1.25E+03 5.32E+03 0.00E+00 0.00E+00 4.27E+02 0.00E+00 1.72E+01 5.98E+02 1995 1.82E+02 8.26E+02 5.12E+03 1.23E+01 6.00E+00 4.11E+02 0.00E+00 1.48E+01 5.68E+02 1996 1.90E+02 4.05E+02 7.22E+03 0.00E+00 0.00E400 4.29E+02 0.00E+00 4.92E+00 6.95E+02 Section 3 Page 23

I 1

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Section 3 - Page 24 l

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i

3.12 LAND USE CENSUS I

The 1996 Annual Land Use Census was conducted July 19 through July 22 as required by SLCs 16.11-14. Table 3.12 summarizes census results. Figure 3.12 contains a map showing identified locations. Sectors shown in Table 3.12 that have no values listed had no corresponding location identified in that sector.

i Based upon 1996 Annual Land Use Census results for nearest residences and gardens, dose evaluations were performea to ensure current air and broadleaf vegetation sampling l

locations complied with requirements of SLCs. No changes to the locations were necessary. The evaluations showed that all existing air and broadleaf vegetation i

sampling locations complied with SLCs requirements. No changes or additions to the locations were required or made as a result of the 1996 census.

l l

section 3 - Page 25

1 I

l Table 3.12 Annual L,and Use Census Date(s) Performed 07/19/96- 07/22/96 i

l Sector Distance Sector Distance (Miles)

(Miles) m N

Nearest Residence 0.64 S

Nearest Residence 0.83 Nearest Garden 1.54 Nearest Garden 0.98 l

Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.87 Nearest Beef Cow 4.05 Nearest Goat Nearest Goat NNE Nearest Residence 0.63 SSW Nearest Residence 0.89 Nearest Garden 2.07 Nearest Garden 0.96 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.04 Nearest Goat Nearest Goat NE Nearest Residence 0.60 SW Nearest Residence 0.65 Nearest Garden 2.39 Nearest Garden 0.66 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 2.59 Nearest Goat Nearest Goat 2.95 ENE Nearest Residence 0.62 WSW Nearest Residence 0.79 Nearest Garden 0.60 Nearest Garden 2.04 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.17 Nearest Beef Cow 2.87 Nearest Goat 1.27 Nearest Goat E

Nearest Residence 0.65 W

Nearest Residence 0.96 Nearest Garden 0.84 Nearest Garden 0.95 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.81 Nearest Goat Nearest Goat ESE Nearest Residence 0.84 WNW Nearest Residence 1.10 Nearest Garden 3.63 Nearest Garden 1.11 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 4.34 Nearest Goat Nearest Goat 3.63 SE Nearest Residence 0.99 NW Nearest Residence 1.31 Nearest Garden 1.52 Nearest Garden 1.52 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.05 Nearest Beef Cow 2.30 Nearest Goat 4.89 Nearest Goat 1.44 SSE Nearest Residence 0.62 NNW Nearest Residence 1.%

Nearest Garden 1.70 Nearest Garden 2.19 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 2.21 Nearest Goat 3.54 Nearest Goat 2.62 I

Section 3 - Page 26 i

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j 4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL l

MEASUREMENTS VERSUS 1

l ESTIMATED DOSE FROM RELEASES 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS i

l l

Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 1996 CNS REMP samples. The primary purpose of estimating doses based on sample results was to allow l

comparison to effluent program dose estimates. Doses based on sample results I

were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates.

Doses based on sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses. Where applicable, average background concentration at the corresponding control l

location was subtracted. Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. When the guide listed "NO DATA" as the dose factor for a given radionuclide and organ, a dose i

factor of zero was assumed.

One radionuclide detected in 1996 REMP samples, Sb-125 had no dose factor i

listed in Regulatory Guide 1.109. The dose factor for Sb-125 was taken from Appendix C, NUREG/CR-1276.

Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, milk, broadleaf vegetation and shoreline sediment sample results are reported in Table 4.1-A.

REMP-based dose estimates were not reported for airbome radioiodine, airborne i

particulate or ground water sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates were not reported for surface water or bottom sediment sample types because sampled surface water is not considered to be a potable drinking water source and t

section 4 - Page 1

l l

sample bottom sediment is permanently submerged. Exposure estimates based I

upon REMP TLD results are discussed on Section 3.9.

The maximum dose to each organ from any single sample type (the " limiting" sample type) other than direct radiation from gaseous effluents was determined I

and reported in Table 4.1-A. For bone, liver, kidney, total body and lung, the l

limiting sample type was broad leaf vegetation, collected at Location 226. The l

maximum organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 1996 was 1.37 mrem to the maximum exposed child's bone from consuming broad leaf vegetation collected at Location 226.

In order to generate REMP-based dose estimates that are comparable to reported effluent-based dose estimates, two additional evaluations were performed:

Maximum 1996 REMP-based dose estimates for drinking water, shoreline sediment and fish sample results were summed to determine maximum total doses for all sampled liquid effluent release pathways. The dose contribution from shoreline sediment to each organ other than skin was assumed equal to total body contribution from shoreline sediment. The maximum total organ dose estimates for the critical age groups are reported on Table 4.1-A. The maximum total organ dose estimate for all liquid release pathways sampled during 1996 was 0.0079 mrem to the maximum exposed adult's GI-LLI. The l

critical pathway was forager fish that accounted for 71% of the total GI-LLI dose of 0.0104 mrem.

Maximum 1996 REMP-based dose estimates for airborne radiciodine, airborne particulate and broadleaf vegetation sample results were summed to determine the maximum total REMP-based doses for all sampled gaseous effluent release pathways. The resulting maximum total organ dose estimates for the critical age groups are reported in Table 4.1-A.

The maximum total organ dose estimate for all gaseous effluent release pathways sampled during 1996 was 2.02 mrem to the maximum exposed child's bone. The l

critical pathway was vegetation which accounted for 68% of the total bone dose.

l 4.2 ESTIMATED DOSE FROM RELEASES l

Throughout the year, dose estimates were calculated based on actual 1996 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the LADTAP and GASPAR computer programs that employ methodology and data presented in NRC Regulatory Guide 1.109. The 1996 CNS Annual Radioactive Effluent Release Report included calendar year dose estimates for the maximum exposed individual from liquid and gaseous effluent releases. Reported i

Section 4 - Page 2

doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimate.

Effluent-based liquid release doses are summations of dose contributions from drinking water, fish and shoreline sediment (estimated for discharge canal) pathways.

The effluent-based gaseous release doses of Table 4.1-A report noble gas exposure and iodine, particulate and tritium exposure. For noble gas exposure I

there is no critical age group as the maximum exposed individuals are assumed to receive the same doses, regardless of age group. For iodine, particulate and l

tritium exposure, maximum total organ dose was 0.064 mrem for thyroid and the l

critical age was child. The critical pathway for exposure was broadleaf l

vegetation.

4.3 COMPARISON OF DOSES Table 4.1-A shows comparisons of REMP-based versus effluent-based maximum dose estimates, critical ages and critical pathways for liquid and gaseous release pathways. As discussed in Part 4.1, REMP-based estimates have been calculated to be analogous to corresponding effluent-based estimates. The estimates can then be compared directly.

One difference between environmental and effluent-based dose estimates is all effluent-based dose estimates include pathway contributions from trititun contained in liquid and gaseous effluents. Drinking water pathways include dose contributions from tritium. Air, milk and broadleaf vegetation pathways do not include a contribution from tritium. Similar differences exist for other radionuclides detected in effluent samples. However, as a result of dilution, transport and radioactive decay, the concentrations are too low to be detected in REMP samples (and their associated dose contributions are therefore not accounted for in REMP-based dose estimates). These differences result in REMP-based dose estimates that are lower in comparison to effluent-based estimates.

Significant levels of tritium and Cs-137 are present throughout the environment and not attributable to CNS effluents. REMP samples often contain these radionuclides, often at detectable levels much greater than levels anticipated due to station effluents. In addition, high variability in the frequency and level that l

tritium and Cs-137 are detected in REMP indicator and control location samples introduce uncertainties when estimating REMP-based dose contributions from net detectable concentrations of the radionuclides. All 1996 REMP-based dose estimates, other than those samples collected at the discharge canal, are entirely attributable to detection of tritium or Cs-137 in corresponding REMP samples.

section 4 Page 3 l

i i

i Doses typically overestimate the true contributions from tritium and Cs-137 released via CNS effluents.

Airborne noble gas samples are not collected as part of the REMP, which prevent an analogous comparison of effluent-based noble gas exposure estimates.

REMP-based dose estimates were lower than the corresponding effluent-based estimates for liquid and gaseous release pathways during 1996. This indicates that the effluent program dose estimates are appropriate and reasonably conservative. Considering current 40CFR190 requirements, no dose limits were exceeded. Doses to members of the public attributable to the operation of CNS are maintained well within regulatory guidelines and limits.

r l

Section 4 - Page 4

i l

TABLE 4.1-A Page 1 of 2 1996 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON FOR LIQUID AND GASEOUS WASTE RELEASE PATHWAYS LIOUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose

E'"

Emuent Data Age Pathway (mrem) l l

Skin Environmental Teen Shoreline Sediment 8.62E-03 1

Skin Effluent Teen Shoreline Sediment 7.18E-02 Bone Environmental Teen Fish 1.65E-02 Bone Effluent Child Fish 4.64E-01 l

l Liver Environmental Teen Fish 3.59E-02 Liver Effluent Teen Fish 6.22E-01 l

T. Body Environmental Teen Fish 3.38E-02 T. Body Effluent Adult Fish 4.02E-01 Thyroid Environmental Teen Fish 2.05E-02 Thyroid Effluent Teen Shoreline Sediment

'.44E-02 Kidney Environmental Teen Fish 2.47E-02 Kidney Effluent Teen Fish 2.64E-01 Lung Environmental Teen Fish 2.21 E-02 Lung Effluent Teen Fish 1.53E-01 GI-LLI Environmental Adult Fish 7.87E-02 GI-LLI Effluent Adult Fish 4.84E-01

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

l Section 4 - Page 5 l

Page 2 of 2 GASEOUS RELEASE PATHWAY Environmental or Critical Critical Maximum Dose 4""

Emuent Data Age Pathway (mrem)

NOBLE GAS EXPOSURE Skin Environmental Not Sampled Skin Emuent N/A Noble Gas 1.04E-01 T. Body Environmental Not Sampled T. Body Emuent N/A Noble Gas 4.58E-02 i

Environmental or Critical Critical Maximum Dose

t 4'"

Emuent Data Age Pathway (mrem)

IODINE, PARTICULATE, and TRITIUM Bone Environmental Child Vegetation 2.02E+00 l

Liver Environmental Child Vegetation 1.94E+00 T. Body Environmental Adult Vegetation 8.69E-01 Thyroid Environmental 0.00E+00 Thyroid Emuent Child Vegetation 6.44E-02 Kidney Environmental Child Vegetation 6.30E-01 Lung Environmental Child Vegetation 2.26E-01 GI-LLI Environmental Adult Vegetation 2.57E-02 0 Maximum dose is a summation of the inhalation, milk and vegetation pathways.

Section 4 - Page 6 1

TABLE 4.1-B Maximum Individual Dosefor 1996 based on Environmental Measurements (mrem)for Cct:wba Nuclear St: tion Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 4.47E-03 4.47E-03 4.47E-03 4.47E-03 4.47E-03 4.47E-03 0.00E+00 Milk 1.04E+00 1.22E+00 8.64E-02 0.00E+00 3.27E-01 1.33E-01 3.81E-03 0.00E+00 TOTAL 1.04E+00 1.22E+00 9.09E-02 4.47E-03 3.31E-01 1.37E-01 8.28E-03 0.00E+00 Child Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 4.56E-03 4.56E-03 4.56E-03 4.56E-03 4.56E-03 4.56E-03 0.00E+00 Milk 6.53E-01 6.25E-01 9.22E-02 0.00E+00 2.04E-01 7.33E-02 3.91E-03 0.00E+00 Broadleaf Vegetation 1.37E+00 1.31E+00 1.93E-01 0.00E+00 4.26E-01 1.53E-01 8.19E-03 0.00E+00 Fish 1.15E-02 2.25E-02 1.82E-02 8.95E-03 1.25E-02 1.02E-02 2.33E-02 0.00E+00 Shoreline Sediment 1.54E-03 1.54E-03 1.54E-03 1.54E-03 1.54E-03 1.54E-03 1.54E-03 1.80E-03 TOTAL 2.04E+00 1.96E+00 3.10E-01 1.51E-02 6.49E-01 2.43E-01 4.15E-02 1.80E-03 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.38E-03 2.38E-03 2.38E-03 2.38E-03 2.38E-03 2.38E-03 0.00E+00 Milk 2.71 E-01 3.61 E-01 1.26E-01 0.00E+00 1.23 E-01 4.77E-02 5.13E-03 0.00E+00 Broadleaf Vegetation 7.56E-01 1.01E+00 3.51 E-01 0.00E+00 3.42E-01 1.33E-01 1.43E-02 0.00E+00 Fish 9.14E-03 2.62E-02 2.22E-02 1.08E-02 1.50E-02 1.24E-02 5.24E-02 0.00E+00 Shoreline Sediment 7.35E-03 7.35E-03 7.35E-03 7.35E-03 7.35E-03 7.35E-03 7.35E-03 8.62E-03 TOTAL 1.04E+00 1.41 E+00 5.09E-01 2.05E-02 4.90E-01 2.03E-01 8.16E-02 8.62E-03 Adult Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 3.37E-03 3.37E-03 3.37E-03 3.37E-03 3.37E-03 3.37E-03 0.00E+00 Milk 1.49E-01 2.04E-01 1.34E-01 0.00E+00 6.94E-02 2.31 E-02 3.96E-03 0.00E+00 Broadleaf Vegetation 8.20E-01 1.12E+00 7.35E-01 0.00E+00 3.81E-01 1.27E-01 2.17E-02 0.00E+00 Fish 8.54E-03 2.89E-02 2.87E-02 1.41E-02 1.81E-02 1.54E-02 7.40E-02 0.00E+00 Shoreline Sediment 1.32E-03 1.32E-03 1.32E-03 1.32E-03 1.32E-03 1.32E-03 1.32E-03 1.54E-03 TOTAL 9.79E-01 1.36E+00 9.02E-01 1.88E-02 4.73E-01 1.70E-01 1.04E-01 1.54E-03 NOTE: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4-Page 7

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t Dosefrom Milk Pathwayfor 1996 Data

+

Maximum Exposed Infant Infant Dose from Milk Pathway (mrem) = Usage (1) m Dose Factor (mrem /pCi ingested) x Concentiation (pCi/t)

Usage Ontakein one year) =

330 I Ilighest Annual Net Mean Investion Dose Factor Concentration Dose (mrem)

Indicater Mith Gedieneclide Bone Liver T. Body nyroid Kidney Long GI-LLI tacetion (pCIA)

Bone Liver T. Body Thyroid Kidney lang GI-LLI I-131 3.59E-05 4.23E-05 1.06E-05 IJ9E-02 4.94 E-05 NO DATA 1.5 t E-06 ALL 6.00 0.00E+00 0.00E+00

.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 3.77E44 7.03E-04 7.IDE45 NO DATA I. ele-04 7.42E-05 I.91 E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

?

Cs-137 5.22E-04 6.ll E-04 4.33E-05 NO DATA I.64E-04 6.64E-05 I.9t E-06 209 6.05 1.04E+00 1.22E+00 0.64E-02 0.00E+00 3.27E41 1.33E-0I

3. ele 43 i

i Bata-840 1.7t E-04 1.71 E-07 0.0lE46 NO DATA 4.06E-00 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1

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Dese Commitment (mrem) =

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Dosefrom Milk Pathwayfor 1996 Data Maximum Exposed Child Chiki Dose from Milk Pathwmy (mrem) = Usage (1) x Dose Factor (mrern/pCiingested) x Concentration (pCL1)

Usage (intake in one year) =

330 I

Highest Annual Net Mean Instestion Dose Factor concentration Dose harem)

Indicator Milk RadionuctiJe Bene IJver T. Bety Thyroid Kidney Imng CI-Lil Imcation (pCla)

Done IJ m T. Body Thyroid Kidney Imng Cl-IJJ I-131 1.72E-05 1.73E45 9.83 E-06 5.72 E-03 2.84E45 NO DATA 1.54E46

AIJ, 0.00 0.00E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00E+00 Cs.134 2.34E44 3.84E44 8.10E45 NO DATA 1.19E-04 4.27E-05 2.07E46 ALL 0.00 0.00E+00 0.00E+00 0.00 E +00 0.00E+00 0.00 E +00 0.00E+00 0.00 E+00 Cs-137 3.27E44 3.13 E-04 4.62E-05 NO DATA 1.02E-04 3 67E-05 1.96E46 209 6.05 6.53 E-01 6.25 E-01 9.22 E42 0.00E+00 2.04E41 7J3 E-02 3.9t E43 Bala-140 0.3 t E-05 7.20 E-08 4.85 E46 NO DATA 2.37E48 4J4E48 4.2t E-05 A11 0.00 0.00 E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 E+00 Dese Commitment (mrem) =

6.53E41 6.25 E41 9.22E-02 0.00 E+00 2.04E41 7.33E-02 3.9t E43

Dosefrom Broadleaf Vegetation Pathwayfor 1996 Data Maximum Etposed Child Child Dese from Vegetation Pathway (mrem) = Usage (kg) Dese Factor (mrem /pCi ingested) x Concentration (pCi/kg)

Usage (intake in.ne year) =

26 kg Highest Annual Net Mean Jonestion Dose Factor Cancentration Dese (mrem)

Indicator Food Radionectide Bene Liver T. Body Thyreld Midney Long CI-LtI Location (pCMg)

Bone IJver T. Body nyroid Kidney -

Lung Cl-LLI l-I3I I.72E-05 1.73005 9.83E-06 S.72003 2.84E-05 NO DATA t.54006 ALL 4.00 0.00E+00 100E+00 0.00E+00 0.00E+89 0.00E+00 8.00E+00 0.e#E+ee Os-134 2.34E-04 3.84E-04 8.10005 NO DATA 1.19E44 4.27E-05 2.07E46 AIL 8.00 8.00E+08 0.00E+00 4.00E+08 0.00E+e8 9.80E+08 8.eeE+4e 4.eeE+ee Os-137 3.2 4 -04 3.13E-04 4.62E-95 NO DATA 1.02004 3.67E45 1.96E-06 226 168.88 f.37E+e8 1.3tE+00 1.93E41 6.0M 40 4.26E41 1.53E41 S.19E43 Dese Commitment (arem) =

1.37E+ee 1.3tE+00 f.93E O' O.00E+98 4.26E-01 1.53E-01 8.19003

I.

Dosefrom Fisit Pathwayfor1996 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dese Factor (mrem /pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCl/l x Bioaccumulation Factor 0.9 pCi/I = 7102 pCill x 0.9 = 6392 pCl/kg Usoge (intake in one year) =

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

Indicater Fish Rodienuclide Bene Liver T. Body Thyroid Kidney Long Gl.LLI Location (pCl/kg)

Bene IJver T. Body Thyroid Kidney Long Cl-1.lJ Mn-54 NO DATA 1.07E-05 2.85006 NO DATA 3.00E-06 NO DATA B.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E 06 5.51 E.06 NO DATA NO DATA NO DATA 1.05E45 208 10.40 0.00E+00 1.29E44 3.95E-04 0.00E+00 0.00E+00 0.00E+00 7.53E-04 Fe.59 1.65E-05 2.67E45 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05

All, 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ED40 NO DATA 5.29E-06 1.56E45 NO DATA NO DATA NO DATA 2.93E45 200 66.80 0.00E+00 2.44E.03 7.19E.03 0.00E+00 0.00E+00 0.00E+00 1.35E42 l

f Zn45 1.37E45 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41 E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(

Os.134 2.34E-04 3.84004 8.10E-05 NO DATA 1.19004 4.27E45 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.33E.04 4.62E-05 NO DATA l.02E-04 3.67E-05 1.96E46 208 5.10 1.15E-02 1.10E42 1.63E43 0.00E+00 3.59E-03 1.29003 6.90E-05

[

H-3 NO DATA 2.03007 2.03E.07 2.03E 07 2.03E47 2.03E47 2.03E47 208 6392.00 0.00E+00 8.95E-03 8.95E-03 8.95E-03 S.95E-03 8.95E-03 8.95003 Dese Commitment (erem) =

1.15E.02 2.25E-02 1.02E-02 S.95E43 1.25E42 1.02 E.02 2.33E-02 i

i t

5

Dosefrom Shoreline Sediment Pathwayfor 1996 Data Maximum Exposed Child Shoreline Recreation =

14 hr (in one year)

Shore Width Factor =

0.2 Sedinient Surface Mass =

40 kg/m2 Child Dese femm Simrline Sedinient Pathway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem /hr per pC1/m2) x Shore Width Factor Sediment Surface Mass (kg/m2) x Sediment Concentration (pGig)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mreniihr per pClim2)

Indicator Sediment (nareen)

Radionuclide T. Body Skin Location (pCl/kg)

T.Bmly Sidn Mn-54 5.80E-09 6.80E-09 208 87.30 5.67E-05 6.65E-05 Co-58 7.00E-09 8.20E-09 208 339.00 2.66E-04 3.11 E-04 Co-60 1.70E-08 2.09E-09 208 581.00 1.11E-03 1.30 E-03 Cs-134 1.20E-08 I.40E-08 208 0.00 0.00E+ 00 0.00E &00 Cs-137 4.20E-09 4.90FA19 208 83.00 3.90E-05 4.56E-05

'Sb-125 3.10E-Ot 3.50E-09 208 196.00 6.81E-05 7.68E-05 Dose Conmiltnient (norem) =

1.54E-03 1.80E 03

Dose Factor fmn Reference 6.11

Dosefrom Drinking Water Pathwayfor 1996 Data Maximum Exposed Teen Teen Dose from Drinking Water Patlawny (mrem) = Usage (1) x Dose Factor (mrem /pCilagest 4) x Concentretion (pCl/I)

Usage tintake nn e.e yeart =

510 i Highest Annual Net Mean Insrestion Dose Factor Concentration Dp.y (mrem)

Indicater Water Radienschte Bene Liver T. Body Thyroid Kidney Long CI-LLI Iment6en (pCL4)

Base Liver T. Body Thyroid kidney Long GI-LLI Me-54 NO DATA S.90E-86 1.17E-86 NO DATA 1.76E-06 NO DATA 1.2 t E-05 ALL 4.00 6.SeE+00 0.00E+0e 0.00E+ee 4.eeE+60 000E+0e e.eeE+ee e.eeE+4e Co-58 NO DATA 9.72E.47 2.24E 46 NO DATA NO DATA NO DATA IJ4E-05 AI.L 4.00 0.00E+0e e.eeE+ee e.eeE+ee

e. nee +00 9.eeE+0e e.eeE+44 0.00E+0e Fs-59 5.87E-e6 1.37E-05 129006 NO DATA NO DATA 4.32E-06 3.24Le5 ALL 0.00 0.00E+ee e.eeE+ee e.eeE+0e 4.06E+00 e.eeE+04 4.80E+90 e.eeE+0e Co.se NO DATA 2.81606 633E ee NO DATA NO DATA NO DATA 3.66FA5 ALL S.00 8.eeE+ee 4.00E+0e 0.00E+00 e.eeE+0e e.eeE+ee 0.00E+0e 0.eeE+es En-65 176E-06 2.etE-85 9.33E-06 NO DATA 1.28E-05 NO DATA e 47E-06 All 4 00 e.eeE+08 0.eeE+00 0.00E+ee eseE+ee 0.00E+0e 4.seE+ee e.seE+0e Nb-95 8.22E-99 4.56E-09 2.S t E-09 NO DATA 4.42 E-09 NO DATA 1.9FE-05 ALL e.ee 0.00E+0e 0.00E+0e e.e0E+0e 0.eeE+0e 8.00E+0e e.eeE+00 9.eeE+0e Er-95 4.12 E-ee 8.3eE-88 8.94E-89 NO DATA t.9 t E48 NO DATA 3 00E-05 ALL 4.08 e.eeE+0e 6.eeE+0e 0.eeE+0e teeE+0e e.80E+0e e.coE+0e e.seE+0e I-131 5.55E-46 8.19E-86 4.40E-06 2.39E-93 1.4 t E-05 NO DATA l.62E-06 ALL 6.00 0.00E+0e

e. nee +80 0.eeE+0e e.SeE+ee e.eeE+00 0.00E+ee e.eeE+0e Cs-134 S.37E-05 t.97F 84 9.34E-05 NO DATA 6.26E.e5 2.39E-45 2.45E46 ALL 0 00 a.etE+ee e.e0E+ee 4.00E+0e e.eeE+0e 0.08E+0e 0.00E+0e e.eeE+ee Cs-837 1.12 E-04 1.49004 S.19E.05 NO DATA 5.07L05 I.97E-05 2.12006 ALL 6.00 0.00E+0e 0.80E+0e e.eeE+00 0.00E+0e e.00E+0e e.eeE+ee e.eeE+0e Bala-148 2.84E-85 3.48E-08 1.83E-06 NO DATA I.18E-te 2.3tE.es 438F 05 ALL 4.00 a.etE+ee e.eeE+80 6.SeE+4e e.eeE+6e 8.00E+00 0.8eE+ee 0.00E+00 H-3 NO DATA I.06E-87 1.06E.07 1.86E-07 5.06Le7 t.06E-67 1.06FA7 214 44.00 4.seE+00 238E.03 2.38FA3 2.38E43 2.38E-83 2J8F 83 1.35E43 Dose Conseiltmens (merene e.08E+6e 2.38E-03 2.38E-03 2.38E-03 2.38E-43 238L43 2.38E43

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Dosefrom Broadleaf Vegetation Pathwayfor 1996 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem /pCi ingested) x Concentration (pCilkg)

Usage (hweke in one year} =

42 kg Highest Annuel Net Mean

.jpgestion Dose Facter Concentration Dose f airein)

Indicator Feed Stedienuclide Bene IJver T. Body Dyroid Kidney Lung GI-l.l.I Leeselon (pCWkg)

Bene IJver T. Body nyrend Kidney Lang Ch-lit 1-131 5.05E-06 0.19E-06 4.40F 86 2.39E-03 1.41E-05 NO DATA 1.62E-06 A11 0.0e 0.00E+00 0.00E+00

0. tee +00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e Cs-134 0.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 All 0.00 0.00E+00 0.00E+0e 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 Cs-137 1.12E-04 1.49E.04 5.19E-05 NO DATA 5.07E-05 8.97E-05 2.12E-06 126 160.09 7.56E-01 f.etE+00 3.5tE 01 0.SeE+00 3.42E-01 1.33E-01 1.43E42 Dese Commhment (mrem)=

7.56E-St

1. ole +00 3.5IE-01 0.8eE+00 3.42E 81 1.33E-08 3.43E-02

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Dosefrom Shoreline Sediment Pathwayfor 1996 Data Maximum Exposed Teen Shoreline Recreatloan -

67 hr (in one year) i Shore width Factor-0.2 Sedinient Sunface Mass =

40 kg/m2 Teen Dese from Sherline Sedhnent Pathway (mrem) = Sherline Recreation (hr) x Extemal Dese Factor (mrem /hr per pOni2) x Shore width Factor x Sedhnent Surface Mass (kg/ni2) x Sedhnent Concentration (pCL%g)

Extential Dese Factor Standing Ifighed AnnualNet Das_e on Contanninated Ground Mean Concentrath.si (mreni/hr per pWm2)

Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pC1/kg)

T. Body Skin Mn-54 5.80E-09 6.80E-09 208 87.30 2.71E-04 3.18E-04 Co-58 7.00E-09 8.20F 09 208 339.00 1.27E-03 1.49F 03 Co-60 1.70E-08 2.00E-08 208 581.00 5.29E-03 6.23E-03 Cs-134 1.20F 08 1.40E-08 208 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 208 83.00 1.87E-04 2.18E-04

Sb-125 3.10E-09 3.50E-09 208 196.00 3.26F 04 3.68F 04 Dose Comunitnient (mrem)=

7.35E-03 8.62E-03

Dose Factor from Reference 6.1I

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i Dosefrom Broadleaf Vegetation Pathwayfor 1996 Data Maximum ExposedAdult Ad1It Dese from Vegetation (mrem) = Usage (kg) u Dose Factor (mrem /pCi ingested) u Concentration (pCi/kg)

U$3ge (intake in one year) =

64 kg Highest Annual Net Mean Ingestion Dosclatlet CD.nfinirat6en Dose (mremi i

indicator reed Radienschde Bene Iber T. Body Thyroid Kidney Long GI Llj Location (pCllkg)

Bene lAer T. Body Thyroid Kidney Long Cl-l LI I

l-131 4.16E-06 5.95E-06 3.41 E-06 1.95E43 l.02Le5 NO DATA l.57E-06 ALL 0.00 0.00E+00 8.8eE+00 8.8eE+08 0.00E+88 0.00E+09 0.00E+00 9.00E+00

[

Cs-134 6.22E45 1.48E44 1.21 E-84 NO DATA 4.79005 1.59E-05 2.59006 ALL 9.90 8.00E+00 0.80E+09 9.96E+00 8.80E+00 0.00E+00 0.euE+48 0.00E+96 i

Cs-137 7.97E.05 1.09E44 7.14E.05 NODATA 3.70005 l.23E-85 2.II E-06 226 160.90 8.20001 1.12E+00 7J5E-01 9.OSE+09 3.81E45 1.27E41 2.17E42 f

Dese Commitment (mrem)=

8.20001 1.12E+00 7.35E41 8.eeE+ee 3.81E41 1.27L61 2.17E-02 a

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I

1 i

Dosefrom Fish Pathwayfor 1996 Data Maximum ExposedAdult 2-Adtil Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem /pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCill x Bioaccumulation Factor 0.9 pCill = 7102 pCill u 0.9 = 6392 pCi/kg Usage (ineeke in one yeer) =

21 kg Highest Annual i

Net Mean Jamestion Dose Factor Concentration Dose f arem)

Radienectide Bene ther T. Body Thyroid Kidney Long GI.l.LI incation (pCl/kg)

Bene IAer T. Body Thyroid Kidney Imag GI-LLI Mn-54 NO DATA 4.57E.86 4.72E-07 NO DATA 1.36E 06 NODATA 1.4eE-05 AIL 4.08 0.08E+99 0.80E+00 0.00E+48 e.08E+00 e.SeE+0e

0. tee +0e e.80E+4e Co-Se NO DATA 7.45E-47 f.47E 86 NO DATA NO DATA NO DATA l.5 t E-05 20e 10.40 e.88E+08 f.63E-04 3.65E-04

e. tee +4e 8.00E+0e 0.eeE+49 3.3eE-43

'r r

Fe-59 4.34E-06 1.02E45 3.9t E46 NO DATA NO DATA 2.05E-86 3.48005 AIL e.88 4.90E+ee 8.seE+0e 0.80E+0e e.00E+00 0.08E+00 e.8eE+40 0.9eE+00 6

Ce40 NO DATA 2.14E-06 4.72E-06 NODATA NO DATA NO DATA 4.02E-05 288 66.80 e.00E+0e 3.89E-03 6.62E43 e.80E+86 4.88E+00 8.08E+08 5.64E-02 ZHS 4.44E-06 1.54095 6.96E-06 NO DATA 1.03E-05 NO DATA 9.7eE-06 ALL 4.00 9.8eE+ee e.e8E+00 0.80E+88 4.00E+ee 8.8eE+0e 8.88E+0e eteeE+et i

i Cn.134 6.22E-85 1.40E-04 1.2 t E44 NOesATA 4.79E-e5 8.59E-05 2.59E-06 ALL 4.00 a.en'iM G.eeE+08 0.00E+00 0.00E+0e CeE+06 e.eeE+ee 8.00E+49 a

s Os-137 7.97E-85 1.09E-04 7.14E45 NO DATA 3.7eE-85 1.23E-05 2.!!E-86 284 5.10 8.54E-03 1.17E-84 7.65E43 9.88E+0e 3.96 E-03 1.32E43 2.26E44 i

15-3 NO DATA 1.e5E-87 1.05E-47 1.05E-87 Le5E-87 1.05E-87 8.95E-07 288 6312.88 0.80E+0e 3.41 E-42 1.41E42 8.41002 f.41E-82 B.41E42 1.41E-92 t

Dese Commitment (erem) =

S.54E-03 2.09E-82 2.07E-82 1.41 E-02 1.0f E42 1.54E42 7.48E-02 L

i l

r v

i 6

m

___.________,_m.._

-__,_m._.-___-_..______m__...m____.-___-_-___._..______m_______.

--z m

a

-w m -- m-

Dosefrom Shoreline Sediment Pathwayfor 1996 Data Maximum ExposedAdult i

Shoreline Recreation =

12 hr(in oneyear)

Shore Width Factor =

0.2 Sediment Surface Mass =

40 kehn2 Adult Dose from Shedine Sediment Pathway (mrem) = Sherline Recreation (hr) x External Dose Factor (mreni/hr per pC1/m2) x Shore width Factor x Sediment Surface Mass (kg/m2) x i

Sediment Concentration (pClag)

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

(mrem /hr per pG/m2)

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

T. Body Skin Mn-54 180E-09 6.80E-09 208 87.30 4.86E-05 170E 05 Co-58 7.00E-09 8.20E-09 208 339.00 2.28E-04 2.67E-04 Co-60 1.70E-08 2.00E-08 208 581.00 9.48E-04 1.12E-03 Cs-134 1.20E-08 1.40E-08 208 0.00 0.00E+00 0.00E+00 i

Cs-137 4.20E-09 4.90E-09 208 83.00 3.35E-05 3.90E-05

Sb-125 3.10E-09 3.50E-09 208 196.00 Ss93E-05 6.59E-05 Dose Conunitment (mrem) =

1.32E-03 1.54E-03

Dose Factor from Reference 6.11

5.0 QUALITY ASSURANCE 5.1 DUKE POWER COMPANY'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.1.2 SAMPLE ANALYSIS The Radiological and Environmental Services Group performed the environmental sample analyses as specified by approved analysis procedures.

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

5.1.4 INTRALABORATORY QUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type ofinstrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

Additionally, National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid.

The frequency is dependent upon instrument use and performance. Investigations are performed and documented when calibration verification data fall out oflimits.

section 5 - Page 1

Radiological and Environmental Services (R&ES) did not participate in the Environmental Protection Agency (EPA) cross check program during 1996 due to the EPA power plant cross-check program being discontinued by EPA. R&ES contracted a similar cross-check program using North American Scientific as the supplier of the cross-checks. Results of these cross-checks are displayed in Table 5.0-A.

5.1.5 INTERLABORATORY OUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISION The Catawba Nuclear Station Radiation Protection Section participated in a Quality Assurance audit in February and March 1995. This audit was conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group. No recommendations pertaining to the Catawba Radiological Environmental Monitoring Program were identified in the audit. No audit was conducted in 1996.

5.1.5.2 DUKE POWER'S INTERCOMPARISON PROGRAM The Radiological and Enviromnental Services group participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1996. Interlaboratory cross-check standards, including Marinelli beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 1996 is documented in Table 5.0-A.

5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION l

INSPECTIONS l

The Catawba Nuclear Station Radiation Protection section was audited by the NRC in February 1996. The Radiological Environmental Monitoring Program Report was reviewed and there were no recommendations as a result of this audit.

Radiological and Environmental Services (R&ES) was not audited by the NRC in 1996, section 5 - Page 2

5.1.5.4 NRC/ STATE OF S.C. INTERCOMPARISON PROG' RAM Radiological and Environmental Services routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program.

Radiological and Environmental Services sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory for intercomparison analysis.

5.1.5.5 STATE OF N.C. TLD INTERCOMPARISON EROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. Every six to eight months, the State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 1996 is documented in Table 5.0-B.

5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1996.

section 5. Page 3

l TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 1996 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gamma in Charcoal Cartridge:

Collection Geometry Nuclide Acceptance Range Reference Value Reported Date (pCi/ total)

(pCi/ total)

Value (pCi/ total) 4/9/96 Cartridge Co-57 1.30E 2.30E-2 1.73E-02 1.93 E-02 Co-60 2.65E 4.69E-02 3.53 E-02 3.87E-02 Y-88 5.60E 9.94E-02 7.47E-02 8.93 E-02 Cd-109 5.36E 9.51E-01 7.15 E-01 7.57E-01 Sn-ll3 3.41 E 6.05E-02 4.55E-02 4.92 E-02 ~

Cs-137 1.64E 2.91 E-02 2.19E-02 2.30E-02 6/1/96 Cartridge Ba-133 1.94E+04 - 3.48E+04 2.62E+04 2.45 E+04 l

Gamma in Marinelli Beaker:

Collection Geometry Nuclide Acceptance Range Reference Value Reported Value Date (pCi/ total)

(pCi/ total)

(pCi/ total) 6/1/96 3.5 liter Cr-51 1.34E+04 - 2.3 8E+04 1.79E+04 1.88E+04 Co-57 8.9E+02 - 1.58E+03 1.19E+03 1.32E+03 Co-60 2.06E+03 - 3.64E+03 2.74 E+03 2.94E+03 Y-88 7.87E+03 - 1.40E+04 1.05E+04 1.07 E+04 Sn-113 3.73E+03 - 6.6iE+03 4.97E+03 5.ISE+03 l

Te-123m 7.83E+02 - 1.39E+03 1.04 E+03 1.01E+03 12/17/96 3.5 liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.43 E+05 Co-60 4.83E+04 - 8.57E+04 6.44E+04 6.24E+04 I-131 5.02E+04 - 8.90E+04 6.69E+04 6.35 E+04 Cs-134 7.14E+04 - 1.27E+05 9.52E+04 8.03E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.06E+04 Section 5 - Page 4 l

l f

l Collection Geometry Nuclide Acceptance Range Reference Value Reported Value Date (pCi/ total)

(pCi/ total)

(pCi/ total) 6/1/96 1.0 liter Cr-51 3.59+04 - 6.37E+04 4.79E+04 4.71 E+04 i

Co-57 2.39E+03 - 4.23 E+03 3.18E+03 3.18E + 03 l

Co-60 5.50E+03 - 9.75B 'l 7.33 E+03 7.50E+03 Y-88 2.1 l E+ 04 - 3.74 E+ 04 2.81 E+04 2.68E+04 Sn-113 9.98E+03 - 1.77E+04 1.33 E+04 1.31E+04 Te-123m 2.10E+03 - 3.72E+03 2.80E+03 2.58E+03 Cs-137 1.04E+04 - 1.84E+04 1.38E+04 1.30E+04 12/17/96 1.0 liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.58E+05 Co-60 4.83 E+04 - 8.57E+04 6.44E+04 6.45 E+04 1-131 5.02E+04 - 8.90E+04 6.69E+04 6.68E+04 Cs-134 7.14E+04 - 1.27E+05 9.52E+04 8.69E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.18E+04 12/17/96 0.$ liter Cr-51 2.00E+05 - 3.54E+05 2.66E+05 2.43 E+05 Co-60 4.83E+04 - 8.57E+04 6.44E+04 6.24 E+04 1-131 5.02E+04 - 8.90E+04 6.69E+04 6.35E+04 Cs-134 7.14E+04 - 1.27E+05 9.52E+04 8.03 E+04 Cs-137 9.00E+03 - 1.60E+04 1.20E+04 1.06E+04 7/11/96 Gamma in Cs-137 1.25E+02 - 2.22E+02 1.67E+02 1.47E+02 Water 7/l1/96 Gamma in Cs-137 1.7 I E+02 - 3.03 E+02 2.28 E+02 1.96E+02 Milk 12/17/96 lodine in 1-131 1.24E+01 - 2.19E+01 1.65E+01 1.80E+01 Water Section 5. Page 5

Gross Beta in Air Particulate:

\\

Collection Geometry Nuclide Acceptance Range Reference Value Reported Date (DPM)

(DPM)

Value (DPM) 4/9/96 Gross Beta Cs-137 1.55 E+04 - 2.74E+04 2.06E+04 2.05 E+04 l

in Air Filter 6/1/96 Gross Beta Cs-137 5.84E+04 - 1.04E+05 7,79E+04 7.21 E+ 04 in Air Filter Tritium:

Collection Geometry Nuclide Acceptance Range Reference Value Reported.

Date (pCi/ liter)

(pCi/ liter)

Value (pCi/ liter) 3/25/96 Tritium in H-3 1.3 I E+05 - 2.33 E+05 1.75E+05 2.23 E+05 Water H-3 3.03 E+06 - 5.37E+06 4.04E+%

4.33 E+06 7/9/96 Tritium i

Water 11-3 5.92E+03 - 1.05E+04 7.89E+ 03 8.22 E+03 l

l l

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Section 5 - Page 6

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TAB;LE 5.0-B STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1996 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS l

Radiation Cross-Check State of N.C.

Dosimetry &

Acceptance Date Delivered Value Records Criteria Reported Value (mR)

+/- 10 %

(mR)

Jun-96 55 51.6 Pass Dec-96 40 38.4 Pass l

l t

l section 5 - Page 7 1

i

6.0 REFERENCES

6.1 Catawba Selected License Commitments 6.2 Catawba Technical Specifications 6.3 Catawba Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 1995 6.6 Catawba Annual Effluent Report 1985 - 1996 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery,1969, pages 287-293.

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

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual 1

Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.

6.10 Radiological and Environmental Services Operating Procedures 6.11 NUREG/CR-1276, Users Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor i

Liquid Effluents.

l i

t I

section 6 - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES i

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l 1

1 APPENDIX A l

ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling r.nd analysis of all environmental media at Catawba Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.

l Environmental sampling and analyses were performed by Radiological and Environmental Services, Dosimetry and Records, Fisheries and Aquatic Ecology.

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

I.

CHANGE OF SAMPLING PROCEDURES No sampling changes were made to the sampling procedure during 1996.

II. DESCRIPTION OF ANALYSIS PROCEDURES l

Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to

(

appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples l

such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.

l l

Low-level iodine analyses are perfonned by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium Appendix A. Page 1

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

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate j

and analyzing by gas-flow proportional counters. Samples are batch processed with a spike sample to verify instrument performance and a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES Weekly gamma spectroscopy analysis of air particulate filters was discontinued for all air sampling sites in 1996. Air particulate filters continue to receive weekly gross beta analysis as required by Selected Licensee Commitments. Gross beta results on a per site basis have historically been less than 10 times the annual mean of the control location. Air particulate filters are segregated by site and composited quarterly for gamma spectroscopy analysis.

Low-Level Iodine-131 (LLI-131) for drmking water was discontinued. This analysis is not required if demonstrated that annual dose from the consumption of water is not greater than 1 mrem. Historical data from 1991 through 1996 indicated that the annual dose from consumption of drmkmg water was less than 1 mrem.

IV. SAMPLING AND ANALYSIS PROCEDURES 1

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

Site Boundary (0.6 mi. NNE)

Location 200

=

Site Boundary (0.5 mi. NE)

Location 201

=

Site Boundary (0.3 mi. SW)

Location 205

=

Tega Cay, SC (3.3 mi. E)

Location 212

=

Rock Hill Substation (10.3 mi. SSE)

Location 217

=

Appendix A-Page 2

l l

A.2 DRINKING WATER l

Biweekly composite dankmg water samples were collected at each of two locations.

i A low-level Iodine-131 analysis was performed on each biweekly composite sample. A gross beta and gamma analysis was performed on monthly composites.

Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.

Rock Hill Water Supply (7.3 mi. SE)

Location 214

=

Belmont Water Supply (13.4 mi. NNE)

Location 218

=

A.3 SURFACE WATER Biweekly composite samples were collected at each of three locations. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.

Discharge Canal (0.5 mi. S)

Location 208

=

Wylie Dam (4.0 mi. ESE)

Location 211

=

River Pointe - Hwy 49 (4.2 mi.NNE)

Location 215

=

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

Wood Dairy -(6.0 mi. SSW)

Location 209

=

Pursley Dairy - (5.7 mi. SW)

Location 219

=

Oates Dairy -(14.5 mi. NW)

Location 221

=

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

Site Boundary (0.6 mi. NNE)

Location 200

=

Site Boundary (0.5 mi. NE)

Location 201

=

Rock Hill Substation (10.3 mi. SSE)

Location 217

=

Site Boundary (0.5 mi. S)

Location 226

=

Appendix A - Page 3

. _

A.6 SHORELINE SEDIMENT l

Semiannual samples were collected at each of three locations. A gamma analysis was performed on each sample following the drying and removal of rocks and 1

clams. The samples were collected from the locations listed below.

l l

Location 208 Discharge Canal (0.5 mi. S)

=

Location 210 Ebenezer Access (2.3 mi. SE)

=

Location 215 River Pointe - Hwy 49 (4.2 mi. NNE)

=

A.7 FISH l

Semiannual samples were collected at each of two locations. A gamma analysis l

was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) l were prepared whole minus the head and tail portions. The samples were collected from the locationslisted below.

i Location 208 Discharge Canal (0.5 mi. S)

=

Location 216 Hwy 49 Bridge (4.0 mi. NNE)

=

l l

A.8 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty locations. A l

gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.

An inner ring of 16 TLDs, one in each meteorological sector in the general area of the site boundary.

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

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

TLD locations are listed in Table 2.1-A.

l A.9 FOOD PRODUCTS Monthly samples were collected when available during the harvest season at one location. A gamma analysis was performed on each sample. The samples were collected from the location listed below.

Location 253 Cloninger Irrigated Garden (2.1 mi. SSE)

=

Appendix A - Page 4

A.10 GROUND WATER Grab samples were collected quarterly from residential wells at each of two locations. A gamma analysis and tritium analysis were performed on each sample.

The samples were collected from the locations listed below.

Residence (0.7 mi. SW)

Location 252

=

Location 254 Residence (0.8 mi. N)

=

A.11 ANNUAL LAND USE CENSUS An Annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

The Nearest Residence The Nearest Meat Animal j

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

This census was inititated on July 19,1996 and completed on July 22,1996.

Results are shown in Table 3.12.

V. PROGRAM IMPROVEMENTS Trending of air sampler and water sampler site locations is performed for continuous identification of problems impacting deviation rate of the Radiological Environmental Monitoring Program.

Each air sampler site has been evaluated for correct grounding, proper voltage range and equipment requirements necessary, including installation of surge and lightning suppressers.

l Modifications were completed during 1996.

Additional equipment upgrades were completed for air samplers and water samplers during 1996. Operation and reliability of the samplers have improved significantly over 1995 performance. A continued program of preventive maintenance, improved equipment quality and trending have proven to be extremely beneficial.

Appendix A Page 5

l APPENDIX B l

\\

l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS l

1996 l

i i

l

l Environmental Radiological Monitoring Program Summary Focility: Catawba Nuclear Station Docket No. 50-413,414 Locction: York County South Carolina Report Period: Ol JAN-1996 to 31 DEC-1996 l

tal h$#

All Indicator E "*

Control ou i e Pathway Limit of Annual Mean Number Locations Location Report Sampled Detection Name, Distance, Direction g

Mm i

Unit of Analyses Mean (Fraction)

Location (LLD)

Mean Range Mean Range Measurement Performed Range Code j

Air Particulate 217 (pCi/m3)

(10.3 mi SSE)

BETA 260 1.00E-02 2.98E-02 (208/208) 212 3.49E-02 (52/52) 2.60E-02 (52/52) 0 5.50E 8.39E-02 (3.3 mi E) 1.06E 8.39E-02 9.80E 4.79E-02 CS134 20 5.00E-02 0.00 (0/16) 0.00 (0%)

'0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 20 6.00E-02 0.00 (0/16) 0.00 (0/4) 0.00(0/4) 0 i

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1131 20 7.00E-02 0.00 (0/16) 0.00 (0/4) 0.00(0/4) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 _._ _ _

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

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments l

i r

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Peport Generated @ 3/18S7 1:38 PM Appendix B - Page 1

Environmental Radiological Monitoring Program Summary Fr.cility: Catawba Nuclear Station Docket No.

50-413,414 Loc:tio2: York County. South Carolina Report Period: 01-JAN-199;

'

DEC-1996 j

yPe and Medium or Lower Location with Highest Total All Indicator Control Routine Pathway Limit of Annual Mean Number Locations Location Report Sampled Detection Name, Distance, Direction of M.cas.

Unit of Analyses Mean (Fraction)

Location (LLD)

Mean Range Mean Range Measurement Performed Range Code Air Radioiodine 217 (pCi/m3)

(10.3 mi SSE)

CSI34 260 5.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 260 6.00E-02 1.23E-02 (3/208) 201 1.29E-02 (1/52) 0.00 (0/52) 0

~

1.13E 1.29E-02 (0.5 mi NE) 1.29E 1.29E-02 0.00 - 0.00 1131 260 7.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments I

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l Report Generated @ 3/18/97 1:40 PM Appendix B Page 2

i Environmental Radiological Monitoring Program Summary i

i Facility: Catantu Nuclear Station Docket No.

50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1996 to 31-DEC-1996 No. of Non-l Medium or Type and Total L,ower Location with liighest y, g; Control Routine l

Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Location

}

""E

"E" Measurement Performed Range Code Broadleaf 217 Vegetation (10.3 mi SSli)

(pCi/kg wet) l CSI34 47 60 0.00 (0/35) 0.00 (0/12) 0.00 (0/12) 0 O.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 47 80 147(8/35) 226 223(2/12) 62.2 (1/12) 0 22.9 423 (0.5 mi S) 22.9 -423 62.2 - 62.2 1I31 47 60 0.00 (0/35) 0.00 (0/12) 0.00 (0/12) 0 l

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only i

Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) l Zero range indicates no detectable activity measurements l

If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments l

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Report Generated @ 3/18/97 1:41 PM Appendix B - Page 3

i Environmental Radiological Monitoring Program Summary i

Focility: Catawba Nuclear Station Docket No.

50-413,414 Location: York County, South Carolina Report Period: Ol-JAN-1996 to 31-DEC-1996 l

Medium or Type and Total Lower Location with Highest Pathway Number Limit or.

All Indicator Control Routme Annual Mean Cah. n Pod Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Locatioa

(

can ange can Range Measurement Performed Range Code Crops NO CONTROL (pCi/kg wet)

LOCATION CSI34 6

60 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0 00 - 0.00 0.00 - 0.00 CS137 6

80 0.00 (0/6)

LOO (0/6) 0.00 (0/6) 0 0.00 0.00 0.0t, - 0.00 0.00 - 0.00 1131 6

60 0.00(0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 UE 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements,

if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 1

j Report Generated @ 3/18/97 1:42 PM Appendix B - Page 4

Environmental Radiological Monitoring Program Suniniary Facility: Catawba Nuclear Station Docket No.

50-413,414 Location: York County, South Carolina Report Period: Ol JAN 1996 to 31-DEC-1996 No. of Non-Medium or Type and Total Lower L cati n with liighest All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction M

Unit or Analyses Mean (Fraction)

Location

""E'

""8' Measurerren Performed Range Code Drinking Wn.

218 (pCi/ liter)

(13.4 mi NNE)

BALAI40 26 15 0.00 (0/I3) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 BETA 26 4

3.08 (13/13) 214 3.08 (13/13) 3.14 (12/13) 0 1.21 - 5.78 (7.3 mi SE) 1.21 - 5.78 1.44 - 8.34 CO58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CC60 26 15 0.00 (0/13) 0.00 (0/I1) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CSI34 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H3 8

2000 371 (4/4) 214 371 (4/4) 327 (4/4) 0 305 473 (7.3 mi SE) 305-473 144 - 447 1131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 MN54 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0$00 0.00 - 0.00 ZN65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/I3) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 ZR95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3/l8/97 1.43 PM Appendix B Page 5

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

50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1996 to 31-DEC-1996*

No. of Non-Medium or Type and Total Lower Location with liighest

,,,g; Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Unit of Analyses Mean (Fraction)

Location

(

""E' "E'

Measurement Performed Range Code Fish 216 (pCi/kg-wet)

(4.0 mi NNE)

C058 24 130 59.5(6/12) 208 59.5 (6/12) 49.1 (1/12) 0 16.0 - 192 (0.5 mi S) 16.0 - 192 49.1 -49.1 CO60 24 130 66.8 (2/12) 208 66.8 (2/12) 0.00 (0/12) 0 38.9 - 94.6 (0.5 mi S) 38.9 - 94.6 0.00 - 0.00 CS134 24 130 0.00 (0/12) 0.00(0/12) 0.00 (0/12) 0 0.00,0.00 0.00 _0.00 0.00 - 0.00 CS137 24 150 30.2 (6/12) 208 30.2 (6/12) 25.1 (2/I2) 0 13.3 - 24.0 (0.5 mi S) 13.3 - 24.0 15.3 - 34.9 FE59 24 260 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 (i.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN54 24 130 O M (0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN65 24 260 0.00 (0/12)_

0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments

Includes allfish samples collectedfor period 1/1/96 - 12/31/96 (First throughfourth quarter sampling)

Report Generated @ 3/18/97 1:45 PM l

Appendix B Page 6

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

50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1996 to 31 DEC-1996 No. of Non-Medium or Type and Total Lower All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction M

Unit of Analyses Mean (Fraction)

Location (LLD)

Mean Range Mean Range Measurement Performed Range Code l

Ground Water NO CONTROL (pCi/ liter)

LOCATION BALA140 4

15 0.00 (0/4) 0.00(0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 C058 4

15 0.00 (0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO60 4

15 0.00 (0/4) 0.00 (0/4) 0.00(0/4) 0 0.00 - 0.00 0.00 - 0.00 0 00 - 0.00 CS134 4

15 0.00 (0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 CSI37 4

I8 0.00 (0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0 00 0.00 - 0.00 0.00 - 0.00 FE59 4

30 0.00(0/4) 0.00(0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 113 4

2000 0.00 (0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1131 4

15 0.00(0/4) _

0.00 (0/4) 0.00 (0/4) 0 0 00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN54 4

15 0.00(0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 0.00 0.00 - 0.00 0.00 0.00 NB95 4

15 0.00 (0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 ZN65 4

30 0.00 (0/4) 0.00(0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0 00 - 0.00 ZR95 4

15 0.00(0/4) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3/l 8/97 1:46 PM Appendix B Page 7

Environmental Radiological Monitoring Program Summary O

Facility: Catawba Nuclear Station Docket No.

50-413.414 Location: York County, South Carolina Report Period: Ol-JAN-1996 to 31-DEC-1996 No. of Non-Medium or Type and Total Lower Location with flighest All Indicator Control Routine Pathway Number Limit of L cati n Report Annual Mean Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Location (LLD)

Mean Range Mean Range Measurement Performed Range Code Milk 221 (pCi/ liter)

(14.5 mi NW)

BALA140 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CSI34 78 15 0.00 (0/52) 0.00(0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 78 18 6.05 (1/52) 209 6.05 (1/26) 0.00 (0/26) 0 6.05 - 6.05 _

(6.0 mi SSW) 6.05 - 6.05 0.00 - 0.00 I131 78 15 0.00 (0/52) 0.00(0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLII31 78 1

0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments e

Report Generated @ 3/18/97 1:47 PM Appendix B - Page 8

?

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

50-413.414 Location: York County, South Carolina Report Period: Ol-JAN-1996 to 31-DEC-1996*

No. of Non-Medium or Type and Total Lower Location with liighest All Indicator Control Routine Pathway Number Limit of Annual Mean PO Sampled of Detection Name, Distance, Direction M

Unit of Analyses Mean (Fraction)

Location

}

can ange Mean Range Measurement F:rformed Range Code Shoreline 215 Sediment (4.2 mi NNE)

(pCi/kg-dry)

C058 20 0

324 (12/16) 208-IS 339 (4/4) 0.00 (0/4) 0 96.7 - 552 188 - 552 0.00 - 0.00 CO60 20 0

51) (12/16) 208-1S 58t t4/4) 0.00 (0/4) 0 177 - 1016 177 - 1016 0.00 - 0.00 CS134 20 150 0.00 (0/16) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS137 20 180 82 (10/16) 208-1S 83.0 (4/4) 0.00 (0/4) 0 26.4 - 126 34.0 - 126 0.00 - 0.00 MN54 20 0

69.7 (9/16) 208-2S 87.3 (2/4) 0.00 (0/4) 0 30.7 - 110 64.5 - l l 0 0.00 - 0.00 SB125 20 0

113 (4/16) 208-IS 196 (1/4) 0.00 (0/4) 0 116 - 243 196 - 196 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses,(Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments

Includes all shoreline sediment collectedforperiod 1/1/96 - 12/31/96 (First throughfourth quarter sampling)

Report Generated @ 3/18/97 1:48 PM Appendix B - Page 9

Environmental Radiological Monitoring Program Sumn ary Facility: Catawba Nuclear Station Docket No.

50-413,414 Location: York County, South Carolina Report Period: Ol-JAN-1976 to 31-DEC-1996 No. of Non-Medium or Type and Total Lower xa nw est All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction M

Unit of Analyses Mean (Fraction)

Location

}

""E*

""E Measurement Performed Range Code Surface Water 215 (pCi/ liter)

(4.2 mi NNE) 11ALA140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 C058 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0 00 0.00 - 0.00 0.00 - 0.00 CS134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CSI37 39 18 0.00(0/26) 0.00 (0/I3) 0.00(0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE59 39 30 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H3 12 2000 392I (8/8) 208 7363 (4/4) 261 (3/4) 0 392 - 9791 (0.5 mi S) 4749 - 9791 167 - 415 l131 39 15 0.00(0/26) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 UN54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 ZN65 39 30 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR95 39 15 0.00 (0/26) 0 00 (0/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3/18/97 1:50 PM Appendix B - Page 10

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

50-413,414 Location: York County, South Carolina Report Period: Ol-JAN-1996 to 31-DEC-1996 No. of Non-Medium or Type and Total Lower ca nw est All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Locat. ion Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Location (LLD)

Mean Range Mean Range Measurement Performed Range Code Direct Radiation 217 (10.0 mi SSE)

TLD 247 (7.5 mi ESE)

(m!UQuarter) 251 (9.8 mi WNW) mR/Qtr 154 0.00E+00 19.4 (142/142) 203 27.3(4/4) 15.9 (12/12) 0 11.3 - 27.9

(.4 mi ESE) 23.9 - 30.7 I1 5 - 21.5 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3/18/97 1:50 PM Appendix B - Page 11

p,...

0 k

J APPENDIX C

+

t >% -

g

. T SAMPLING DEVIATIONS UNAVAILABLE ANALYSES

~

d i

APPENDIX C CATAWBA NUCLEAR STATION SAMPI,ING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES l

13F Blown Fuse PO Power Outage

(

FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample 1 oss/ Lost due to Laboratory Accident LC Line Clog to Sainpler SM Motor / Rotor seized OT Other TF Torn f ilter Pi Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Location Scheduled Actual Henson Corrective Action Collection Dates Collection Dates 205 10/16 - 10/23/96 10/16 - 10/20/96 BF Sampler was removed from service l

and replaced with a new sampler.

C.2 UNAVAILABLE ANALYSES The following unavailables from sampling requirements occurred during 1996:

Ground Water Location Scheduled Reason Corrective Action Collection Dates Sample was not collected. Sample location was missing 252 3/20/96 OT from collection calendar. Performance test requirement 254 6/19/96 was implemented by collection personnel to verify accurate sample collections are performed.

Appendix C - Page 1

TLD Location Scheduled Reason Corrective Action Collection Dates 238 12/29 - 3/28/96 VN TLD missing. 2nd Quarter TLD was placed in field.

241 12/29 - 3/28/96 VN TLD missing. 2nd Quarter TLD was placed in tield.

244 12/29 - 3/28/96 SL TLD was collected but could not be located for analysis in the laboratory.

230 3/28 - 6/27/96 VN TLD missing. 3rd Quarter TLD was placed in field.

244 3/28 - 6/27/96 VN TLD missing. 3rd Quarter TLD was placed in field.

238 3/28 - 6/27/96 VN TLD missing. 3rd Quarter TLD was placed in field.

l Appendix C - Page 2

APPENDIX D ANALYTICAL DEVIATIONS I

No analytical deviar:ons were incurred for the 1996 Radiological Environmental Monitoring Program.

Appendix D - Page i

l APPENDIX E RADIOLOGICAL ENVIRONMENTAL

~

MONITORING PROGRAM RESULTS 1996 This appendix includes all of the sample analysis reports generated from each sample medium for 1996. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

l Appendix E - Page i Y

ML20140F272

Contents

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

. _

SUMMARY

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ML20140F272

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

. _

SUMMARY

Navigation menu

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