ML061360477
| ML061360477 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/11/2006 |
| From: | Jamil D Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML061360477 (94) | |
Text
Duke AvEnergye D.M. JAMIL Vice President Catawba Nuclear Station 4800 Concord Rd. / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax May 11, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Power Company, LLC d/b/a Duke Energy Carolina, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 2005 Annual Radiological Environmental Operating Report Pursuant to Catawba Nuclear Station Technical Specification 5.6.2 and Selected Licensee Commitment 16.11-16, please find attached the 2005 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 2005 calendar year.
There are no commitments contained in this submittal.
Any questions concerning this report should be directed to Kay Nicholson at 803.831.3237.
Dhiaa M. Jamil Attachment xc:
W. D. Travers, Regional Administrator, Region II J. R. Stang, Jr., Senior NRR Project Manager E. F. Guthrie, Senior Resident Inspector -
- 17t'- ',
www. duke-energy. com
_ Duke rPower.
Catawba Nuclear Station Units 1 and 2 AREOR Annual Radiological Environmental Operating Report 2005 E5~
Duke OkPower.
A Duke Eneag Company I
I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY CATAWBA NUCLEAR STATION Units 1 and 2 2005 I
TABLE OF CONTENTS 1.0 Executive Summary.
1-I 2.0 Introduction 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 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 and Minimum Detectable Activity 2-3 2.3.3 Trend Identification.
2-3 3.0 Interpretation of Results.
3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water.
3-4 3.3 Surface Water.
3-6 3.4 Ground Water.
3-8 3.5 Milk.
3-9 3.6 Broadleaf Vegetation.
3-10 3.7 Food Products.
3-12 3.8 Fish.
3-13 3.9 Shoreline Sediment 3-16 3.1 0 Direct Gamma Radiation 3-18 3.11 Land Use Census 3-20 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-1 4.3 Comparison of Doses.
4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis.
5-1 5.4 Laboratory Equipment Quality Assurance.
5-1 5.4.1 Daily Quality Control 5-1 5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Duke Power Intercomparison Program 5-2 5.6 Duke Power Audits.
5-2 5.7 U.S. Nuclear Regulatory Commission Inspections 5-2 5.8 State of South Carolina Intercomparison Program 5-2 5.9 TLD Intercomparison Program.
5-2 5.9.1 Nuclear Technology Services Intercomparison Program 5-2 5.9.2 State of North Carolina Intercomparison Program 5-3 5.9.3 Internal Crosscheck (Duke Power) 5-3 6.0 References 6-1 i
Appendices Appendix A: Environmental Sampling and Analysis Procedures I.
Change of Sampling Procedures II. Description of Analysis Procedures
- m. Change of Analysis Procedures.
IV. Sampling and Analysis Procedures A.1 Airborne Particulate and Radioiodine A.2 Drinking Water A.3 Surface Water A.4 Ground Water A.5 Milk A.6 Broadleaf Vegetation A.7 Food Products.
A.8 Fish A.9 Shoreline Sediment.
A.10 Direct Gamma Radiation (TLD)
A. 11 Annual Land Use Census V.
Global Positioning System (GPS) Analysis.
Appendix B: Radiological Env. Monitoring Program - Summary of Results Air Particulate.
Air Radioiodine.
Drinking Water.
Surface Water Ground Water Milk.
Broadleaf Vegetation Food Products.
Fish.
Shoreline Sediment Direct Gamma Radiation (TLD)
Appendix C: Sampling Deviations and Unavailable Analyses C. 1 Sampling Deviations C.2 Unavailable Analyses Appendix D: Analytical Deviations Appendix E: Radiological Environmental Monitoring Program Results A-I A-2 A-2 A-3 A-3 A-3 A-3 A-4 A-4 A-4 A-4 A-5 A-5 A-5 A-5 A-6 A-6 B-1 B-2 B-3 B-4 B-5 B-6 B-7 B-8 B-9 B-10 B-1l B-12 C-l C-2 C-3 D-1 E-1 LIST OF FIGURES 2.1-1 2.1-2 3.1 3.2 3.3 3.6 3.8-1 3.8-2 3.9-1 3.9-2 3.10 3.11 Sampling Locations Map (One Mile Radius)
Sampling Locations Map (Ten Mile Radius)
Concentration of Gross Beta in Air Particulate Concentration of Tritium in Drinking Water Concentration of Tritium in Surface Water.
Concentration of Cs-137 in Broadleaf Vegetation Concentration of Co-58 in Fish.
Concentration of Co-60 in Fish.
Concentration of Co-58 in Shoreline Sediment Concentration of Co-60 in Shoreline Sediment Direct Gamma Radiation (TLD) Results 2005 Land Use Census Map 2-4 2-5 3-2 3-5 3-6 3-10 3-14 3-14 3-16 3-17 3-18 3-21 ii
LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2.2-B REMP Analysis Frequency 2.2-C Maximum Values for the Lower Limits of Detection 3.1-A Mean Concentration of Gross Beta in Air Particulate 3.1-B Mean Concentration of Air Radioiodine (I-13 1).
3.2 Mean Concentrations of Radionuclides in Drinking Water 3.3 Mean Concentrations of Radionuclides in Surface Water 3.5 Mean Concentration of Radionuclides in Milk 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3.7 Mean Concentration of Radionuclides in Food Products 3.8 Mean Concentrations of Radionuclides in Fish 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3.10 Direct Gamma Radiation (TLD) Results 3.11 Land Use Census Results 4.1-A 2005 Environmental and Effluent Dose Comparison 4.1-B Maximum Individual Dose for 2005 based on Environmental Measurements for Catawba Nuclear Station 5.0-A 2005 Cross-Check Results for EnRad Laboratories 5.0-B 2005 Environmental Dosimeter Cross-Check Results.
LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order) 2-6 2-7 2-8 2-8 2-9 3-3 3-3 3-5 3-7 3-9 3-11 3-12 3-15 3-17 3-19 3-20 4-3 4-6 5-4 5-13 BW BiWeekly C
Control CNS Catawba Nuclear Station DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency (I-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System LLD Lower Limit of Detection M
Monthly MDA Minimum Detectable Activity nrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCiA picocurie per liter pCi/m3 picocurie per cubic meter pip Problem Investigation Process Q
Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter P
wCi/m microcurie per milliliter UFSAR Updated Final Safety Analysis Report W
Weekly iii
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 2005.
Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.
Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs).
Required analyses were performed and detection capabilities were met for all collected samples as required by SLCs.
Nine-hundred two samples were analyzed comprising 1,219 test results in order to compile data for the 2005 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 2005 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 il 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 3.02E-01 mremE for 2005. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.
Shoreline Sediment sampling Section I - 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 effluents are released into Lake Wylie via 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.
Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the 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 a one mile radius of CNS. Figure 2.1-2 comprises all sample locations within a 10 mile radius of CNS.
2.2 SCOPE AND REQUIREMENTS OF THE REMP An environmental monitoring program has been in effect at Catawba Nuclear Station since 1981, four years prior to operation of Unit 1 in 1985. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.
The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.
This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from Catawba Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of Section 2 - Page I
the company, public and state and federal agencies concerned with the environment.
c Reporting levels for activity found in environmental samples are listed in Table 2.2-A.
Table 2.2-B lists the REMP analysis and frequency schedule.
The Annual Land Use Census, required by Selected Licensee Commitments, is performed to 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 are shown in Table 3.11.
Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.
2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting 0
from the environmental sample analysis program.
The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the REMP. The following equation was used to estimate the mean (Reference 6.8):
0 N
ExiXx N
Where:
x = estimate of the mean,
()
i =individual sample, 0
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 0
to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
Section 2 - Page 2
23.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD), and Minimum Detectable Activity (MDA) are used throughout the REMP.
LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield and the radioactive decay of the sample between sample collection and counting.
The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.
MDA - The MDA may be thought of as an "actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.
2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.
Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident).
Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include some judgment by plant personnel.
Section 2 - Page 3
Figure 2.1-1 Section 2 - Page 4 I
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Figure 2.1-2 Section 2 - Page 5 C<I2-
TABLE 2.1-A CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-B Codes W
Weekly SM Semimonthly BW BiWeekly Q
Quarterly M
Monthly SA Semiannually C
Control Q
Q Sie Location Description*
Air Rad. &
Surfae Dfetidng Shorefte Food Fkib Milk Broad Ground sieLcto ecito*Part.
Water Water sediment Products La ae
____I (a)ii 200 Site Boundary (0.63 mi NNE)
W M
201 Site Boundary (0.53 mi NE)
W M
205 Site Boundary (0.23 mi SW)
W
=
208 Discharge Canal (0.45 mi S)
M ISA I
SA I 210 Ebenezer Access (2.31 mi SE)
=
211 Wylie Da(4.06 mi ESE)
M
=
_
212 Tega Cay (3.32 mi E)
W 214 Rock Hill Water Supply (7.30 mi SSE)
M 215 C River Pointe - Hwy 49 (4.21 mi NNE)
M SA
=
216 C Hwy 49 Bridge (4.19 mi NNE)
SA 218 C Belmont Water Supply (13.5 mi NNE)
M 221 C Dairy(14.5 mi NW)
_:___=_
SM 222 Site Boundary (0.70 mi N)
M 226 Site Boundary (0.48 mi S)
=
M 252 Residence (0.64 mi SW)
=
Q 253 Irrigated Gardens (1.90 mi SSE)
M(a) 254 Residence (0.82 mi N)
I_
=
=
Q 258 C Fairhope Road (9.84 mi W)
W M
(a) During Harvest Season (b) When Available
- GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
)
Section 2 - Page 6
TABLE 2.1-B CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
Site Location Distance Sector Site Location*
Distance Sector 200 SITE BOUNDARY 0.63 miles NNE 234 HOME FEDERAL BANK 4.50 miles E
201 SITE BOUNDARY 0.53 miles NE 235 LAKE WYLIE DAM 4.07 miles ESE SC WILDLIFE 203 SITE BOUNDARY 0.38 miles ESE 236 FEDERATION OFFICE 4.25 miles SE TWIN LAKES ROAD AND 204 SITE BOUNDARY 0.48 miles SSW 237 HOMESTEAD ROAD 4.75 miles SSE PENNINGTON ROAD AND 205 SITE BOUNDARY 0.23 miles SW 238 WEST OAK ROAD 4.02 miles S
CARTER LUMBER 206 SITE BOUNDARY 0.67 miles WNW 239 COMPANY 4.49 miles SSW 207 SITE BOUNDARY 0.95 miles NNW 240 PARAHAM ROAD 4.07 miles SW 212 Si TEGA CAY AIR SITE 3.32 miles E
241 CAMPBELL ROAD 4.58 miles WSW TRANSMISSION TOWER 217 C ROCK HILL AIR SITE 10.3 miles SSE 242 ON PARAHAM ROAD 4.56 miles W
222 SITE BOUNDARY 0.69 miles N
243 KINGSBERRY ROAD 4.39 miles WNW BETHEL 223 SITE BOUNDARY 0.57 miles E
244 ELEMENTARY SCHOOL 4.02 miles NW CROWDERS CREEK 225 SITE BOUNDARY 0.68 miles SE 245 BOAT LANDING 4.01 miles NNW CAROWINDS 226 SITE BOUNDARY 0.48 miles S
246 SI GUARD HOUSE 7.87 miles ENE 227 SITE BOUNDARY 0.52 miles WSW 247 C FORT MILL 7.33 miles ESE PIEDMONT 228 SITE BOUNDARY 0.61 miles W
248 Si MEDICAL CENTER 6.54 miles S
YORK COUNTY 229 SITE BOUNDARY 0.84 miles NW 249 Si OPERATIONS CENTER 7.17 miles S
RIVER HILLS YORK 230 COMMUNITY CHURCH 4.37 miles N
250 Si DUKE POWER OFFICE 10.4 miles WSW RIVER HILLS 231 FRONT ENTRANCE 4.21 miles NNE 251 C CLOVER 9.72 miles WNW 232 PLEASANT HILL ROAD 4.18 miles NE 255 SITE BOUNDARY 0.61 miles ENE ZOAR ROAD AND 233 THOMAS DRIVE 3.95 miles ENE 256 SITE BOUNDARY 0.58 miles SSE 258 FAIRHOPE ROAD 9.84 miles W
C = Control SI = Special Interest
- GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 2 - Page 7
TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Food Products (pCi/liter) or Gases (pCi/kg-wet)
(pCi/liter)
(pCi/kg-wet)
(pC i/mn )_
H-3 20__
_a)_(b)
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 1
300 (a) If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.
(b) H-3 Reporting level not applicable to surface water TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic I-131 Beta Air Radioiodine Weekly X
Air Particulate Weekly X
X Direct Radiation Quarterly X
Surface Monthly Composite X
Water Quarterly Composite X
Drinking Monthly Composite X
(a)
X Water Quarterly Composite X
Ground Water Quarterly X
X Shoreline Sediment Semiannually X
Milk Semimonthly X
X Fish Semiannually X
Broadleaf Vegetation M
b)
X Food Products Monthly(b)
X Q
(a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is
> I mrem per year. An LLD of I pCi/liter will be required for this analysis.
(b) When Available iw.,
kmy
'u 40 Section 2 - Page 8
TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION Analysis Water Air Particulates Fish Milk Food Products Sediment (pCi/liter) or Gases (pCi/kg-wet)
(pCi/liter)
(pCi/kg-wet)
(pCi/kg-dry)
(pCi/m3)
Gross Beta 4
0.01 H-3 2000 (a)
Mn-54 15 130 Fe-59 30 260 l
Co-58,60 15 130 l
Zn-65 30 260 Zr-Nb-95 15 I-131 1 (b) 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 1
(a) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
(b) If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
Section 2 - Page 9
3.0 INTERPRETATION OF RESULTS Review of all 2005 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 2005 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 2005.
Summary tables containing 2005 information required by Technical Specification Administrative Control 5.6.2 are located in Appendix B.
Evaluation for significant trends was performed for radionuclides that are listed as required within Selected Licensee Commitments 16.11-13.
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. Other radionuclides detected that are the result of plant operation, but not required for reporting, are trended.
A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related to SLC reporting levels (Table 2.2-A) were used as criteria for trending conclusions. All 2005 maximum percentages of reporting levels were well below the 100% action level. The highest value noted during 2005 was 6.00% for tritium in drinking water collected at the Rock Hill Water Supply, Location 214.
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.
During 1979-1986, all net activity results (sample minus background), both positive and negative were included in calculation of sample mean. A change in the EnRad gamma spectroscopy system on September 1, 1987, decreased the number of measurements yielding detectable low-level activity for indicator and control location samples. It was thought that the method used by the previous system was vulnerable to false-positive results.
All 2005 sample analysis results were reviewed to detect and identify any 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 2005 data presented in this section supports the conclusion that there were no significant changes in environmental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.
Section 3 - Page I
3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2005, 265 radioiodine and particulate samples were analyzed, 212 from four indicator locations and 53 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.
Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 2005. The two sample locations' results are similar in concentration and have varied negligibly since preoperational periods.
There were no detectable gamma emitters identified for particulate filters analyzed during 2005. Table 3.1-A shows the highest indicator annual mean and control location annual mean for gross beta in air particulate.
There was no detectable 1-131 in air radioiodine samples analyzed in 2005. Table 3.1-B shows the highest indicator annual mean and control location annual mean for 1-131 since 1984 (preoperational period).
K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was not detected on any cartridges in 2005. Cs-137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal.
A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.
_0
- S CT.
0 There is no reporting levelfor gross beta in air particulate Figure 3.1 pCVIiter Concentration of Tritium in Drinking Water 3500 2500 i-25000
-;4
.I,.;_I__IIIII 1500 1 000 500 0
1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location Controi Location
-10%
Reporting Level Section 3 -Page 2
Table 3.1-A Mean Concentration of Gross Beta in Air Particulate
.Indicator Location (pCitr)
Control Location (pCi/r) 1984 2.25E-2 1.82E-2 1985 2.12E-2 1.53E-2 1986 3.62E-2 3.41E-2 1987 2.67E-2 2.32E-2 1988 2.29E-2 2.30E-2 1989 2.1IE-2 2.13E-2 1990 2.39E-2 2.72E-2 1991 2.19E-2 2.51E-2 1992 1.90E-2 2.01E-2 1993 1.87E-2 1.94E-2 1994 2.03E-2 2.03E-2 1995 4.88E-2 3.23E-2 1996 3.49E-2 2.60E-2 1997 2.83E-2 2.28E-2 1998 2.69E-2 2.12E-2 1999 2.53E-2 2.04E-2 2000 2.28E-2 1.86E-2 2001 1.76E-2 1.78E-2 2002 1.60E-2 1.57E-2 2003 1.54E-2 1.42E-2 2004 1.65E-2 1.49E-2 Average (1995 -2004) 2.53E-2 2.04E-2 2005 1.66E-2 1.68E-2 Table 3.1-B Mean Concentration of Air Radioiodine (1-131)
Year Indicator Location (pCilm)
Control Location (pCifm3) 1984 1.30E-3 1.46E-2 1985 4.75E-3 2.38E-2 1986 1.43E-2 1.02E-2 1987 1.38E-2 Q.OOEO 1988 0.OOEO O.OOEO 1989 O.OOEO O.OOEO 1990 Q.OOEO O.OOEO 1991 Q.OOEO O.OOEO 1992 Q.OOEO 0.OOEO 1993 O.OOEO Q.OOEO 1994 O.OOEO O.OOEO 1995 O.OOEO Q.OOEO 1996 Q.OOEO O.OOEO 1997 O.OOEO O.OOEO 1998 O.OOEO O.OOEO 1999 O.OOEO O.OOEO 2000 O.OOEO O.OOEO 2001 O.OOEO O.OOEO 2002 O.OOEO O.OOEO 2003 O.OOEO O.OOEO 2004 O.OOEO O.OOEO 2005 O.OOEO O.OOEO O.OOEO= no detectable measurements Section 3 - Page 3
3.2 DRINKING WATER 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 tritium. One indicator location was sampled, along with one control location.
No gamma emitting radionuclides were identified in 2005 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.
Q Table 3.2 shows highest annual mean gross beta concentrations for the indicator location and control location since preoperation. The indicator location (downstream of the plant effluent release point) average concentration was 2.05 pCi/I in 2005 and the control location Q
concentration was 1.84 pCi/l. The 2004 indicator mean was 1.88 pCi/l. The table shows that current gross beta levels are not statistically different from preoperational concentrations.
Tritium was detected at low levels in the four indicator samples and the four control samples 4
during 2005. The mean indicator tritium concentration for 2005 was 769 pCi/l, 3.85% of reporting level. The mean control tritium concentration for 2005 was 450 pCi/l, 2.25% of reporting level. Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean concentrations for tritium since 1984.
Planned drainage from the fueling water storage tank (FWST) during 2005 (to ensure proper Q
safety system operation) contributed to higher tritium concentrations at the indicator drinking Q
water sampling location (PIP C-05-02259).
Q The drinking water control location is influenced by the McGuire Nuclear Station located approximately 40 miles upstream of Catawba on the Catawba River.
Q The dose for consumption of water was less than one mrem per year, historically and for 2005; therefore low-level iodine analysis is not required.
Section 3 - Page 4
Figure 3.2 0
0 0
0 S
0 0
0 0
S 0
0 0
0 0
S Table 3.2 Mean Concentration of Radionuclides in Drinkin2 Water Gross Beta (pCi/l)
Tritium (pCi/l)
YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.1OE-2 3.1OE-2 1985 2.70 2.24 4.13E2 4.00E2 1986 3.11 2.26 7.23E2 7.33E2 1987 3.10 2.40 7.80E2 4.80E2 1988 3.60 2.60 6.64E2 O.OOEO 1989 3.60 2.90 8.9 1E2 5.72E2 1990 4.50 3.20 7.03E2 O.OOEO 1991 3.70 2.20 7.04E2 0.OOEO 1992 3.20 2.40 7.65E2 5.38E2 1993 3.50 2.50 7.06E2 O.OOEO 1994 3.30 2.70 8.66E2 O.OOEO 1995
_4.80
_4.50 4.28E2 2.2 1E2 1996 3.08 3.14 3.7I1E2 3.27E2 1997 3.74 3.15 3.54E2 2.28E2 1998 2.51 2.44 5.07E2 1.83E32 1999 3.55 2.48 6.7 1E2 2.70E2 2000 3.04 2.27 5.87E2 3.26E2 2001 3.49 2.30 8.66E2 4.50E2 2002 3.44 2.36 1.22E3 4.1IE2 2003 2.27 2.02 6.36E2 2.88E2 2004 1.88 1.69 5.47E2 2.54E2 2005 2.05 1.84 7.69E2 4.50E2 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 5 COLF
3.3 SUJRFACE WATER A total of 39 monthly surface water samples was 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.
Tritiuin was the only radionuclide identified in surface water samples collected during 2005.
All indicator location samples contained tritium with an average concentration of 7387 pCi/l.
Indicator Location 208 (Discharge Canal) showed a range of activities from 8240 to 18000 pCi/l which had the highest mean concentration of 14000 pCi/l. Tritium was detected in all four control samples during 2005 with an average concentration of 378 pCi/l.
Figure 3.3 displays the indicator and control annual means for tritium since 1984. Table 3.3 lists indicator annual means.
Tritium in surface water in 2005 was higher than usual due to planned drainage from the fueling water storage tank (FWST) to ensure proper operation of plant safety systems (PIP C-05-02259). This tank contains tritiated water.
Figure 3.3 pCi/liter Concentration of Tritium in Surface Water 30000 l-25000 20000 15000 10000,
5000 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location
-0"- Control Location There is no reporting levelfor tritium in suiface water, however. if no drinking water pathway exists, a value of 30,000 pCi/I ma v be used. A drinking water pathwvay existspJr Catiwba Nuclear Station, so this limit does not applv for sufatce water. See section 3.21br drinking water results.
Section 3 - Page 6 (S' '"
r
Table 3.3 Mean Concentrations of Radionuclides in Surface Water (WCiMl)
YEAR Co-58 Co-60 Nb-95 Cs-137 H-3 Indicator H-3 Control 1984 4.59E-1 5.71E-1 6.48E-1 9.08E-1 3.35E2 3.18E2 1985 3.46E0 4.83E-2 2.70E0 8.19E-t 1.19E3 5.05E2 1986 3.10E-1
-4.12E-2 2.05E0 4.85E-1 2.34E3 5.05E2 1987 O.OOEO 3.1OEO 4.30E0 9.90E0 4.17E3 6.20E2 1988 9.20E0 O.OOEO 0.OOEO O.OOEO 6.03E3 6.07E2 1989 0.OOEO O.OOEO Q.OOEO O.OOEO 5.27E3 O.OOEO 1990 6.50EO O.OOEO O.OOEO 0.OOEO 3.98E3 7.73E2 1991 0.OOEO O.OOEO O.OOEO O.OOEO 4.87E3 Q.OOEO 1992 0.OOEO O.OOEO O.OOEO O.OOEO 6.91E3 6.64E2 1993 4.70E0 1.80E0 QOOEO O.OOEO 5.98E3 O.OOEO 1994 O.OOEO O.OOEO Q.OOEO O.OOEO 8.42E3 0.OOEO 1995 0.OOEO O.OOEO O.OOEO O.OOEO 5.13E3 2.89E2 1996 O.OOEO O.OOEO 0.OOEO O.OOEO 7.36E3 2.61E2 1997 O.OOEO O.OOEO 0.OOEO O.OOEO 7.77E3 2.20E2 1998 O.OOEO 0.OOEO 0.OOEO 0.OOEO 6.61E3 O.OOEO 1999 O.OOEO O.OOEO O.OOEO 0.OOEO 8.13E3 2.41E2 2000 O.OOEO O.OOEO O.OOEO O.OOEO 7.19E3 2.56E2 2001 O.OOEO O.OOEO O.OOEO O.OOEO 7.13E3 3.28E2 2002 0.OOEO 0.OOEO O.OOEO O.OOEO 1.00E4 3.80E2 2003 0.OOEO O.OOEO O.OOEO O.OOEO 1.31E4 2.37E2 2004 0.OOEO 0.OOEO O.OOEO 0.OOEO0 9.43E3 2.601E2 2005 0.OOEO 0.OO1EO 0.OOEO0 0.OOEO 1.40E4 3.7E O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 7
3.4 GROUND WATER A total of eight ground water samples was 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 2005.
There have been no radionuclides identified in ground water samples since 1988. Only naturally occurring K-40 and Be-7 were noted.
Section 3 - Page 8
3.5 MILK A total of 26 milk samples was analyzed by gamma spectroscopy and low level iodine during 2005.
There was one control location sampled.
No indicator dairies were identified by the 2005 land use census.
There were no gamma emitting radionuclides identified in milk during 2005. Airborne Cs-137 has not been released from the plant since 1992.
Cs-137 was last detected in an indicator sample during 1996. The occurrence of Cs-137 in milk samples has been noted several times since 1984. During 1995 there was also one sample analyzed in which Cs-137 was identified with a concentration of 8.6 pCi/i. 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 annual mean and control location annual mean for Cs-137 since the preoperational period. Concentrations are similar for the two sample types.
Cs-137 is the only radionuclide, other than K-40 and Be-7, reported in milk samples since 1988.
Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pC0i)
Cs-137 Control (pWi) 1984 2.95E0 2.98E0 1985 2.11EO 2.12E0 1986 3.76E0 4.54E0 1987 5.00E0 5.50E0 1988 3.20E0 3.80E0 1989 O.OOEO O.OOE0 1990 8.OOEO 6.70E0 1991 O.OOEO 0.OOE0 1992 3.40E0 5.00E0 1993 5.OOEO O.OOEO 1994 2.80E0 0.OOE0 1995 8.60E0 O.OOEO 1996 6.05E0 0.OOE0 1997 O.OOE0 O.OOEO 1998 O.OOE0 O.OOEO 1999 O.OOEO O.OOEO 2000 O.OOE0 O.OOEO 2001 O.OOEO O.OOEO 2002 0.OOE0 0.OOE0 2003 O.OOEO 0.OOE0 2004 0.OOE0 0.OOEO 2005 O.OOE0 O.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on al net activity Section 3 -Page 9
3.6 BROADLEAF VEGETATION Gamma spectroscopy was performed on 60 broadleaf vegetation samples during 2005.
Four indicator locations and one control location were sampled.
Five of the forty-eight samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in one of the twelve samples collected at Location 222. The highest concentration detected at Location 222 was 54.8 pCi/kg which is 2.74%
of the reporting level. Cs-137 was not detected in any of the twelve control location samples.
Figure 3.6 shows indicator and control annual means for Cs-137 in vegetation since 1984. Table 3.6 lists indicator and annual means. Values shown from 1984 to 2005 show a stable trend for Cs-137 in vegetation.
No airborne Cs-137 has been released from the plant since 1992.
Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.
K-40 and Be-7 were observed in broadleaf vegetation samples.
0 0
4_
0 0
46
- F 0-S 40 0-W a
0 W
0.
S W
_-_Q Figure 3.6 pCi/kg 1200 -
1000.
800 -
600 -
400 -
Concentration of Cs-137 in Broadleaf Vegetation 200 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location ~Control Location 50% Reporting Level Section 3 - Page 10
Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg)
Cs-137 Control (pCi/kg) 1984 3.76E1 1.30EI 1985 5.48E1 4.16EI 1986 7.42E1 2.22EI 1987 6.1OE1 5.10EI 1988 9.10E1 7.40EI 1989 L.OOE2 4.80EI 1990 7.70E1 5.80EI 1991 1.98E2 8.60EI 1992 9.70EI O.OOEO 1993 1.13E2 3.20EI 1994 7.OOEI O.OOEO 1995 3.60EI O.OOEO 1996 2.23E2 6.22EI 1997 7.57EI 0.OOEO 1998 6.53EI O.OOEO 1999 1.08E2 O.OOEO 2000 1.04E2 O.OOE0 2001 3.76EI O.OOEO 2002 7.02EI O.OOEO 2003 4.96E1 2.40EI 2004 5.45EI O.OOE0 2005 5.48EI O.OOE0 O.OOEO = no detectable measurements 1984 - 1986 rnean based on all net activity Section 3 - Page II
3.7 FOOD PRODUCTS Collection of food product samples (crops) from an irrigated garden began in 1989. The garden is located on Lake Wylie downstream from CNS, Location 253. During the 2005 growing season, five samples were collected and analyzed for gamma radionuclides.
There is no control location for this media type.
Table 3.7 shows Cs-137 indicator location highest annual mean concentrations since 1989.
Table 3.7 Mean Concentration of Radionuclides in Food Products YEAR Cs-137 Indicator (pCiAkg) 1989 O.OOEO 1990 O.OOEO 1991 O.OOEO 1992 O.OOEO 1993 2.50EI 1994 O.OOEO 1995 O.OOEO 1996 O.OOEO 1997 O.OOEO 1998 O.OOEO 1999 O.OOEO 2000 O.OOEn 2001 O.OOE0 2002 O.OOE0 2003 O.OOE0 2004 O.OOE0 2005 O.OOE0 RO.OEO =no detectable measurements Section 3 - Page 12
3.8 FISH Gamma spectroscopy was performed on 12 fish samples collected during 2005. One downstream indicator location and one control location were sampled.
Co-58, Co-60, and Cs-137 are normally the predominant radionuclides identified in fish samples, but were not detected in any indicator or control location samples.
Figures 3.8-1 and 3.8-2 are graphs displaying annual mean concentrations for Co-58 and Co-60. Table 3.8 depicts the highest indicator location annual mean for radionuclides detected.
In addition, radionuclides identified in fish samples since 1988 have been included in the table. Overall, radionuclides have not shown a
significant trend or accumulation.
K-40 was observed in fish samples collected during 2005.
Section 3 - Page 13
Figure 3.8-1 pCi/kg Concentration of Co-58 in Fish 2000 1800 i
1600 T
t -.-
1400 1200 --
-e L--
800 200 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004
-U-Indicator Location aControl Location 5 % Reporting Level I
4 t
0I S
£ E
£ 0
S a~
U It
£ 0
£ I
Figure 3.8-2 pCi/kg Concentration of Co-60 in Fish 700 600 500 400
] -
300 1-A 1984 1986 1988 1990 1992 1994 1996 1998 2000 200 2
0
-Indicator Location Control Location 5% Reporting Level it I-0 it 6
It I-
£ I
4 lt I
it S
6 S
I-t
(-fo~It 6=41111
?
2004 Section 3 - Page 14
Table 3.8 Mean Concentrations of Radionuclides in Fish (pCi/kg)
Year Mn-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 1984 3.07E0 3.OOEO 6.11E-1
-5.32E0 1.83EO O.OOEO O.OOEO O.OOEO O.OOEO 1985 7.68E-1 3.40E1 9.1 IEO 3.22E0 1.28E1 5.07EO O.OOEO O.OOEO O.OOEO 1986 2.01E1 1.86E2 4.01EI 3.51E1 9.29EI O.OOEO 7.30EO O.OOEO O.OOEO 1987 7.24E0 7.57E1 4.81El 3.83E0 4.27E1 5.40EO O.OOEO O.OOEO O.OOEO 1988 2.85E1 1.40E2 9.70E1 1.67E1 8.24EI O.OOEO O.OOEO O.OOEO O.OOEO 1989 8.28E0 1.33E2 3.83E1 1.47E1 4.37E1 8.58E-1 O.OOEO O.OOEO O.OOEO 1990 2.51EI 1.75E2 7.77E1 1.32E1 4.66Ei 3.33EO O.OOEO 7.OOEO 9.25EO 1991 3.15E1 1.46E2 1.29E2 1.03E1 4.60E1 7.90E-1 2.30EO O.OOEO 7.45EO 1992 1.34E1 9.02E1 6.20E1 1.27E1 4.61Ei O.OOEO O.OOEO O.OOEO O.OOEO 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56EI O.OOEO O.OOEO O.OOEO O.OOEO 1994 I.91E0 4.75El 1.81EI O.OOEO 1.75EI O.OOEO O.OOEO O.OOEO 1.45EI 1995 5.65E1 8.90E2 2.66E2 O.OOEO 6.77E1 1.38EI O.OOEO O.OOEO O.OOEO 1996 O.OOEO 5.95E1 6.68EI O.OOEO 3.02EI O.OOEO O.OOEO O.OOEO O.OOEO 1997 O.OOEO 4.93E1 9.88EO O.OOEO 2.74EI O.OOEO O.OOEO O.OOEO O.OOEO 1998 0.OOEO 6.44E_
2.86E1 0.OOEO 1.58E1 0.OOEO 0.OOEO 0.OOEO O.OOEO 1999 O.OOEO 3.12E1 2.71EI O.OOEO 1.87EI O.OOEO O.OOEO O.OOEO O.OOEO 2000
_.OOEO 2.13E2 2.69E2 0.OOEO 1.52E1 0.OOEO O.OOEO 0.OOEO 0.OOEO 2001 O.OOEO 4.66EI O.OOEO O.OOEO 2.08EI O.OOEO O.OOEO O.OOEO O.OOEO 2002 O.OOEO 5.23E1 7.OOEI O.OOEO 1.73EI O.OOEO O.OOEO O.OOEO O.OOEO 2003 O.OOEO 1.43E2 2.61EI O.OOEO 1.19EI O.OOEO O.OOEO O.OOEO O.OOEO 2004 4.92E1 1.81EI O.00E0 OMEO 0.OOEO 0.OOEO O.O0EO 0.0OE0 O.OOEO 2005 O.00E0 0.00E0 0.00E0 O.00E0 0.OOEO 0.00E0 0.00E0 0.OOEO 0.urEt O.OO1EO = no detectable measurements Section 3 - Page 15
3.9 SHORELINE SEDIMENT During 2005, a total of 6 shoreline sediment samples was analyzed, four from two indicator locations and two from the control location.
Co-58, Co-60, and Cs-137 were identified in samples collected from indicator location 208-IS, which is closest to the plant's liquid effluent release point. Naturally occurring K-40 was identified in many of the indicator and control locations. Activity released in plant effluents has decreased since 1996 and as a result decreased activity has been measured in the environment.
The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-iS. Cs-137 was identified at location 208-IS with an annual mean concentration of 30.4 pCi/kg. Other radionuclides identified during 2005 at shoreline sediment location 208-1S included Co-58 with an annual mean of 161 pCi/kg, and Co-60 with an annual mean of 141 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from this location.
Table 3.9 lists highest indicator location annual mean since 1984. Included in the table are radionuclides that have been identified in shoreline sediment samples since 1988.
Figure 3.9-1 graphically depicts Co-58 annual mean concentrations. Figure 3.9-2 depicts Co-60 annual mean concentrations.
Figure 3.9-1 0
6 0
0 0
O 0
if W
O if O
6 af It 4
if a
if O
14f 10 jQ6 pCi/kg 2000 1800 1600 1400 1200 1000 800 600 400 200 0
1984 Concentration of Co-58 in Shoreline Sediment 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Indicator Location Control Location There is no reporting levelfor Co-58 in Shoreline Sediment Section 3 - Page 16
Figure 3.9-2 pCi/kg Concentration of Co-60 in Shoreline Sediment 2000 1800 t
1600 8
000 t--
0 400
~
1200 0
1984 1986 1988
_1990 1992 1994 1996 1998 _2000 2002 2004 0
Indicator Location
+-
Control Location There is no reporting level for Co-60 in Shoreline Sediment 00 Table 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/k2)
Year M n-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 Co-57 Sb-125 1984 1.03E0 4.40E0
-2.34E0 O.OOE0 O.OOE0 3.19E1 1.07E2 O.OOE0 0.OOE0
_1985
-3.12E0 1.16E2 5.18E0 O.OOE0 O.OOE0 2.1 IE2 2.97E2 O.OOE0 O.OOE0 1986 I.O9E2 3.79E2 2.05E2 O.OOE0 3.96E1 6.50E1 1.61E2 O.OOE0 O.OOE0 1987 8.83E1 4.08E2 1.61E2 4.22EI O.OOE0 6.08E1 1.26E2 O.OOE0 O.OOE0 1988 1.07E2 3.29E2 2.63E2 2.28E1 7.54E0 2.59E1 1.07E2 7.65E-1 3.68E0 1989 4.58E1 1.94E2 1.21E2 5.02E0 O.OOE0 1.65E1 5.77EI O.OOE0 1.57EI
- 1990 5.39E1 2.08E2 1.77E2 O.OOE0 O.OOE0 1.66E1 8.18EI O.OOE0 7.15E0 1991 8.50E1 3.70E2 4.19E2 5.30E0 O.OOE0 1.82E1 8.33E1 1.20E0 I.50EI 0
1992 1.17E2 1.13E3 5.80E2 3.50E0 O.OOE0 1.69E1 1.07E2 3.00E0 2.70EI 1993 1.33E2 1.07E3 1.04E3 O.OOE0 O.OOE0 2.80EI 1.26E2 2.47E1 2.16E2 1994 4.93E1 7.98E2 5t73E2 oR oncd in Shorel Sedim ent
- ._0E1 1995 1.02E2 1.33E3 8.65E2 1.13E2 O.OOE0 2.OOE0 8.50E1 3.69E1 1.49E2 1996 8.73E1 3.39E2 5.81E2 O.OOEO O.OOE0 O.OOE0 8.30EI O.OOE0 1.96E2 1997 6.96E1 5.90E2 7.64E2 O.OOE0 O.OOEO O.OOE0 1.43E2 O.OOE0 1.76E2 1998 3.07E1 1.88E2 2.30E2 O.OOE0 O.OOE0 O.OOE0 7.1IEI O.OOE0 O.OOE0 1999 7.28E1 2.29E2 4.39E2 O.OOE0 O.OOE0 O.OOE0 9.42EI O.OOEO 1.40E2 2000 O.OOE0 3.90E1 1.03E2 O.OOE0 O.OOE O.OO
.E0 4.96EI O.OOE0
.OOEO 2001 3.86E1 8.27E1 3.29E2 O.OOEO O.OOE0 O.OOE0 5.58EI O.OOE0 O.OOE0 2002 3.51E1 2.41E2 2.22E2 O.OOE0 O.OOE0 O.OOE0 8.83EI O.OOE0 O.OOE0 2003 2.17E1 8.75E1 1.08E2 O.OOEO O.OOE0 O.OOEO 2.69E1 O.OOE0 O.OOEO 2004 6.60E1 2.67E2 3.83E2 O.OOEO 0.OOE0 O.OOEO 3.79EI O.OOE0 O.OOE0 2005 O.OOEO 1.619E2 1.41E2 O.OOEO O.OOE0 O.OOE0 O.OOE0 O.OOE0 O.OOEO O.OOEO
= no detectable rneasurenents 1984 -1986 mean based on all net activity Negative values are calculated as zeroes 0
- Section 3 - Page 17 cjoq
3.10 DIRECT GAMMA RADIATION In 2005, 162 TLDs were analyzed, 150 at indicator locations and 12 at control locations.
TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 102.7 milliroentgen. The annual mean exposure for the control locations was 57.7 milliroentgen.
Figure 3.10 and Table 3.10 show TLD inner ring (site boundary), outer ring (4-5 miles),
and control location annual averages in milliroentgen per year. Preoperational data and rolling ten year operational data averages are also given. As shown in the graph, inner ring, outer ring, and control data averages historically compare closely. Inner and outer ring averages comprise a number of data points with control averages representing only three locations.
The calculated total body dose (from gaseous effluents) for 2005 was 5.37E-1 mrem, which is 0.7% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.
Figure 3.10 mR/year 250 E-Direct Gamma Radiation (TLD) Results 200 I
A 100/
50 1984 1986 1988 1990 1992 1994 1996 1998 2(
A Inner Ring Outer Ring
-Control
'00 2002 2004 There is no reporting levelfor Direct Radiation (TLD)
Section 3 - Page 18 cGV
Table 3.10 Direct Gamma Radiation (TLD) Results Inner Ring Average Outer Ring Average Control Average Year (mR/yr)
(mlRyr)
(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 1997 82.4 71.9 57.4 1998 85.3 74.2 64.6 1999 80.0 68.1 57.8 2000 75.0 63.0 52.4 2001 81.0 70.5 55.2 2002 78.8 69.5 55.2 2003 81.7 72.6 56.0 2004 78.6 73.8 55.6 Average (1995 - 2004) 82.7 72.7 59.9 2005 79.8 75.2 57.7
- Preoperational Data Section 3 - Page 19
3.11 LAND USE CENSUS The 2005 Annual Land Use Census was conducted July 5 and July 6, 2005 as required by SLC 16.11-14.
Table 3.11 summarizes census results.
A map indicating identified locations is shown in Figure 3.11.
During the 2005 census, no new or closer irrigated gardens were identified. The nearest residence is located in the NE sector at 0.56 miles. No program changes were required as a result of the 2005 land use census.
Table 3.11 Catawba 2005 Land Use Census Results C-Sector Distance Sector Distance (Miles)
(Miles)
Nearest Residence 0.63 Nearest Residence 0.63 N
Nearest Garden 1.55 S
Nearest Garden 0.80 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.66 Nearest Residence 0.81 NNE Nearest Garden 2.53 Ssw Nearest Garden 1.70 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.56 Nearest Residence 0.66 NE Nearest Garden 2.87 Sw Nearest Garden (irrigated) 0.66 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.61 Nearest Residence 0.78 ENE Nearest Garden (irrigated) 0.61 Wsw Nearest Garden 2.04 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.65 Nearest Residence 0.97 E
Nearest Garden 3.51 w
Nearest Garden 0.96 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.84 Nearest Residence 1.10 ESE Nearest Garden 1.04 WNW Nearest Garden 1.19 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.97 Nearest Residence 1.39 SE Nearest Garden (irrigated) 2.55 NW Nearest Garden 1.54 Nearest Milk Animal Nearest Milk Animal Nearest Residence 0.74 Nearest Residence 1.06 SSE Nearest Garden 1.69 NNW Nearest Garden 2.21 Nearest Milk Animal Nearest Milk Animal
"-" indicates no occurrences within the 5 mile radius kMv C-4.1 (wv U.~
tu L
L LC CO Section 3 - Page 20
Figure 3.11 Section 3 - Page 21
4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2005 CNS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program 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 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 factor of zero was assumed.
Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, broadleaf vegetation, fish, and shoreline sediment sample results are reported in Table 4. 1-A. The individual critical population and pathway dose calculations are reported in Table 4.1-B.
REMP-based dose estimates are not reported for airborne radioiodine, airborne particulate, milk, or ground water sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates are not reported for surface water because sampled surface water is not considered to be a potable drinking water source. Exposure estimates based upon REMP TLD results are discussed in Section 3.10.
The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2005 was 4.66E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.
4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2005 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. These doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.
Summaries of RETDAS dose calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).
Section 4 - Page I
The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas exposure there is no critical age group; as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, inhalation, milk and vegetation pathways.
4.3 COMPARISON OF DOSES The gaseous environmental and effluent dose estimates given in Table 4.1-A agree reasonably well. The calculated environmental doses for liquid pathways are slightly lower than liquid effluent doses. Effluent models are based on historical averages.
There are some differences in how effluent and environmental doses are calculated that affect the comparison.
Doses calculated from environmental data are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.
In calculations based on liquid release pathways, fish, drinking water, and shoreline sediment were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2005 environmental sample results was 5.19E-2 mrem to the adult total body. The maximum total organ dose of 1.73E-l mrem for liquid effluent-based estimates was to the child liver.
In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 5.37E-I mrem to the child's liver, total body, thyroid, kidney, lung, and GI-LLI. Vegetation was the predominant dose pathway for environmental samples. The maximum total organ dose for gaseous environmental estimates was 4.66E-l mrem to the child bone.
Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.
The doses calculated do not exceed the 40CFR190 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of CNS are being maintained well within regulatory limits.
Section 4 - Page 2
TABLE 4.1-A Page I of 3 CATAWBA NUCLEAR STATION 2005 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose (3)
Organ Effluent Data Age (1)
Pathway (2)
Location (mrem)
Skin Environmental Teen Shoreline Sediment 208 (0.45 mi S) 2.30E-03 Skin Effluent Teen Shoreline Sediment 0.5 mi S
- 1. 14E-02 Bone Environmental O.OOE+00 Bone Effluent Child Fish 0.5 mi S 7.03E-02 Liver Environmental Adult Fish 208 (0.45 mi S) 5.15E-02 Liver Effluent Child Fish 0.5 mi S 1.73E-0 I T. Body Environmental Adult Fish 208 (0.45 mi S) 5.19E-02 T. Body Effluent Adult Fish 0.5 mi S 1.48E-01 Thyroid Environmental Adult Fish 208 (0.45 mi S) 5.15E-02 Thyroid Effluent Child Drinking Water 0.5 mi S 9.85E-02 Kidney Environmental Adult Fish 208 (0.45 mi S) 5.15E-02 Kidney Effluent Child Drinking Water 0.5 mi S 1.22E-01 Lung Environmental Adult Fish 208 (0.45 mi S) 5.15E-02 Lung Effluent Child Drinking Water 0.5 mi S 1.07E-01 GI-LLI Environmental Adult Fish 208 (0.45 mi S) 5.15E-02 GI-LLI Effluent Adult Fish 0.5 mi S 1.36E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.
(2) Critial Pathway is the highest individual dose within the identified Critical Age group.
(3) Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
Section 4 - Page 3
Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose (3)
Organ Effluent Data Age (1)
Pathway (2)
Location (mrem)
Skin Environmental O.OOE+00 Skin Effluent 0.5 mi S O.OOE+00 Bone Environmental Child Vegetation 222 (0.70 mi N) 4.66E-01 Bone Effluent 0.5 mi S O.OOE+00 Liver Environmental Child Vegetation 222 (0.70 mi N) 4.46E-01 Liver Effluent Child Vegetation 0.5 mi S 5.37E-01 T. Body Environmental Adult Vegetation 222 (0.70 mi N) 2.50E-01 T. Body Effluent Child Vegetation 0.5 mi S 5.37E-01 Thyroid Environmental O.OOE+00 Thyroid Effluent Child Vegetation 0.5 mi S 5.37E-01 Kidney Environmental Child Vegetation 222 (0.70 mi N) 1.45E-01 Kidney Effluent Child Vegetation 0.5 mi S 5.37E-01 Lung Environmental Child Vegetation 222 (0.70 mi N) 5.23E-02 Lung Effluent Child Vegetation 0.5 mi S 5.37E-0O GI-LLI Environmental Adult Vegetation 222 (0.70 mi N) 7.40E-03 GI-LLI Effluent Child Vegetation 0.5 mi S 5.37E-01 L
k.,
t..
tll
(.d ttm (1) Critical Age is the highest total dose (all pathways) to an age group.
(2) Critial Pathway is the highest individual dose within the identified Critical Age group.
(3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.
40-Section 4 - Page 4
Page 3 of 3 NOBLE GAS Air Environmental or Critical Critical Location Maximum Dose Dose Effluent Data Age Pathway (mrad) t)
Beta Environmental Not Sampled
- 1) Beta Effluent N/A Noble Gas 0.5 mi. NNE 1.61E-02 Gamma Environmental Not Sampled k
Gamma Effluent N/A Noble Gas 0.5 mi. NNE 3.94E-02 Sn0 w
so 00 V0 WO No 10 do Pa I
~Section 4 -Page 5
TABLE 4.1-B Maximum Individual Dosefor 2005 based on Environmental Measurements (mrem)for Catawba Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne Drinking Water Milk TOTAL Child Airborne Drinking Water Milk Broadleaf Vegetation Fish Shoreline Sediment TOTAL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.24E-02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.24E-02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.30E-02 3.30E-02 3.30E-02 3.30E-02 3.30E-02 3.30E-02 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.66E-01 4.46E-01 6.58E-02 0.00E+00 1.45E-01 5.23E-02 2.79E-03 O.OOE+00 0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 0.00E+00 0.00E+00 0.00E+00 4.09E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.80E-04 4.66E-01 4.96E-01 1.16E-01 5.02E-02 1.95E-01 1.03E-01 5.30E-02 4.80E-04 Teen Airborne Drinking Water Milk Broadleaf Vegetation Fish Shoreline Sediment TOTAL Adult Airborne Drinking Water Milk Broadleaf Vegetation Fish Shoreline Sediment TOTAL 0.00E+00 0.00E+00 0.00E+00 0.001E+00 0.001E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 1.72E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.58E-01 3.43E-01 1.19E-01 0.00E+00 1.17E-01 4.53E-02 4.88E-03 0.00E+00 0.00E+00 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 0.00E+00 0.00E+00 0.00E+00 1.96E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.30E-03 2.58E-01 3.81E-01 1.59E-01 3.80E-02 1.55E-01 8.33E-02 4.29E-02 2.30E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 2.45E-02 2.45E-02 2.45E-02 2.45E-02 2.45E-02 2.45E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 2.80E-01 3.82E-01 2.50E-01 0.00E+00 1.30E-01 4.31E-02 7.40E-03 0.00E+00 0.00E+00 2.70E-02 2.70E.-02 2.70E-02 2.70E-02 2.70E-02 2.70E-02 0.00E+00 0.00E+00 0.00E+00 3.51E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.12E-04 2.80E-01 4.34E-01 3.02E-01 5.15E-02 1.82E-01 9.46E-02 5.89E-02 4.12E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.
Section 4 - Page 6 C
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Catawba Nuclear Station Dose from Drinking Water Pathway for 2005 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
330 1 Radionudide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-9S 1.131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 3.08E.05 NO DATA 1.84E-05 420E.08 2.06FA07 3.59E-05 3.77E 04 5122E04 1.71E-04 NO DATA Ineestion Dose Factor Liver T. Body Thyroid Kidney Lung GI-LLI 1.99E-05 4.51E-06 NO DATA 4A1E.06 NO DATA 731E-06 3.60E.06 8 9E-06 NO DATA NO DATA NO DATA 8.97E-06 5.38E-05 2.12E-05 NO DATA NO DATA 159E-05 2-57E-05 1.OSE-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 631E-05 2.91E-05 NO DATA 3.6E-05 NO DATA 533E-05 1.73E-08 L.OOE48 NO DATA 1.24E-08 NO DATA 1A6E405 5.02E-08 356E-0S NO DATA 5AIE.-8 NO DATA 2.50E-05 4.23E.05 105 139E.02 4.94E-05 NO DATA 1.51E.06 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 6.11E-04 433E.05 NO DATA 1.64E-04 6.64E.05 1.91E-06 1.71E-07 8.81E-06 NO DATA 4.06E-0S 1.05E-07 4.20E-05 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 Highest Annual Net Mean Concentration Dose (mrem)
Indicator Water Location (pCi/l)
Bone Liver T. Body Thyroid Kidney Lung GI-LLI ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+O0 0.OOE+00 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE0O OOE+00 0.00E+00 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 ALL 0.00 0.00E+00 0.OOE+00 O.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 ALL 0.00 O.OOE+00 o.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+0 ALL 0.00 0.00E+00 0.OOE+00
+00000E0 0.E+O0 0.00E+00 0.00E+00 0.00E+00 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 214 319 0.OOE+00 3.24E-02 3.24E.02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 Dose Commitment (mrem) =
0.OOE+00 3.24E-02 3.24E.02 3.24E-02 3.24E-02 3.24E-02 3.24E-02 Section 4 - Page 7
Catawba Nuclear Station Dose from Drinking Water Pathway for 2005 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
510 1 Radionuclide Mn-54 Co-58 Fe-59 CO-60 ZA-65 Nb-95 Zr.95 I-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 1.65F05 NO DATA 137R05 2.25E-08 1.t6E-07 1.72E-05 2.34E-04 3.27E-04 8.31E-05 NO DATA Liver 1.07E-05 1.89E-06 2.67E-05 S.29E-06 3.65E-05 8.76E-09 2.S5E-08 1.73E-OS 3.84E-04 3.13E-04 7.28E-O 2.03E-07 Ineestion Dose Factor T. Body Thyroid Kidney Lung GI-LLI 2.85E-06 NO DATA 3.00E6 NO DATA 8.98E-06 5.51E-06 NO DATA NO DATA NO DATA 1.OSE-05 133EFAS NO DATA NO DATA 7.74E-06 2.78E-05 156E-05 NO DATA NO DATA NO DATA 2.93E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41ER06 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 227E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 9.83E-06 S.72E-03 2.84E-05 NO DATA 1.54E-06 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 4.85E-06 NO DATA 2.37E-08 4.34E-0S 4.21E.05 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCiuI)
Bone ALL 0.00 0.00E+00 ALL 0.00 O.OOE+00 ALL 0.00 O.00E+00 ALL 0.00 0.00E+00 ALL 0.00 O.OOE+o0 ALL 0.00 O.OOE+00 ALL 0.00 O.OOE+0o ALL 0.00 0.00E+00 ALL 0.00 O.0OE+o0 ALL 0.00 O.OOE+o0 ALL 0.00 O.OOE+0O0 214 319 0.OOE+00 Liver 0.OOE+O0 0.00E+00 0.OOE+00 0.OOE.O00 0.OOE+00 0.OOE+00 0.OOE+00 O.0E.O00 O.OOE.O0 0.001340 0.00E+O0 3.30E-02 Dose (mrem)
T. Body Thyroid Kidney 0.OOE+00 0.00E+00 0.O0E+O0 0.00E4J0 0.OOE+00 0.OOE+00 0.00E.O0 0.OOE*00 0.O0E+00 0O.OO&O O.OOE.0 0.00E.O00 0.OOE.O0 0.00E M0 O.00E+00 0.00E+-00 0.00E+00 0.OOE+0O 0.OOE+00 O.OOE+O0 0.00E+00 0.00E.O 000 OE.O0 0.003+O00 0 OOE+00 0.OOE400 0.OOE+O0 0.00E4O0 0.00E+00 0.00P400 0.OOE O00 0.00EE O00 0.00EE O00 3.30E-02 3.30E-02 3.30E-02 Lung GI-LI 0.00E+00 0.OOE+O0 0.00E.O0 0.O0E 400 0.00E*00 0.OOE+00 0.0 0 EO 0 0.0 0 F 40 0 0.00E + O0 0.O OE.O 0.00E400 0.OOE+00 O.OOEO00 O.OOE*-00 0.00E+00 0.00E O00 0.OOE1+00 O.00E+00 0.0O F*00 0.OOE+O0 0.00E+00 0.00EO&
3.30E-02 3.30E-02 Dose Commitment (mrem) =
Section 4-Page8 0OO0E+O00 330E-02 3.30E-02 3.30E.02 3.30E-02 3.30E-02 3.30E-02 rrrC, -)C crr Cc C, c C C C c1C C C C CCC
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Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2005 Data Maximum Exposed Child Child Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)
Usage (Intake in one year) =
26 kg Radionuclide 1-131 Cs-134 Cs-137 Highest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)
Indicator Food Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)
Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 O.OOE+00 O.OOE+00 0.00Et00 O.001 0.E00 0.00E.000
.OOE+00 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E406 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 222 54.8 4.66E-01 4.46E-1 6.58E-02 O.OOE+00 1.45E-01 5.23E-02 2.79E-03 Dose Commitment (mrem) =
4.66E-01 4.46E-01 6.58E-02 0.00E+00 1.45E-01 5.23E-02 2.79E-03 Section 4 - Page 9
Catawba Nuclear Station Dose from Fish Pathway for 2005 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)
H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 13622 pCi/I x 0.9 = 12260 pCi/kg Usage (Intake In one year) =
6.9 kg Radionudide Mn-54 Co-58 Fe-59 CO-60 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 1.65K-OS NO DATA 137E-05 2.34E-04 3.27E-04 NO DATA Liver 1.07E-05 1.801-06 2.67E-OS 5.29K-06 3.65R0S 3.84E-04 3.13E-04 2.03R-07 T. Body 2.85R-06 5.51E-06 1331-05 1.56E-O5 2.Z7E-0S 8.101305 4.62K-S 2.03R-07 Incestion Dose Factor Thyroid Kidney Lung NO DATA 3.00K06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 7.74E-06 NO DATA NO DATA NO DATA NO DATA 2.30E-05 NO DATA NO DATA 1.19E-04 427K-O5 NO DATA 1.02E-04 3.67E-05 2.03E-07 2.03E-07 2.03E-07 Gi-LLI S.98K-06 1.05E-05 2.78E-05 2.93E-05 6AIE-06 2.07E-06 1.96E-06 2.03E-07 Highest Annual Net Mean Concentration Indicator Fish Location (pCi/kg)
ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 208 12260 Bone 0.0011+00 0.900+00 0.00E+O0 0.OOE+OO O.09E+O0 0.OOE+00 0.OOE+OO 0.00K+00 Liver O.O0E+00 O.O0E4-00 0.O0K+00 0.OOE+O0 0.00E+OO 900E.OO 0.OOE4-00 1.72E-02 T. Body O.0K+O00 0.001?+0O 0.O0E+00 0.OK+O00 O.00E+0O 0.00K4OO 0.00E+00 1.72E-02 Dose (mrem)
Thyroid Kidney 8.00E+OO 0.00E+O0 0.OO0A+O0 0.00K+O0 0.00K+00 0.O0E+OO 0.90E+00 0.O0E+00 0.00E+00 0.O0E+00 0.00E+0O O.00E+0O 0.00E*O0 0.00E+00 1.72E-02 1.72E-02 Lung 0.O0E+0O 0.90K+O0 0.O0EtOO 0.0O13.OO 0.O0E*00 0.09F*OO 0.00E+0O 1.72E-02 GI-LLI 0.00E+OO 0.09K+00 0.O0E+00 0.09E*00 0.00E.O0 O.00E.OO 0.90E00+
1.72E-02 Dose Commitment (mnremn) =
0.00E+00 1.72E-02 1.72E-02 1.72E-02 1.7211-02 1.72E-02 1.72E-02 Section 4 -Page 10 r r r c c c c c
cc cc c c cc c r cc c c :(Cc cCC c c~c C c C~ t)c 1,CC C
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t t t kt Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2005 Data Maximum Exposed Child Shoreline Recreation =
Shore Width Factor =
Sediment Surface Mass =
14 hr (in one year) 0.2 40 kgIm2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (rnrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/r 2) x Sediment Concentration (pCi/kg)
External Dose Factor Standing on Contaminated Ground Highest Annual Net Mean Concentration Dose (mren-/hr per pCi/m2)
Indicator Sediment (mrem)
Radionuclide T. Body Skin Location (pCi/kg)
T. Body Skin Mn-54 5.80E-09 6.80E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70F-O8 2.00E-08 Cs-134 1.20E-0S 1A40E-08 Cs-137 4.20E-09 4.90E-09 ALL 0.00 O.OOE+00 O.OOE+00 208-IS 161 1.26E.04 lA8E-04 208-IS 141 2.68E-04 3.16E-04 ALL 0.00 O.OOE+00 O.OOE+00 208-IS 30A 1.43E-05 1.67E-05 Dose Commitment (mrem) =
4.09E-04 4.80B-04 Section 4 - Page 11
Catawba Nuclear Station Dose from Drinking Water Pathway for 2005 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/A)
Usage (intake In one year) =
510 1 Radionuclide Mn-54 Co-SB Fe-S9 Co-60 zn*S Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA S.7E-06 NO DATA 5.76E106
.22E-09 4.12EM08 5.85E406 837E05 1.12E-04 2.84EO0S NO DATA Liver 53901E06 9.72E-07 137IE-O LRSE-06 L0011-05 4.5611-09 1301E-08 8.191E-06 1.97E044 1.491E.04 3A48E-08 1.061E47 Ingestion Dose Factor T. Body Thyroid Kidney Lung GI-LLI 1.17E-OC NO DATA 1.76E-06 NO DATA 1.21E05 2.24B-06 NO DATA NO DATA NO DATA 1.34E4f5 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 6.33E-06 NO DATA NO DATA NO DATA 3.66E05 933E406 NO DATA 1.28E405 NO DATA 8.47E-06 2.51E-09 NO DATA 4.42E409 NO DATA 1.95E-05 8.94E-09 NO DATA 1.91EO08 NO DATA 3.OOE05 4.40E.06 2.39E-03 1A1E-05 NO DATA 1.62E-06 9.14E-45 NO DATA 6.26E405 2.39E405 2.45E-06 5.19E.05 NO DATA 5.07E.OS 1.97E-05 2.12E-06 1.83E-06 NO DATA 1.18E408 2.34E408 4.38E-05 1.06E.07 1.06E-07 1.06E-07 1.06E47 1.06E-07 Highest Annual Net Mean Concentration Dose (mrem)
Indicator Water Location (pCil)
Bone Liver T. Body Thyroid Kidney Lung GI.LLI ALL 0.00 0.00E+00 0.00E00+ O.OOE+OO O.OOE400 QOOE+0O 0.00E+00 0.00E+00 ALL 0.00 O.OOE+OO O.OOE+0 0.00E+00 0.00E+00 O.OOE+0 0.0OE+00 0.0OE+00 ALL 0.00 0.00E+O0 0.OOE+00 O.OOE+O0 O.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 ALL 0.00 O.00E+00 0.00E+00 O.OOE+0 0.00E+OO O OOE+0 0.00 E+. O O.OOE+00 ALL 0.00 O.00E4+00 0.00OE+4O0 O.0OE+00 0.00E+O0 0.OOE+00 O.0E+0 0.00E+00 ALL 0.00 0.OOE+00
.OOE+00 0.00E+00 0.OOE+O0 0.OOE+OO O.OOE+00 0.00E+0O ALL 0.00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+0 0.00E+00 0.OOE4+O0 0.OOEOO ALL 0.00 O.OOE+OO O.OOE+OO O.OOE+00 0.00E+00
.OOE+O0 O.OOE+4OO 0.00E+00 ALL 0.00 0.00E+00 0.00E+O0 O.OOE+0O 0.OOE+0
.OOE+OO 0.OOE1+O0 0.00E+00 ALL 0.00 O.OOE+00 O.OOE+O0 0.0E440 0.OOE+O0 0.00E4+00
.OOE+00 0.00E+00 ALL 0.00 0.0E+e0 0.OOE+00 0.0E+00 0.OOE+0 0.OOE+00 0.OOE+00 0.0E+00 214 319 0.00E1+40 1.72E402 1.72E-02 1.72E102 1.72E-02 1.72E402 1.72E.02 Dose Commitment (mrem)=
Section 4 - Page 12 0.OOE+00 1.721E.02 1.721E02 1.72E.02 1.72E.02 1.72E.02 1.72E-02 arg, tC, )f C'~C, e C C C' C) C. C C C C C C CiC, C((fTC (C
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Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2005 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mremlpCi ingested) x Concentration (pCi/kg)
Usage (intake in one year) =
42 kg Highest Annual Net Mean Inzestion Dose Factor Concentration Dose (mrem)
Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)
Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 5.85E.06 8.19E-06 4.40E-06 2.39E.03 1AlE.05 NO DATA 1.62E.06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 0.0E+00 O.OOE+00 Cs-134 837E.05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2A5E-06 ALL 0.00 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Cs-137 1.12EB04 IA9E.04 5.19E-05 NO DATA 5.07E05 1.97E05 2.12E-06 222 54.8 2.58E-01 3A3E.01 1.19E.01 O.OOE+00 1.17E-01 4.53E-02 4.88E.03 Dose Commitment (mrem) =
2.58E-01 3.43E-O1 l.19E-01 O.OOE+00 1.17E-01 453E-02 4.88E-03 Section 4 - Page 13
Catawba Nuclear Station Dose from Fish Pathway for 2005 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)
H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 13622 pCi/i x 0.9 = 12260 pCi/kg Usage (intake in one year) =
16 kg Radionudide Mn-54 Co-S8 Fe-59 Co-6 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 537E-06 NO DATA 5.76E-06 8.37E-05 1.12E-04 NO DATA Liver 5.90E06 9.72E.07 137E-05 2.81E-06 2.0oE.05 1-7E.04 IA9E.04 1.0607 T. Body 1.17E-O6 2.24E-06 5.29E-06 633E-06 933E-06 9.14E-05 5.19E-05 1.06E-07 Inwestion Dose Factor Thyroid Kidney Lung GI-LLI NO DATA 1.76E-06 NO DATA 121E-05 NO DATA NO DATA NO DATA 1.34E-05 NO DATA NO DATA 432E-06 3.24E-05 NO DATA NO DATA NO DATA 3.66E05 NO DATA 1.28E-05 NO DATA 8A7E-06 NO DATA 6.26E.05 2.39E-05 2MR5E-O NO DATA 5.07E-05 1.97E-05 2.12E-06 1.OCE 07 1.061-07 1.06E-07 1E-07 Highest Annual Net Mean Concentration Location (pCi/W ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 208 12260 Dose (mrem)
Bone Liver T. Body Thyroid Kidney Lung GI-LLI O.OOE+OO o.o0E+0o 0.0E+00 O.OOE.+00 0.0E+00 0.00E+00 0.0E+00 0.OOE+0O 0.OOE+00 0.00E+00 0.OOE+0 0.OOE+00 0.OOE+00 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0O O.OOE+00 O.OOE.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OE+00 0.001+00 O.OOE+00 O.OOE+00 0OOE+00 O.OOE+00 O.0OE+00 0.00E+00 O.OOE+00 0 OOE+00 O. OOE+O 0.OOE+0O 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+O0 2.08E-02 2.OSE.02 2.08E-02 2.08E-02 2.OSE-02 2.O8E-02 Dose Commitment (mrem) =
O.OOE+00 2.OSE-02 2.08E-02 2.08E-02 2.OSE-02 2.08EJ02 2.08E-02 Section 4 - Page 14
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Catawba Nuclear Station Dosefrom Shoreline Sediment Pathway for 2005 Data Maximum Exposed Teen Shoreline Recreation =
67 hr (in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/mr Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCim2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mremihr per pCi/m 2)
Radionuclide T. Body Skin Mn-54 5.80E-09 6.80E-09 Co.58 7.OOE-09 8.20E-09 Co-60 1.70ER08 2.OOE-08 Cs-134 1.20E-08 1.40E-08 Cs-137 4.20E-09 4.90E-09 Dose Commitment (mrem) =
Indicator Location ALL 208-IS 208-IS ALL 208-IS Sediment (pCitkg) 0.00 161 141 0.00 30.4 (mrem)
T. Body Skin O.OOE+00 O.OOE+00 6.04E-04 7.08E-04 1.28E-03 1.51E-03 O.OOE+00 O.OOE+00 6.84E-05 7.98E-05 1.96E-03 2.30E.03 Section 4 - Page 15
Catawba Nuclear Station Dosefrom Drinking Water Pathwayfor 2005 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)
Usage (intake in one year) =
730 1 Ingestion Dose Factor Highest Annual Net Mean Concentration Indicator Water Location (pCi/i)
Bone Dose (mrem)
Liver T. Body Thyroid Kidney Lung GI-LLI Radionudide Bone Mn-54 CO-58 Fe-59 Co-60 Zn-65 Nb.95 Zr-95 I.131 Cs-134 Cs-137 BaLa.140 H-3 NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E.09 3.04W8O 4.16E-06 6.22S-05 7.97E-05 2.03E-05 NO DATA Liver T. Body Thyroid Kidney Lung Gl-LLI 457E.06 8.72EW07 NO DATA 136E-06 NO DATA A10E.05 7A5W.07 1.67E6 NO DATA NO DATA NO DATA 1iSIE-05 1.02E.05 3.91E-06 NO DATA NO DATA 2.85W6 3.40E.05 2.14E-06 4.72E406 NO DATA NO DATA NO DATA 4.02E105 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 3A6E409 16E-09 NO DATA 3.42E409 NO DATA 2.10E-05 9.75E.09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 5.95E.06 3AIE-06 1.95E"03 1.02E.05 NO DATA 157E-06 IA8E.04 1.211E-04 NO DATA 4.79E.05 159E105 2.59E-06 1.09E.04 7.14E.05 NO DATA 3.70W.O5 1.23E.05 2.1 IE-06 2.55E-08 133E.06 NO DATA 8.67EW09 IA6E-W8 4.18E-05 I.OSE07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL 214 0.00 0.00E+00 0.0E+00 0.00E.00 O.0E400 0.00E.00 0.OOE.00 0.0E400 0.00 0.00E.MO 0.00E.00 0.001E+O0 0.00E400 0.00EFg.0 0.OOE.00 0.0011i00 0.00 00E00 0.OOE+00 0.OOEEi00 0.00E 4.00 0.0 0E400 0.00EE.00 0.OOE+00 00 1 00 0.00 0.OOE.00 0.00E.00 0.00E400 0.00E+00 0.OOE+00 0.0011+0 0.OOE+00 0.00 0.09E-.00 0.00E+00 0.00E.00 0.00E+00 0.OOE*00 0.OOE+00 0.O0E400 0.00 0.00E400 0.OOEOO0 0.00E+00 O.OOE+i00 0.00E+00 0OAE-iO0 0.OOEO00 0.00 0.OOE+O0 0.OOE+00 0.OOE-.00 0.OOE+00 0.OE.*O0 0.00E-00 0.OOE+O0 0.00 0.00E+00 0.0E+00 0.O0E400 O.0E400 O.0E.00 0.00E.00 0.OOFAOO 0.00 0.OOE+00 0.110.OOE+00 0
.OOE+
00 0.00E4 00 0.0.O
.00E400 O.OOE+.00 0.00 0.O0E+00 0.00E..00 0.00E400 0.00E400 0.00E.O0 0.00E.00 0.OOE-i00 0.00 0.O0E+00 0.OOE+00 0.00E4400 0OOE+00 0.O0E+00 0.OOE+i00 0.OO1E+00 319 0.OOE+i00 2ASM.2 2A45E.02 2ASE.02 2A45E-2 2A45E.02 2A45E-02 Dose Commitment (mrem) =
0.00E+O0 2.45E-02 2.45E.02 2A45E.02 2.45E.02 2.45E.02 2.45E-2 Section 4 - Page 16
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Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2005 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)
Usage (intake in one year) =
64 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)
Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Location (pCiUg)
Bone Liver T. Body Thyroid Kidney Lung GI-LLI I-131 4.16fE06 5.95E406 3AlE-06 1.95EM03 1.02E-0S NO DATA 157E-06 ALL 0.00 O.OOE+OO O.OOE+00
.OOE+00 0.OO OOOEOO.OOE+00 O.OOE+0O.00OO Cs-134 6.22E-05 lA8E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 O.OOE+OO O.00E+00 O.OOE+OO O.OOE+00 O.OOE+0O O.00E+00 0.OOE+OO Cs-137 7.97EA05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 222 54.8 2.80E-01 3.B2E-01 2-50E.01 0.OOE+OO 1.30E-01 4.31E-02 7AOE-03 Dose Commitment (mrem) =
2.80E-01 3.82E-01 250E-41 0.00E+00 130EBO1 4.31E-02 7AOE-03 Section 4 - Page 17
Catawba Nuclear Station Dose from Fish Pathway for 2005 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)
H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 13622 pCi/l x 0.9 = 12260 pCi/kg Usage (intake in one year) =
21 kg Radionuclide Mn-54 co-Ss Fe-S9 Co460 Zn..65 Cs-134 Cs-137 H.3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-05 7-97E-05 NO DATA Liver 4.57E-06 7ASE-07 1.02E.05 2.14E-06 1.54E.05 lA8E-04 1.09E-04 1.05-E07 Incestion Dose Factor T. Body Thyroid Kidney Lung GI-LLI 8.72E-07 NO DATA 136E-06 NO DATA 1AOE-05 1.67E-06 NO DATA NO DATA NO DATA 1.51E05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E105 4.72E.06 NO DATA NO DATA NO DATA 4.02E.05 6.961-06 NO DATA 1.03E-05 NO DATA 9.70E.06 1.21E-04 NO DATA 4.79E-05 159E-05 2.59E-06 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 1.05E07 1.05E-07 1.05E-07 1.05E.07 1.05E-07 Highest Annual Net Mean Concentration Location (pCi/kg)
ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 208 12260 Bone 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Liver 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 2.70E-02 T. Body 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.70E-02 Dose (mrem)
Thyroid Kidney Lung Gl-LLI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.70E-02 2.70E.02 2.70E-02 2.70E-02 Dose Commitment (mrem) =
0.00E+00 2.70E-02 2.70E-02 2.70E-02 2.70E-02 2.70E-02 2.70E102 Section 4 - Page 18 Cr9rr;r)
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Catawba Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2005 Data Maximum Exposed Adult Shoreline Recreation =
12 hr (in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/rn2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremlhr per pCilm2) x Shore Width Factor x Sediment Surface Mass (kg/r 2) x Sediment Concentration (pCUi/k)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)
(mrem/lhr per pCi/m2)
Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg)
T. Body Skin Mn-54 5.803E09 6.80E-09 ALL 0.00 O.OOE+00 O.OOE+00 Co.58 7.00E-09 8.20E-09 208-1S 161 1.08E-04 1.27E-04 Co-60 1.70E-08 2.00E-08 208.1S 141 2.30E.04 2.71E.04 Cs-134 1.20E-08 IAOE-08 ALL 0.00 O.OOE+00 O.OOE+00 Cs-137 4.20E-09 4.90E-09 208.1S 30A 1.23E-05 1.43E-05 Dose Commitment (mrem) =
3.51E-04 4.12E-04 Section 4 - Page 19
5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.
5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures.
EnRad Laboratories is located in Huntersville, North Carolina, at Duke Power Company's Environmental Center.
5.3 DOSIMETRY ANALYSIS Duke Power Company's Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.
5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.
5A.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.
Section 5 - Page I
5A3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and tritium analyses.
5.5 DUKE POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2005. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2005 is documented in Table 5.0-A.
5.6 DUKE POWER AUDITS The Catawba Radiation Protection Section was not audited by the Quality Assurance Group in 2005. The program was audited in 2004.
EnRad Laboratories was not audited by the Quality Assurance Group in 2005. The laboratory was audited in 2004.
Q 5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2005 (Reference 6.12). There were no findings or issues identified by the audit.
5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory for intercomparison analysis.
5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.
of Roswell, GA.
Nuclear Technology Services irradiates environmental Section 5 - Page 2
dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.
5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2005 is documented in Table 5.0-B.
5.9.3 INTERNAL CROSSCHECK (DUKE POWER)
Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Power) Result is documented in Table 5.0-B.
Section 5 - Page 3
TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2005 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "I Pass" indicates that one analysis of the cross-check was performed.
Footnote explanations are included following this data table.
Gamma in Water 3.5 liters I
Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pcin_
pCi/I pCi 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.39 E5 3 Pass Mn-54 2.26 -4.01 E4 3.02 E4 3.04 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.85 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.62 E4 3 Pass Sr-85 5.11 - 9.07 E4 6.82 E4 6.52 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 7.05 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.66 E5 3 Pass Cs-137 1.64-2.91 E4 2.19 E4 2.05 E4 3 Pass Ce-139 1.86-3.30 E4 2.48 E4 2.49 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 -6.94 E3 5.22 E3 5.40 E3 3 Pass Co-57 2.14 - 3.80 E2 2.86 E2 2.98 E2 3 Pass Co-60 1.22-2.16 E3 1.63 E3 1.62 E3 3 Pass Sr-85 1.08-1.91 E3 1.43 E3 1.39 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.53 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.81 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.27 E3 3 Pass Te-123M 2.50-4.43 E2 3.33 E2 3.26 E2 3 Pass Cs-137 0.99-1.75 E3 1.32 E3 1.27 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 -2.75 E4 2.06 E4 2.16 E4 l
3 Pass Co-60 0.88-1.55 E5 1.17 E5 1.16 E5 3 Pass Sr-85 0.80- 1.41 E5 1.06 E5 1.04 E5 3 Pass Y-88 1.42 - 2.52 E5 1.90 E5 1.89 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.82 E5 3 Pass Sn-1 13 6.93 - 12.28 E4 9.24 E4 9.27 E4 3 Pass Cs-137 7.18-12.72 E4 9.57 E4 9.25 E4 3 Pass Ce-139 1.88-3.34 E4 2.51 E4 2.60 E4 3 Pass Hg-203 4.02-7.13 E4 5.36 E4 O.OOE+00 3 Low r
Hg-203 4.02-7.13 E4 5.36 E4 5.41 E4 3 Passe' k4E0 (U'
Section 5 - Page 4
- 6 46
Gamma in Water.15 liters. continued Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCi/l pCi/I 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.35 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.47 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.20 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.24 E3 3 Pass Cd-109 1.38-2.46 E4 1.85 E4 1.77 E4 3 Pass Sn-I 13 2.32 - 4.11 E3 3.09 E3 3.04 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.75 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 7.77 E2 3 Pass Hg-203 N/A N/A N/A N/A (2 Gamma in Water 1.0 liter Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/l 3/29/2005 QOSCGWSL Cr-51 6.44-11.41 E5 8.58 E5 8.25 E5 3 Pass Mn-54 2.26 -4.01 E4 3.02 E4 3.03 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.85 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.55 E4 3 Pass Sr-85 5.11 -9.07 E4 6.82 E4 6.48 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 6.94 E4 3 Pass Cd-109 1.97 - 3.50 E5 2.63 E5 2.64 E5 3 Pass Cs-137 1.64-2.91 E4 2.19 E4 2.04 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.43 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 -6.94 E3 5.22 E3 5.31 E3 3 Pass Co-57 2.14-3.80 E2 2.86 E2 3.09 E2 3 Pass Co-60 1.22-2.16 E3 1.63 E3 1.61 E3 3 Pass Sr-85 1.08-1.91 E3 1.43 E3 1.35 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.50 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.12 E3 3 Pass Sn-I 13 0.98-1.74 E3 1.31 E3 1.28 E3 3 Pass Te-123M 2.50 - 4.43 E2 3.33 E2 3.29 E2 3 Pass Cs-137 0.99-1.75 E3 1.32 E3 1.26 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 - 2.75 E4 2.06 E4 2.12 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 E5 1.15 E5 3 Pass Sr-85 0.80- 1.41 E5 1.06 E5 1.01 E5 3 Pass Y-88 IA2-2.52 E5 1.90 E5 1.88 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.86 E5 3 Pass Sn-I 13 6.93 - 12.28 E4 9.24 E4 9.05 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.05 E4 3 Pass Ce-139 1.88-3.34 E4 2.51 E4 2.54 E4 3 Pass Hg-203 4.02-7.13 E4 5.36 E4 O.OOE+00 3 Low Hg-203 4.02-7.13 E4 5.36 E4 5.32 E4 3 Pass~t Section 5 - Page 5
Gamma in Water 1.0 liter, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCi/l pCi/
11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.29 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.47 E3 3 Pass Sr-85 2.54-4.50 E3 3.38 E3 3.17 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.15 E3 3 Pass Cd-109 1.38-2.46 E4 1.85 E4 1.84 E4 3 Pass Sn-I 13 2.32 - 4.11 E3 3.09 E3 3.02 E3 3 Pass Cs-137 2.17-3.85 E3 2.90 E3 2.71 E3 3 Pass Ce-139 5.89-10.44 E21 7.85 E2 8.04 E2 3 Pass Hg-203 N/A N/A N/A N/A (2)
Gamma in Water 0.5 liter Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/
p, in 3/29/2005 Q051GWSL Cr-51 6.44 - 11.41 E5 8.58 E5 8.54 E5 3 Pass Mn-54 2.26 -4.01 E4 3.02 E4 3.04 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.81 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.70 E4 3 Pass Sr-85 5.11 -9.07 E4 6.82 E4 6.51 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 6.96 E4 3 Pass Cd-109 1.97 -3.50 E5 2.63 E5 2.59 E5 3 Pass Cs-137 1.64-2.91 E4 2.19 E4 2.03 E4 3 Pass Ce-139 1.86-3.30 E4 2.48 E4 2.46 E4 3 Pass 5/12/2005 Q052GWR Cr-51 3.91 -6.94 E3 5.22 E3 5.44 E3 3 Pass Co-57 2.14-3.80 E2 2.86 E2 2.89 E2 3 Pass Co-60 1.22-2.16 E3 1.63 E3 1.62 E3 3 Pass Sr-85 1.08-1.91 E3 1.43 E3 1.35 E3 3 Pass Y-88 1.93 - 3.43 E3 2.58 E3 2.60 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 I
8.24 E3 3 Pass Sn-113 0.98-1.74 E3 1.31 E3 1.34 E3 3 Pass Te-123M 2.50-4.43 E2 3.33 E2 3.63 E2 3 Pass Cs-137 0.99-1.75 E3 1.32 E3 1.28 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 -2.75 E4 2.06 E4 2.09 E4 3 Pass Co-60 0.88-1.55 E5 1.17 E5 1.16 E5 3 Pass Sr-85 0.80- 1.41 E5 1.06 E5 1.00 E5 3 Pass Y-88 1.42-2.52 E5 1.90 E5 1.87 E5 3 Pass Cd-109 4.45 - 7.90 E5 5.94 E5 5.87 E5 3 Pass Sn-113 6.93-12.28 E4 9.24 E4 9.00 E4 3 Pass Cs-137 7.18-12.72 E4 9.57 E4 9.10 E4 3 Pass Ce-139 1.88-3.34 E4 2.51 E4 2.53 E4 3 Pass Hg-203 4.02 -7.13 E4 5.36 E4 O.OOE+00 3 Low Hg-203 4.02-7.13 E4 5.36 E4 5.32 E4 3 Pass~i Section 5 - Page 6
Gamma in Water 0.5 liter. continued Reference Sample L.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCiA piA 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.38 E2 3 Pass Co-60 2.64 -4.68 E3 3.52 E3 3.55 E3 3 Pass Sr-85 2.54 - 4.50 E3 3.38 E3 3.22 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.10 E3 3 Pass Cd-109 1.38-2.46 E4 1.85 E4 1.75 E4 3 Pass Sn-I 13 2.32 - 4.11 E3 3.09 E3 2.94 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.77 E3 3 Pass Ce-139 5.89 - 10.44 E2 7.85 E2 8.03 E2 3 Pass Hg-203 N/A N/A N/A N/A (2)
Gamma in Water 0.25 liter Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi pCiA 3/29/2005 Q051GWSL Cr-51 6.44-11.41 E5 8.58 ES 8.45 ES 3 Pass Mn-54 2.26 -4.01 E4 3.02 E4 3.12 E4 3 Pass Co-57 1.36 - 2.42 E4 1.82 E4 1.86 E4 3 Pass Co-60 2.82 - 5.00 E4 3.76 E4 3.69 E4 3 Pass Sr-85 5.11 -9.07 E4 6.82 E4 6.57 E4 3 Pass Y-88 5.42 - 9.60 E4 7.22 E4 7.05 E4 3 Pass Cd-109 1.97 -3.50 E5 2.63 ES 2.72 ES 3 Pass Cs-137 1.64 - 2.91 E4 2.19 E4 2.08 E4 3 Pass Ce-139 1.86 - 3.30 E4 2.48 E4 2.51 E4 3 Pass 5/12/2005 Q052GWR Cr-SI 3.91 -6.94 E3 5.22 E3 5.34 E3 3 Pass Co-57 2.14-3.80 E2 2.86 E2 2.95 E2 3 Pass Co-60 1.22-2.16 E3 1.63 E3 1.58 E3 3 Pass Sr-85 1.08-1.91 E3 1.43 E3 1.34 E3 3 Pass Y-88 1.93 -3.43 E3 2.58 E3 2.61 E3 3 Pass Cd-109 6.15 - 10.91 E3 8.20 E3 8.74 E3 3 Pass Sn-113 0.98 - 1.74 E3 1.31 E3 1.28 E3 3 Pass Te-123M 2.50-4.43 E2 3.33 E2 3.43 E2 3 Pass Cs-137 0.99-1.75 E3 1.32 E3 1.23 E3 3 Pass 8/10/2005 Q053GWS Co-57 1.55 -2.75 E4 2.06 E4 2.16 E4 3 Pass Co-60 0.88 - 1.55 E5 1.17 ES 1.17 E5 3 Pass Sr-85 0.80- 1.41 ES 1.06 E5 1.03 E5 3 Pass Y-88 1.42 - 2.52 ES 1.90 ES 1.88 ES 3 Pass Cd-109 4.45 - 7.90 ES 5.94 ES 6.19 ES 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.16 E4 3 Pass Cs-137 7.18-12.72 E4 9.57 E4 9.23 E4 3 Pass Ce-139 1.88-3.34 E4 2.51 E4 2.54 E4 3 Pass Hg-203 4.02 - 7.13 E4 5.36 E4 O.OOE+O0 3 Low Hg-203 4.02-7.13 E4 5.36 E4 S.SO E4 3 Pass~l I
Section 5 -Page 7
Gamma in Water 0.25 liter. continued Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCitl pCill 11/21/2005 Q054GWR Co-57 4.68 - 8.30 E2 6.24 E2 6.92 E2 3 Pass Co-60 2.64 - 4.68 E3 3.52 E3 3.53 E3 3 Pass Sr-85 2.54 -4.50 E3 3.38 E3 3.25 E3 3 Pass Y-88 4.73 - 8.38 E3 6.30 E3 6.26 E3 3 Pass Cd-109 1.38-2.46 E4 1.85 E4 1.93 E4 3 Pass Sn-113 2.32 - 4.11 E3 3.09 E3 3.06 E3 3 Pass Cs-137 2.17 - 3.85 E3 2.90 E3 2.87 E3 3 Pass Ce-139 5.89-10.44 E2 7.85 E2 8.11 E2 3 Pass I
Hg-203 N/A N/A N/A N/A (2)
Gamma in Water 0.05 liter Reference Sample 1.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA_
pCi/I pCil 8/10/2005 Q053GWS Co-57 1.55 -2.75 E4 2.06 E4 2.14 E4 3 Pass Co-60 0.88 - 1.55 ES 1.17 ES 1.18 E5 3 Pass Sr-85 0.80- 1.41 ES 1.06 ES 1.03 ES 3 Pass Y-88 1.42 - 2.52 E5 1.90 ES 1.86 ES 3 Pass Cd-109 4.45 -7.90 ES 5.94 ES 5.95 E5 3 Pass Sn-113 6.93 - 12.28 E4 9.24 E4 9.17 E4 3 Pass Cs-137 7.18 - 12.72 E4 9.57 E4 9.05 E4 3 Pass Ce-139 1.88-3.34 E4 2.51 E4 2.59 E4 3 Pass g-203 4.02 -7.13 E4 5.36 E4 0.OOE+00 3 Low Hg-203 4.02-7.13 E4 5.36 E4 5.23 E4 3 Pass" Gamma in Filter Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status I
pCi pCO pCi 7/15/2005 1120-63-1 Co-57 3.48 -6.17 E3 4.64 E3 4.74 E3 3 Pass Co-60 1.86 - 3.30 E4 2.48 E4 2.42 E4 3 Pass Sr-85 2.21 - 3.91 E4 2.94 E4 2.82 E4 3 Pass Y-88 3.54 - 6.27 E4 4.72 E4 4.69 E4 3 Pass Cd-109 0.97 - 1.72 E5 1.30 E5 1.26 E5 3 Pass Sn-113 1.70-3.02 E4 2.27 E4 2.24 E4 3 Pass Cs-137 1.51 -2.68 E4 2.01 E4 1.91 E4 3 Pass Ce-109 4.51 -8.00 E3 6.01 E3 5.96 E3 3 Pass Hg-203 0.99-1.76 E4 1.32 E4 1.38 E4 3 Pass 12/8/2005 E4806-37 Cr-51 1.02 - 2.15 E2 1.48 E2 1.49 E2 3 Pass Mn-54 0.88 -1.56 E2 1.17 E2 1.24 E2 3 Pass Co-58 4.43 -7.85 El 5.90 El 5.79 El 3 Pass Fe-59 4.73-8.38 El 6.30 El 6.92 El 3 Pass Co-60 6.38 - 11.31 El 8.50 El 8.51 El 3 Pass Zn-65 0.89 - 1.57 E2 1.18 E2 1.16 E2 3 Pass Cs-134 5.03 - 8.91 El 6.70 El 6.47 El 3 Pass Cs-137 1.09-1.93 E2 1.45 E2 1.37 E2 3 Pass Ce-141 1.29-2.29 E2 1.72 E2 1.70 E2 3 Pass Section 5 - Page 8
Iodine in Water Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/Q pCit pCi/t 3/9/2005 Q05 ILIW I 1-131 N/A O.OOE+00 O.OOE+00 3 Pass 3/912005 Q051LIW2 1-131 1.99-3.53 E2 2.65 E2 3.20 E2 3 Pass 3/9/2005 Q051LIW3 1-131 1.66-2.94 E3 2.21 E3 2.31 E3 3 Pass 8/8/2005 Q053LIW1 1-131 2.87-5.09 E2 3.82 E2 3.74 E2 3 Pass 8/8/2005 Q053LIW2 1-131 2.83 -5.01 El 3.77 El 3.36 El 3 Pass 8/8/2005 Q053LIW3 1-131 N/A O.OOE+00 O.OOE+00 3 Pass Iodine in Milk Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status IIpCiAI pCiAI pCi/l 5/4/2005 Q052LIMI 1-131 5.67 - 10.05 El 7.55 El 6.95 El 3 Pass 5/4/2005 Q052LIM2 1-131 16.76-11.98 El 9.01 El 8.85 El 3 Pass 5/4/2005 lQ052LIM3 I -131 N/A l
O.OOE+00 l
O.OOE+00 l
3 Pass 11/21/2005 lQ054LIMI I -131 l1. 13 -2.00 E27 1.50 E2 1.50 E2 7
3 Pass 1lt2t/2005 lQ054LIM2 1-131 2.76 -4.89 El l 3.68 El 3.43 El I 3 Pass' 11/21/2005 Q054LIM3 1-131 3.94-9.07 EO 5.96 EO 5.18 E0 3 Pass Iodine on Cartridge Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pci pCi pci 5/l/2005 1103-74-4 1-131 3.16-5.60 E5 4.21 E5 3.89 E5 3 Pass Cs-137 N/A N/A 3.45 El N/A (3) 8/15/2005 1120-63-2 1-131 2.30-4.09 E5 3.07 E5 3.38 E5 3 Pass 12/8/2005 E4807-37 1-131 5.55 - 9.84 El 7.40 El 8.23 El 3 Pass Beta in Water Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/A pCi/
pCi/A 3/17/2005 E4484-37 Beta 2.01 - 3.56 E2 2.68 E2 2.35 E2 3 Pass 6/23/2005 lQO52ABWI Beta 3.79-6.71 E2 5.05 E2 4.88 E2 3 Pass Section 5 - Page 9
Beta in Water, continued Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCiA pCiAI 6/23/2005 Q052ABW2 Beta 2.02 - 3.59 E2 2.70 E2 2.56 E2 3 Pass 6/23/2005 Q052ABW4 Beta 2.08 - 3.69 E2 2.77 E2 2.58 E2 3 Pass 6/23/2005 Q052ABW5 Beta 5.06 - 8.97 El 6.75 El 6.19 El 3 Pass 9/15/2005 E4710-37 Beta 0.92-1.64 E2 1.23 E2 1.33 E2 3 Pass Beta Air Partculate Reference Sample T.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pci Po.
pCi 8/19/2005 A19486-37 Cs-137 0.96-1.70 E4 1.28 E4 1.21 E4 3 Pass Beta Smear Reference Sample l.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status dpm dpmr dpm 2/25/2005 A18848-37 Beta 4.71 -8.36 E3 6.28 E3 6.44 E3 3 Pass 2/25/2005 A18850-37 Beta 0.98-1.74 E4 1.31 E4 1.25 E4 3 Pass 8/19/2005 A19484-37 Cs-137 0.87-1.55 E4 1.17 E4 1.21 E4 3 Pass 11/1/2005 A19759-37 Beta 0.96-1.70 E4 1.28 E4 1.18 E4 3 Pass Tritum in Water Reference Sample I.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCiA 4/19/2005 QOSITWSLI H-3 1.44-2.55 E5 1.92 E5 1.80 E5 3 Pass 4/19/2005 QOITWSL2 H-3 N/A O.OOE+00 O.OOE+00 3 Pass 5/12/2005 Q052TWRI H-3 1.86-3.30 E3 2.48 E3 2.33 E3 3 Pass 5/IV2/2005 7 QO52TWR2 H-3 N/A O.OOE+00 0.00E+00 3 Pass 5/12/2005 1 Q052TWR3 H-3 2.67 - 6.74 E2 4.24 E2 3.68 E2 3 Pass (Ii' Section 5 - Page 10
lb) 6V V0 W
O V
W kJ V
w V0 V4 V0 V0 V0 Vo
%V VO V4 w
Vo OA Tritium in Water, continued Reference Sample 1.D.
Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/A pCi/l pCi/l 7/20/2005 Q053TWSI H-3 N/A O.OOE+00 0.OOE+00 3 Pass 7/20/2005 Q053TWS2 H-3 4.21 - 7.46 E4 5.61 E4 5.25 E4 3 Pass 7/20/2005 Q053TWS3 l
H-3 1.54 - 2.73 E5 2.05 E5 1.94 E5 3 Pass 11/21/2005 Q054TWRI H-3 1.64-2.90 E3 2.18 E3 2.12 E3 3 Pass 11/1/1/2005 Q054TWR2 H-3 2.98 - 8.02 E2 4.89 E2 3.68 E2 3 Pass 11/21/2005l Q054TWR3 H-3 N/A O.OOE+00 O.OOE+00 3 Pass Section S - Page II
Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q053GWS, Reference Date 8/10/2005: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli, 0.05 L bottle Failure to identify Hg-203 [279.19 keV] during initial cross-check analysis.
(J Gamma spectroscopy library "XENVIRON" updated to include Hg-203 nuclide.
Cross-check reanalyzed, yielding acceptable data.
PIP G-05-00331 written to record corrective actions taken.
(2) Gamma in Water, Sample ID Q054GWR, Reference Date 11/21/2005: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Cross-check analysis yielded low Hg-203 results for all geometries tested.
Investigation indicated Hg-203 volatility (plate out) despite cross-check preservation. PIP G-06-00038 written.
4 (3) Iodine on Cartridge, Sample 1103-74-4, Reference Date 5/l/2005 Cs-137 observed in all cross-check analyses. There was no reference value for Cs-137 in this cross-check. Cs-137 is a known contaminant of charcoal cartridges (Reference 6.13). Iodine-131 data were acceptable.
Section 5 - Page 12
TABLE 5.0-B 2005 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100260 95.4 104.1 9.12
<+/-15%
Pass 100225 95.4 96.4 1.05
<+/-15%
Pass 100266 95.4 101.9 6.81
<+/-15%
Pass 100147 95.4 96.3 0.94
<+/-15%
Pass 100112 95.4 103.5 8.49
<+/-15%
Pass Average Bias (B) 5.28 Standard Deviation (S) 4.00 Measure Performance IBI+S 9.29
<15%
Pass 2nd Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100053 76.4 78.4 2.62
<+/-15%
Pass 100056 76.4 79.1 3.53
<+/-15%
Pass 100762 76.4 71.2
-6.81
<+/-15%
Pass 100870 76.4 78.6 2.88
<+/-15%
Pass 100873 76.4 76.4 0.00
<+/-15%
Pass Average Bias (B) 0.45 Standard Deviation (S) 4.27 Measure Performance IBI+S 4.72
<15%
Pass 3rd Quarter 2005 TLD Delivered Reported Number (mrem)
(mrem) 101124 92.0 96.8 101136 92.0 98.0 101249 92.0 94.8 101366 92.0 97.5 101241 92.0 95.2 Average Bias (B)
Standard Deviation (S)
Measure Performance IBI+S Bias Pass/Fail
(% diff)
Criteria Pass/Fail 5.22
<+/-15%
Pass 6.52
<+/-15%
Pass 3.04
<+/-15%
Pass 5.98
<+/-15%
Pass 3.48
<+/-15%
Pass 4.85 1.53 6.38
<15%
Pass 4th Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 102037 62.5 63.3 1.28
<+/-15%
Pass 102233 62.5 65.5 4.80
<+/-15%
Pass 102234 62.5 62.7 0.32
<+/-I 5%
Pass 102454 62.5 63.1 0.96
<+/-15%
Pass 102060 62.5 62.6 0.16
<+/-15%
Pass Average Bias (B) 1.50 Standard Deviation (S) 1.90 Measure Performance IBI+S 3.40
<15%
Pass State of North Carolina, Division of Radiation Protection Spring 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100089 60.0 63.0 5.00
<+/-15%
Pass 100215 60.0 59.8
-0.33
<+/-15%
Pass 100268 60.0 59.0
-1.67
<+/-15%
Pass 100110 60.0 58.9
-1.83
<+/-15%
Pass 100814 60.0 58.5
-2.50
<+/-15%
Pass 100411 60.0 61.7 2.83
<+/-15%
Pass 100154 60.0 55.9
-6.83
<+/-15%
Pass 100174 60.0 59.7
-0.50
<+/-15%
Pass Average Bias (B)
-0.73 Standard Deviation (S) 3.55 Measure Performance IBI+S 4.28
<15%
Pass Fall 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100076 30 29.6
-1.33
<+/-15%
Pass 101309 30 30.7 2.33
<+/-15%
Pass 101314 30 31.0 3.33
<+/-15%
Pass 101306 30 29.7
-1.00
<+/-1 5%
Pass 101209 30 29.3
-2.33
<+/-15%
Pass 101281 30 30.5 1.67
<+/-15%
Pass 100631 30 28.8
-4.00
<+/-15%
Pass 101188 30 31.4 4.67
<+/-15%
Pass Average Bias (B) 0.42 Standard Deviation (S) 3.02 Measure Performance IBI+S 3.44
<15%
Pass Section 5 - Page 13
Internal Crosscheck (Duke Power) 1st Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 101035 50.0 46.3
-7.33
<+/-15%
Pass 100215 50.0 48.4
-3.29
<+/-15%
Pass 100411 50.0 48.9
-2.13
<+/-15%
Pass 100174 50.0 48.7
-2.52
<+/-15%
Pass 100154 50.0 46.5
-6.92
<+/-I 5%
Pass 100089 50.0 52.6 5.24
<+/-15%
Pass 100814 50.0 47.8
-4.44
<+/-15%
Pass 100786 50.0 47.9
-4.25
<+/-1 5%
Pass 100455 50.0 55.0 9.92
<+/-15%
Pass 100354 50.0 48.9
-2.19
<+/-15%
Pass Average Bias (B)
-1.79 Standard Deviation (S) 5.37 Measure Performance IBI+S 7.16
<15%
Pass 2nd Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 102394 50.0 47.3
-5.49
<+/-15%
Pass 102390 50.0 47.8
-4.45
<+/-15%
Pass 102490 50.0 47.0
-5.94
<+/-15%
Pass 102507 50.0 47.2
-5.66
<+/-15%
Pass 102508 50.0 47.2
-5.53
<+/-15%
Pass 102509 50.0 48.3
-3.39
<+1-l 5%
Pass 102510 50.0 47.5
-5.09
<+/-15%
Pass 102521 50.0 47.5
-5.09
<+/-15%
Pass 102391 50.0 47.9
-4.22
<+/-15%
Pass 102389 50.0 48.8
-2.39
<+/-15%
Pass Average Bias (B)
-4.73 Standard Deviation (S) 1.13 Measure Performance lBl+S 5.85
<15%
Pass 3rd Quarter 2005 TLD Delivered Reported Number (mrem)
(mrem) 102402 50.0 48.8 102367 50.0 47.9 102369 50.0 48.9 102361 50.0 47.9 102346 50.0 47.7 102343 50.0 49.7 102399 50.0 48.9 102398 50.0 48.7 102400 50.0 48.8 102401 50.0 49.1 Average Bias (B)
Standard Deviation (S)
Measure Performance IBI+S Bias Pass/Fail
(% diff)
Criteria Pass/Fail
-2.34
<+/-15%
Pass
-4.14
<+/-15%
Pass
-2.13
<+/-15%
Pass
-4.26
<+/-15%
Pass
-4.67
<+/-15%
Pass
-0.66
<+/-15%
Pass
-2.14
<+/-15%
Pass
-2.52
<+/-15%
Pass
-2.48
<+/-15%
Pass
-1.77
<+/-15%
Pass
-2.71 1.26 3.97
<15%
Pass 4th Quarter 2005 TLD Delivered Reported Bias Pass/Fail Number (mrem)
(mrem)
(% diff)
Criteria Pass/Fail 100308 62.0 61.1
-1.45
<+/-15%
Pass 100312 62.0 63.5 2.42
<+/-15%
Pass 100313 62.0 62.0 0.01
<+/-15%
Pass 100316 62.0 60.1
-3.01
<+/-15%
Pass 100317 62.0 59.2
-4.59
<+/-15%
Pass 100318 62.0 61.0
-1.60
<+/-15%
Pass 100319 62.0 60.4
-2.57
<+/-15%
Pass 100321 62.0 60.9
-1.75
<+/-15%
Pass 100322 62.0 59.2
-4.56
<+/-15%
Pass 100327 62.0 63.1 1.71
<+/-15%
Pass Average Bias (B)
-1.54 Standard Deviation (S) 2.37 Measure Performance IBI+S 3.90
<15%
Pass 4mw (I-0
~UP 4.01 Section 5 - Page 14
6.0 REFERENCES
6.1 Catawba Selected License Commitments 6.2 Catawba Technical Specifications 6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 2004 6.6 Catawba Annual Effluent Report 1985 - 2005 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.
6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.
6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.
6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report 05-04 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page I
APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PRO CEDURES Appendix A - Page I
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and 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.
Environmental sampling and analyses were performed by EnRad Laboratories, 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 Location 258 (Air Radioiodine, Air Particulate, Vegetation) was added as a replacement for control location 217, which was removed from the program.
A special interest TLD was placed at location 258.
Movement of the control air radioiodine, air particulate, and vegetation location is described in PIP C-02-06038.
Location 217 remains a control TLD location.
Il. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.
Low-level iodine analyses are performed by passing a designated sample aliquot through a pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being transferred to appropriate counting geometry i
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 or Perkin-Elmer 2900TR liquid scintillation system. Tritium samples are batch processed with a Appendix A - Page 2
tritium spike to verify instrument performance and sample preparation technique are acceptable.
Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Tennelec XLB Series 5 gas-flow proportional counters.
Samples are batch processed with a blank to ensure sample contamination has not occurred.
II.
CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2005.
IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of five locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned 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 separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.
Location 200
=
Site Boundary (0.63 mi. NNE)
Location 201
=
Site Boundary (0.53 mi. NE)
Location 205
=
Site Boundary (0.23 mi. SW)
Location 212
=
Tega Cay (3.32 mi. E)
Location 258
=
Fairhope Road (9.84 mi. W)
A.2 DRIKING WATER Monthly composite drinking water samples were collected at each of two locations. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected monthly from the locations listed below.
Location 214
=
Rock Hill Water Supply (7.30 mi. SSE)
Location 218
=
Belmont Water Supply (13.5 mi. NNE)
Appendix A - Page 3
A3 SURFACE WATER Monthly 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 monthly from the locations listed below.
Location 208 Location 211 Location 215 AA GROUND WATER Discharge Canal (0.45 mi. S)
Wylie Dam (4.06 mi. ESE)
River Pointe - Hwy 49 (4.21 mi. NNE)
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.
Q~
kC-4C Location 252 Location 254 Residence (0.64 mi. SW)
Residence (0.82 mi. N)
AS MILK Biweekly grab samples were collected at one location. A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the location listed below.
Q..
Location 221
=
Dairy (14.5 mi. NW)
A.6 BROADLEAF VEGETATION Monthly samples were collected at each of five locations. A gamma analysis was performed on each sample. The samples were collected from the locations listed below.
Q~
Location 200 Location 201 Location 222 Location 226 Location 258 Site Boundary (0.63 mi. NNE)
Site Boundary (0.53 mi. NE)
Site Boundary (0.70 mi. N)
Site Boundary (0.48 mi. S)
Fairhope Road (9.84 mi. W)
Appendix A - Page 4
A.7 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
=
Irrigated Gardens (1.90 mi. SSE)
A.8 FISH Semiannual samples were collected at each of two locations. A gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.
Location 208
=
Discharge Canal (0.45 mi. S)
Location 216
=
Hwy 49 Bridge (4.19 mi. NNE)
A.9 SHORELINE SEDIMENT 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 clams. The samples were collected from the locations listed below.
Location 208
=
Discharge Canal (0.45 mi. S)
Location 210
=
Ebenezer Access (2.31 mi. SE)
Location 215
=
River Pointe - Hwy 49 (4.21 mi. NNE)
A.10 DIRECT GAMMA RADIATION (TLD)
Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations. A gamma exposure rate was determined for each TLD.
TLD locations are listed in Table 2.1-B. 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.
Appendix A - Page 5
A11 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 Garden greater than 50 square meters or 500 square feet The Nearest Milk-giving Animal (cow, goat, etc.)
The census was conducted during the growing season on 7/5 and 7/6/2005.
Results are shown in Table 3.11. No changes were made to the sampling procedures during 2005 as a result of the 2005 census.
(
C V.
GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The Catawba site centerline used for GPS measurements was referenced from the Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location.
Waypoint coordinates used for CNS GPS measurements were latitude 350-3'-5"N and longitude 81'-4'-10"W.
Maps and tables were generated using North American Datum (NAD) 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement. All GPS field measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.
i Appendix A - Page 6
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 2005 Appendix B - Page 1
'U,'
4..
Qu Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005
'V.
TypeandNo.
of Non Medium or Tote and Lower All Indicator Locaon with Highest Control Routine Pathway Numbr Limit of ALocations Annual Mean Location Report Sampled of DetectionName, Distance, Direction Meas.
Unit of Analyses Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Measurement Performed (LLD)
Range Code Range Range Air Particulate 258 (pCi/m3)
(9.84 mi W)
BETA 265 11.OOE-02 1.62E-2 (212/212) 200 1.66E-2 (53/53) 1.68E-2 (53/53) 0 2.56E 3.14E-2 (0.63 mi NNE) 7.55E 3.12E-2 6.91E 3.28E-2 CS-134 265 5.OOE-02 0.00 (0/212) 0.00 (0/53) 0.00 (0/53) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 265 6.00E-02 0.00 (0/212) 0.00 (0/53) 0.00 (0/53) 0 0.00- 0.00 0.00 -0.00 0.00 - 0.00 1-131 265 7.00E-02 0.00 (0/212) 0.00 (0/53) 0.00 (0/53) 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 (U
- i Report Generated @ 12412006 6:37 AM Appendix B - Page 2 km
Environmental Radiological Monitoring Program Summary A) Facility: Catawba Nuclear Station b
Location: York County, South Carolina Docket No.
50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 Medium or Type and Lower Location with Highest No. of Non-Pathway Total Limit of All Indicator Annual Mean Cntrol Routine Sampled Nuober Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses (LLD)
Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Measurement Performed Range Code Range Range Air Radioiodine 258 (pCi/m3)
(9.84 mi W)
CS-134 265 5.OOE-02 0.00(0/212) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 CS-137 265 6.00E-02 0.00 (0/212) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 265 7.00E-02 0.00(0/212) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/24/2006 6:39 AM Appendix B - Page 3
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50413,414 Report Period: O1-JAN-2005 to 31-DEC.2005 Medium or Type and Total Lower All Idit Location with Highest Contol No. of Non-Pathway Number Limit of Annual Mean Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LLD)
Range Code Range Range Drinking Water 218 (pCi/liter)
(13.5 mi NNE)
BALA-140 26 15 0.00(0/13) 0.00(0114) 0.00(0113) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 BETA 26 4
2.05 (13/13) 214 2.05 (13/13) 1.84 (13/13) 0 0.79 - 3.62 (7.30 mni SSE) 0.79 - 3.62 0.64 - 2.50 e
CO-58 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/14) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00(0/13) 0.00(0114) 0.00(0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 CS-137 26 18 0.00(0/13) 0.00(0/14) 0.00(0/13) 0 0.00 -0.00 0.00 - 0.00 0.00- 0.00 FE-59 26 30 0.00 (0/13) 0.00(0/14) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00- 0.00 H-3 8
2000 769 (4/4) 214 769 (4/4) 450 (4/4) 0 393-1200 (7.30miSSE) 393-1200 317-543 1-131 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/14) 0.00(0/13) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 NB-95 26 15 0.00 (0/13) 0.00(0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 ZN-65 26 30 0.00(0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 ZR-95 26 15 0.00(0/13) 0.00 (0/14) 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 Report Generated @ 1/24/2006 6:42 AM Appendix B - Page 4 L
Environmental Radiological Monitoring Program Summary WI Facility: Catawba Nuclear Station
@i Location: York County, South Carolina Docket No.
50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 Medium or Type and Total Lower Location with Highest No. of Non-Paha Nubr Lmto All Indicator Control Routine Pathway Number Limt of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location RMepaosr Unit of Analyses Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Measurement Performed (ID)
Range Code Range Range Surface Water 215 (pCi/liter)
(4.21 mi NNE)
BALA-140 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 CO-5B 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 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00(0/26) 0.00(0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 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 H-3 1 2 2000 7387 (8/8) 208 14000 (4/4) 378 (4/4) 0 492 - 18000 (0.45 mi S) 8240 - 18000 271 - 556 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13)
° 0.00- 0.00 0.00- 0.00 0.00 - 0.00 MN-54 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 NB-95 39 15 0.00 (0126) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/24/2006 6:46 AM Appendix B - Page 5
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50.413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 t.
Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of locaton Annual Mean Lontion Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LLD)
Range Code Range Range Ground Water NO CONTROL (pCi/liter)
LOCATION I
BALA-140 8
15 0.00(0/8) 0.00(0/8) 0.00(0/0) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 CO-58 8
15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 L.
0.00-0.00 0.00- 0.00 0.00 - 0.00 CO-60 8
15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 CS-134 8
15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 8
18 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 Q
FE-59 8
30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8
2000 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 L) 0.00 - 0.00 0.00- 0.00 0.00- 0.00 1-131 8
15 0.00(0/8) 0.00(0/8) 0.00(0/0) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 8
15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00- 0.00 0.00- 0.00 NB-95 8
15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 ZN-65 8
30 0.00(0/8) 0.00(0/8) 0.00 (0/0) 0 0.00-0.00 0.00- 0.00 0.00 - 0.00 ZR-95 8
15 0.00 (0/8) 0.00 (018) 0.00 (0/0) 0 0.00- 0.00 0.00 - 0.00 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements k.av Report Generated @ 1/24/2006 6:47 AM Appendix B - Page 6
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses LLD Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed (L
)
Range Code Range Range Milk NO INDICATOR 221 (pCiAiter)
LOCATION (14.5 mi NW)
BALA-140 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00(0/0) 0.00(0/0) 0.00(0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00(0/0) 0.00(0/0) 0.00(0/26) 0 0.00 -0.00 0.00 - 0.00 0.00 - 0.00 1-131 26 15 0.00(0/0) 0.00(0/0) 0.00(0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 LLI-1 31 26 1
0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/24/2006 6:48 AM Appendix B - Page 7
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 kwi 4Q Medium or Type and Total Lower Location with Highest No. of Non-All Indicator Control Routine Pathway Number Limit of Annual Mean Lo R
Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Li Unit of Analyses LLD Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Measurement Performed (D)
Range Code Range Range Broadleaf 258 Vegetation (9.84 mi W)
(pCi/kg-wet)
.i; CS-134 60 60 0.00 (0/48) 0.00 (0/12) 0.00 (0/12) 0 X
0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 v
CS-137 60 80 50.0(5/48) 222 54.8(1/12) 0.00(0/12) 0 i;
38.0 - 66.5 (0.70 mi N) 54.8 - 54.8 0.00 - 0.00 1-131 60 60 0.00(0/48) 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 Report Generated @ 1/24/2006 6:51 AM Appendix B - Page 8
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50.413,414 Report Period: 01-JAN-2005 to 31-DEC.2005 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of Locator Annual Mean Control Rout Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses (LLD)
Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet)
LOCATION CS-134 5
60 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 5
80 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 5
60 0.00(0/5) 0.00 (0/5) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/24/2006 6:52 AM Appendix B - Page 9
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50.413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 4..
Medium or Type and Total Lower All Idit Location with Highest Control No. of Non-Pathway Number Limit of Locator Annual Mean Control Rout Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses LL Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LD)
Range Code Range Range Fish 216 (pCi/kg-wet)
(4.19 mi NNE)
CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 (0/6) 0.00- 0.00 CO-60 12 130 0.00(0/6) 0.00-0.00 0.00(0/6) 0 0.00-0.00 0.00 (0/6) 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 - 0.00 0.00- 0.00 CS-137 12 150 0.00(0/6) 0.00-0.00 0.00(0/6) 0 0.00 - 0.00 0.00 (0/6) 0.00- 0.00 FE-59 12 260 0.00(0/6) 0.00(0/6) 0.00(0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00(0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00- 0.00 0.00 -0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/24/2006 6:54 AM Appendix B - Page 10
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station
)
Location: York County, South Carolina Docket No.
50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 Medium or Type and Total Lower All Indicator Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses Mean (Fraction)
Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LLD)
Range Code Range Range Shoreline 215 Sediment (4.21 mi NNE)
(pCi/kg-dry)
MN-54 6
0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0.00 - 0.00 0.00 - 0.00 0.00 -0.00 CO-58 6
0 161 (1/4) 208-1S 161 (1/2) 0.00(0/2) 0 161-161 (0.45 mi S) 161 - 161 0.00 - 0.00 CO-60 6
0 141 (2/4) 208-1S 141 (2/2) 0.00(0/2) 0 72.7 - 210 (0.45 mi S) 72.7 - 210 0.00- 0.00 CS-134 6
150 0.00(0/4) 0.00(0/2) 0.00(0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6
180 27.1 (2/4) 208-IS 30.4 (1/2) 0.00 (0/2) 0 23.8 - 30.4 (0.45 mi S) 30.4 - 30.4 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 @ 1/26/2006 3:30 PM Appendix B - Page II
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.
50-413,414 Report Period: 01-JAN-2005 to 31-DEC-2005 Type and Lower No. of Non-Medium or Total L
of All Indicator awith Highest Control Routine Pathway Sampled Number Detction Locations Name, Distance, Direction Report of Deeto ae itne iehnMeas.
i Analyses Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction) 4 Performed Range Code Range Range Direct Radiation 217 (10.3 mi SSE)
TLD 247 (7.33 mi ESE)
(mR/standard quarter) 251 (9.72 mi WNW) 162 O.OOE+00 19.1 (150/150) 235 25.7 (4/4) 14.4 (12/12) 0 10.7 - 28.0 (4.07 mi ESE) 21.8 - 28.0 10.6 - 19.3 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 1/2412006 7:06 AM Appendix B - Page 12 I
6m-~Q kmm I;;
G~
t.0 C£
APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page I
APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES
'4W C
DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment interrupted by breaker trip; probable cause was recent storm. Equipment ran for about 68.29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />. Breaker was reset, power restored, 200 5/17-5/24/2005 5/17-5/20/2005 PO and normal sampling was resumed.
Drinking Water Scheduled Actual Reason Location Colection Dates Codection Code Corrective Action Dates 7
0 Water supply to reservoir was turned off by water treatment plant personnel despite an existing sign on supply valve requesting Duke Energy Corporation be contacted prior to shutting off water supply. A grab sample was collected, flow restored, and 218 11/22-12/20/2005 12/20/2005 OT normal sampling was resumed.
Surface Water Scheduled Actual Reason Location Collection Dates Collection Code Corrective Action Dates Power to sampling equipment interrupted during composite period. Power was restored, a grab sample collected, and 211 10/25-11/22/2005 11/22/2005 PI normal sampling resumed.
Appendix C - Page 2
C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 227 1
12115-3/1612005 1 CN ITLD missing. 2nd quarter 2005 TLD placed in field.
250 9/14-12/14/2005 CN TLD missing. " quarter 2006 TLD placed in field.
Appendix C - Page 3
APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2005 Radiological Environmental Monitoring Program Appendix D - Page I
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2005. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.
Appendix E - Page I