ML20082R926
| ML20082R926 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1994 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505020278 | |
| Download: ML20082R926 (124) | |
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i U. S. Nuclear Regulatory Commission -
A'ITN: Document Control Desk Washington, DC 20555 Sul$tt:
Catawlwi Nuclear Station, Units 1 and 2 Docket Nos. 50413 and 50-414 l
19W Annual Radiological I?nvironmental O wrating Report l
Pursuarit to Technical S,wification 6.9,1.6, find attached the 1994 Annual Radiological j
I!nvironmental Olvrating Report. This relmrt covers the ogwration of Catawlwi Units 1 and 2 during the 1994 calendar year, l
Sincerely, O
4 D. L Rehn Kl!N/94Rl!OR I
Attachment xc:
(W/O Apiwndix IIof Attaciunent) i S. D.1,hneter, Regional Administrator R. I!. Martin, ONRR i
i R. J lireudenlerger, SRI i
9505020273 941231
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ANNUAL FIADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY CATAWBA NUCLEAR STATION UNITS 1 AND 2 JANUARY 1,1994 - DECEMBER 31,1994
1994 CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS TITLE PAGE 1
i List of Figures....
............................................. v Li st o f Ta bl e s................................................... vi 1.
Executive S ummary.......................................
1 -1 2.
Introduction.............................................
2-1 2.1 Site Description and Sample Locations..................... 2-1 2.2 Scope and Requirements of the Environmental Monitoring Program 2-2 2.3 Statistical and Cak ulational Methodology................... 2-3 2.3.1 Estimation of the Mean Value 2-3 2.3.2 Lower Limit of Detection and Minimum Detectable A cti vi t y......................................
2-4 2.3.3 Trend Identification..............................
2-5 2.3.4 Test Statistics.................................
2-6 3.
Radiological Environmental Monitoring Program - Discussion, Interpretation, and Trending of Results..........................
3-1 3.1 Airborne Radioiodines and Particulates..................... 3-4 3.1.1 Ra diciodines..................................
3-4 3.1.2 Particulate s...................................
3-4 t
3.2 G round Wate r......................................
3-4 3.3 Drinking Wate r......................................
3-4 3.4 S urfa c e Wa ter......................................
3-5 3.5 Milk............................................3-11 i
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I
e TABLE OF CONTENTS (Continued)
TITLE PAGE 3.6 Broadleaf Vegetation
................................3-11 3.7 Sh oreline Sediment..................................
3-12 3.8 Fish
............................................3-16 3.9 Direct Gamma Radiation (TLD).......................... 3-20 3.10 Food Prod ucts.....................................
3-2 3 3.11 Bottom Sediment...................................
3-23 3.12 Land Use Census...................................
3-27 4.
Evaluation of Dose From Environmental Measurements Versus Estimated Dose From Releases
...............................4-1 4.1 Dose from Environmental Measurements.................... 4-1 4.2 Estimated Dose from Releases........................... 4-3 4.3 Com parison of Doses.................................
4-3 5.
Quality A ssura nce.......................................
5-1 5.1 Radiological Environmental Monitoring Program............... 5-1 5.1.1 S am ple Collection...............................
5-1 5.1. 2 S a m ple Analysis................................
5-1 5.1.3 Dosimetry Analysis............................,.
5-1 5.1.4 Intralaboratory Quality Assurance.................... 5-1 5.1.5 Interlaboratory Quality Assurance.................... 5-1 5.2 Contra ctor Laboratory.................................
5-3 ii
TABLE OF CONTENTE (Continued)
TITLE PAGE 6.
Ref erences.............................................
6-1 Appendix A Environmental Sampling and Analysis Procedures A-1 1.
Change of Sampling Procedures.......................... A-1 11.
Change of Analysis Procedures.......................... A-1 Ill.
Sampling and Analysis Procedures........................ A-1 IV.
Sampling and Analysis improvements...................... A-3 Appendix B Radiological Environmental Monitoring Program Summary of Analysis Results..................... B-1 B.1 Airborne Radioiodines and Particulates..................... B-1 B.1.1 Radioiodines B-1 B.1. 2 Pa rtic ulates...................................
B-1 B.2 G rou n d Wa t e r......................................
B-1 B.3 Drinking Wa te r......................................
B-1 B.4 S urfa ce Wa te r......................................
B-1 B.5 Milk.............................................
B-1 B.6 Broadleaf Vegetation B-1 B.7 Shoreline Sediment...................................
B-1 B.8 Fish.............................................
B-1 B.9 Direct Gamma Radiation (TLD)........................... B-1 B.10 Food Products (Crops)
B-1 iii
TABLE OF CONTENTS (Continued)
TITLE f1GE Appendix C Sampling Deviations and Unavailable Analyses C-1 Appendix D Analytical Deviations D-1 Appendix E Radiological Environmental Monitoring...................... E-1 Program Analysis Results iv
i a
i LIST OF FIGURES ELQMBE TITLE PAGE i
2-C Map of Radiological Monitoring Program Sampling i
Locations (Near to Catawba)......................... 2-11 2-D Map of Radiological Monitoring Program Sampling Locations (Distant from Catawba) 2-12 4
4 2-E Map of Radiological Monitoring Program Sampling i
Locations (Location 208 Shoreline and Bottom Sediment Sampling Points).......................... 2-13 3-A Catawba Nuclear Station 1994 Land Use Census Map....... 3-29 I
1 2
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LIST OF TABLES FIGURE TITLE PAGE 1
2-A Catawba Radiological Monitoring Program Sampling Locations (TLD Locations)..................... 2-8 2-B Catawba Radiological Monitoring Program Sampling Locations (Other Sampling Locctions)............ 2-10 2-F Reporting Levels for Radioactivity Concentrations in Environmental Samples........................... 2-14 2-G Lower Lis::t of Detection (LLD) Capabilities for Environmental Sample Analysis....................... 2-15 3.4-A Surface Water Sample Tritium Results - Location 208 3-6 l
3-A 1994 Maximum Calendar Quarter Average Percent of Re porting Le vels.................................. 3-7 l
l 3.B Radionuclide(s) Detected During 1994 and Not Listed in Selected Licensee Commitments......................
3-9 3-C Fraction and Percent of 1984 Radionuclide Measurements l
Yielding Detectable Activity 3-10 3.7-A Shoreline Sediment Sample Results - Location 208-1S, l
2 S, a nd 3 S..................................... 3-14 l
3.8-A Fish Sample Results - Location 208.................... 3-18 3.9-A Direct Gamma Radiation (TLD) Results.................. 3-21 3.9-B Comparison of Inner Ring / Outer Ring (TLD) Results......... 3-22 3.11 -A Bottom Sediment Sample Results - Location 208-1M, 2 M, a nd 3 M.................................... 3-25 3.12-A 1994 Catawba Nuclear Station Annual Land Use Census Re s ult s..................................
3-28 l
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LIST OF TABLES (Continued)
FIGURE TITLE PAGE 4-A Dose Estimates Based on Limiting 1994 Environmental Sample Results......................... '4-6 4-B 1994 Environmental and Effluent Dose Comparison for Liquid Waste Release Pathways....................
4-7 4-C 1994 Environmental and Effluent Dose Comparison for Gaseous Release Pathways.......................
4-8 4-D Pathway Dose Estimates 4-9 5-A U.S. Environmental Protection Agency Interlaboratory Comparison Program 1994 Cross-Check Results for the ERL....................... 5-4 5-B State of North Carolina Department of Environmental Health and Natural Resources Environmental Dosimeter Cross-C hec k 1994................................. 5-7 vii f
i i
SECTION 1 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report describes the Catawba Nuclear Station Radiological Environmental Monitoring Program and the results of the program for.
the 1994 calendar year.
Included in the report are regulatory requirements associated with. the program, identification of sampling locations, descriptions of environmental sampling and analysis procedures, results of the Annual Land Use Census, a summary of sample analysis results, discussion of the results, comparisons of present environmental radioactivity levels with preoperational data, analysis of trends in environmental radioactivity levels,-
comparisons of dose estimates based upon environmental measurements with estimates calculated using effluent release data, discussion of quality assurance activities associated
- with the program and identification of deviations from program requirements.
Sampling activities were conducted as prescribed by Selected Licensee Commitments.
Supplemental fish and sediment samples were collected to better monitor these media.
Required sample analyses were performed and detection capabilities were met for all samples.
The following predominant radionuclide(s), detected in sample media collected from the discharge canal, could be attributable to the operation of Catawba:
Mn-54 Co-58 Co-60 Cs-134 Cs-137 l
Shoreline Sed.
D S
D D
S Fish D
D D
D S
Bottom S
S S
D S-Sediment Surface Water Tritium - D
!= Increasing (from 1993), D = Decreasing, S = Steady 1-1 l
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Trends in radionuclide concentrations observed over the past year reflected comparable changes in radionuclide activities discharged annually or cumulatively via liquid effluents.
No other significant trends regarding environmental radioactivity levels were evident in the sampling results.
Dose estimates based upon environmental measurements were compared with those calculated based upon effluent release data. The estimates correlated well.
Catawba's contribution to environmental radioactivity is small.
The highest dose calculated from environmental sampling (excluding TLD results) for 1994 was only 0.27 mrem. All positive indications of radioactivity attributable to station operations were below the reporting levels imposed by Selected Licensee Commitments. Operation of
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Catawba has had no significant radiological impact upon the health and safety of the general public.
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SECTION 2 i
INTRODUCTION a
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS i
i Duke Power Company's Catawba Nuclear Station is a two-unit facility located on j
the shore of Lake Wylie in York County, South Carolina.
Each of the two l
)
essentially identical units employs a pressurized water reactor Nuclear Steam 1
Supply System furnished by Westinghouse Electric Corporation. - Each generating a
unit is designed to produce a net electrical output of approximately 1145 MWe.
j Units 1 and 2 achieved initial criticality on January 7,1985 and May 8,1986, respectively.
Condenser cooling is accomplished utilizing a closed cycle system incorporating 6
l cooling towers, instead of utilizing lake water directly. Liquid effluents are released into Lake Wylie via the station discharge canal and are not accompanied by the l
large additional dilution water flow associated with "once-through" condenser
-i i
cooling. This design difference results in greater radionuclide concentrations in the l
I discharge canal given comparable liquid effluent source terms.
A map depicting the site and the area within one mile of CNS can be found in j
Figure 2-C. An area map encompassing a ten mile radius from the station can be
)
j found in Figure 2-D.
1 i
The CNS Radiological Environmental Monitoring Program (REMP) sampling i
locations are summarized in Tables 2-A and 2-B. Table 2-A lists the environmental i
)
Thermoluminescent Dosimeter (TLD) locations. Table 2-B lists all other sampling locations.
The REMP sampling and analysis procedures are summarized in Appendix A.
Figures 2-C, 2-D, and 2-E are maps depicting the specific positions of all REMP sampling locations. The location numbers shown on these maps correspond to I
those listed in Tables 2-A and 2-B. Figure 2-C comprises all sample locations within one mile of CNS. Figure 2-D comprises all rerr aining locations. Figure 2-E identifies Location 208 (Discharge Canal) shoreline sediment (1S,2S, and 3S) and bottom sediment (1M, 2M, and 3M) sampling points. Of these six sediment samples, only shoreline sediment at Location 208-1S is required by CNS Final Safety Analysis Report (FSAR); the remaining five are supplemental samples first collected during 1986.
I i
2-1
2.2 SCOPE AND REQUIREMENTS OFTHE ENVIRONMENTAL MONITORING PROGRAM -
l The Radiological. Environmental Monitoring Program required by CNS FSAR, Selected Licensee Commitments Manual, Section 16.11-13 provides representative measurements of radiation and radioactive materials in those exposure pathways 4
and for those radionuclide(s) that lead to the highest potential radiation exposures to members of the public resulting from plant operation. This monitoring program l
implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby i
supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of effluent measurements and modeling of environmental exposure pathways.
Guidance for this monitoring program is i
provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
i The Annual Land Use Census required by Selected Licensee Commitments, Section 16.11-14 is performed to ensure that changes in the use of areas at or beyond the site boundary are - identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use.
This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR j
Part 50. The results of this census are required to be included in this annual report i
by Technical Specification Administrative Control 6.9.1.6.
I Participation in an approved Interlaboratory Comparison Program as required by Selected Licensee Commitments Section 16.11-15 provides for independent i
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 1 to 10 CFR Part
- 50. A cummary of the resu!ts obtained as part of this comparison program are required to be included in this annual report by Technical Specification l
Administrative Control 6.9.1.6.
This Annual Radiological Environmental Operating Report is required by Technical Specification Administrative Control 6.9.1.6, and it adheres to the content -
requirements of this specification.
Selected Licensee Commitments (Table 16.11-7) specifies the conduct of the Radiological Environmental Monitoring Program. The Duke Power Company Of fsite i
Dose, Calculation Manual further defines the specific type.s,frecuencies, and locations of sampling and measurement.
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Belected Licensee Commitments (Table 16.11-8) lists thirteen radionuclide(s); H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95,1-131, Cs-134, Cs-137, Ba-140, and La-140. These thirteen radionuclide(s) are collectively referred to l
throughout this annual report as "Radionuclide(s) Listed in Selected Licensee Commitments", or " Selected Licensee Commitments Radionuclide(s)".
l' Selected Licensee Commitments Manual (Table 16.11-7) provides reporting levels as a function of sample type and radionuclide. These reporting levels are listed in Table 2-F of this report. If sample radionuclide activity exceeds 100% of reporting
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level (when summed over all detected radionuclide(s) having a reporting level for j
.the applicable sample type and when the sums are averaged by location over the
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applicable calendar quarter), a special report must be submitted to the Nuclear 3
Regulatory Commission. When radionuclide(s) other than those listed in Table; l
16.11-7 are detected,,they must be addressed in this annual report. Not all I
radionuclide(s) have a reporting level for a given sample type. For example, there
- i are no reporting levels listed for gross beta analysis of any sample type and sedirnent samples have no reporting levels for any radionuclide(s).
1 Selected Licensee Commitments Manual (Table 16.11-8) lists required Lower Limit j
of Detection (LLD) capabilities for REMP sample analyses as a function of sample l
type and radionuclide. These LLD values are listed in Table 2-G of this report.
Refer to Part 2.3.2 for the definition of LLD and Minimum Detectable Activity (MDA). Not all radionuclide(s) have a required LLD for a given sample type. Any i
analyses for which the required LLD values were not achievable must be discussed in this annual report.
l 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY i
2.3.1 ESTIMATION OF THE MEAN VALUE f
There was one basic statistical calculation performed on the raw data f
resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The n aan is a widely used 4
statistic. This value was used in the reduction of the data generated by the l
sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following ' equation was used to estimate the mean:
1 a
2 i= N E X; i= 1 i
X=
(Equation 2-1) i N
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,.,,,.,_..__,m.-..._,.,.,.,,,my,,,
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X estimate of the mean,
=
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=
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=
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X net activity (or concentration) for sarnple 1.
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=
NOTE:
" Net activity (or concentration)" is the. activity (or concentration) determined to be present in the sample. No l
" Minimum Detectable Activity", " Lower Limit of Detection",.
"Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
2.3.2 LOWER LIMIT OF DETECTION, MINIMUM DETECTABLE ACTIVITY, AND CRITICAL LEVEL The Lower Limit of Detection (LLD), Minimum Detectable Activity (MDA),
and Critical Level (CL) are used throughout the Radiological Environmental Monitoring Program.
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 system background, that will be detected with 95%
l probability with only 5% probability of falsely concluding that a blank
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observation represents a "real" signal. The LLD is an a oriori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sarnple size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The " required" LLD values for each sample medium and selected radionuclides are given in Selected Licensee Commitments.
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.
)
The CL is defined as the net count rate which must be exceeded before a sample is considered to contain any measurable activity above the background.
i 2-4
2.3.3 Trend Identification One of the purposes of an environmental. monitoring program is to
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determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. Historically, this has been done by looking at data (including preoperational data) and determining if a trend exists.
Various liquid effluent pathways have been evaluated based on a number of parameters for the past several years.. From these parameters certain conclusions have been made which reflect how radionuclides which have been released from the station appear to be taken into the environment.
The various pathways available: fish, shoreline sediment, milk, broadleafi vegetation, food products, display different charact0ristics of _ uptake and t
buildup. Thereforei each pathway is discussed separately and conclusions made for both the reporting year and for prior years including in most cases preoperational years.
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2.3.4 Test Statistic l
l In some cases, we would not expect to observe a buildup of radionuclide(s) in the environment, but instead would expect to see a measurable increase in levels over a short duration.
This is the case for direct radiation measurements, where the radiation level is measured over a finite period and is dependent upon whether plant discharges were occurring at that time or not. If we assume that the naturally occurring radiation levels around the plant are normally distributed and that the effluents are not affecting the environment outside of this normal distribution, then we can compare the values of two sets of measurements taken at different times around the plant. One measurement can be taken when we are certain no effect is occurring and one when an effect may be occurring, to determine if they are
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statistically different from one another.
The statistic that compares the means from two sets of measurements to determine if there is a statistically significant difference is called the test i
statistic, or t-statistic, and is calculated as follows:
j X
X 3
I z-l Spl1/ni +- 1/n2 Where:
X the mean value of the first set of measurements
=
l X
the mean value of the second set of measurements
=
Sp the average standard deviation of the two sets of
=
measurements l
l jS2
=
p I
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I the number of measurements in the first set ni
=
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=
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l 1
The calculated value of the test statistic is then compared to expected
' values of the test statistic tabulated based on the number of measurements taken and the degree of confidence required for the results. For this report, the expected value of the test statistic will always be chosen to give a 95%
confidence level that a positive result is truly positive with only a 5%
j probability that a positive result is truly negative. This confidence levelis chosen since it is consistent with the standard confidence levels specified for similar measurements.
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Due to the existence of naturally occurring differences in background radiation levels over time - (as a result of solar cycles and other meteorological - phenomena) and systematic errors-due to instrument variability, ratios of measurements can be used to calculate the t-statistic instead of individual measurements. By using ratios, the errors associated l
with the measurement process then cancel each other out and allow us to more accurately compare results from one year to the next. Specifically, in the case of TLD measurements, the inner ring of TLD results is ratioed with the outer ring of TLD measurements in a given year and the ratio for one year is compared to the ratio for another year.
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As with other environmental samples, outside factors may affect the results l
observed and the resulting trends identified. The significance of trends will l
be based on judgement of plant personnel familiar with the factors affecting environmental levels and the statistical results.
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TABLE 2-A i
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CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS l
(TLD LOCATIONS) 1 1
l LOCATION DESCRIPTION DISTANCE (MILES)
SECTOR 1
I.
Site Boundary 0.6 NNE 200 201 Site Boundary 0.5 NE i
l 202
- Site Boundary 0.6 E
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Site Boundary 0.4 ESE 203 204 Site Boundary 0.5 SSW 205 Site Boundary 0.3 SW I
206 Site Boundary 0.7 WNW l
l 207 Site Boundary 0.9 NNW 212 Special Interest 3.3 E
i 217 Control 10.3 SSE l
222 Site Boundary 0.7 N
l l
223 Site Boundary 0.6 E
l 224
- Site Boundary 0.6 ESE I
225 Site Boundary 0.7 SE i
226 Site Boundary 0.5 S
l 227 Site Boundary 0.5 WSW 228 Site Boundary 0.6 W
229 Site Boundary 0.8 NW 230 4 - 5 Mile Radius 4.4 N
l 231 4 - 5 Mile Radius 4.2 NNE 232 4 - 5 Mile Radius 4.1 NE i
i Deleted 09/14/89 l
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TABLE 2-A (Continued)
CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)
LOCATION DESCRIPTION DISTANCE (MILES)
SECTOR 233 4 - 5 Mile Radius 3.9 ENE 1
234 4 - 5 Mile Radius 4.5 E
j 235 4 - 5 Mile Radius 3.9 ESE 236 4 - 5 Mile Radius 4.3 SE l
237 4 - 5 Mile Radius 4.8 SSE 238 4 - 5 Mile Radius 4.0 S
i 239 4 - 5 Mile Radius 4.5 SSW 240 4 - 5 Mile Radius 4.1 SW 241 4 - 5 Mile Radius 4.6 WSW 242 4 - 5 Mile Radius 4.6 W
243 4 - 5 Mile Radius 4.4 WNW 244 4 - 5 Mile Radius 4.0 NW l
245 4 - 5 Mile Radius 4.1 NNW 246 Special Interest 7.8 ENE 1
1 247 Control 7.3 ESE 248 Special Interest 6.6 S
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249 Special Interest 8.1 S
250 Special Interest 10.4 WSW 251 Control 9.7 WNW 255 **
Site Boundary 0.6 ENE 256 **
Site Boundary 0.6 SSE Added 09/14/89 4
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Page 2-12 50502.0 Z.76-d/-
FIGURE 2-E MAP OF RADIOLOGICAL MONITORING PROGRAM SAMPLING L.,ATIONS (LOCATION 208 SHORELINE AND BOTTOM SEDIMENT SAMPLING POINTS)
RL DISCHARGE g
1 WC DISCHARGE 208 (35) 2$8(1M) 208 (25) 208 (2M) i FLOW 208 (15)
-PIER 208 (3H) e ROAD 1132 BRIDGE CATAWBA NUCLEAR STATION DISCHARGE CANAL 2-13
-mm
--v TABLE 2-F REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulates Water or Gases Fish.
Milk-Food Products Sediment Analysis (pci/ liter)
(pci/ cubic meter)
(pci/kg wet)
(pci/ liter)
(pci/kg wet)
(pci/kg dry)
H-3 20,000(*
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-140 200 300 Note (a):
If no drinking water pathway exists, a value of.30,000 pCi/ liter-may be used.
2-14 I>.
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TABLE 2-G LOWER LIMIT OF DETECTION (LLD) CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS r
Airborne Particulates Water.
or Gases Fish Milk Food Producta Sediment Analysis (PC1/ liter)
(pCi/ cubic meter)
(pCi/kg wet)
(pC1/ liter)
(pCi/kg wet)
(pCi/kg dry)
Gross Beta 4~
0.01 5
2000 "
H-3 130 Mn-54 15 260 Fe-59 30 130 Co-58,60 15 260 -
Zn-65 30 Zr-Nb-95 15 1(b) 0.07 1
60 I-131 Cs-134 15 0.05 130 15 60 150 I
Cs-137 18 0.06 150 18 80 180 i
15 Ba-La-140 15 l
I Notes:
(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.
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l SECTION 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
DISCUSSION, INTERPRETATION, AND TRENDING OF RESULTS GENERAL INFORMATION l
j-j in addition to the " required" sampling and analyses described in CNS Selected Licensee
. Commitments Table 10.11-7, the following " supplemental" measures were taken during l
i 1994. These supplemental measures were first adopted during 1986 to better assess the impact of CNS operations on the environment in a more timely and reliable manner-l j
1)
Shoreline sediment (requiring collection at only one point along the CNS i
j discharge canal (Location 2001 S)) was collected at three points (Locations.
i 208-1 S, 208-2S, and 208-3S).
1
{
2)
Shoreline sediment (requiring collection semiannually) was collected quarterly. The first and third quarter samples from Locations 208-1S,210 and 215 were considered to be the required samples and all remaining
]
samples were considered supplemental.
l 3)
Fish (requiring collection from Locations 208 and 216 semiannually) were collected quarterly. This year the second and fourth quarter samples were
]_
considered to be the required samples and the first and third quarter j
samples were considered supplemental.
ii 4)
Bottom sediment (not requiring collection) was collected quarterly at CNS l
Discharge Canal Locations 208-1M, 208-2M, and 208-3M. These were j.
considered to be supplemental samples.
1
{
Summary tables containing 1994 information required by Technical Specification Administrative Control 6.9.1.6 for each required REMP sample type, can be found in l
Appendix B. These summary tables are based upon required sample results only, the supplemental sample results are not reflected in these tables. The mean values tabulated j
in these 1994 summary tables are based upon detectable measurements only.
l l
All deviations from the sampling and analytical requirements of Selected Licensee Commitments Table 16.11-7 which occurred during 1994, are addressed in Appendices t
j C and D, respectively. For all 1994 REMP samples collected, required as well as supplemental, the reporting level limitations of Selected Licensee Commitments Table l
16.11-7 were not exceeded. For 1994 REMP analyses, the LLD requirements of Selected Licensee Commitments Table 16.11-8 were met for all required and supplemental samples. The required reporting levels and LLD capabilities for REMP samples are listed i
in Tables 2-F and 2-G.
4
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3-1 k
J l
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Selected Licensee Commitments Table 16.11-7 (included as Table 2-F) provides reporting levels, as a function of sample type and radionuclide. If sample radionuclide activity exceeds 100% of reporting level (when summed over all detected radionuclide(s) having a reporting level for the applicable sample type, and when the sums are averaged by location over the applicable calendar quarter), a special report must be submitted to the Nuclear Regulatory Commission. Table 3-A contains the maximum percent of reporting level (when averaged over a calendar quarter) reached during 1994 for each sample type and location combination. Values are not listed for shoreline sediment or bottom sediment samples because there are no corresponding reporting levels.
With one exception, all of the 1994 maximum percent of reporting level values were less than 10%, well below the 100% action level. The highest value reached during 1994 was 81.8%, for surface water tritium collected during the third quarter at CNS discharge canal Location 208.
Selected Licensee Commitments Section 16.11-13 addresses the actions to be taken when radionuclide(s) other than the thirteen radionuclide(s) listed are detected in REMP samples.
Table 3-B summarizes those radionuclide(s). The occurrences of these radionuclide(s) are the result of CNS liquid effluents which contained the radionuclide(s).
The naturally occurring radionuclide(s) of Table 3-B (K-40 and Be-7) were considered to have resulted from natural background radioactivity, not plant effluents.
The Nuclear Data ND6620 gamma spectroscopy system (which was used to analyze REMP samples collected during 1984,1985,1986, and most of 1987) was replaced by the Nuclear Data ND9900 gamma spectroscopy system on September 1,1987. When the ND6620 system was used to analyze samples prior to September 1,1987, a small but steady percentage (approximately five percent) of measurements for most of the thirteen radionuclide(s) listed in technical specifications, yielded detectable low-level activity, even when the presence of such activity was highly unlikely as for control location samples and preoperational samples collected during 1984. This phenomenon has not occurred using the ND9900 system, thus ending this trend and suggesting that the ND6620 system may have been vulnerable to false-positive results, possibly due to the method by which it estimated net activity even when its peak search routine failed to detect a peak.
This attribute must be considered when trending and comparing recent REMP results to those generated during the preoperational period and the operational period through August,1987.
3-2
i
)
l During 1984, the last completely preoperational year at CNS, tritium and Cs-137 were l
detected with sufficient frequency to imply their existence as background radioactivity (See Table 3-C). For ground water, drinking water, and surface water samples, tritium was frequently detected (at levels of about 300 pCi/ liter), and 1-131 was occasionally detected in surface water at all three locations when performing low-level radioiodine analysis (at levels ranging from 0.3 to 1.7 pCi/ liter). For all sample types other than water, Cs-137 was detected occasionally during 1984. Note that for shoreline sediment, Cs-134 was detected at all three locations in four of six samples at levels ranging from 24 to 39 pCi/ liter.
All 1994 REMP analysis results were reviewed in order to detect and identify any significant trends. Many sources of information were examined to accomplish this and the resultant trending observations were included in Parts 3.1 through 3.11. Quarterly REMP verification reports were generated in order to track commitment requirements, and these reports were also used to evaluate potential trends. The 1994 Summary of Analysis Results tables from Appendix B, as well as the analogous tables for the years 1984 and the years 1989 through 1993, were reviewed.
To aid in trending, additional summaries were generated for each individual location for cach sample. type and for key groups of locations for each sample type. These additional summaries were not included in this annual report. With the exception of certain 1986 results affected by the Chernobyl accident, these summaries incorporated all required and '
supplemental REMP sample results.
P Parts 3.1 through 3.12 discuss 1994 REMP results for each sample type specifically, and for the. Annual Land Use Census. Unless noted otherwise, these discussions are based on REMP sample results, required as well as supplemental (with exception of certain 1986 results affected by the Chernobyl accident).
I I
I I
3-3 l
f m
,e,._._
.m.
i 4
l 3.1 AIRBORNE RADIOIODINES AND PARTICULATES l
3.1.1 RADIOlODINES During 1994, 265 radioiodine samples were analyzed, 212 from the four indicator locations and 53 from the control location.
The term " airborne radioiodines" is used throughout this report to j
generically categorize sample results for the air charcoal cartridge filter.
}
Radioactive iodines and other halogens are the only radionuclide(s) (other j
than some which occur naturally) normally expected to be detected in these j.
REMP samples.
For the purpose of this report, the term " airborne radioiodines" refers to any and all radionuclide(s) reported in REMP air i
charcoal cartridge sample results, not just radioiodines.
K-40 and Be-7Lwhich occur naturally, were routinely detected in REMP charcoal cartridge samples collected during 1994. Cs-137 activity was present on one cartridge, but not on the particulate filter. This was
~
determined to be inherent in the charcoal and was not included for trending purposes.
l 5
1 2
3.1.2 PARTICULATES l
During 1994,265 particulate filter samples were analyzed, 212 from the J
indicator locations and 53 from the control location.
Be-7 which occurs naturally, was routinely detected in REMP airborne
{
particulate filter samples collected during 1994. K-40 was occasionally detected in these samples. No other radionuclide(s) were detected in any i
1994 airborne particulate filter samples. These results were consistent with l-1993 sarnple results.
)
3.2 GROUND WATER j
K-40 was the only radionuclide reported in the eight ground water samples
{
collected during 1994. The K-40 results were relatively consistent with results i
from previous years. There are no control ground water sample locations.
I i
3.3 DRINKING WATER i
K-40 which occurs naturally, was the only radionuclide detected in drinking water j
samples collected during 1994. Tritium was detected in one of eight samples (12.5% frequency) during 1993. This detection frequency was less than in 1984, l
when tritium was detected in eleven of the twelve samples (92% frequency).
i 2
3-4 i
During 1984 (preoperation) and 1985, tritium was detected in drinking water samples with 71 % frequency, at average detectable concentrations ranging from 1
approximately 300 to 400 pCi/ liter. During the period from 1986 through 1989, tritium was detected in drinking water samples with 41% frequency, at average detectable concentrations ranging from approximately 500 to 800 pCl/ liter. This concurrent decrease in detection frequency and increase in average detectable concentration, is probably attributable to the change in tritium analysis laboratories occurring during 1986, from a contractor laboratory to the Radioanalysis Laboratory.
The tritium detection frequencies and low average concentrations which have been reported in previous years for all drinking water locations are consistent with ambient background levels and were probably not affected by CNS effluents.
3.4 SURFACE WATER K-40, Be-7 and tritium, all of which occur naturally, were detected in surface water samples collected during 1994. Tritium was detected in all of the four composite samples collected from discharge canal Location 208.
Tritium was detected in all 33 surf ace water samples collected from Location 208 during the seven year period from 1984 to 1991. Table 3.4-A lists the annual average Location 208 surface water sample tritium concentrations for this period.
The table also lists the total tritium activity released into the CNS discharge canal via liquid effluents during each year. Ratios of the tritium sample concentration divided by the tritium effluent activity are also included.
Tritium concentrations in surface water collected from Location 208 exceed ambient background levels. CNS liquid effluents appear to be affecting discharge canal surface water tritium concentrations. The concentration / activity ratios are relatively consistent, considering the uncertainties inherent in such an evaluation.
The ratios shown indicate a good correlation between Location 208 surface water tritium concentrations and liquid releases of tritium from CNS. The average percent of reporting level values for surface water collected from Location 208 for the four calendar quarters of 1994 were 34.4%, 34.9%, 81.8%, and 17.3%,
respectively. The third quarter value was the result of a proportionately high concentration of tritium released via liquid effuents. Tritium was solely responsible for these reporting level values.
3-5
i l
TABLE 3.4-A SURFACE WATER SAMPLE TRITIUM RESULTS - LOCATION 208 Year Surface Water Total H-3 Activity Concentration /
Average H-3 Conc.
Released in Liquid Activity Ratio (pCi/ liter)
Effluents (Curies) 1984 313 0
N/A 1985 1190 175 6.8 1986 2340 236 9.9 1987 4170 728 5.7 1988 6030 706 8.5 1889 5270 890 5.9 1990 3980 594 6.7 1991 4868 646 7.5 1992 6583 774 8.5 1993 5980 826 7.2 1994 2106 585 3.6 1985-1994 4273 616 6.9 Average
?
3-6
)
)
)
)
)
TABLE 3-A 1994 MAXIMUM CALENDAR QUARTER AVERAGE PERCENT OF REPORTING LEVELS Sample Type Sample Location
% of Rpt. Level Calendar Quarter Sampling Dates Airborne Radioiodines 200 0
ALL
{
201 O
ALL 205 0
ALL 1
212 0
ALL 217 Control 0
ALL nummmm -
)
Airborne Particulates 200 0
ALL 201 0
ALL 205 0
ALL 212 0
ALL 217 Control 0
ALL Airborne Radiciodines 200 0
ALL and Particulates 201 O
ALL 205 0
ALL 212 0
ALL 217 Control 0
ALL Ground Water 252 0
ALL 254 0
ALL Drinking Water 214 0
ALL 218 Control 0
ALL Surface Water 208 81.8 06/08/94 - 09/28/94 211 2.0 12/22/93 - 03/16/94 215 Control 1.8 12/22/93 - 03/16/94 Milk 209 0.67 06/08/94 -09/28/94 219 0
ALL 221 Control 0
ALL 3-7
TABLE 3-A (Continued) 1994 MAXIMUM CALENDAR QUARTER AVERAGE PERCENT OF REPORTING LEVELS Sample Type Sample Location
% of Rpt. Level Calendar Quarter Sampling Dates Broadleaf 200 0
ALL 9*
- 201 2.04 06/08/94 -09/28/94 217 Control 0
ALL 226 2.93 09/28/94 -12/21/94 Fish 208 1.95 04/04/94 (Predator) 216 Control 0
ALL Fish 208 1.11 10/07/94 0
216 Control 0
ALL l
mammmmmmmmmmmmmmmmmmm-Fish 208 2.09 04/04/94 216 Control 0
ALL C'
i Food Products 253 0
ALL 3-8
4 i
i TABLE 3-B i
I l
Radionuclide(s)S DETECTED DURING 1994 AND NOT LISTED IN SELECTED LICENSEE COMMITMENTS l
l SHORELINE SEDIMENT l
f Co-57 4.0 pCi/ dry Kg Location 208-1 S Co-57 4.7 pCi/ dry Kg Locattm 208-3 S Sb-125 157 pCi/ dry Kg Location'208-1 S i
Sb-125 526 pCi/ dry Kg Location 208-2 S -
Sb-125 127 pCi/ dry Kg Location 208-3 S -
I f
i BOTTOM SEDIMENT Co-57 31 pCi/ dry Kg Location 208 - 1M Sb-124 20 pCi/ dry Kg Location 208 - 1M Sb-125 490 pCi/ dry Kg Location 208 - 1M i
Co-57 56 pCi/ dry Kg Location 208 - 2M j
Sb-125 1078 pCi/ dry Kg Location 208 - 2M i
l Sb-125 451 pCi/ dry Kg Location'208 - 3M l
i Most Sample Types and Locations:
i K-40 i
l Be-7 3-9
TABLE 3-C FRACTION AND PERCENT OF 1984 Radionuclide(s) MEASUREMENTS YlELDING DETECTABLE ACTIVITY SAMPLE TYPE ALL LOCATIONS PREDOMINANT Radionuclido(s)S Fractions Fractions unusumuu ---
Airbome Radioiodines 99[5068 4.8 Cs-137 26/188 13.8 Airbome Particulates 108/2717 4.0 Cs-137 22/247 8.9 Ground Water 2/52 3.8 H3 2/4 50.0 Drinking Water 351465 7.5 H-3 11/12 91.7 4
i Surface Water 30/454 6.6 H3 12/12 100.0 l-131/LL 5/24 20.8 j
Milk 43/960 4.5 Cs-137 12/80 15.0 Broadleaf Vegetation 24/396 6.1 Cs-137 9/36 25.0 Shoreline Sediment 7/66 10.6 Cs-134 4/6 66.7 Cs-134 2/6 33.3 Fish 4/132 3.0 Cs-137 2/12 16.7 Food Products Not Sampled Bottom Sediment Not Sampled All Sample Types 352/7310 4.8 i
f 3-10
3.5 MILK During 1994,78 milk samples were analyzed, 52 at the two indicator Locations and 26 at the control Locations.
Cs-137 was detected in one milk sample collected during 1994 with frequencies of 3.8% (1/26),0% (0/26), and 0% (0/26) at indicator Locations 209 and 219 and at control Location 221, respectively. The accompanying average detectable Cs-137 concentrations were 2.8, O and 0 pCi/ liter. These concentrations are very comparable to results obtained since 1987.
During 1984, Cs-137 was detected with 15.0% frequency (12/80), at concentrations ranging from 5.00 to 10.0 pCi/ liter.
The single detection of Cs-137 in 1994 Indicator location milk sample occurred during the third quarter. Cs-137 was not detected in any airborne effluents from CNS during 1993 or 1994. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.
Based upon the overall consistency between indicator location, control location, and preoperational milk sample results, low-level Cs-137 activity in the single milk sample collected during 1994 cannot reasonably be attributed to CNS effluents.
The maximum quarterly average percent of reporting level was only 0.7%, for milk collected from indicator Location 209 during the third quarter and was attributable to Cs-137 activities.
3.6 BROADLEAF VEGETATION in 1994, 32 broadleaf vegetation samples were analyzed, 24 at three indicator Locations and 8 at the control Location. Low levels of Cs-137 were detected in broadleaf vegetation samples collected throughout 1994 with frequencies of 0%
(0/8),37% (3/8),50% (4/8) and 0%, at indicator Locations 200,201, and 226, and at control Location 217, respectively.
These frequencies were comparable to previous years value.s. The respective average detectable Cs-137 concentration's were 0, 62, 70 and 0 pCl/ wet kilogram.
During 1984, Cs-137 was detected with 25.0 % frequency (9/36), at 4
concentrations ranging from 20.1 to 130 pCi/ wet kilogram.
l l
3-11
).
p
i l
I l
Cs-137 was not detected in airborne effluents from CNS during 1993 or 1994.
l Also, Cs-137 attributable to past nuclear weapons testing is known to exist in i
many environmental media at low, highly variable levels.
1 Based upon the consistency between indicator location, control location, and l
preoperational broadleaf vegetation sample results, as well as the other considerations listed -above, low-level Cs-137 activity in broadleaf vegetation i
samples collected during 1994 is not likely attributable to CNS effluents. The maximum quarterly average percent of reporting level was only 2.93% for broadleaf vegetation collected from indicator Location 226 during the third quarter and was attributable to Cs-137 activity. Quarterly percent of reporting level values j
for broadleaf vegetation were calculated using Selected Licensee Commitments i
4 l
reporting levels for food products because reporting levels for broadleaf vegetation l
are not listed.
i l
3.7 SHORELINE SEDIMENT l
Cs-137 was detected in two of four samples collected from indicator Location 210 at a low average concentration of 17.7 pCi/ dry kilogram.
No radionuclide detections other than these were reported in indicator Location 210 or control Location 215 samples collected during 1994.
I t
i During 1984, Fe-59 was reported in one of the six shoreline sediment samples, at a concentration of 67.3 pCi/ dry kilogram. Cs-134 was reported in four of these samples, at concentrations ranging from 24.4 to 39.2 pCl/ dry kilogram Cs-137 l
was reported in two of these samples, at concentrations of 41.7 and 173 pCi/ dry r
kilogram.
f l
With exception of Cs-137, it was unlikely that these radionuclide(s) were present l
in these preoperational samples; their detection was probably attributable to the.
i ND6620 sensitivity phenomenon discussed previously.
No other technical
(
specification radionuclide(s) were detected in any 1984 shoreline sediment samples.
I During 1994, Mn-54, Co-58, Co-60, Cs-134, and Cs-137 were detected in the majority of the twelve shoreline sediment samples collected from CNS discharge canal Locations 208-1 S, 208-2S, and 208-3S. The five radionuclide(s) have been predominant in shoreline cediment samples every year since 1986. The same i
radionuclide(s)s have been predominant in fish and bottom sediment samples collected from the discharge canal. Other radionuclide(s) reported in the twelve samples (besides K-40 and Be-7) were Co-57 and Sb-125 (see Table 3-B). All i
seven detected radionuclide(s) other than K-40 and Be-7 were attributable to liquid effluents.
I 3-12 i
p
j 1
Table 3.7-A summarizes shoreline sediment sample results for discharge canal Location 208 during the five year period from 1989 to 1994.
l From.1989 through 1993, average detectable radionuclide concentrations have generally shown an increasing trend. For 1994, most concentrations were lower
{
than previous year's. Parameter D which is the ratio of concentration to annual activity released displays a general increasing trend for Co-60 and Cs-137 l
concentrations. Co-58 ratios were virtually flat (stable) for the 1989 - 1994 i
period. Correlations observed between Parameter D and Parameter F (ratio of i
sample concentration to cumulative decay corrected activity released) exhibit a positive or increasing trend. Therefore, these observations seem to show that environmental removal processes have not overcome the accumulation of annual activity released via liquid effluents in shoreline sediment samples, with the exception of Co-58.
From the observations, annual activity released in liquid effluents may contribute j
to previously deposited activity in Location 208 shoreline sediment samples.
I There has been no observable trend in which any of the three sampling points show a greater accumulation of activity than the other two.
t i
b l
l l
i 3-13 4
TABLE 3.7-A SHORELINE SEDIMENT SAMPLE RESULTS - LOCATION 208-1S,2S, AND 3S Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s) j Mn-54
[A]
45.8 58.8 137 155 160 65.8 i
[B]
12/12 11/12 4/12 9/12 10/12 9/12
[C]
14.4 34.4 30.2 23.2 13.5 10.3 I
[D]
3.2 1.7 4.5 6.7 11.9 6.4
[El 45.4 54.6 54.5 47.5 34.6 25.7
[F]
1.0 1.1 2.5 3.3 4.6 2.6 i
Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s) 1 Co-58
[A]
194 227 404 1227 1070 798
[B) 12/12 11/12 6/12 11/12 12/12 12/12
[C]
149 244 196 364 398 272
[D]
1.3 0.9 2.1 3.4 2.7 2.9
[El 156 248 203 370 408 283
[F1 1.2 0.9 2.0 3.32 2.6 2.8 Radio-Parameters 1989 1990 1991 1992 1993 1994 1
nuclide(s) i Co-60
[A]
121 193 488 633 1040 573
[B) 12/12 11/12 5/12 11/12 12/12 12/12
[C]
46.2 127 156 116 67.0 68.1
[D]
2.6 1.5 3.1 5.5 16 8.4
[El 325 412 517 569 566 564
[F) 0.4 0.5 0.9 1.1 1.8 1.0
[A]
Average Detectable Concentration (pCi/ dry kilogram)
[B)
Fraction of Total Measurements Yielding Detectable Activity
[C]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci)
[El Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) i 3-14
TABLE 3.7-A (Continued)
SHORELINE SEDIMENT SAMPLE RESULTS - LOCATION 208-1S,2S, AND 3S Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s)
-mmmmmmmmmmmmmammmmmmmma mummmmmmum-j Cs-134
[A]
18.0 33.2 16.3 50.8 84.0 34
[B) 11/12 6/12 2/12 4/12 4/12 2/12
[C]
4.7 10.2 5.6 4.3 3.20 1.17
[D]
3.8 3.3 2.9 11.8 26.3 29.1
[E]
23.9 27.3 25 23.8 20.2 15.6
[F]
0.8 1.2
.65 2.1 4.2 2.2 1
Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s)
-summmmmmmmmme-mummmmme mmmmmmmma Cs-137
[A]
57.7 81.8 64.9 107 126 107 j
[Bl 12/12 12/12 6/12' 12/12 12/12 12/12
[C]
8.5 17.7 9.5 8.9 7.84 3.88
[D]
6.8 4.6 6.9 12.0 16.1 27.6
[E]
82.4 98.2 105 104 109 110 j
[F]
0.7 0.8 0.6 1.0 1.2 1.0 l
i j
[A]
Average Detectable Concentration (pCi/ dry kilogram)
[B]
Fraction of Total Measurements Yielding Detectable Activity
[C]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci)
[El Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) i J
3-15
i 3.8 FISH i-A total of 24 fish samples were collected during 1994 with 12 collected from Location 208 and 12 from Control Location 216.
]
During 1984, Zn-65 was reported in one of the twelve fish samples, at a concentration of 148 pCi/ wet kilogram. Nb-95 was reported in one of these j
samples at a concentration of 189 pCl/ wet kilogram. Cs-137 was reported in two
-1 of these samples, at concentrations of 25.7 and 64.6 pCi/ wet kilogram. With i
exception of Cs-137, it was unlikely that these radionuclide(s) were present in these preoperational samples; their detection was probably attributable to the ND6620 sensitivity phenomenon discussed previously. No other technical j
specification radionuclide(s) were detected in any 1984 fish samples, i
The maxirnum quarterly percent of reporting level reached for fish during 1994 was i
2.1 % for bottom feeder fish collected at discharge canal Location 208 during the second quarter. The forager fish collected at Location 208 contained the highest average concentration for the year, with reported activities of 23,128 and 46 pCi/ wet kg for Mn-54, Co-58 and Co-60, respectively. As Table 3.8-A shows, the average detectable concentration for all fish collected at Location 208 exhibits an overall decrease in concentration for all radionuclides except Cs-137 which remained stable.
During 1994, Mn-54, Co-58, Co-60, and Cs-137 were frequently detected in the j
l twelve fish samples collected from CNS discharge canal Location 208. The four radionuclide(s)s have been predominant each year since 1986 and have also been i
predominant in shoreline and bottom sediment samples collected from the j
discharge canal. The detected radionuclide(s) other than K-40 and Be-7 were attributable to liquid effluents from CNS. Those effluents contained prevalent levels of the same radionuclide(s). No Cs-134 was identified in fish samples in 1994.
i i
1994 sample results for fish collected at indicator Location 208 were reviewed by l
type of fish. Results showed that all radionuclide detection frequencies and concentrations were higher for forager fish than for predatory and bottom feeding i
fish. This has been a consistent trend over previous years (1989 - 1994).
b Table 3.8-A summarizes fish sampio results for discharge canal Location 208 during the six year period from 1989 to 1994.
1 3-16
I j
i From 1989 through 1994, average detectable concentrations correlated acceptably with annual activities released in liquid effluents [ Parameter D) which is an important aspect of this report and of the data contained in Table 3.8-A.
In i
addition, ratios for Co-58 and Co-60 were lower in 1994 from previous years and j
the ratios for detectable concentrations and cumulative activity released
[ Parameter F] were also lower. The only change _which was not consistent for
- Parameter D was the value for Cs-134. There were no detectable occurrences of 3
Cs-134 in twelve samples analyzed. Observation suggests that annual average
)
detectable radionuclide concentrations at Location 208 fish samples were primarily dependent on the annual and the cumulative activities released via liquid effluents.
'l i
j 3
i 3
1 i
3-17
TABLE 3.8-A FISH SAMPLE RESULTS - LOCATION 208 Radio-Parameter 1989 1990 1991 1992 1993 1994
(
nuclide(s)
[A]
33.1 100 94.4 121.
60.1 22.9
[B1 3/12 3/12 4/12 1/9 5/14 1/12
[C]
14.4 34.4 30.2 23.2 13.5 10.3 l
[D]
2.3 2.9 3.1 5.2 4.4 2.2
[El 45.4 54.6 54.5 47.4 34.6 25.7
[F]
0.7 1.8 1.7 2.5 1.7 0.9 Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s)
Co-58
[A]
194 301 292 270.7 557 114
[B]
5/12 7/12 6/12 3/9 9/14 5/12
[C]
149 244 196 364 398 272
[D]
2.1 1.2
- 1. 5 0.7 1.4 0.4
[El 156 248 203 436 410 283
[
[F]
2.0 1.2 1.4 0.6 1.4 0.4 l
r Radio-Parameters 1989 1990 1991 1992 1993 1994 nuclide(s) r Co-60
[A]
115 311 387 557 212 43.5
[B]
4/12 3/12 4/12 1/9 8/14 5/12
[C]
46.2 127 156 116 67.0 68.1 l
i i
[D]
2.5 2.4 2.5 4.8 3.2 0.6 l
[El 325 412 517 569 566 564 J
[F]
0.4 0.8 0.7 0.9 0.4 0.1
[A]
Average Detectable Concentration (pCi/ dry kilogram) l
[B)
Fraction of Total Measurements Yielding Detectable Activity IC]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci) i
[E]
Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) 3-18 3
TABLE 3.8-A CONTINUED FISH SAMPLE RESULTS - LOCATION 208 Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s)
Cs-134
[A]
22.1 31.7 25.7 38 38.2 0
[B]
8/12 5/12 6/12 3/9 1/14 0/12
[C]
4.7 10.2 5.6 4.3 3.20 1.17
[D]
4.7 3.1 4.6 8.8 11.9 0.0
[E]
23.9 27.3 25.1 22.3 19.1 14.8
[F]
0.9 1.2 1.0 1.7 2.0 0.0 Radio-Parameters 1989 1990 1991 1992 1993 1994 nuclide(s)
[A]
43.7 55.9 45.9 51.8 29.8 26.2
[B]
12/12 10/12 12/12 8/9 12/14 8/12 i
[C]
8.5 17.7 9.5 8.9 7.84 3.88
[D]
5.1 3.2 4.9 5.8 3.8 6.8 L
[El 82.4 98.2 105 111 116 117.2
[F]
0.5 0.6 0.4 0.5 0.3 0.2 1
l
[A]
Average Detectable Concentration (pCi/ dry kilogram) l
[B]
Fraction of Total Measurements Yielding Detectable Activity I
[C]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci) l
[El Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) l 1
l l
i l
t l
3-19 l
s
)
3.9 DIRECT GAMMA RADIATION (TLD)
Forty thermoluminescent dosimeters (TLD's) are located in the vicinity of CNS in order to monitor direct gamma (whole-body) radiation. The TLD locations can be divided into four major subgroups: three control locations, sixteen site boundary ring locations, sixteen 4-5 mile ring locations and five special interest locations.
The doserate for these groups of TLD's were 63.9 mrem /yr,76.3 mrem /yr,69.3 mrem /yr and 66.5 mrem /yr, respectively, for 1994 with an average doserate of 70.7 mrem /yr for all indicator locations. This data is shown in Table 3.9-A along with the respective values for previous years.
In order to determine whether CNS operations had a significant impact on direct radiation levels the t-statistic or t-test was used to compare 1994 TLD results to I
TLD measurements taken during preoperation. The ratio of site boundary and 4-5 mile ring results for 1994 was compared to the ratio of results for preoperation.
Since the inner ring of TLD's is most likely to be affected by plant operations, the hypothesis _used was that a significant change in ratio from one year to the next would be indicative of an environmental effect or some other phenomena requiring investigation. A statistically significant change in the ratio was determined by comparing the calculated value of the t-statistic to expected values of the t-statistic based on the number of measurements and desired accuracy of the results.
The value of the t-statistic calculated by comparing preoperational results to 1994 TLD results was -0.352. As shown in Table 3.9-B, this is within the boundary values of 2.042, based on 32 measurements and a 95% confidence interval.
From this evaluation, it can be concluded that the doserates measured around Catawba during 1994 did not differ significantly from those existing during preoperation.
1 3-20
)
?
TABLE 3.9-A DIRECT GAMMA RADIATION (TLD) RESULTS All Locations Site Boundary Ring 4-5 Mile Ring Special Interest Control Locations Year (40 Locations)
(16 Locations)
(16 Locations)
(5 Locations)
(3 Locations)
Avg. Dose Avg. Dose Avg. Dose Avg. Dose Avg. Dose (mrem)
(mrem)
(mrem)
(mrem)
(mrem) 1984 82.9 87.5 82.6 71.2 79.3 1985 110.7 116.9 108.7 98.6 108.9 1986 98.9 104.3 98.5 85.7 94.4 1987 90.0 97.0 87.4 78.6 84.7 1988 70.9 74.6 70.3 63.1 67.1 1989 62.6 67.1 60.8 54.3 60.0 1990 46.4 52.0 44.5 39.1 39.1 1991 56.7 62.0 54.1 48.0 46.7 1992 74.3 80.4 72.5 66.2 64.5 1993 63.6 70.3 60.8 56.2 53.6 1994 69.0 76.3 69.3 66.5 63.9 3 - 21
1 TABLE 3.9-B Comparison of Inner Ring / Outer Ring TLD Results i
1994 (mrem /qtr)
Preop. (mrem /qtr)
Inner Ring 21.54 21.87 Outer Ring 20.06 20.65 Ratio 1.07 1.06 Variance 0.06 0.07 t-value
-0.352 t-table 2.042 i
l l
l l
3 - 22
3.10 FOOD PRODUCTS Collection'of food product samples from an irrigated garden at a residence located on Lake Wylie downstream from CNS (Location 253) began in July,1989. During 1994, eleven samples were collected from this location.
During 1994, K-40 was detected in all 11 samples. These results were consistent with all sample results since 1989.
3.11 BOTTOM SEDIMENT During 1984, REMP bottom sediment samples were not collected. These samples were first collected during 1986 from three points in the dischar,e canal. Bottom sediment control samples have never been collected.
During 1994, Mn-54, Co-58, Co-60 and Cs-137 were detected in most of the twelve bottom sediment samples collected from CNS discharge canal Locations 208-1M,208-2M, and 208-3M. The four radionuclide(s) have been predominant each year since 1986 along with Cs-134. These five radionuclide(s) have been predominant in shoreline sediment samples collected from the discharge canal, samples for which average detectable concentrations are considerably lower, as should be expected. In addition Co-57, Sb-124.and Sb-125 were identified in samples. See Table 3-B. All detected radionuclide(s) were attributable to liquid effluents from CNS during 1994. Location 208-2M displayed the highest overall concentrations for the major radionuclide. Co-60 concentration was significantly higher with an average detectable. concentration of 6975 pCi/ dry kilogram.
Compared to 208-1M and 208-3M, the concentration was 3.1 and 1,03 times higher, respectively.
Table 3.11-A summarizes the bottom sediment sample results for discharge Location 208 during the period from 1989 to 1994.
Detection frequencies remained high and relatively stable throughout the period. Shoreline sediment frequencies paralleled this trend.
Average detectable concentrations of all radionuclides showed a decrease compared to 1993 data.
From 1989 through 1994, average detectable concentrations for bottom sediment correlated extremely well with cumulative, corrected activities released in liquid effluents since preoperation [ Parameter El as indicated by the consistent ratios of these values (Parameter Fl. The only radionuclide with data out of range of the other radionuclide(s) is Cs-134. The most probable reason for this is the lower frequency of detection. Over the period of trending, indications are that no significant environmental " removal" processes have limited Co-60 accumulation to levels below what would be expected based on cumulative, decay corrected activities released in liquid effluents since preoperation.
3 - 23
l 1
in all cases, the liquid effluent concentrations in 1994 followed the same changes as the average detectable concentrations. Therefore, the impact of plant operation l
on bottom sediment from Location 208 was at an expected level when considering the liquid effluent data for 1994, i
l The annual average detectable radionuclide concentrations for Location 208 bottom sediment samples tend to be largely dependent on the cumulative and to a moderate degree for Co-60 and Cs-137 on annual activities released via liquid effluents. It appears that discharge canal activities deposited annually in bottom sediment are not removed by environmental processes at a rate shown by activity measured in shoreline sediment and fish.
l l
l i
i 3 - 24
TABLE 3.11-A 4
BOTTOM SEDIMENT SAMPLE RESULTS - LOCATION 208-1M,2M, AND 3M Radio-Parameter 1989 1390 1991 1992 1993 1994
+
nuclide(s)
[A]
398 381 453 525 372 277
[B]
12/12 12/12 11/12 12/12 12/12 12/12 I
[C]
27.6 34.4 30.2 23.2 13.5 10.3
[D]
14.4 11.1 15.0 22.6 27.6 26.9
[El 45.4 54.6 54.5 47.4 34.6 25.7
[F1 8.8 7.0 8.3 11.1 10.8 10.8 Radio-Parameter 1989 1990 1991 1992 1993 1994 l
nuclide(s)
Co-58
[A]
670 783 691 1603 1597 1498
[B) 8/12 8/12 10/12 7/12 10/12 10/12
[C]
149 244 196 364 398 272
[D]
4.5 3.2 3.5 4.4 4.0 5.5
[El 156 248 203 423 410 283.5
[F) 4.3 3.2 3.4 3.8 3.9 5.3 Radio-Parameters 1989 1990 1991 1992 1993 1994
)
nuclide(s)
[A]
3420 4120 5100 7095 5792 5322
[B) 12/12 12/12 12/12 12/12 12/12 12/12
)
[C]
46.2 108 156 116 67.0 68.1
[D]
74.0 29.4 32.7 61.2 86.4 78.1 l
IEl 325 318 517 569 566 564
[F) 10.5 10.0 9.9 12.5 10.2 9.4
[Al Average Detectable Concentration (pCi/ dry kilogram)
[Bl Fraction of Total Measurements Yielding Detectable Activity IC]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci)
[El Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) 3 - 25
TABLE 3.11-A (Continued)
BOTTOM SEDIMENT SAMPLE RESULTS - LOCATION 208-1M,2M, AND 3M Radio-Parameter 1989 1990 1991 1992 1993 1994 nuclide(s)
Cs-134
[A]
140 127 122 78 184 0
IB]
9/12 9/12 8/12 7/12 5/12 0/12
[C]
4.7 10.2 5.6 4.3 3.20 1.2
[D]
29.5 12.5 21.7 18.1 57.5 0.0
[E]
23.9 27.3 25.1 22.3 19.1 14.8
[F]
5.9 4.7 4.9 3.5 9.6 0.0 Radio-Parameters 1989 1990 1991 1992 1993 1994 nuclido(s)
[A]
504 506 548 494 538 427
[B]
12/12 12/12 12/12 11/12 12/12 12/12
[C]
8.5 17.7 9.5 8.9 7.84 3.9 ID]
59.3 28.6 57.9 55.6 68.6 110.1
[E]
82.4 98.2 105 111 116 117.2 IF]
6.1 5.2 5.2 4.5 4.6 3.6
[A]
Average Detectable Concentration (pCi/ dry kilogram)
[B]
Fraction of Total Measurements Yielding Detectable Activity
[C]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/ dry kilogram per mci)
[El Decayed Cumulative Activity Released in Liquid Effluents (mci)
IF]
Concentration / Cumulative Activity Ratio (pCi/ wet kilogram per mci) k
)
)
)
)
3 - 26
)
l 3.12 LAND USE CENSUS The 1994 Annual Land Use Census was conducted as required by Selected Licensee Commitment 16.11-14. Table 3.12-A summarizes the census results.
Figure 3-A contains the map showing identified locations. For those data in Table 3.12-A for which a distance value was not listed, no corresponding location was identified in the sector within a distance of five miles from CNS.
Based upon 1994 Annual Land Use Census results for the nearest residences and gardens, dose evaluations were performed to ensure that the current air and broadleaf vegetation sampling locations complied with the requirements of Selected Licensee Commitment and that no changes or additions to these locations were required.
The evaluations showed that all existing air and bsoadleaf vegetati7n sampling locations complied with the requirements. No changes or additions to these locations were required or made as a result of the 1994 Annual Land Use Census.
The 1994 Annual Land Use Census included a search for all locations within a distance of five miles (eight kilometers) from CNS where any cattle or goats were kept (not just the nearest location in each sector). Numerous locations were identified within the five mile radius. Each location was investigated to determine whether the animals were being used for meat production, milk production, reproduction or a combination of these purposes. Investigation of all locations revealed that none of the animals were " milking animals" (milk was not being consumed by humans). The three current CNS REMP milk sampling locations (dairies located at distances greater than five miles from CNS), have been sampled since preoperation. No changes or additions to CNS REMP milk sampling locations were made as a result of the 1994 Annual Land Use Census.
3 - 27
I TABLE 3.12-A i
1994 CATAWBA NUCLEAR STATION ANNUAL LAND USE CENSUS RESULTS l
Date(s) Performed 7/28/94 - 8/19/94 l
l Sector Distance Sector Distance (Miles)
(Miles)
N Nearest Residence 0.64 S
Nearest Residence 0.83 Nearest Garden 1.54 Nearest Garden 0.98 Nearest Milk Cow Nearest Milk Cow l
Nearest Beef Cow 4.87 Nearest Beef Cow 4.05 Nearest Goat Nearest Goat i
NNE Nearest Residence 0.63 SSW Nearest Residence 0.89 l
Nearest Garden 2.07 Nearest Garden 1.69 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.04 Nearest Goat Nearest Goat 2.75 NE Nearest Residence 0.60 SW Nearest Residence 0.65 Nearest Garden 2.39 Nearest Garden 0.66 Nearest Milk Cow Nearest Milk Cow l
Nearest Beef Cow Nearest Beef Cow 2.59 i
Nearest Goat Nearest Goat 2.95 ENE Nearest Residence 0.62 WSW Nearest Residence 0.79 l
Nearest Garden 0.60 Nearest Garden 2.04 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.17 Nearest Beef Cow 2.87 Nearest Goat 1.27 Nearest Goat E
Nearest Residence 0.65 W
Nearest Residence 0.96 Nearest Garden 0.84 Nearest Garden 1.15 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.41 Nearest Beef Cow 3.81 Nearest Goat 4.28 Nearest Goat ESE Nearest Residence 0.84 WNW Nearest Residence 1.10 Nearest Garden 2.83 Nearest Garden 1.11 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow Nearest Goat Nearest Goat 4.34 SE Nearest Residence 0.99 NW Nearest Residence 1.31 Nearest Garden 1.52 Nearest Garden 1.52 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.19 Nearest Beef Cow 2.30 l
Nearest Goat 4.80 Nearest Goat 1.44 SSE Nearest Residence 0.62 NNW Nearest Residence 1.06 Nearest Garden 1.70 Nearest Garden 2.19 Nearest Milk Cow Nearest Milk Cow i
Nearest Beef Cow Nearest Beef Cow 3.49 Nearest Goat Nearest Goat 2.62 3 - 28 l
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l SECTION 4
)
?
EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS i
VERSUS ESTIMATED DOSE FROM RELEASES i
l' 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured l
]
concentrations of radionuclide(s) in 1994 CNS REMP samples. The primary j
j purpose of estimating doses based on sample results was comparing them to effluent program dose estimates.
Doses based on sample results were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates.
j' Doses based on sample results were calculated using the methodology and data
)
i-presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year (with nondetectable measurements averaged in as zero) for a specific radionuclide, indicator location, and sample type, were used to calculate REMP-based doses, after subtracting applicable average background i
concentration (as measured at the corresponding control location). Regulatory i.
Guide 1.109 consumption rates for the maximum exposed individual were used in j
the calculations. When the guide listed "NO DATA" as the dose f actor for a given radionuclide and organ, a dose factor of zero was assumed.
j Two radionuclide(s) detected in 1994 REMP samples: Co-57 and Sb-125 had no j
dose factors listed in Regulatory Guide 1.109.
Dose' factors-for these i
radionuclide(s) were taken from Appendix C of NUREG/CR-1276.
j Dose contributions from detectable concentrations of naturally-occurring l
j radionuclide(s) other than tritium (K-40 and Be-7) were not included in the dose calculations. All other detected radionuclide(s), including those not listed in l
Selected Licensee Commitments (see Section 3),' were included. Results for all j
1994 samples were included in the dose calculations.
i i
Maximum dose estimates (Highest Annual Mean Concentration) based upon milk, i
5 broadleaf vegetation, shoreline sediment and fish sarnple results are reported in j
Tables 4-D.
l i-REMP-based dose estimates were not reported
- for the airborne radiciodine,
{
airborne particulate, or ground water sample types because no radionuclide(s) other i
than naturally-occurring K-40 and Be-7 were ' detected in these samples. Dose j
estimates were not reported for the surface water or bottom sediment sample types because sampled surface water is not considered to be a potable drinking i
water source and because sampled bottom sediment is permanently submerged.
Dose estimates based upon REMP TLD results are discussed in Part 3.9.
1 i
L
)
4-1 i
i
d The maximum dose to each organ from any single sample type (the " limiting"~
sample type) other than direct radiation from gaseous effluents, was determined i
and reported in Table 4-A. For skin dose, the limiting sample type was shoreline _
sediment collected at discharge canal Location 208-2S. For bone, liver, kidney, total body and lung, the limiting sample type was broadleaf vegetation collected at Location 226. The maximum organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 1994 was 0.263 mrem / year to the maximum exposed child's bone from consuming broadleaf vegetation collected at Location 226.
in order to generate REMP-based dose estimates which could be compared to reported ' effluent-based dose estimates, two additional evaluations -were 1
performed:
Maximum 1994 REMP-based dose. estimates for shoreline sediment and fish j
sample results were summed to determine the maximum total doses for all sampled liquid effluent release pathways. This summation was performed individually for all 32 combinations of organ and age group. The dose contribution from shoreline sediment to each organ other than the skin was assumed to equal the total body contribution from shoreline sediment. The maximum total organ dose estimates for the critical age groups have been reported in Table 4-B. The maximum total organ dose estimate for all liquid effluent release pathways sarnpled during 1994 was 0.187 mrem / year to the maximum exposed teen's GI-LLI. The critical pathway was forager fish which accounted for 95% of the total GI-LLI dose of l
0.178 mrem / year. Shoreline sediment accounted for 5% of the total GI-LLI dose.
Maximum 1994 REMP-based dose estimates for airborne radioiodine (zero),
airborne particulate (zero), milk, broadleaf vegetation and food product (zero) sample results were summed to determine the maximum total REMP-based doses for all sampled gaseous ef fluent release pathways. This summation was performed individually for all 32 combinations of organ and age group.
The resulting maximum total organ dose estimates for the critical age groups have been reported in Table 4-C.
The maximum total organ dose estimate for all gaseous effluent release pathways i
sampled during 1994 was 0.275 mrem / year to the maximum exposed child's bone.
The critical pathway was broadleaf vegetation which accounted for 96% of the
)
total bone dose.
Excluding REMP TLD results (which are discussed in Part 3.9), all 1994 REMP-i based annual organ dose estimates were less than 0.28 mrem / year and were typically an order of magnitude below this level.
All of the annual dose estimates were less than the corresponding calendar year dose limits applicable to effluent-based dose calculations found in Selected Licensee Commitments.
4-2
. -. - ~
4.2-ESTIMATED DOSE FROM RELEASES -
l
. Throughout the year dose estimates were calculated based on actual 1994 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the LADTAP and GASPAR' computer programs, which employ the methodology and data presented in NRC Regulatory Guide 1.109. The 1994 CNS Annual Radioactive Effluent Release Report included calendar year dose estimates for the maximum exposed individual from liquid and gaseous effluent releases.
These reported doses are shown in Table 4-B (liquid releases) and Table 4-C i
(gaseous releases), along with the corresponding REMP-based dose estimates.
The effluent-based liquid release doses of Table 4-B are summations of dose contributions from the fish and shoreline sediment pathways (estimated for the j
discharge canal).
The drinking water pathway (estimated for the nearest downstream potable water intake) was not used this year due to no detectable radionuclides occurring.
The effluent-based gaseous release doses of Table 4-C report separately noble gas I
exposure and iodine, particulate and tritium exposure. For noble gas exposure i
there is no critical age group; as the maximum exposed individuals are assumed to i
receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure the 1994 CNS Annual Radioactive Effluent Release Report listed the maximum total organ dose for the highest dose location (0.5 miles ENE), but only for the maximum organ (thyroid) for the critical age group (child). Effluent-l based dose estimates for organs other than the thyroid are not given in the iodine, particulate and tritium exposure summary of Table 4-C.
l 4.3 COMPARISON OF DOSES 2
Tables 4-B and 4-C allow for comparison of REMP-based versus effluent-based maximum dose estimates, critical ages, and critical pathways for the liquid and gaseous release pathways. As discussed in Part 4.1, the REMP-based estimates have been calculated to be as analogous as possible to the corresponding effluent-based estimates. The estimates can then be compared directly.
One difference between estimates is all effluent-based dose estimates include pathway contributions from tritium contained in liquid and gaseous effluents.
Although REMP-based dose estimates for drinking water pathways include dose contributions from tritium when detected, dose estirnates for the fish, air, milk, and broadleaf vegetation pathways do not include tritium dose contributions; as tritium analysis is not performed on these samples. Similar differences exist for other i
radionuclide(s) detected in effluent samples. However, as a result of dilution, transport, and radioactive decay, they are normally too low to be detected in REMP j
samples (and their associated dose contributions are therefore not accounted for in REMP-based dose estimates). These differences result in REMP-based dose estimates that are biased low in comparison to effluent-based estimates.
)
4-3 1
l l
i 1
in addition, significant levels of tritium and Cs-137 are present throughout the environment and are not attributable to CNS effluents. REMP samples often i
contain these radionuclide(s), sometimes at detectable levels much greater than the i
levels anticipated to result from station effluents. This compounded by the high
' variability in the frequency and level that tritium and Cs-137 are detected in REMP indicator and control location samples, introduces large uncertainties when estimating REMP-based dose contributions from net detectable concentrations of these radionuclide(s). All 1994 REMP-based dose estimates, other than those for samples collected at the discharge canal, are entirely attributable to detection of tritium or Cs-137 in the corresponding REMP samples. It is probable that the doses typically overestimate the true contributions from tritium and Cs-137 released in CNS effluents.
Finally, airborne noble. gas samples are not collected as part of the;REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates. Dose estimates based on REMP TLD results (which could be affected l
by noble gases in airborne effluents) are discussed in Part 3.9.
Comparison of the data in Table 4-B reveals good agreement between 1994 REMP and effluent-based maximum dose estimates for liquid effluent release pathways.
Table 4-B gives environmental / effluent dose estimate ratios for each organ. REMP-based dose estimates ranged between 7% and 37% (average of 14%) of the-j effluent based estimates. The 1994 effluent-based dose estimates for liquid effluent release pathways were 38% lower on average than their 1993 levels, reflecting a similar average decrease of 33% in the quantities of key radionuclide(s) released in CNS liquid effluents. The above observations indicate a reasonable correlation between liquid effluents, REMP fish and shoreline sediment sample results and the associated dose estimates.
For iodine, particulate, and tritium exposure via gaseous effluent release pathways (Table 4-C), the maximum effluent-based dose estimate was 0.355 mrem / year to the maximum exposed cnitd's thyroid (critical pathway was vegetation). The maximum REMP-based dose estimate was 0.275 mrem / year to the maximum exposed child's bone (critical pathway was vegetation). This value was 77% of the maximum effluent-based dose estimate. The REMP-based dose estimates were entirely attributable to four detections of Cs-137 from eight samples of broadleaf vegetation. These doses are overestimates of the dose contribution from Cs-137 released in CNS gaseous effluents because during 1994 no Cs-137 was detected in gaseous effluents. The REMP-based dose estimates do not include dose contributions from tritium (as tritium analysis is not performed on the corresponding REMP samples) which accounted for 95% of the effluent-based thyroid dose estimate.
i l
l 4-4 l
.,..---,---.-,-,..i
The REMP-based dose estimates were consistently comparable to and less than the corresponding effluent-based estimates for the liquid and gaseous release pathways. This evidence indicates that effluent program dose estimates are both valid and reasonably conservative and that doses to members of the public attributable to the operation of CNS are being maintained well within regulatory guidelines.
1994 annual dnse estimates based upon REMP sample results compared very well with effluent program dose estimates considering the uncertainties inherent in comparing dose estimates based upon extremely low levels of environmental radioactivity.
l I
l i
l l
l l
l l
1 4-5 i
TABLE 4-A DOSE ESTIMATES BASED ON LIMITING 1994 ENVIRONMENTAL SAMPLE RESULTS ORGAN DOSE RATE CRITICAL CRITICAL CRITICAL (mrem / year)
AGE PATHWAY LOCATION Skin 1.04E-02 Teen Shoreline Sediment 208-2S Bone 2.63E-01 Child Broadleaf Vegetation 226 Liver 2.51 E-01 Child Broadleaf Vegetation 226 T. Body 1.41 E-01 Adult Broadleaf Vegetation 226 Thyroid 8.89E-03 Teen Shoreline Sediment 208-2S Kidney 8.19E-02 Child Broadleaf Vegetation 226 Lung 2.95E-02 Child Broadleaf Vegetation 226 GI-LLI 1.78E-01 Teen Fish (Forager) 208 4-6
f TABLE 4-B 1994 CNS ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON FOR LlOUlD WASTE RELEASE PATHWAYS ORGAN DOSE RATE CRITICAL CRITICAL
'94 ENV /
(mremiyr)
AGE PATHWAY
'93 ENV.
Env 1.04E-02 TEEN Shoreline Sed.
Skin Eff 4.32E-02 TEEN Shoreline Sed.
-0.29 Ratio 0.24 Env 1.79E-02 TEEN Fish (Forager)
Bone Eff 2.70F-01 CHILD Fish (Forager)
-0.36 Ratio 0.07 Env 2.50E-C2 TEEN Fish (Forager)
Uver Eff 3.68 E-01 TEEN Fish (Forager)
-0.30 Ratio 0.07 Env 2.13 E-02 TEEN Fish (Forager) l l
T. Body Eff 2.49E-01 ADULT Fish (Forager)
+ o,20 Ratio 0.09 i
Env 8.89E-03 TEEN Shoreline Sed.
l Thyroid Eff 8.78E-02 TEEN Fish (Forager)
+0.53 Ratio 0.10 Env 1.32E-02 TEEN Shoreline Sed.
Kidney Eff
- 1. 30E-01 TEEN Fish (Forager)
+0.29 Ratio 0.08 Env 1.05 E-02 TEEN Shoreline Sed.
Lung Eff 9.84 E-02 TEEN Fish (Forager)
+ 0.2 5 Ratio 0.11 Env 1.87 E-01 TEEN Fish (Forager)
GI-LLI Eff 5.02E-01 ADULT Fish (Forager)
-0.34 Ratio 0.37 l
l l
4-7 1
TABLE 4-C 1994 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON I.
FOR GASEOUS RELEASE PATHWAYS NOBLE GAS EXPOSURE
SUMMARY
3 ORGAN DOSE RATE CRITICAL CRITICAL l
(mrem / year)
AGE PATHWAY mmmmmmmmmmu mmmmmmmmmmmmmmmmmmmmemam mmmmmmmmmmm Skin Env N.G. not sampled N/A N/A j
Eff 1.78E + 00 N/A Noble Gas Exposure i
T. Body Env N.G. not sampled N/A N/A Eff 9.62E-01 N/A Noble Gas Exposure i
IODINE, PARTICULATE, AND TRITIUM EXPOSURE
SUMMARY
ORGAN DOSE RATE CRITICAL CRITICAL (mrem / year)
AGE PATHWAY Bone Env 2.75E-01 Child Broadleaf Vegetation t
Liver Env 2.62E-01 Child Broadleaf Vegetation i
j T. Body Env 1.43E-01 Adult Broadleaf Vegetation j
Env 0
N/A N/A Thyroid Eff 3.55E-01 Child Broadleaf Vegetation i
Kidney Env 8.56E-02 Child Broadleaf Vegetation Lung Env 3.08E-02 Child Broadleaf Vegetation GI-LLI Env 4.24E-03 Adult Broadleaf Vegetation i
t i
1 4
4-8 i
T TABLE 4-D PATHWAY DOSE ESTIMATES l
l l
Dese front Air Radionedmes inhalation Pathway for 1994 Data Maximum Exposed Adult j
Usage (intake rate) =
9000.00 (m3/yr) l Highest Annual Mesa Concentration Adult Inhalation dose factor (unas in @ ingested)
Air Dose (aree/yr) th henucEde Bone liver T. Body nyreM Kidney Lang GI.LLI location (pCl/m3)
Bene liver T. Body n yssid Kidney laang GI-Lil Ms.54 NO DATA 4.95E06 7.87E-07 NO DATA 1.23E 06 1.74E-C4 9.67E46 ALL 0.00E+00 0.00E+00 0.00E4 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Co.58 NO DATA 1.98E 07 2.59E 07 NO DATA NO DATA 1.16E44 1.33E45 ALL 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 Fe-59 1.47E-06 3.47E.06 1.32E 06 NO DATA NO DATA 1.27E44 2.35E45 ALL 6.00E+ 00 0.00E +00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+04 0.00E+00 Co40 NO DATA 1.44E.06 1.85E-06 NO DATA NO DATA 7.46E44 3.56E45 ALL 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.0$E-06 1.29E45 5.28E46 NO DATA 8.62E.06 1.08E44 6.68E46 ALL 0.00E+00 0.0dE+00 0.00E+00 0.00E+00 0.00E+00 0.ME+00 0.00E+00 0.00E+00 Nb.95 1.76E-06 9.77E 07 5.26E47 NO DATA 9.67E47 6.31E45 1.30E45 ALL 6.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 1.34E45 4.30E 06 2.91006 NO DATA 6.77E46 2.21E44 1.88E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1131 3.15L86 4.47E46 2.56E46 1.49E43 7.66E46 NO DATA 7.85E47 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.POE+00 0.00E+44 0.00E+00 0.00E+00 Cs.134 4.66E45 1.06E44 9.10E45 NO DATA 3.59E45 1.22E45 1.30E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 5.95E45 7.76E45 5.35E45 NO DATA 2.78E45 9.40E46 1.05E46 ALL 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 BaLa.140 4.88E46 5.13E49 3.20E47 NO DATA 2.09E49 1.59E44 2.73E45 ALL O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL DOSE EQUIVAIINT(nerven/yr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4-9
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Deee from Air ParJeuiate Imbalahen Pathway for 1994 Data Maximuma Exposed Adult Usate (intake rate) =
9000 (m3/yr)
Highest AmmualMesa Concentratism Adult Inhalation dose factor (urve per pClingested)
Air Does kruum/yr)
Cachomuclide Bone IJver T. Bedy Thyroid Klehwy Lung GI-LIl Imation (pCi/m3)
Bene IJver T. Bedy Thymid Kidmey Imag Gl.LLI Ma-54 NO DATA 4.95E46 7.87E47 NO DATA
'E46 1.74E44 9.67E 06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.98E47 2.59E47 NO DATA NO DATA 1.16E44 1.33E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.47E46 3.47E46 IJ2E46 NO DATA NO DATA 1.27F 84 2J5E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.60 NO DATA 1.44FA6 1.85E46 NO DATA NO DATA 7.46F 04 3.56E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Za45 4.05E46 1.29FA5 5.28E46 NO DATA 8.62E46 1.08F 04 6.68E46 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb.95 1.76F 86 9.77E47 5.26E47 NO DATA 9.67E47 6.31E45 1.30E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.34E45 4.30E46 2.9tE46 NO DATA 6.77E46 2.21E44 1.88E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 3.15E46 4.47E46 2.56E46 1.49E43 7.66E46 NO DATA 7.RSE47 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2
Cs.134 4.66FA5 1.06E44 9.10E45 NO DATA 3.59E45 IJ2E45 1.30F-86 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.95FA5 7.76E45 5.35E45 NO DATA 2.78E45 9.40E46 1.05E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+80 0.00E+00 0.00E+00 Ba14 140 4.98E46 6.13E49 3.20F 87 NO DATA 2.09E49 1.59E44 2.73E45 All 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00f;+00 0.00E+00 0.00E+00
{
TOTAL DOSE EQUIVAl2NT(erem/yr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+tri 8.00E+00 0.00E+00 0.00E+00 l
4-10 i
I
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) i t
Dese frees Dnsking Water Pathwsy for 1994 Data Maximum Exposed Aduk Usate (intake rate) =
730 Olyr)
Hi hest Ammeal Meam Concentratwo t
Adult Inte. ben Dese Facter (arem per pCiintated) 8=aw Water Dese (aremlyr)
Rashemutlide Bene Liver T. Body H yroid Kidney Img GI-LIl Imcation (yCill)
Bose IJver T. Body Thyreed Eidmey I.asmg GI-LIJ Mm-54 NO DATA 4.57E46 8.72E47 NO DATA 1.36E 06 NO DATA LASE 45 ALL 0 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 Co-58 NO DATA 7A5E47 1.67F-86 NO DATA NO DATA NO DATA 1.51E45 ALL 9 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 Fe-59 4.34E46 1.02E45 3.91E46 NO DATA
'O DATA 2.85E46 3AOF 05 ALL 6 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+48 Co4e NO DATA 2.14E46 4.72F 86 NO DATA NO DATA NO DATA 4.02E45 ALL 8 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+08 Zm.65 4.84E46 1.54E45 6.96E46 NO DATA 1.03E45 NO DATA 9.70E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+00 Nb-95 6.22E49 3A6E49 1.96E49 NO DATA 3A2E49 NO DATA 2.10E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E4R 9.75E49 6.60E49 NO DATA 1.53E4B NO DATA 3.09E45 ALL 6 0.00E+00 0.00E+00 0.'00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 4.16F 86 5.95E46 3AIE46 1.95E43 1.02E45 NO DATA 1.57E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 '
{
i Cs-134 6.22E45 1ASE44 1.21E44 NO DATA 4.79E45 1.59E45 2.59E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 7.97E45 1.09E44 7.14E45 NO DATA 3.70E45 1.23E45 2.llE46 ALL 0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E45 2.55E46 1.33E46 NO DATA 8.67E49 IA6E48 4.10E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+08 0.00E+00 0.00E+00 I
H-3 NO DATA 1.05E47 1.05E47 1.05E47 1.05E47 1.05E47 1.05E47 214 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
TOTAL DOSE EQUIVAIENT(aremelyr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
1 4-11 v
m
~1-wm m
TABLE 4-D PATHWAY DOSE ESTIMATES (COWT)
Dese fkeen Dem Fashway for 1994 Data IJenge Getake rees) =
310 1/yr Maxiseman Exposed Admit Admit IEgbest Amamal Mean Comromtraties Inesselen Dese Farter (sureen per pCllussuesd)
Indrater nWk Dame (ameadyr)
Radlemucede Bene IJwr T. Body nyrend 10dmey Imag Q.IL termalem (yCl/tJ Bene IJwr
. T. Body Dyreid IGdmey Imag G.1H Mm.54 NO DATA 4.57F 86 c.72FA7 NO DATA 1.36EA6 NO DATA 1.4eE45 All e.00 e.88E+ 80 8.8OE+ 80
- e. tee + M 8.seE+88 e.seE+ 00
- 0. tee +0e 6.00E+M Co.50 NO DATA 7.45EW1 1.67E-06 NODATA NO DATA NODATA 1.51F 85 All e.00 8.eOE+ 00 e.SeE+ee 0.00E+ 00 e.SeE+ 88 8.SeE+et e.00E+00 0.seE+64 F -59 4.34FA6 1.02FAS 3.91FA6 NO DATA NO DATA 2.05FA6 3.40E45 AIL 0.00 e.seE+ 00 0.00E+ es
- e. tee + 0S
- 0. gee + 08 0.8eE+ M 0.00E+0e 9.eeE+00 Co4e NO DATA 2.14FA6 4.72E.06 NO DATA NO DATA NO DATA 4.82E45 All e.80 e.SeE+ et e.SeE+M ' e.seE+M
- e. gee +es 0.8EE+ 00 0.eeE+0e 0.00E+80 Zm45 4.84E4 1.54F 85 6.96FA6 NODATA 1.83F 85 NO DATA 9.7eEA6 All e.00 e.SeE+ 88 e.seE+ 0e e.00E+ 80
- e. gee + 00 0.eeE+ es 8.SeE+0S e.00E+ 0e Nb.95 6.22E.09 3.46EA9 1.86E49 NODATA 3.42F 89 NO DATA 2.leEA5 All 8.00 e.seE+0S
- 8. gee + es
- e. gee + es e.esE+ee e.seE+ e8 8.SeE+ 88 0.0eE+ 08 Zr.95 3.04E-te 9.75EA9 6.68EA9 NODATA 1.53E4e NO DATA
- 3. MEAS AIL e.00 0.00E+0e 0.88E+ ee 0.seE+0e e.eeE+00 8.eeE+ 0e 8.stE+0e
- 8. tee +0S I.131 4.16EA6 5.95EA6 3.41E.06 1.95EA3 1.01FA5 NODATA I.57EA6 All 8.00 0.00E+ 0S 0.OSE+ 0S 0.seE+ 0e 8.eE+ 00 e.seE+00 e.seE+ee 8.etE+00 Co-134 6.22 Fee 5 I.40FA4 1.21FA4 NO DATA 4.79E-05 1.59FAS 2.59Em All e.00 e.eOE+ 00 e.seE+ es 0.00E+ 0S
- 6. tee + 98 e.eeE+es 8.eeE+ 00
- 0. gee + 88 Co.137 7.97E-05 ' t.09E-04 7.14EA5 NODATA 3.7eEAS 1.23E45 2.tlE46 289 c.11 2.72EA3 3.72E4 2.43EA3 e.eOE+ 00 1.2EE el 4.19FA4 7.2eE45 Bata let 2.e3E45 2.55EAS 1.33F 86 NODATA e.67F 89 1.4e840 9.25E45 AIL 0.00 e.etE+ et e.SeE+ et e.eEE+ 0S 8.eeE+ 00 S.SeE+ 00 0.OE+ 00 0.00E+ 00 Toese Dese Eguivalent immendyrl=
2.72E43 3.72E48 2.43E4e 0.00E + 0e 1.20E43 4.18E44 7.20E40 i
f 4-12
~
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese front Broedeaf Vegetaties Fathway for 1994 Data Maununuma Exposed Adult Usage (intake ra 4) =
64 kglyr Highest Ammmet Mean Concentrahem Adult Ingestion Dese Factor (unresa per pCIimeested)
Indicster Feed Dese (unremelyr)
Radnemuclide Bone IJver T. Body n yroid Kidney Lung GI-LIJ Location (pCilha)
Beme IJver T. Body R yroid Esdney Imag Cl.LIJ Ms-54 NO DATA 4.57E46 8.72E47 NO DATA 1.36E46 NO DATA 1 AGE 45 ALL 9 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7A5E47 1.67E46 NO DATA NO DATA NO DATA 1.5tE45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe59 4.34E46 1.02F 05 3.9tF 86 NO DATA NO DATA 2.85E46 3 AGE 45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs 40 NO DATA 2.14E-06 4.72E46 NO DATA NO DATA NO DATA 4.02E45 ALL 0 0.00E+M 0.00E+00 0.00E+00 a 40E+00 0.00E+00 0.00E+08 0.00E+00 Zm-65 4.84FA6 1.54E-05 6.96E46 NO DATA 1.03E45 NO DATA 9.70FA6 ALL 0 0.00E+00 0.00E+00 0.00E+M s
+00 0.00E+00 0.00E+00 0.00E+00 Nb.95 6.22E49 3A6E49 1.96E49 NO DATA 3A2E49 NO DATA 2.10E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Zr.95 3.04E48 9.75FA9 6.64EG NO DATA IJ3E48 NO DATA 3.09FA5 ALL 0 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 1
1 131 4.16E46 5.95E46 3.4tFA6 1.95E43 1.02E45 NO DATA 1.57E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.134 6.22E45 1ABE44 IJ1E44 NO DATA 4.79E45 1.59E45 2.59E46 ALL 0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Cs.137 7.97E45 1.09FA4 7.148E45 NO DATA 3.70E45 1.23E45 2.11E46 226 30.9 1.5BE41 2.16E41 1AIE41 0.00E+00 7.32E42 2A3E42 4.17E43 1
I BeLa.140 2.03E45 2m 1.33E46 N0 DATA 8.67E49 1A6E46 4.18E45 ALL 0 0.00E+M 0.00E+M 0.00E+00 0.00E Fee 0.00E+00 0.00E+00 0.00E+M i
i Total Dese Equivalemt(anremelyr)=
1.NE41 2.16E41 1A1E41 0.00E+M 7.32E42 2A3E42 4.17E43 4
4-13
=.
TABLE 4-D PATHWAY bOSE ESTIMATES (CON'T)
Dese frein Mah Pathway for 1994 Data Maximam Exposed Adult i
Usage (intake rate) =
21 kg/yr Highest Amment Mean Cemeemtration Aduk Ingestion Dese Facter (sarema per pClimtested)
. Indicator Illsh Deee tenrums/yr)
K* ncy Imme GI-Lil Imcaties (pCn/kg)
Bene ther T. Body Thyroid. Kidney Imag Os.LLI 4
Rashemmelide Bene Uver T. Body Thyroid Mm-54 NO DATA 4.57FA6 8.72E47 NO DATA 1.36E46 NO DATA 1 AGE-45 208 5.73 0.00E+00 5.50E44 1.05E44 0.00E+00 1.68E44 0.00E+00 1.seE.03 Ccw38 NO DATA 7ASE47 1.67E46 NO DATA NO DATA NO DATA 1.51E45 208 128 0.00E+00 2.00E43 4A9E43 3.00E+00 0.00E+00 0.00E+M 4.0eE-02 Fe-59 4.34E46 1.02E45 3.91E46 NO DATA NO DATA 2.85E46 3ASE45 ALL 0 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E + 00 Co-60 NO DATA 2.14E46 4.72E46 NO DATA NO DATA NO DATA 4.02E45 208 34.9 0.00E+00 1.57E43 3A6E43 0.00E+M 0.00E+M 0.00E+00 2.esE-02 Zm-65 4.84FA6 1.54E45 6.96E46 NO DATA 1.03FA5 NO DATA 9.70E46 ALL 0 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 Nb-95 6.22FA9 3A6E49 1.06FA9 NO DATA 3A2E49 NO DATA 2.10FA5 ALL 8 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 Zr-95 3.04E48 9.75E49 6.60E49 NO DATA 1.53FAS NO DATA 3.09E45 ALL 0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E +00 1131 4.16E46 5.95E46 3AIE46 1.95FA3 1.02E45 NO DATA 1.57E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.StE+M 0.00E+M 0.00E + 00 Cs-134 6.22E45 1A8E44 1.21E44 NO DATA 4.79E45 1.59E45 2.59E46 ALL 0 0.00E+00 0.00E+00 0.002+00 0.00E+M 0.NE+00 0.00E+00 0.00E + 00 Cs-137 7.97E45 1.09E44 7.14E45 NO DATA 3.70E45 1.23FA5 2.11E46 208 5.05 8ASE43 1.16E42 7.57E43 0.00E+00 3.92E43 1.30E43 2.24E.04 Belm-140 2.03E45 2.55E48 1.33E46 NO DATA 8.67E49 1A6E48 4.18E45 ALL 0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.0tE+00 0.00E+00 0.00E + 00 4
Ag-110mm 1.60E47 1A8E47 8.79E4B NO DATA 2.91E47 NO DATA 6.04E45 208 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 TOTAL DOSE EQUFVALENTimrom/yrl=
8.45E-03 1.67E-02 1,56E-02 0.00E + 00 4.00E-03 1.30E-03 7.20E-02 4-14 l
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) t i
i Dese frean Food Freducts (Crops) for 1994 Data Usage (intake rates =
520 helyr Maximause Esposed Aduk ADULT Hiebest AmamalMean Concestration Im0estsen Dese Facter (airena per pCIlatested) smac.n=r Feed Deee (sareadyr)
Radiomuclide Bene Uver T. Body Thyroid Kidney Lung GI-ID I4 cation (yCilke)
Bene Uver T. Body Thyroid Kidney Lang GI-ID Me-54 NO DATA 4.57E46 R.72E47 NO DATA 1.36E46 NO DATA 1 AGE 45 ALL 3.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E47 1.67E46 NO DATA NO DATA NO DATA l'.51E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E45 3.91E46 NO DATA NO DATA 2.RSE46 3ASE45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 2.14E46 4.72E46 NO DATA NO DATA NO DATA 4.02E45 ALL 4.00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 i
Zm-65 4.54E46 1.54E45 6.96E-06 NO DATA 1.03E45 NO DATA 9.70E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+0t 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E49 3.46E49 1.96E49 NO DATA 3.42E49 NO DATA 2.10E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E48 9.75E49 6.60E49 NO DATA 1.53E48 NO DATA 3.0pE45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 4.16E46 5.95E46 3AIE46 1.95E43 1.02FAS NO DATA 1.57E46 Al.L 0.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E45 1ASE 04 IJ1E44 NO DATA 4.79E45 1.59FA5 2.59E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+08 4
O>l37 7.97E45 1.09E44 7.14E45 NO DATA 3.70E45 1.23E45 2.11E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.fl0E+00 0.00E+00 0.00E+00 Belm-140 2.03E45 2.55E48 1.33E46 NO DATA 8.67E49 1A6E48 4.10FA15 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SJ0E+00 0.00E+00 0.00E+00 Total Dese Equivaisu$nareemlyr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 SAGE +00 0.00E+00 0.00E+00 L
4-15 i
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) i Dese frema Air Raabeledenes th Fathway for 1994 Data Manianasa Esposed Teen Usage (intake rate) =
9000 (at3/yr)
Ihsheet AmmuelMeanConcentratism TEEN I=helanas dose factor (anna per pCiingested)
Air Deee 6mrumsfyr)
Radsomuclide Bene Ilver T. Body n yroid E dmey Lung GI-LLI Locaties (pCl/mi3)
Bene IJver T. Body Thyroid Kidney Lung ' GI-IJJ Mm-54 NO DATA 6.39E46 1.05F 86 NO DATA 1.59FA6 2ABE44 8.35E46 ALL 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+M O 00E+00 0.00E+00 Co-58 NO DATA 2.59E47 3A7E47 NO DATA NO DATA 1.68E44 1.19E45 ALL 6.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.09E46 4.62E46 ' l.79E46 NO DATA NO DATA 1.91E44 2.23E45 ALL 4.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+M 0.00E+00 Co-64 NO DATA 1.89E46 2ASE46 NO DATA NO DATA 1.09E43 3.24E45 ALL 0.00E+00 0.00E+00 0.00E+M 4.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 Zm-65 4.82E 06 1.67E45 7.90E46 NO DATA 1.08E45 1.55E44 5.83E46 ALL 4.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 Nb-95 2.32E46 1.29E46
- 7. ORE 47 NO DATA 1.25E46 9.39E45 1.21E45 ALL 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 95 1.82F 45 5.73E46 3.94E46 NO DATA 8A2E46 3.36E44 1.96E45 ALL 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M l-131 4A3E46 6.14E46 3.30E46 1.83E43 1.05E45 NO DATA 8.11E47 ALL 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Q>134 6.2SE45 IAIE44 6.96E45 NO DATA 4.69E45 1.83E45 1.22F 86 ALL 4.00E+M 0.00E+00 0.00E+00 0.00E+00 0.001', ~00 0.00E+00 0.00E+ 00 0.00E+00 Cs-137 8.38E45 1.06E44 3.89FA5 NO DATA 3.90E45 1.51F-05 1.06E46 ALL 0.00E+M P.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+GO 0.00E+00 BeLa-140 6.84E46 8.30E49 4ASE47 NO DATA 2.85E49 2.54E44 2.96E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Total Dese Equivalent (aremilyr)=
SJ0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4-16
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese from Air Particulate Inhalainee Pathway for 1994 Data Mammasan Enyesed Teen Usage (intake rate) =
9000 (m3/yr)
Hagbeat AmmeallWW Concentrahes TEEN W dose facter (arem per pCilatested)
Indicator Air Deee (aremlyr)
RadienucEde Bene ther T. Body Thyreld Kadaey Lang GI-LLI I4caties (yCi/m3)
Bose IJver T. Body Thyroid Kiemey lasag GI-LIJ Ma-54 NO DATA 6.39E4 1.05E46 NO DATA 1.59E46 2ABE44 8.35E4 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 2.59E47 3A7E47 NO DATA NO DATA 1.68E44 1.19E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 Fe.59 1.09E46 4.62E4 1.79E4 NO DATA NO DATA 1.91E44 2.23F,45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.99F 86 2ASE46 NO DATA NO DATA 1.09E43 3.24E45 ALL 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
.Zm45 4.82E46 1.67E45 7.90E46 NO DATA 1.08E45 1.55E44 5.83EW ALL 4.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E4 00 0.00E+M 0.00E+00 0.00E+00 Nb-95 2.32E46 1.29E46 7.08E47 NO DATA-1.25E4 9.39E45 1.21E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E4 M 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.82E45 5.73E46 3.94E46 NO DATA BA2E4 3.36E44 1.96E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E +00 0.00E4 80. 0.00E+00 0.00E+00 0.00E+00 1 131 4A3EM 6.14E46 3.30E46 1.83E43. I.0$E45 NO DATA 8.llE47 ALL 4.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E4 00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.28E45 IAIE44 6.96E45 NO DATA 4.69E45 1.83E45 1.22E46 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cel37 8.38E45 1.06E44 3.99E45 NO DATA 3.90E45 1.51E45 1.06E46 ALL 4.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bale-140 6.94E46 8.30E49 4 AGE 47 NO DATA 2.85E49 2.54E44 2.96E45 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E4-00 0.00E+00 0.00E+00 0.00E+00 Total Dese Equivahat (mean/yr)=
0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 4-17
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) l l
Dese froma Dnnidag Water Pathway for 1994 Data l
Usage (intake rate) =
510 Llyr Maximmma Exposed Teen Teen Highest Ammeal Mesa Caecentraties Ingenhen Dese Factor Dnalums (arem per pCIIngested)
Indicator Water
, Dere (unremelyr)
Radiommelide Bene IJ,er T. Body Thyroid. Kidney Imag GI-LLI 1mcation (pCi/L)
Bene IJ,er T. Bedr linyroid Kidney Img GI-LIJ Mm-54 NO DATA 5.90E46 1.17E46 NO DATA 1.76F-86 NO DATA 1.21E45 ALL 4.0 0.00E+ 00 0.00E+ 00 0.00E+00 SJ0E+00 0.00E+00 0.00E+M 0.00E+00 Co-58 NO DATA 9.72E47 2.24E46 NO DATA NO DATA NO DATA 1.34E45 ALL 4.0 0.00E+M 0.HE+00 0.00E+00 GIM+00 0.00E+ 00 0.00E+00 0.00E+00 Fe-59 5.87E46 1.37E45 5.29F 86 NO DATA NO DATA 4.32E46 3.24E45 ALL 0.0 0.00E+00 0.ME+00 0.00E+00 036+00 0.00E+00 0.00E+00 0.00E+M Cc.60 NO DATA 2.8tF 86 6.33E46 NO DATA NO DATA NO DATA 3.66F 05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.IW+00 0.00E+00 0.00E+00 0.00E+00 Zm-65 5.76E46 2.00E45 9.33E46 NO DATA 1.28E45 NO DATA 8.47F 86 ALL 0.0 0.00E+00 0.00E+M 0.00E+00 GJM+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E49 4.56E49 2.51E49 NO DATA 4A2E49 NO DATA 1.95E45 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 SJ10E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12F 08 1.30E48 8.94E49 NO DATA 1.01E48 NO DATA 3.00E45 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 OJ10E+00 0.00E+00 0.00E+00 0.00E+00 1-131 5.85E46 8.19E46 4 AGE 46 2.39E43 1AIE45 NO DATA 1.62E46 ALL 4.0 0.00E+00 0.0(E+M 0.00E+00 0.90E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8J7E45 1.97E44 9.14E45 NO DATA 6.26E45 2.39E45 2ASE46 ALL 0.0 0.00E+ 00 0.00E+00 0.00E+00 0.t10E+49 0.00E+00 0.00E+00 0.00E+00 -
Cs-137 1.12E44 IA9E44 5.19E45 NO DATA 5.07E4' l.97E45 2.12E46 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 0.1M+00 0.00E+00 0.00E+00 0.00E+00 Bata-let 2.84F 05 3ASE48 1.83F-86 NO DATA 1.18E48 2.34E48 4.38E45 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
H-3 NO DATA 1.06E47 1.06E47 1.06E47 1.06E47 1.06E47 1.06E47 214 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totai Do.e E,.ie-.re.,y,>.
0.00E+00 0. E+00 0. E+00.40E.00 0.00E+00 0.00E+00 0,E+00 i
a 4
4-18 4
i
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese frean M'E Fathway for 1994 Data Usage (intake rate) =
400 Ilyr Mambauen Exposed Teen Teen Highest AmmuelMean Concentraties Ingestion Dese Facter (arvan per pCIimgested)
Indicator Mik Dese (unreum/yr)
Radnemmelide Bone Uver T. Body Hyroid Kidney Lung GI-LIJ I4caties (pCi/L)
Bene Uver T. Body n yroid Kidney Imag GI-IJJ f
Mm-54 NO DATA 5.90E46 1.17FA6 NO DATA 1.76E46 NO DATA 1.21FA5 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72FA7 2.24E46 NO DATA NO DATA NO DATA 1.34E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E46 1.37F 45 5.29E46 NO DATA NO DATA 432E46 3.24E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Code NO DATA 2.81E46 633E46 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zm-65 5.76E46 2.00FA5 933E46 NO DATA 1.28E45 NO DATA 8.47E46 ALL 0.M 0.00E+00 0.00E+00 0.00E&M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Nb.95 8.22E49 4.56E 09 2.51E-09 NO DATA 4.42E49 NO DATA 1.95E45 ALL 4.00 0.00E+00 0.00E+M 0.00E F00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12FA8 1.30E48 8.94E.49 NO DATA
- 1. ole 4R NO DATA 3.00E45 ALL 4.00 0.00E+M 4.NE+M 0.00E+00 0.00E+00 0.00E+08 0.00E+00 0.00E+00 I-131 5.85E46 8.19E46 4.40E46 2.39E43 1.41E45 NO DATA 1.62E46 ALL 0.00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j
Cs.134 837E45 1.97E44 9.14E45 NO DATA 6.26E45 2.39E45 2.45E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+46 Cs-137 1.12E44 1.49E44 5.19E45 NO DATA 5.07E45 1.97E45 2.12E46 209 0.11 4.93E43 6.56E43 2.28E43 0.00E+00 2.23E43 8.67E44 933E45 Bata.140 2.84E45 3.48E48 1.83E46 NO DATA 1.18E48 2.34E48 438E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+48 I
Total Dese F mivalent (moreenfyr)=
4.93E43 6.56E43 2.28E43 0.OOE+00 2.23E43 8.67E44 9.33FAS 4
4-19
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dose from Broadleaf Vegetation Fathway for 1994 Data Usage (intake rate) =
42 (kglyr)
Maximan Exposed Teen i
Teen liisbest AmmaalMean Concentration Ingestion Dose Factor (arean per pCIingested) ladicator Food Dese (arentlyr)
Radionuclide Bone IJver T. Body nyroid kidney Imag GI-LIJ I4 cation (kglyr)
Bone ther T. Body H yroid Kidney 1.ams GI.LIJ Mn-54 NO DATA 5.90F 06 1.I?E46 NO DATA 1.76F 06 NO DATA 1.21E45 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E46 NO DATA NO DATA NO DATA 1.34E-05 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E46 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E46 3.24E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E46 6.33E46 NO DATA NO DATA NO DATA 3.66F-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 0.00E+00 Zn45 5.76E.06 2.00E-05 9.33E46 NO DATA 1.28F-05 NO DATA 8.47E 06 ALL 0.0 0.00E+00 0.00E +00 0.00E+ 00 0.00E+00 0.00E+00 0.00E + 00 0.00E+00 Nb-95 8.22E 09 4.56E.09 2.51E-09 NO DATA 4A2F89 NO DATA 1.95E45 ALL 4.0 0.00E+00 0.00E+00 0.00E+00 8.03E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E48 1.30E 08 8.94F49 NO DATA 1.0lF-08 NO DATA 3.00E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 5.85F-06 8.19E-06 4ADE46 2.39E43 1.41E45 NO DATA 1.62E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 $_00E+00 0.00E+00 0.00E+00 0.00E+ 84 Cs.134 S.37E45 1.97E-04 9.14E45 NO DATA 6.26E45 2.39E45 2ASE46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.137 1.12E 04 1.49E-04 5.19E45 NO DATA 5.07E45 1.97E45 2.12E46 226 30.9 IASE41 1.93E41 6.74E42 0.00E + 00 6.58E42 2.56E42 2.75E43 Bala-140 2.84E45 3A8E08 1.83E46 NO DATA 1.18FA8 2.34E48 4.38E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E t00 0.00E+00 0.00E+00 Total Dese Equivalent (aress/yr)=
1ASE41 1.93E41 6.74E42 0.liGE+08 6.58E42 2.56E42 2.75E43 4-20
.. ~. _.
. - - - ~ _ -. - - - - -. - - - -. - ~ _. -. _ ~ ~. ~.. -.... ~ _ ~. -.-..nx.-~~-.~.
TABLE 4-D h
PATHWAY DOSE ESTIMATES (CON'T)
I i
{
Dese from Mah Pathway for 1994 Data Usage (intake rate) =
16 (kStyr)
Maximum Exposed Teen TEEN Highest Ammuel Mean Concentration 1
Ingesties Dese Factor)
(urve per pCI Engested) 14=sar Msh Deee tareen/yr)
Chaide Bone ther T. Body nyroid Kadmey Imag GI-LIl locaties (pCs/kg)
Bene IJrer T. Body n yroid Kidney Imag Gl.LLI Me-54 NO DATA 5.90E46 1.17E46 hG OATA 1.76E46 NO DATA 1.21E45 208 5.73 0.00E+00 5.41E44 1.07E44 0.00E+00 1.61E48 0.00E+00 1.IIE43 l
Co-58 NO DATA 9.72E47 2.24E46 NO DATA NO DATA NO DATA 1.340 45 208 128.00 0.00E+00 1.99E43 4.59E43 0.00E+00 0.00E+49 0.00E+00 2.74E42 Fe-59 5.87E46 1.37E45 5.29E46 NO DATA NO DATA 4.32E46 3.24E45 ALL 6.00 0.00E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.40 NO DATA 2.81E46 6.33E46 NO DATA NO DATA NO DATA 3.66E45 208 34.90 0.00E+00 1.57E43 3.53E43 0.00E+00 0.00E+00 0.00E+et 2.04E42 Zm45 5.76E46 2.00E 45 9.33E46 NO DATA 1.28E45 NO DATA S.47F 86 ALL 0.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E49 4.56E49 2.51E49 NO DATA 4A2E49 NO DATA 1.95E45 ALL 6.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+90 0.00E+00 0.00E+00 I
Zr-95 4.12E48 1.30E48 8.94E49 P'O DATA 1.01E48 NO DATA 3.00E45 ALL 4.00 0.00E+00 0.00E+M G.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 I-131 5.85E46 8.19E46 4.40E46 2.39E43 1.4tE45 NO DATA 1.62E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+09 0.00E+00 0.00E+00 0.00E+00 Cs.134 8.37E45 1.97E44 9.14E45 NO DATA 6.26E45 2.39E45 2A5E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+06 0.00E+00 Cs-137 1.12E44 1A9E44 5.19E45 NO DATA 5.07E45 1.97E45 2.12E46 208 5.05 9.05E43 1.20E42 4.19E43 0.00E+00 4.10E43 1.59E43 1.71E44 Bala-140 2.84F 45 3ABE48 1.83E46 NO DATA 1.18E48 2.34E48 4.38E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Total Dese Equivalemt (erums/yr)=
9.05E43 1.61FA2 1.24E42 0.00E+00 4.26E43 1.59Er43 1.70E41 4
k i
t 4-21 i
4 i
t e
~
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese from Food Products Fathway (Crops) for 1994 Data i
Usage restake rate) =
630 (kglyr)
Maxiseum Exposed Teen l
Teen Highest A====I Meen Concentralien tagesties Dese Factor (ersum per pCIlagested)
Indicador Feed Deee (aremlyr)
Radionschde Bone Uver T. Body Thyroid Kidney Imag GI-IM I4caties (yCilwk )
Been Uver T. Body
'lleyroid Kidney Imag GI.IU t
Ma-54 NO DATA 5.90E-06 1.17E46 NO DATA 1.76E46 NO DATA 1.21FA5 ALL 4.0 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co 58 NO DATA 9.72E47 2.24E46 NO DATA NO DATA NO DATA 1.34E45 ALL 4.0 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe 59 5.87E46 1.37E45 5.29E46 NO DATA NO DATA 4J2E46 3J4E45 ALL 4.0 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 231E46 6.33E46 NO DATA NO DATA NO DATA 3.66E45 ALL 4.0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Za45 5.76E46 2.00E45 9.33E46 NO DATA 1.28E45 NO DATA 8.47E46 ALL 0.0 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 S.22E49 4.56E49 2.51E49 NO DATA 4.42E49 NO DATA 1.95E45 All 4.0 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+M - 0.00E+M Zr-95 4.12E48 1.30E.08 8.94E49 NODATA 1.0lE48 NO DATA 3.00E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 I.131 5.85E46 8.19E46 4.40FA6 2.39E43 1.41E45 NO DATA 1.62E46 ALL 0.0 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.134 S.37E45 1.97E44 9.14E45 NO DATA 6.26E45 2.39FA5 2.45FA6 ALL 4.0 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 1
Cs.137 1.12E44 1.49E44 5.19E45 NO DATA 5.07E45 1.97E45 2.12E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 0'S 0.00E+00 0.00E+00 i
BaLa.140 2.84E45 3.4BE48 1.83E46 NO DATA 1.18E48 2.34E48 4.3BE45 ALL 8.0 0.00E+M 4.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Total Dese Equivalent (aremnlyr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~
4-22
TABLE 4-D PATHWAY DOSE ESYlMATES l
(CON'T) f Dese funn th Air Radneiedimos for 1994 Data Maximmma Exposed Child Breathnag rate =
3700 m3lyr Highest Ammmet Mesa Cemeentration CHIID Inheamhna Done Facter (unrum per pCii.dualed)
Immester Air Deee (arems/yr) 1 a h sde Bene Unr T. Body M yroid Kinney lamas GI-Lil IAcatism (yCI/mE3)
Bene 13Yer T. Body Thyroid El&mey lamme GI-LIJ i
Ma-54 NO DATA 1.16E45 2.57E46 NO DATA 2.71E46 4.26E44 6.19E46 ALL 4.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Co 58 NO DATA 4.79E47 8.55E47 NO DATA NO DATA 2.99E44 9.29E46 ALL G.00E+00 8.00E+00 0.00E+M G.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Fe-59 5.59E46 9.04E46 4.51E46 NO DATA NO DATA 3A3E44 1.9tF 05 ALL 6.00E+00 0.00E+00 0.00E+M G.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.40 NO DATA 3.55E46 6.12E46 NO DATA NO DATA 1.91E43 2.60E45 ALL G.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zm45 1.15E45 3.06E45 1.90E45 NO DATA 1.93E45 2.69E44 4AIE46 ALL 6.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
)
Nb-95 6.35E46 2.48E46 1.77E46 NO DATA 2.33E46 1.66F,04 1.00E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j
Zr.95 5.13E45 1.13E45 1.00E45 NO DATA 1.6tE45 6.03E44 1.65E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 1-131 1.30E45 1.30E45 7.37E46 4.39E43 2.13E45 NO DATA 7.68F 47 ALL 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 1.76E44 2.74E44 6.07E45 NO DATA 8.93E45 3.27FA5 1.04E46 ALL 4.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.80E+00 0.00E+00 1
i Cs-137 2ASE44 2.23E44 3A7E45 NO DATA 7.63E45 2.81E45 9.7BE47 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-BaLa-140 2.00E45 1.75E4B 1.17E46 NO DATA 5.7tE49 4.71E44 2.75FA5 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
l Total Deee Equivalemt(eren/yr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4
I 4-23
TABLE 4-D PATHWAY DOSE ESTIMATES (CON T)
Dese fream.a.n~ Air Particulate Padaway for 1994 Data u
Mammme Exposed Child Breatlung rate =
3700 (m3/yr)
Highest AmamalMesa Cemeentraties ClllLD n=balah== Deee Facter (arem per pCIinhaled)
Indicator Air Done (mrum/yr)
Radiommelide Bone Uver T. Body nyndd Kubicy lang GI-LLI Locaties (pCl/m3)
Bene Uver T. Body D yroid Kidney Imag GI-Lil Mm-54 NO DATA 1.16E 05 2.57F 86 NO M ATA 2.71E.06 4.26E44 6.19FA6 ALL 0.00E+M 0.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+M 0.00E+M 0.00E+M Co-58 NO DATA 4.79E47 8.55E47 NO DATA NO DATA 2.99E44 9.29E46 ALL 0.00E+M 0.00E+M 0.00E+PG 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Fe-59 5.59E46 9.04E46 4.5tE46 NO DATA NO DATA 3.43E44 1.9t E45 ALL 0.00E+M 0.00E+00 0.00E+00 0.NE+00 0,00E+00 0.00E+M 0.00E+M 0.00E+M Ce40 NO DATA 3.55E46 6.12E46 NO DATA NO DATA 1.9tF 03 2.60E45 ALL 6.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Zm-65 1.15E45 3.06E45 1.90E45 NO DATA 1.93E45 2.69E44 4.4t E46 ALL 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb.95 6.35F 86 2.48E46 1.77E46 NO DATA 2.33E46 ~ 1.66F 84 1.00E45 ALL 4.00E+M 0.00E+M 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Zr.95 5.13E45 1.13E45 1.00E45 NO DATA 1.61E45 6.03E44 1.65E45 ALL 4.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+M j
1-131 1.30E45 1.30F 45 7J7E46 4.39E43 2.13F 05 NO DATA 7.68F 07 ALL 4.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+M Co.134 1.76F 84 2.74F 84 6.07E45 NO DATA 8.93E45 3.27F 05 1.04E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+M Cs.137 2.45E44 2.23E44 3.47E45 NO DATA 7.63E45 2.SIE45 9.78E47 ALL 0.00E+M 0.00E+M 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M Bata-140 2.00E45 1.75E48 1.17E46 NO DATA 5.71E49 4.71E44 2.75E45 ALL 6.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 Total Deee Eagmivalent (artma/yr) =
0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 4-24 i
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese frean Dremiums Water Pathwg for 1994 Data Usage Getake rate) =
Sit G/yr)
Mannemuse Exposed Child CHilm Highest Am==al Mesa Concentration Imgestion Deee factor (merema per pCIingested)
Indicator Water Dese (miremelyr)
Rashemmelide Bone ther T. Body Thyroid Kidney Lums GI.LLI I4 cation (pCi/I)
Bene Uver T. Body Thysipid Esdmey lamme GI-Lil Mm.54 NO DATA 1.07E45 2.85E46 NO DATA 3.00E46 NO DATA 8.98E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E46 5.51E46 NO DATA NO DATA NO DATA 1.05E 05 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+08 0.00E+00 0.00E+00 Fe-59 1.65E 05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E 06 2.78E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CD-60 NO DATA 5.29E-06 1.56E45 NO DATA NO DATA NO DATA 2.93E45 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+M 0.00E+00 0.00E+00 Zm-65 1.37E45 3.65E45 '2.27E45 NO DATA 2.30F 45 NO DATA 6.41E46 ALL 0.00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.25F 08 8.76F 89 6.26E49 NO DATA 8.23F 89 NO DATA 1.62E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E47 2.55E-08 2.27F 08 NO DATA 3.65E48 NO DATA 2.66E45 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1131 1.72E45 1.73E45 9.83E46 5.72E43 2.84E45 NO DATA 1.54E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+08 j
Cs.134 2.34E44 3.84E44 8.10E45 NO DATA 1.19E44 4.27E45 2.07E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 3.27E44 3.13E44 4.62E45 NO DATA 1.02E44 3.67E45 1.96E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Bala.140 8.31E45 7.28E48 4.85E46 NO DATA 2.37E48 4.34E.08 4.21E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H.3 NO DATA 2.03E47 2.03E47 2.03E47 2.03E47 2.03F-07 2.03E47 214 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
l Total Dese Egsivalemt(miress/yr) =
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
I 4-25 l
t
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dose froan Mik Pathway for 1994 Usage (intake rate) =
330.M Glyr)
Manimaan Exposed Child CHIIE Ihghest Ammuel Mean Concentration Ingestion Dese Factor (arens per pCiingested)
E=&casar Mik Dese (sareadyr)
Radionuclide Bone Uver T. Body Thyroid Kid:sey Lung GI-LLI 1Ataties (yC1/t)
Bene Uver T. Body Thyroid Keney Imag Gl.Lil Ma-54 NO DATA 1.07E45 2.85E46 NO DATA 3.0HW6 NO DATA 8.98FA6 ALL 0.00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 Co58 NO DATA 1.80E46 5.51E46 NO DATA NO DATA NO DATA 1.05F 05 ALL 4.00 0.00E+M 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 Fe.59 1.65E45 2.67E45 1.33FA5 NO DATA NO DATA 7.74F 86 2.78E45 ALL 0.M 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+M CO-60 NO DATA 5.29E46 1.56E45 NO DATA NO DATA NO DATA 2.93E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M Za45 1.37E45 3.65E45 2.27FA5 NO DATA 2.30E45 NO DATA 6.41E46 ALL 4.M 0.00E+M 0.00E+M 0.00E+M 0.00E+M 4.00E+M 0.00E+M 0.00E+M i
Nb-95 2.25E48 8.748',09 6.26E49 NO DATA 8.23E49 NO DATA 1.62E45 ALL 4.00 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 1.16E47 2.55E48 2.27E48 NO DATA 3.65E48 NO DATA 2.66E45 ALL 0.M 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+00 1 131 1.72E45 1.73F 05 9.83E46 5.72E43 2.84E45 NO DATA 1.54E46 ALL 4.M 0.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+M 4
Cs.134 2.34E44 3.84E44 8.10E45 NO DATA 1.19E44 4.2*E45 2.07E46 ALL 4.00 0.NE+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 3.27E44 3.13E44 4.62FA5 NO DATA 1.02E44 3.67E45 1.96E46 209 0.11 1.19E42 1.14E42 1.60E43 0.NE+00 3.70E43 1.33E43 7.11E45 BaLa.140 8.31E45 7.28E48 4.85E46 NO DATA 2J7E48 4.34E48 4.21E45 ALL 6.00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M j
Total Dese (aremelyr) =
1.19E42 1.14E42 1.60E43 0.00E+M 3.70E43 1.33E43 7.11E45 i
4-26
.m.-
m TABLE 4-D PATHWAY DOSE ESTIMATES' (CON'T) e Dese from Breasueef Vegetatsee Fathway for 1994 Data.
Usage waha rate) =
26 kglyr Mammmuun Empeeed Child.
r Ih hat AmmealMeanConcestraties CHIID t
Ingesties Dese Facter (arem per pCIimgested Imarator Food Does (unrem/yr)
Raabeauclide Bone IJver T. Body Thyroid Khiney Lang GI.Ill Incaties (pCilks)
Bone Liver T. Body Thyroid Kidney Imag GI-LIJ Me-54 NO DATA 1.07E45 2.85E46 NO DATA 3.00E46 NO DATA 8.98E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
Co-58 NO DATA 1.90E46 5.5tE46 NO DATA NO DATA NO DATA 1.05E.05 ALL 0.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.65E45 2.67FA5 1.33F 05 NO DATA NO DATA 7.74E46 2.78E45 ALL 6.M 0.00E+00 0.NE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M CD 60 NO DATA 5.29E46 1.56E45 NO DATA NO DATA NO DATA 2.93E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zm45 137E45 3.65F 05 2.27E45 NO DATA 2.30E45 NO DATA 6.41E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.25F 08 8.76E49 6.26E49 NO DATA 5.23FAO NO DATA 1.62E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 1.16E47 2.55FA8 2.27E48 NO DATA 3.65FA8 NO DATA 2.66E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.131 1.72E45 1.73E45 9.83E46 5.72FA3 2.84E45 NO DATA 1.54E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E44 3.84E44 8.10FAS NO DATA 1.19E44 4.27E45 2.07E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Cs-137 3.27E4 8 3.13E44 4.62E45 NO DATA 1.02E44 3.67FA5 1.96E46 226 30.90 2.63E41 ' 2.51E41 3.71E42 0.00E+00 8.19E42 2.95E42 1.57E43 BaLa-let SJ1E45 7.28E48 4.85fA6 NO DATA 2.37E48 4.34E48 4.21E45 AIL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Total Dese (aremelyr) =
2.63E41 2.51FA1 3.71E42 0.00E+00 8.19E42 2.95E42 1.57E43 4
i i
}
4-27 e
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dess freom Pish Pashway for 1994 Data Unnes doeste rese) -
6.9 ks/yr Maamanum Exposed ChBd CHIID Highest Ammeel Mesa Conrestration Imeesties Dese Forter (assess per pClingssted)
Irh Fish Dese Smream/yr)
RedemocEdo Beme IJver T. Body Dyroid Kidssy lang Q-1.11 Isarstine (pCl/kg)
Bene IJzer T. Body Hyroid Kidssy
.Imus G-LIJ Mn-54 NO DAT 1.e E 05 2.SSFA6 NODAT 3.00FA6 NODAT 3.9eFA6 208 5.73 0.0eE+0e 4.2E44 1.13FA4 S.8SE+00 1.19FA4 0.eeE+00 3.55IM4 Co-58 NO DAT 1.eeF,06 5.51E46 NO DAT NO DAT NO DAT t.05FA5 2e8 120.00 e. tee +08 1.59E43 4.8503 0.eeE+00 0.0eE+et e.seE+00 9.27F 03 Fe-59 1.65 Fee 5 2.67F,05 1.33F 45 NO DAT NO DAT 7.74FA6 2.7eFA5 AE 0.00 0.esE+00 8.esE+M 0.esE+et 0.eOE+00 0.esE+08 0. tee +00 e.esE+et C040 NO DAT 5.29F-86 1.56E45 NO DAT NO DAT NO DAT 2.93FAS 200 34.90 0.esE+00 1.27FA3 3.7EIMS 0.seE+et e.eE+et 0.eeE+00 7.9EFA3 Ze-65 1.3 E 45 3.65Fres 2.27E45 NO DAT 2.30EM5 NO DAT 6.4tFA6 AIL 6.e0 0. tee +00 0. tee +0e 4.00E+00 0.eOE+90 9.80E+et 9.eOE+00 0.00E+0e Nb-95 2.25E48 S.76E49 6.26FA9 NO DAT 3.23E49 NO DAT 1.62E45 AIL 9.00 0.00E+00 0.SeE+et 0.00E+00 0.SeE+et 9.seE+80 0.seE+00 0.seE+00 Ir.95 1.16F 47 2.55FA S 2.27E48 NO DAT 3.65FAO NO DAT 2.66 Fee 5 AIL 0.80 0.seE+et 8. tee +0e 0.eeE+00 0.etE+00 0.eeE+00 9.seE+80 0.eOE+00 I-131 t.72E45 1.73E45 9.83E46 5.72E43 2.84FAS NODAT 3.54E46 AIL 6.00 0.seE+00 0.eeE+00 9.eOE+00 0.00E+00 0.08E+00 0.eeE+00 0.eeE+00 Co-134 2.34E44 3.e4EM4 S.teF 05 NODAT 1.19EM4 4.27E45 2.07FA6 All 0.00 0.esE+ es 0.0eE+00 0.00E+00 0.seE+00 0.00E+00 0.90E+00 e.seE+00 Co-137 3.27EM4 3.13FA4 4.62E45 NO DAT 1.82E44 3.67E45 1.96EM6 205 5.05 I.14EM2 1.99F 82 1.6tFA3 0.00E+00 3.55FAS 1.2eIMS 6.R3IMS BeLe-140 S.3tE45 7.20E45 4.85EM6 NODAT 2.37 Free 4.34F 48 4.2tFAS AIL 6.00 9.88E+00 0.8eE+00 C.seE+00 0.8eE+00 0.eE+et 0.esE+et 0.00E+00 l
Total Dese (amem/yr) =
1.tWret 1.42E-02 1.83E42 0. tee +es 3.67E45 1.2eIW3 1.dOIM2 i
f 4-28 i
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Dese frean Food Fathway (Crops) for 1994 Data Usage (intake rate) =
520 katyr Maximenen Exposed Child CHII.D Highest Ammual Mean Concentraties lagestion Dese Facter (anan per pCIingemeed) thaer Feed Deee queremnlyr)
Radsommelide Bene liver T. Body Thyroid Kidney Imag GI-l U IAcatIem (pCI/kg)
Bene Uter T. Body Thyroid Khey Imag GI.IR Mm-54 NO DATA 1.07FA5 2.85E-06 NO DATA 3.00E46 NO DATA 8.98FA6 AE 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E46 NO DATA NO DATA NO DATA 1.0$FAS AE 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 Fe-59 1.65E 05 2.67FA5 1.33E45 NO DATA NO DATA 7.74E46 2.78FA5 AE 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-60 NO DATA 5.29E 06 1.56FA5 NO DATA NO DATA NO DATA 2.93FAS AE 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Za-65 1.37E45 3.65E 05 2.27FA5 NO DATA 2.30E45 NO DATA 6.4tE46 AE 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 4
Nb-95 2.25E 08 8.76E49 6.26E49 NO DATA 8.23E49 NO DATA 1.62E45 AE 0.00 0.000+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 1.16E47 2.55F,08 2.27E48 NO DATA 3.65E48 NO DATA 2.66E45 AE 0.00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 1.72FA5 1.73E45 9.83E46 5.72E43 2.84E45 NO DATA 1.54E46 AE 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E44 3.84FA4 8.10E45 NO DATA 1.19E44 4.27E45 2.07E46 AE 0.00 0.00E+00 0.00E+00 0.00E+49 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 3.27E44 3.13E44 4.62E45 NO DATA 1.02E44 3.67E45 1.96E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 a
Bala-let 8.31E45 7.2SE48 4.95E46 NO DATA 2J7E48 4.34E48 4.2EE45 AE 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
l Total Dese * 'C(meresslyr)=
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
4-29
]
1 i
T
\\
TABLE 4-D PATHWAY DOSE ESTIMATES l
i (CON'T) l l
l i.
Dese from Air Radionedme I4alah== Faekway for 1994 Data Manianuma Exposed Infant Breedens rate =
1400 m3/yr Ibsheet A-at Mesa Cemeestratten INFANT Iaalaham Dese Facter (menen per pCIimbaled)
Air Dese (unremnlyr)
Radionuclide Beme Uver T. Body Thyroid Kidney Lung GI-LIJ IAcaties (yCi/m3)
Bone Uver T. Body Thyreid Kidney Img GI-Lil Me-54 NO DATA 1.81E45 3.56E46 NO DATA 3.56E46 7.14E44 5.04E46 ALL 4.00 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 Co-58 NO DATA 8.71E47 1.30E46 NO DATA NO DATA 5.55E44 7.95E46 ALL 4.00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Fe-59 9.69E-06 1.68E45 6.77E46 NO DATA NO DATA 7.25E44 1.77E45 ALL 6.M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 Co40 NO DATA 5.73E46 8.4tE46 NO DATA NO DATA 3.22E43 2.2SE45 ALL 0.00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Za45 1.38E45 4A7E45 2.22E45 NO DATA 2.32E45 4.62E44 3.67E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 h
Nb-95 1.12E45 4.59E46 2.70E46 NO DATA 3.37E46 3.42E44 9.05E46 ALL 6.00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 8.24E45 1.99E45 1.45E45 NO DATA 2.22E45 1.25E43 1.55E45 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I.131 2.71E45 3.17E45 1.40E45 1.06E42 3.70E45 NO DATA 7.56E47 ALL 4.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 Cs.134 2.83E44 5.02E44 5.32E45 NO DATA 1.36E44 5.69E45 9.53E 07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.137 3.92E44 4.37E44 3.25E45 NO DATA 1.23E44 5.09E45 9.53E47 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BnLa-140 4.00E45 4.00E40 2.07E46 NO DATA 9.59E49 1.14E43 2.74E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Total Dese Equivalent (arem/yr) =
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 i
5 4
4-30 4
._.. _ _..~..
- - ~.- ~.-
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
Deee froma Air Partnemiste Ih Pathway for 1994 Data Mashamma Esposed Infant BrW rate =
idet m3/yr Highest Amamal Mesa Cemeentration 1NFANT Imbdahen Does Factor (msresa per pClinhaled) led) hd
- Air Does (marselyr)
RadionucEde Bone Liver T. Body nyreid Kadney Lung GI.tJJ 1mcataea (pCi/ma'3)
Bene IJver.
T. Body Thyroid Kidney Imag GI-LIJ Mn-54 NO DATA 1.81E45 3.56E46 NO DATA 3.56E46 7.14F 84 5.04E46 ALL 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0 00E+00 0.00E+M 0.00E+00 0.00E+00 Co-58 NO DATA 8.71E47 1.30E46 NO DATA NO DATA 5.55E44 7.95E46 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+M 0.00E+00 i
Fe.59 9.69E46 1.68E45 6.77E46 NO DAT NO DATA 7.2SE44 1.77E45 ALL 6.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 5.73E46 SAIE46 NO DATA NO DATA 3J2E43 2.28E45 ALL 6.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zm-65 1.38E45 4A7E45 2.22E45 NO DATA 232E45 4.62E44 3.67E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.12E 05 4.59E.P" 2.70E46 NO DATA 3.37E-06 3.42E44 9.05E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Zr-95 8.24E45 1.99E45 1.45E45 NO DATA 2.22E45 1.25E43 1.55E45 ALL 4.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 131 2.71E45 3.17E45 1.40E45 1.06E42 3.70E45 NO DATA 7.56E47 ALL 4.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs.134 2.83E44 - 5.42E44 SJ2E45 NO DATA 1.36E44 5.69E45 9.53E47 ALL G.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.137 3.92E44 4.37E44 3.25E45 NO DATA 1.23E44 5.09E45 9.53E47 ALL 0.00E+00 0.00E +00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bata-140 4.00E45 - 4.00E48. 2.07E46 NO DATA 9.59E49 1.14E43 2.74E45 ALL 4.00E+0'S 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dese Equivalent (unremelyr)=
0.00E+49 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4-31
{
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) i l
l Dese frein Drimiums Water Pathway for 1994 Data Manismuse Exposed Infant Usese (intake rate) =
334 Ilyr Highest AmmmalMesa Concentration INFANT 1mgestion Deee Facter (meena per pC1ingeseed) 3=aw Water Dese lamramilyr)
RadisencEde Beme Uver T. Body Thyroid Knimey Imag GI.LIJ Imcaties (pCl/L)
Bone Uver T. Body Thyroid Kidney Long GI-LIJ t
Ma-54 NO DATA 1.99FA5 4.51E46 NO DATA 4.41E46 NO DATA 7J1E46 ALL 6.M 0.00E+M 0.00E+M 4.00E+M 0.00E+00 0.00E+00 0.00E+M 0.00E+M Co-58 NO DATA 3.60E46 8.98E46 NO DATA NO DATA NO DATA 8.97E46 ALL 0.M 0.00E+M 0.00E+00. 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+00 le-59 3.08FA5 5.38E45 2.12E45 NO DATA NO DATA 1.59E45 2.57E45 ALL 6.M 4.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co4e NO DATA 1.08E45 2.55E45 NO DATA NO DATA NO DATA 2.57FA5 ALL 0.00. 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M Zm45 1.84E45 6.31FAS 2.91E45 NO DATA 3.06E45 NO DATA 5.33E45 ALL 0.00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0'avF e00 14 95 4.20E48 1.73FA8 1.00FA8 NO DATA 1.24E48 NO DATA 1.46E45 ALL 0.90 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+M 0.00E+M 0.00E+00 Zr.95 2.06E47 5.02E48 3.56E45 NO DATA 5.4tFA8 NO DATA 2.50E45 ALL 6.00 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1131 3.59E45 ' 4.23E45 1.96E45 1.39E42 4.94FA5 NO DATA 1.5tFA6 ALL 4.00 0.00E+00 0.00E+M 0.00E+M 0.00E+M 0.00E+00 0.00E+00 0.00E+M Cs-134 3.77FA4 7.03E44 7.10E45 NO DATA 1.81E44 7.42E45 1.9tFA6 ALL 4.00 0.00E+00 0.00E+M 0.00E+M 0.00E+00 0.00E+M 0.00E+00 0.00E+00 Cs-137 5.22FA4 6.11E44 4.33E45 NO DATA 1.64E44 6.64E45 1.91E46 ALL 0.00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Balo 140 1.71E44 1.7tE47 8.81E46 NO DATA 4.06E48 1.0$E47 4.20E45 ALL 6.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 H.3 NO DATA 3.08E47 3.00E47 3.00E47 3.00FA7 3.00E47 3.00FA7 214 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dese Equivalent (unremelyr) =
0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+00 0.00E+M 4-32
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T) l l
Dese from Mik Pathwg for 1994 Data Maxemimm Exposed Infad Usage (intake rate) =
330 11yr Highest Ammeal Mean Caecentreties INFANT Intestsee Dese Facter (asrums per pCIingested)
Indicator Mik Dese Quareum/yr)
Raabeauclide Bone IJeer T. Body n yroid Kadmey Imag GI-L1J Iacation (pCil1J Bone IJver T. Bedy Thyroid Kidney Imag Cl-111 Me-54 NO DATA 1.99E 05 4.51E46 NO DATA 4AIE46 NO DATA 7.31E46 ALL 4.00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+M 0.00E+48 4 AGE +M Co-58 NO DATA 3.60E46 8.98E' 06 NO DATA NO DATA NO DATA 8.97E46 ALL 4.00 0.00E+00 0.00E+M 0.00E+00 0.00E+00 SAGE +00 SAGE +00 0.00E+00 Fe-59 3.08E45 5.38E45 2.12E45 NO DATA NO DATA 1.59E45 2.57E45 ALL 0.00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 Co.60 NO DATA 1.08E45 2.55E45 NO DATA NO DATA NO DATA 2.57E45 ALL 4.00 0.00E+00 0.00E+00 0.002+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zm45 1.84E45 6.3tF 45 2.91E45 NO DATA 3.06E45 NO DATA 5.33E45 ALL 0.00 0.00E+00 0.00E+ 00 0.00E+ 00 SAGE +00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.20E48 1.73E48 1.00E48 NO DATA ' 1.24E48 NO DATA 1A6E45 ALL G.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr.95 2.06E47 5.02E48 3.56E48 NO DATA 5AIE4B NO DATA 2.50E45 ALL O.00 0.00E+ 00 0.00E+08 GAGE +00 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00 1
i 1-131 3.59F 45 4.23F 45 1.96E45 1.39E42 4.94E45 NO DATA 1.51E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 Cs-134 3.77E44 7.03E44 7.10E45 NO DATA 1AIE44 7A2E45 1.91E46 ALL 4
10E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+48 0.00E+00 0.00E+ 00 Cs.137 5.22E44 6.11E44 4.33E45 NO DATA 1.64E44 6.64E45 1.91E46 209 0.11 1A9E42 2.22E42 1.57E43 0.00E+00 5.95E43 2A1E43 6.93E45 i
f BaLa-140 1.71E44 1.71E47 SA1E46 NO DATA 4.06E4B 1.05E47 4.20E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Deee Equivalent (unres/yr) =
1A9E42 2.22E42 1.57E43 0.00E+00 5.95E43 2A1E43 6.93E45 i
l
}
L 4-33
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
CNS REMP SHORELINE RECREATION PATHWAY DOSE CALCULATION SPREADSHEET (Regulator-Guide 1.109 Methodology) i PERIOD:
1994 LOCATION:
208-1S (CNS Discharge Canal) 0.2
= W = Shore-Width Factor (River Shore) 40.0 kg/ square meter = M = Mass Factor Dose Rate (mrem / hour) - W x M x EDF x Concentration SHORELINE EXTERNAL DC,$E FACTOR SEDIMENT (mrem / hour per pCi/m2)
NUCLIDE Dose Rate CONCENTRATION (mrem /hr)
NUCLIDE T-Body Skin (pCi/ dry kg)
T-Body Skin Na-24 2.50E-08 2.90E-08 0.00 0.00E+00 0.00E+00 Cr-51 2.20E-10 2.60E-10 0.00 0.00E+00 0.00E+00 Mn-54 5.80E-09 6.80E-09 62.50 2.90E-06 3.40E-06 Co-58 7.00E-09 8.20E-09 1212.00 6.79E-05 7.95E-05 Fe-59 8.00E-09 9.40E-09 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 752.00 1.02E-04 1.20E-04 Zn-65 4.00E-09 4.60E-09 0.00 0.00E+00 0.00E+00 Nb-95 5.10E-09 6.00E-09 0.00 0.00E+00 0.00E+00 Zr-95 5.00E-09 5.80E-09 0.00 0.00E+00 0.00E+00 I-131 2.80E-09 3.40E-09 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 6.75 6.4dE-07 7.56E-07 Cs-137 4.20E-09 4.90E-09 145.00 4.87E-06 5.68E 06 Ba-140 2.10E-09 2.40E-09 0.00 0.00E+00 0.00E+00 La-140 1.50E-08 1.70E-08 0.00 0.00E+00 0.00E+00 Ru-103 3.60E-09 4.20E-09 0.00 0.00E+00 0.00E+00 Nuclides not listed in Regulatory Guide 1.109 (EDFs Taken or Derived from data in Appendix C of NUREG/CR-1276) :
I Co-57 T
9.10E-10 1.00E-09 4.00 2.91E-08 3.20E-08 Sn-113 D
1.90E-09 2.20E-09 0.00 0.00E+00 0.00E+00 Sb-122 D
3.00E-09 3.50E-09 0.00 0.00E+00 0.00E+00 Sb-125 T
3.10E-09 3.50E-09 157.00 3.89E-06 4.40E-06 TOTAL 2339.25 1.82E-04 2.14E-04 SHORELINE DOSE RATE RECREATION (mrem /yr)
AGE GROUP (hours / year)
T-Body Skin Adult 12.0 2.19E-03 2.57E-03 Teen 67.0 1.22E-02 1.43E-02 Child 14.0 2.55E-03 3.00E-03 Infant s.0 0.00E+00 0.00E+00 4-34
TABLE 4-D PATHWAY DOSE ESTIMATES (CON'T)
CO REMP - SHORELINE RECREATION PATHWAY DOSE CALCUIATION SPREADSHEET (Regulatory Guide 1.109 Methodology)
PERIOD: 1994 IOCATZON:
208-2S (CNS Discharge Canal) 0.2
= W = Shore-Width Factor (River Shore) 40.0 kg/ square meter = M = 14 ass Factor Dose Rate (mrem / hour) = W x M x EDF x Concentration SHORELINE EXTERNAL DOSE FACTOR SEDIMENT (arem/ hour per pCi/m2)
NUCLIDE Dose Rate CONCEFFRATION (arem/hr)
NUCLIDE T-Body Skin (pC1/ dry kg)
T-Body Skin Na-24 2.50E-08 2.90E-08 0.00 0.00E+00 0.00E+00 Cr-51 2.20E-10 2.60E-10 0.00 0.00E+00 0.00E+00 1
Mn 54 5.80E-b9 6.80E-09 77.00 3.57E-06 4.19E-06 Co-58 7.00E-09 8.20E-09 575.00 3.22E-05 3.77E-05 Fe-59 8.00E-09 9.40E-09 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 649.00 8.83E-05 1.045-04 Zn-65 4.00E-09 4.60E-09 0.00 0.00E+00 0.00E+00 Mb-95 5.10E-09 6.00E-09 0.00 0.00E+00 0.00E+00 Zr-95 5.00E-09 5.80E-09 0.00 0.00E+00 0.00E+00 I-131 2.80E-09 3.40E-09 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 10.20 9.79E-07 1.143-06 Cs-137 4.20E-09 4.90E-09 100.00 3.36E-06 3.92E-06 Ba-140 2.10E-09 2.40E-09 0.00 0.00E+00 0.00E+00 La-140 1.50E-08 1.70E-08 0.00 0.00E+00 0.00E+00 Ru-103 3.60E-09 4..20E-09 0.00 0.00E+00 0.00E+00 j
Nuclides not listed in Regulatoly Guide 1.109 (EDFs Taken or Derived from dat x in Appendix C of NUREG/CR-1276) :
Co-57 T
9.10E-10 1.00E-09 0.00 0.00E+00 0.00E+00 Sn-113 D
1.90E-09 2.20E-09 0.00 0.00E+00 0.00E+00 Sb-122 D
3.00E-09 3.50E-09 0.00 0.00E+00 0.00E+00 Sb-125 T
3.10E-09 3.50E-09 175.00 4.34E-06 4.90E-06 M AL 1586.20 1.33E-04 1.56E-04 SHORELINE DOSE RATE RECREATION (arem/yr)
AGE GROUP (hours / year)
T-Body Skin Adult 12.0 1.59E-03 1.87E-03 Teen 67.0 8.89E-03 1.04E-02 Child 14.0 1.86E-03 2.18E-03 Infant 0.0 0.00E+00 0.00E+00 4-35
l TABLE 4-D
]
PATHWAY DOSE ESTIMATES (CON'T)
CNS REMP - SHORELINE RECREATION PATHWAY DOSE CALCUIATION SPREADSHEET (Regulatory Guide 1.109 Methodology) t i
PERIOD: 1994 LOCATION: 208-3S (CNS Discharge Canal) t l
0.2 = W = Shore-Width Factor (River Shore) 40.0 kg/ square meter = M = Mass Factor Dose Rate (arem/ hour) - W x M x EDF x Concentration SHORELINE l
EXTERNAL DOSE FACTOR SEDIMENT (arem/ hour per pCi/m2)
NUCLIDE Dose Rate i
CONCENTRATION (arem/hr)
NUCLIDE T-Body Skin (pCi/ dry kg)
T-Body Skin Na-24 2.50E-08 2.90E-08 0.00 0.00E+00 0.00E+00 1
Cr-51 2.20E-10 2.60E-10 0.00 0.00E+00 0.00E+00 Mn-54 5.80E-09 6.80E-09 27.70 1.29E-06 1.51E-06 Co-58 7.00E-09 8.20E-09 607.00 3.40E-05 3.98E-05 Fe-59 8.00E-09 9.40E-09 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 319.00 4.34E-05 5.10E-05 Zn-65 4.00E-09 4.60E-09 0.00 0.00E+00 0. t'0E+ 00 Nb-95 5.10E-09 6.00E-09 0.00 0.00E+00 0.0tE+00 Zr-95 5.00E-09 5.80E-09 0.00 0.00E+00 0.00E+00 I-131 2.80E-09 3.40E-09 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 76.50 2.57E-06 3.00E-06 Ba-140 2.10E-09 2.40E-09 0.00 0.00E+00 0.00E+00 La-140 1.50E-08 1.70E-08 0.00 0.00E+00 0.00E+00 Ru-103 3.60E-09 4.20E-09 0.00 0.00E+00 0.00E+00 Nuclides not listed in Regulatory Guide 1.109 (EDFs Taken or Derived from data in Appendix C of NUREG/CR-1276) :
i Co-57 T
9.10E-10 1.00E-09 4.75 3.46E-08 3.80E-08 Sn-113 D
1.90E-09 2.20E-09 0.00 0.00E+00 0.00E+00 Sb-122 D
3.00E-09 3.50E-09 0.00 0.00E+00 0.00E+00 Sb-125 T
3.10E-09 3.50E-09 128.00 3.17E-06 3.58E-06 TorAL 1162.95 8.44E-05 9.90E-05 SHORELINE DOSE RATE RECREATION (arem/yr)
AGE GROUP (hours / year)
T-Body Skin I
l Adult 12.0 1.01E-03 1.19E-03 l
Teen 67.0 5.66E-03 6.63E-03 l
Child 14.0 1.18E-03 1.39E-03 l
Infant 0.0 0.00E+00 0.00E+00 4-36
SECTION 5 QUALITY ASSURANCE 5.1 DUKE POWER COMPANY'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1.1 SAMPLE COLLECTION i
Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.
i 5.1.2 SAMPLE ANALYSIS Radiological and Environmental Services performed the environmental sample analyses as specified by approved analysis procedures, j
5.1.3 DOSIMETRY ANALYSIS Radiation Dosimetry and Records performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.
5.1.4 INTRALABORATORY QUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type 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. Additionally, National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Ini cigations are performed and documented should calibration verification data fall out of limits.
5.1.5 INTERLABORATORY QUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISION j
No audits were performed by Quality Verification in 1994. Following the 1993 audit, it was announced by Quality Ve.rification that audits by them would be performed biannually.
5-1
5.1.5.2 DUKE ' POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM Radiological and Environmental Services participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1994.
Interlaboratory cross-check standards, including marinelli beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program.
5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS Radiological and Environmental Services was not audited by the NRC in 1994.
5.1.5.4
~
UNITED STATES ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM The Radiological and Environmental Services Group participated in the Environmental Protection Agency (EPA) Environmental Monitoring Systems Laboratory Intercomparison Program. The EPA sample types included mixed gamma in. water, mixed gamma in milk, gamma in air filters, iodine in milk, tritium in watcr, iodine in water, gross beta in air filters and gross beta in water. ' Radiological and Environmental Services EPA Intercomparison Report code is "CP".
A summary of the EPA Intercomparison Reports for 1994 is documented in Table 5-A.
5.1.5.5 NRC/ STATE OF S.C. ENVIRONMENTAL MONITORING PROGRAM The ONS Chemistry Section and Radiological and Environmental Services routinely participate with the State of South Carolina in their NRC/ State Contract Environmental Monitoring Program.
The Laboratory splits water, milk, vegetation, sediment, and fish samples with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) for analysis.
DHEC collects air samples from two of the locations sampled for air by CNS. Results of the analyses performed on split and duplicate samples by the Radiological and Environmental Services Group and DHEC Laboratory are compiled by DHEC and provided to the NRC.
TLDs are also co-located with the State and NRC at various environmental sites.
5-2
5.1.5.6 NRC/ STATE OF N.C. INTERCOMPARISON PROGRAM Radiological and Environmental Services, and the Radiation Dosimetry and Records group routinely participate with the State of North Carolina Deprtment of Environmental Health and Natural Resources (DEHNR) in an intercomparison program.
Radiological and Environmentan Services sends air, water, milk, vegetation, sediment, and fish samp!es which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis.
TLDs are also co-located with the State and NRC at various environmental sites. Also, every six to eight months, the State of North Carolina Radiation Protection Section irradiates environmental 2
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 1994 is documented in Table 5-B.
5.1.5.7 U.S. DEPARTMENT OF ENERGY INTERCOMPARISON PROGRAM There was no DOE intercomparison program during calendar year 1994.
5.2 CONTRACTOR LABORATORY l
No contractor laboratories were used during 1994.
1 p
i 5-3
TABLE 5-A (Page 1 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1994 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY C7LLECT10N CONTROL LIMITS ANALYSIS TATE NUCLIDE(S)
KNOWN VALUE (3 SIGMA; N=3)
REPORTED VALUE Gamma in Water 04/19/94 Co-60 20.0 pCill 11.3 - 28.7 pCi/l 20.33 pCi/I Cs-134 34.0 pCill 25.3 - 42.7 pCIA 32.33 pCl/l Cs-137 29.0 pCin 20.3 - 37.7 pCid 24.33 pCill
^
ge^
sp;sa >
^
- ?bt ;V:
> f@s ~
fN g;y gp ;gg g
gp j3];jhw i 'QiggPt 6/10/94 Ba-133 98.0 pCIA 80.7 - 115.3 pCill 91.33 pCin Co-60 50.0 pCIA 41.3 - 58.7 pCin 52.0 m.ill e
Zn-65 134.0 pCin 111.4 - 156.6 pCill 144.0 pCi/I Ru-106 252.0 pCill 208.6 - 295.4 pCi/l 235.0 pCIA Cs-134 40.0 pCIA 31.3 - 48.7 pCill 36.67 pCi/I Cs-137 49.0 pCill 40.3 - 57.7 pCi/I 49.67 pCid
% ~
EII^ f YN H 4
2EE ' 'I
[*.
j Ei '
^;
UNN
^
4294!
W g;
m WW
^
s 10/18/94 Co-60 40.0 pCi/I 31.3 - 48.7 pCid 40.33 pCin Cs-134 20.0 pCi/I 11.3 - 28.7 pCill 18.00 pCIA Cs-137 39.0 pCill 30.3 - 47.7 pCill 40.0 pCid i
5-4
TABLE 5-A (Page 2 cf 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1994 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY CONTROL LIMITS COLLECTION ANALYSIS DATE NUCLIDE(S)
KNOWtl VALUE (3 SIGMA; N=3)
REPORTED VALUE Gamma in Water 11/04/94 Co-60 59.0 pCill 50.3 - 67.7 pCIA 60.67 pCi/l Zn-65 100.0 pCill 82.7 - 117.3 pCill 106.o pCill Cs-134 24.0 pCill 15.3 - 32.7 pCill 23.33 pCl/l Cs-137 49.0 pCIA 40.3 - 57.7 pCIA 50.67 pCill Ba-133 73.0 pCi/I 60.9 - 85.1 pCill 73.33 pCill
$kkkk$hMhkkkkkkh kkhkk
!k k hk hh[
!bbk b
h k b
kkkhE@)hbN lodine in Water 02/04/94 1-131 119.0 pCl/l 98.2 - 139.8 pCill 123.33 pCill Adhhhhfb hkhb Ik bN f
'ki 10/07/94 l-131 79.0 pCl/l 65.1 - 92.9 pCill 78.33 pCIA
$$fb k
Mkr khkikhk$Nhk I
N YN hhd Air Filter 08/26/94 Cs-137 15.0 pCill 6.3 - 23.7 pCi/I 17.67 pCIA Gross Beta 56.0 pCill 38.7 - 73.3 pCIA 58.0 pCill fhbh [$k Ik b
hkNEhk M
Nhhhfb h k h N [h hh
$hkk
!)iNhh}ihfkkhsh Tritium in Water 03/04/94 H-3 4936.0 pCill 4078.9 - 5793.1 pCill 4644.0 pCl/l 1
08/05/94 H-3 9951.0 pCill 8224.7 - 11,677.3 pCill 10,014.0 pCIA 1
i 5-5 j
TABLE 5-A (P;ga 3 cf 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1994 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY COLLECTION CONTROL LIMITS ANALYSIS DATE NUCLIDE(S)
KNOWN VALUE (3 SIGMA; N=3)
REPORTED VALUE Gamma in Milk 9/30/94 l-131 75.0 pCi/I 61.1 - 88.9 pCill 76.33 pCill Cs-137 59.0 pCill 50.3 - 67.7 pCill 60.0 pCl/l y;<. xas M"e - sp!q :43 _ g;w;
,4 4%e.-~.-
jjg
. 3;gg
,e L
x s,
....pg{f
.m
,~
p='
s:s
.,s
~-
qgy
- ~
's g~;g m:
s Beta in Water 1/28/94 Gross Beta 62.0 pCi/1 44.7 - 79.3 pCill 76.0 pCi/l NYkin
['
4Mi si@!! EE pq SII y!
{ NN Q 9s!!! (glhh ' 'Y Nhgg < snsygg[ $$d%gfNkk'~^ $39;; f~ Mi@}Iklh@
7/22/94 Gross Beta 10.0 pCill 1.3 - 18.7 pCill 17.0 pCill gjNW, _ jn#7sylMj!g g ;. ' ;g. g,; ~
.fgjj pg ygg j$$g gif,giiggg;g_ g!;}seggE f.fg ;
J y
^N M
_gg; 10/18/94 Gross Beta 142.0 pCill 105.6 - 178.4 pCill 126.33 pCill
- pphr s 'gg, '-
~
4
' ' k 'qE ME MS@HE isE f5
- l3[O t
' ',(. h [%f,
$ gg(g k M ~ ';'.
~
~ +
S 10/28/94 Gross Beta 23.0 pCi/l 14.3 - 31.7 pCill 29.0 pCill 5-6
TABLE 5-B STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES ENVIRONMENTAL DOSIMETER CROSS-CHECK - 1994 STATE OF N.C.
RD&R ESTIMATED ESTIMATED VALUE VALUE Date of Exposure Exposure Estimated Uncertainty Cross-check (mR)
(mR)
(1S.D. mR)
Jun - 94 50 47.45 i O.59 Nov - 94 70 65.75 0.71 5-7
I SECTION 6 REFERENCES 6.1 Catawba Nuclear Station Units 1 and 2 Technical Specifications.
6,2 Duke Power Company Offsite Dose Calculation Manual.
6.3 Catawba Nuclear Station Final Safety Analysis Report.
6.4 Title 10, Code of Federal Regulations.
6.5 Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, Revision 1, October 1977.
6.6 NUREG/CR-1276, User's Manual for LADTAP ll - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents, May 1980.
6.7 Kocher, D.C., Radioactive Decay Data Tables,1981.
6.8 Catawba Nuclear Station Annual Radiological Environmental Operating Reports,1985 -
1993.
6.9 Catawba Nuclear Station Annual Radioactive Effluent Release Reports, 1985-1993.
6-1
1994 CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDlX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media 4
at Catawba was required to ensure compliance with Station Selected Licensee Commitments (SLC's). Analytical procedures were employed to ensure that Technical Specification detection capabilities were achieved.
Environmental sampling and analyses were performed by Duke Power Radiological and Environmental Services, Radiation Dosimetry and Records, Fisheries, and Aquatic Ecology.
l.
_ CHANGE OF SAMPLING PROCEDUREJ No sampling changes were made to the sampling procedures during 1994.
11.
CHANGE OF ANALYSIS PROCEDURES i
I A new procedure was added in 1994 covering the operation of the Packard 2550
)
Liquid Scintillation system.
On January 1,1994 a new TLD system was placed in service at Duke Power Company's Corporate Office. The Harshaw 8807 replaced the Teledyne PB2 system due to age. The new Harshaw system provides better reliability and stability. A colocation study was performed at Oconee Nuclear Station to compare 2
the performance of the two systems. The data showed that the Harshaw results j
were generally higher, however, good statistical agreement existed between the two systems.
111.
SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE RADIOIODINES AND PARTICULATES l
Airborne particulate and radiciodine samples at each of five locations were composited continuously by means of continuous air samplers. Airborne particulates were collected on a particulate filter and radioiodines were I
collected in a charcoal cartridge situated behind the filter in the sampler.
1 Filters and cartridges were collected weekly. A gamma analysis and gross
)
beta analysis were performed on each filter, and a gamma analysis was performed on each charcoal cartridge.
A.2 GROUND WATER Ground water grab samples were collected quarterly from residential wells at two locations. A gamma analysis, low-level 1-131 analysis, and tritium analysis were performed on each sample.
APPENDIX A - 1 i
e
l l
A.3 DRINKING WATER Drinking water composite samples were collected biweekly from each of two Drinking Water Treatment Plants.
Low-level 1-131 analysis was performed on each biweekly sample.
Each biweekly sample was composited to form a monthly composite for each location, and a gamma analysis and gross beta analysis were performed on each monthly composite.
Biweekly samples were composited quarterly for tritium analysis.
A.4 SURFACE WATER Surface water composite samples were collected biweekly from each of three locations. A low-level 1-131 analysis was performed on each biweekly sample. Two biweekly samples were composited to form a monthly l
composite for each location, and a gamma analysis was performed on each monthly composite.
Biweekly samples were composited quarterly for tritium analysis.
A.5 Ml_LK I
Milk grab samples were collected biweekly from three dairies. A low-level 1-131 analysis and a gamma analysis were performed on each sample.
A.6 BROADLEAF VEGETATION Broadleaf vegetation samples were collected monthly from each of four locations. A gamma analysis was performed on each sample.
1 A.7 SHORELINE SEDIMENT Shoreline sediment samples were collected semiannually from three locations. A gamma analysis was performed on each sample after drying and removal of rocks and clams.
A.8 EISH Three types of fish samples were collected semiannually from each of two locations. The types of fish collected represented predatory fish, foraging fish, and bottom feeding fish. A gamma analysis was performed on the edible portions of each sample. Boney fish, such as sunfish, are prepared whole minus the head and tail.
APPENDIX A - 2
A.9 DIRECT GAMMA RADIATION (TLD) i
-Thermoluminescent dosimeters _(TLDs) were collected quarterly from each The TLDs v/e'e placed surrounding the CNS site as.
j of forty locations.
r follows: Sixteen TLDs were located in an inner ring, one TLD in each of the meteorological sectors, in the genera: area of the site boundary. Sixteen I
TLDs were located in an outer ring, one TLD in each of the meteorological sectors, at approximately six to eight kilometers from the site boundary.
The remaining eight TLDs were placed in five special interest areas (schools, j
recreation areas), and at three control locations. A gamma dose and dose rate were reported quarterly for each location.
F A.10 FOOD PRODUCTS i
Samples were collected monthly when available during the harvest season i
from an irrigated garden at a residence located downstream from CNS. A gamma analysis was performed on each sample.
A.11 ANNUAL LAND USE CENSUS The 1994 Annual Land Use Census was conducted by Radiological and Environmental Services personnel July 28 - August 19,1994. The census identified the location, within eight kilometers (five miles) of the station in each of the sixteen meteorological sectors, of the nearest residence, meat animal, milk cow, milk goat, and garden producing broadleaf vegetation over an area greater than 50 square meters.
IV.
SAMPLING AND ANALYSIS IMPROVEMENTS Emphasis upon reducing deviations for Catawba Nuclear Station envirremental l
sampling was continucd throughout 1994. To support this commitment, voltage I
profiling at air site #212 was conducted during the year. Voltage checks were performed weekly It each of the other sites. Periodic flow verifications were l
performed on the new air samplers.
Continued upgrades were performed at water collection sites with the aid of station personnel. A method was developed to obtain a backup sample when the primary sample pump was inoperable. A new procedure is being researched in j
order to collect composite water samples in the field using lon exchange resin columns.
1
=
APPENDIX A - 3 1
1994 CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF ANALYSIS RESULTS INDEX l
B.1 Airborne Radioiodines and Particulates l
B.1.1 Radioiodines B.1.2 Particulates l
B.2 Ground Water B.3 Drinking Water l
B.4 Surface Water B.5 Milk B.6 Broadleaf Vegetation B.7 Shoreline Sediment B.8 Fish B.9 Direct Gamma Radia' ion (TLD)
B.10 Food Products (Crops)
APPENDIX B - 1
TABLE B.1.1 AIRBORNE RADIOIODINES Environmental Radiological Monitoring Program Stamary iame cf Facility
- Catawba Nuclear Station Docket Ntsnber
- 50-413,414 oc: tion cf Facility : York County, S.C.
Reporting Period : 1-JAN-1994 through 31-DEC-1994 rime Report Generated : 12-JAN 1995 09:43:16 Database Name
- $ DISK 1:(USER.ASC]CNS94.SAF;104 l
l l
l Location with Highest Mean l lNo.of 9editsu cr l Type & Total l Lower l
All Indicator l.......-.-....--.-...7----.---l Non-Pathway l
Nunber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations Routine Sanpled l
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction)
Report (Units) l Performed l
(LLD) l Range l
Code Range l
Range Meas.
RAD 10!au!NESl l
l l
rM3) l l
l217(10.0MiSSE) l l
1 ntions lMN-54 265l 0.00E+00l 0.00E+00(
0/ 212) 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) 0 i
l l
l 0.00E+00-- 0.00E+00 l
0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l l
1 l
l l
Co-58 265l 0.00E+00l 0.00E+00(
0/212)l 0.00E+00(
0/ 53)l 0.00E+00(
0/ 53) [
0 l
l 0.00E+00-- 0.00E+00 '
O.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l
l l
I
! FE-59 265l 0.00E+00l 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) ll 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l l
l 1
l l
l 1 Co-60 265l 0.00E+00l 0.00E+00(
0/212)l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53)l 0
l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
l l
I I
lZN-65 265l 0.00E+00l 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53)l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00-- 0.00E+00 '
I I
I l
l lNS-95 265l 0.00E+00 ( 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) 0 l
l 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 l 0.00E+00-. 0.00E+00 I
l l
lZR95 265 0.00E+0Cl 0.00E+00(
0/212)l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) l 0
l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l
I l
l l
I 131 265l 7.00E-02l 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) l 0.00E+00(
0/ $3)l 0
j l
l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 j
l l
l l
lCS-134 265l 5.00E-02l 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) 0 l
l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l
l l
l212(3.3MiE) l lCS137 265l 6.00E02l 4.49E-03(
1/212)l 4.49E 03(
1/ 53) l 0.00E+00(
0/ 53) 0 l
l 4.49E-03-4.49E03l 4.49E-03~ 4.49E-03 0.00E+00-- 0.00E+00 1
I l
lBALA-140 265l 0.00E+00 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) 0.00E+00(
0/ 53) 0 l
l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 ll and range based upon detectable measurements only I
tion cf detectable measuresents at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements i
LD is equal to 0, then LLD is not required by Selected Licensee Consnitments
' tion 200 s Site Boundary (0.6 Mi NNE) ition 201 s Site Boundary (0.5 Mi NE) ition 205 m Site Boundary (0.3 Mi SW) ition 212 a Tega Cay, SC (3.3 Mi F) ition 217 a Rock Hill Stestation (10.0 Mi SSE)
4 TABLE B.1.2 AIRBORNE PARTICULATES f
i i
Envirormental Radiological Monitoring Program Suusary ame of Ftcility
- Catawba Nuclear Station Docket Number
- 50-413,414 Ostion of Facility : York County, S.C.
Reporting Period : 1.JAN 1994 through 31 DEC 1994
^
ime Report Generated : 12 JAN 1995 09:43:16 Database Name
- SDISK1:lUSER.ASC]CNS94.SAF;104
?
.... ~.........................................................................................................................
l Location with Highest Mean l
lNo.'of edium er l Type & Total Lower All Indicator
~ ~ ~ ~ ~ - - - ~ ~ ~ ~ ~ - ~ - ~
l Non-hthway l
Number of Limitofl Locations Name, Olstance and Of rection ControlLocations.l Routine
'i Sampled l
Analyses Detection Mean (Fraction)
Location Mean (Fraction) l Mean (Fraction)
Report (Units) l Performed (LLD)
Range Code Range l
Range Mees.
~ ~ ~. ~ ~ ~.~.. ~.........................................................................................................
TTICULATE l l
l l
l217(10.0MiSSE) l "3)
I l
l l
l l
lMN54 265 0.00E+00 L 0.00E+00(
0/212)l 0.00E+00(
0/ 53)l 0.00E+00(
0/ 53) 0
- stions 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 0.00E+00 - 0.00E+00 1
C0-58 265l 0.00E+00 0.00E+00(
0/212)l 0.00E+00(
0/ 53) l 0.00E+00(
0/ 53) 0 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 1
l FE 59 265 0.00E+00l 0.00E+00(
0/ 212) 0.00E+00(
0/ 53) 0.00E+00(
0/ 53)Jl 0
l 0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 j
i CO-60 265
, 0.00E+00 l 0.00E+00(
0/212)l 0.00E+00(
0/ 53)l 0.00E+00(
0/ 53)l 0
l O.00E+00- 0.00E+00 l-0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l
l l
l ll 2N 65 265 0.00E+00 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53)l 0.00E+00(
0/ 53) 0 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 1 0.00E+00-- 0.00E+00 I
ll NS 95 265 0.00E+00 0.00E+00(
0/212)l 0.00E+00(
0/ 53) 0.00E+00(
0/ 53) 0
}
0.00E+00-. 0.00E+00 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 '
h l
l ZR 95 265 0.00E+00] 0.00E+00(
0/ 212) 0.00E+00(
0/ 53)l 0.00E+00(
0/ 53) 0 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 l
I 131 265 l 7.00E-02 0.00E+00(
0/ 212) l 0.00E+00(
0/ 53) 0.00E+00(
0/ 53) '
0 ll 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 0.00E+00 - 0.00E+00 l
l lCS134 265 5.00E-021 0.00E+00(
0/ 212) ll 0.00E+00(
0/ 53) ll 0.00E+00(
0/ 53) 0 l
0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 0.00E+00-- 0.00E+00 l
lCS-137 265l 6.00E 02 l 0.00E+00(
0/ 212) 0.00E+00(
0/ 53) 0.00E+00(
0/ 53)l 0
l l
l 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l ll
[
BALA 140 265 0.00E+06 1 0.00E+00(
0/ 212) 0.00E+00(
0/ 53) 0.00E+00(
c.'
53) 0 0.00E+00~ 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 - 0.00E+00 212 (3.3 Mi E)
BETA 265 1.00E 02, 1.90E 02( 212/ 212) 2.03E-02( 53/ 53) 2.03E 02( 53/ 53) 0 ll 1.98E 3.86E 02 7.28E 03-3.86E-02 'l 5.86E-03-. 5.75E-02 j
and range based upon detectable measurements only ion of detectable measurements at specified locations is indicated in perentheses, (Fraction) range indicates no detectable activity measurements i
Is equel to 0, then LLD is not required by Selected Licensee Comeitments ton 200 s Site Boundary (0.6 Mi NNE) ion 201 e $lte soundary (0.5 Mi NE) ton 205 = Site som dery (0.3 Mi SW) fon 212 e Tage Cay, SC (3.3 Mi E) ion 217 m Rock Hill substation (10.0 Mi $$E)
i TABLE B.2 GROUND WATER Environmental Radiological Monitoring Program Stsumery me of Facility
- Catawba Nuclear Station Docket Ntauber
- 50-413,414 c: tion af Facility : York County, S.C.
Reporting Period : 1 JAN 1994 through 31-DEC 1994 me Report Generated : 12 JAN-1995 09:43:16 Database Name
$0lSK1:(USER.ASC1CNS94.SAF;104 l
l l
Location with Highest Mean l lNo.of dium er l Type & Total l Lower l
ALL Indicator
~~-----..-~.--~~~-~~l l Mona gthway l Ntaber of l Limitofl Locations Name, Distance and Direction l Control Locations Routine g led l
Analyses Detection Meen (Fraction)
Location Mean (Fraction)
Mean (Fraction) i Report Units) l Performed (LLO)
Range Code Range l
Range Meas.
l
............................................................................... - - ~. ~. - - - - - - - - - - ~ ~ ~ ~ - " ~ - " * " " "
iWATER l
l l
l No Control Location l
4 I
I I
I I
ANAL 1-LL 8l 1.0 0.00E+00(
0/ 8) 0.00E+00(
0/ 4) 0.00E+00(
0/ 0) l 0
itions l
0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00-0.00E+00l l
- l
- 1 l
H-3 8l 2.00E+03l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 0) 0 l
l 0.00E+00~ 0.00E+00 l 0.00E+00. 0.00E+00 0.00E+00-- 0.00E+00 l
MM-54 8
15.
l 0.00E+00(
0/ 8) 0.00E+00(
0/ 4) '
O.00E+00(
0/ 0) l 0
l 0.00E+00~ 0.00E+00,
0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 l l
l
' C0-58 8l 15.
l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 4) 0.00E+00(
0/ 0) 0 l
l 0.00E+00-0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00 ~ 0.00E+00 I
I l
l FE 59 8l 30.
l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 4) ll 0.00E+00(
0/ 0) l 0
l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l
I l
l l Co-60 8l 15.
l 0.00E+00(
0/ 8)l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 0) 0 l
l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 i l
I I
I ZN-65 8
30.
0.00E+00(
0/ 8) 0.00E+00(
0/ 4) i 0.00E+00(
0/ 0) 0 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 l
l Im-95 8l 15.
l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 0)l 0
l 0.00E+00~ 0.00E+00 !
0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 ll l
l lZR-95 8'
15.
0.00E+00(
0/ 8) 0.00E+00(
0/ 4)l 0.00E+00(
0/ 0) 0 l
0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l
l l
1 1
I ll-131 8
15.
l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 0) 0 l
l 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00 ~ 0.00E+00 1
CS 134 8
l 15.
0.00E+00(
0/ 8) 0.00E+00(
0/ 4) 0.00E+00(
0/ 0) 0 l
0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 l l
CS-137 8l 18.
0.00E+00(
0/ 8) 0.00E+00(
0/ 4) ll 0.00E+00(
0/ 0) '
0 l
0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 I
L l
l lBALA-140 8l 15.
0.00E+00(
0/ 8)l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 0) 0 l
l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 and range based upon detectable measurements only ion cf detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements D is equal to 0, then LLD is not required by selected Licensee Consnitments ion 252 = Residence (0.7 Mi SW) ion 253 e Residence (0.8 Mi N)
TABLE B.3 DRINKING WATER (Pig 31 of 2)
Environmental Radiological Monitoring Program Stamery une cf Facility
- Catawba Nuclear Station Docket Ntaber
- 50 413,414 c tion cf Facility : York County, S.C.
Reporting Period : 1 JAN-1994 through 31*0EC-1994 Ime Report Generated : 12 JAN 1995 09:43:16 Database Name
- 50!SK1:(USER.ASC]CNS94.SAF;104 l
l ll l
Location with Highest Mean l lNo.of Milum er l Type & Total ll Lower ll All Indicator
. -------------------------------l l Non-
'athway l
Ntaber of Limit of Locations Name,DistanceandOfrectionl Control Locations l Routine taapled l
Analyses Detection Mean (Fraction)
Location Mean (Fraction) l Mean (Fraction) l Report runits) l Performed j (LLD) l Range Code Range l
Range l Mees.
ING WATER l l
218 (13.5 Mi N) l
.lTER) l j
l ANAL 1-LL 26 l 1.0 O.00E+00(
0/ 13) ll 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) 0 mtions l
0.00E+00 - 0.00E+00 0.00E+00 0.00E+00 l 0.00E+00-- 0.00E+00 l
l l
l ANAL 2-LL 26 l 1.0 0.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13)l 0
0.00E+00 - 0.00E+00 0.00E+00-0.00E+00l 0.00E+00-- 0.00E+00 l
l; l
MN 54 26 15.
0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0 l
0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00- 0.00E+00 l
l l
l
\\
lCo-58 26 ll 15.
l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13)l 0
[
]
0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l
l l
l l
FE 59 26 ll 30.
l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) l 0
'l l 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l I
l
)
l l
CO-60 26 ll 15.
0.00E+00(
0/ 13)l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) l 0
l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l I
I I
l ZN-6f 26 '
30.
l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) 1 0.00E+00(
0/ 13) l 0
l 0.00E+00 ~ 0.00E+00 1 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l l
l l
1 NS-95 26l 15.
l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) l 0
l
'l 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 0.00E+00-- 0.00E+00 [
ZR-95 26 15.
l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E40- 0.00E+00 I
ll-131 26 15.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13)I, 0.00E+00(
0/ 13) l 0
l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+60 0.00E+00-- 0.00E+00 '
I I
CS434 26 15.
0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) 0 0.00E+00 - 0.00E+00 '
O.00E+00 - 0.00E+00 0.00E+00 ~ 0.00E+00 CS 137 26 l 18.
0.00E+00(
0/ 13) l 0.00E+00(
0/ 13);l 0.00E+00(
0/ 13) ll 0
0.00E+00-0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 1
I BALA 140 26 15.
l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) l 0
l 0.00E+00~ 0.00D00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l and range based upon detectable measurements only lon af detectable measurements at specified locations is indicated in parentheses, (Fraction) range indic:tes no detectable activity measurements D is equel to 0, then LLD la not required by selected Licensee Commitments Ion 214 e Rock Hill Water Supply (7.3 Mi $$E) ion 218 e Belmont Water Supply (13.5 Mi N)
l l
TABLE B.3 DRINKING WATER (Page 2 cf 2)
Envirorusental Radiological Monitoring Program Summary me cf Facility
- Catawbe Nuclear Station Docket Number 50 413,414 nation af Facility : York County, S.C.
Reporting Period : 1.JAN*1994 through 31.DEC 1994 se Report Generated : 12.JAN.1995 09:43:16 Database Name
- SDISK1 (USER.ASClCNS94.SAF;104 I
ll l Location with' Highest Mean l No. of dius er Type & Totst Lower H
All Indicator Non.
ethway Number of l Limit of Locations Name, Distance and Ofrection.
Control Locations Routine espied Analyses Detection Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Report Jnit2)
Perfonned (LLD)
)
Range ll Code Range RanBe Mees.
..................................................................,,,,,,,,,,,,,,,...................,,,,,,,,,,,......i........
NG WATER
[
g l
[TER) l l
218 (13.5 Mi N) l l 214 (7.3 Mi SSE) tiono BETA 26 '
4.0 l
3.3
( 13/ 13) 3.3
( 13/ 13) 2.7
( 13/ 13)L 0
1 1.2 9.4 1.2 9.4 l 0.78 7.7 l
I I
I ITER) l l
1 tions N3 8l 2.00E+03 0.00E+00(
0/ 4) 0.00E+00(
0/ 4) l 0.00E+00(
0/ 4) 0 I
l 0.00E+00.- 0.00E+00
..................,.....,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,l 0.00E+00-.0.00E+00l 0.00E+00-.0.00E+00l nd rarse based upon detectable measurements only m af detectable measurements at specified locations is indicated in perentheses, (Fraction) snee indicates no detectable activity measurements is equal ta 0, then LLD is not required by Selected Licensee Coaumitments m 214 = Rock Hill Water Supply (7.3 Mi SSE) on 218
- B:lmont Water Supply (13.5 Mi N)
TABLE B.4 SURFACE WATER (Pags 1 of 2)
Environmental Radiological Monitoring Program Suunary me of F:cility
- Catawba Nuclear Station Docket Ntaber
- 50-413,414 ction of Facility : York Comty, S.C.
Reporting Period : 1 JAN 1994 through 31-DEC-1994 ne Report Generated : 12 JAN-1995 09:43:16 Database Name
- SDISK1 [ USER.ASC3CNS94.SAF;104 l
l l
l Location with Highest Mean l l No. of dium er l Type & Total l Lower l
All Indicator l----------.----------------l l Non-nthway l. Ntaber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine ampled l
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report Jnits) l Perfonned l (LLD) l Range l
Code Range l
Range l Meas.
E WATER l
l l
l215(4.1MiNNE) l
)
l l
l l
l ANAL 1-LL 39 l 1.0 ll 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0
tions l
[
0.00E+00 0.00E+00 l 0.00E+00-- 0.00E+00 0.00E+00-0.00E+00l l
L l
l l ANAL 2-LL 39l 1.0
, 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13)
. 0.00E+00(
0/ 13)l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
l 1
1 I
I lMN-54 39 l 15.
0.00E+00(
0/ 26)l D.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0
l l
0.00E+00--0.00E+00l 0.00E+00 - 0.00E+00 0.00E+00--0.00E+00l l
l 1
I l
l lCO-58 39l 15.
l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 l
l l
l l
l lFE-59 39 30.
l 0.00E+00(
0/ 26) 0.00E+00(
0/ 13) ll 0.00E+00(
0/ 13)l 0
l l 0.00E+00- 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l l
l l
l lCo-60 39 15.
l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0
l l
l 0.00E+00-- 0.00E+00 0.00E+00 - 0.00c+00 0.00E+00--0.00E+00l 1
1 I
I lZN-65 39 30.
l 0.00E+00(
0/ 26) 0.00E+00(
0/ 13) 0.00E+00(
0/ 13)l 0
l l 0.00E+00-0.00E+00l O'.00E+00-- 0.00E+00 0.00E+00--0.00E+00l l
l 1
l l
l lNS-95 39 l 15.
l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13)li 0.00E+00(
0/ 13) 0 l
l l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 i
l I
I I
lZR-95 39 [
15.
l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13) 1 0.00E+00(
0/ 13) ll 0
l l 0.00E+00- 0.00E+00 l 0.00E+00-- 0.00E+00 ll 0.00E+00 - 0.00E+00 l
l l
ll ll-131 39 l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) !l 0.00E+00(
0/ 13) L 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00 - 0.00E+00 l 1
l l
lCS-134 39 l 15.
l 0.00E+00(
0/ 26) 0.00E+00(
0/ 13) 0.00E+00(
0/ 13) !
0 l
l l 0.00E+00 - 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 l
I I
l lCS-137 39 l 18.
l 0.00E+00(
0/ 26) 0.00E+00(
0/ 13)l 0.00E+00(
0/ 13) 0 l
l l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 '
I I
I I
I lBALA-140 39 l 15.
l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) 0 l
l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 nd range based upon detectable measurements only on af detectable measurements at specified locations is indicated in parentheses, (Fraction) ange indic-tes no detectable activity measurements is equal to 0, then LLD is not required by Selected Licensee Commitments on 208 e Discharge Canal (0.5 Mi S) on 211 = Lake Wylie Dam (4.0 Mi ESE)
Location 215 = River Pointe (4.1 Mi NNE)
TABLE B.4 SURFACE WATER (Pags 2 of 2)
Erwironmentet Radiological Monitorins Program Summary Name af FaclLity
- Cataube Ntxtear Station Docket Number a 50-413.414 Locstion af Facility : York Cotssty, S.C.
Reporting Period : 1.JAN.1994 through 31-DEC.1994 Time Report Generated 12 JAN 1995 09:43:16 Database Name
- 90lSK1:[ USER.ASC)CNS94.SAF;104 l
l 1
Location with Nighest Mean l lNo.of Medlue or Type &Totetl Lower Att Indicator l...>....................-*-**-l Non.
Pathway Number of l Limit of Locations l Name, Olstance and Direction Control Locations Routine Sampled Anotyses l Detection ll Meen (Fraction) l Location Moon (Fraction)
Meen (Fraction) l Report (Units)
Performed l (LLD) l Range l
Code Range Range l Mees.
fTRITIUM l
l l
Cl/ LITER) l l
l
- 215 (4.1 Mi NME) l l
l l206(0.5 mis) l Locations lN-3 12 l 2.00E+03 l 8.42E+03(
4/ 8)l 8.42E+03(
4/ 4) l 0.00E+00(
0/ 4) l 0
l l
l 3.47E+03-- 1.64E+04 l 3.47E+03. 1.64E+04 l 0.00E+00. 0.00E+00 l mn and range based upon detectable measurements only w tion af detectable measurements at specified locations is indicated in parentheses, (Fraction) we range indicates no detectable activity measurements f LLD is equel to 0, then LLD is not required by Selected Licensee Commitments motion 208 = Discharge canst (0.5 Mi S) mation 211 = Lake Wytte Dam (4.0 Mt ESE) mation 215 = River Pointe (4.1 Mi NME)
TABLE B.5 MILK Envirorrnental Radiological ronitoring Program Summary dame cf Facility
- Catawba Nuclear Station Docket Number
- 50-413,414
.ocation af Facility : York County, S.C.
Reporting Period : 1-JAN-1994 through 31-DEC-1994 time Report Generated : 12-JAN-1995 09:43:16 Database Name
- SD!SK1:[ USER. ASC3 CNS94.SAF;104 l
l ll l
Location with Highest Mean l lNo.of 4edlun er l Type & Total l Lower All Indicator l-----------------------------l l Non-Pcthway l Nunber of l Limit of Locations l Name, Distance and Direction l Control Locations l Routine Saapted l
Analyses l Detection l
Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l
Code Range l
Range l Meas.
I I
I I
I
/ LITER) l l
l 221 (12.3 Mi NW) l I
I ntions lMN54 76l 0.00E+00l 0.00E+0C(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) ll 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
I lCo-58 78l 0.00E+00l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
I lFE-59 78l 0.00E+00l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
l C0-60 78l 0.00E+00l 0.00E+00(
0/ 52) 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l 0.00E+00 - 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00--0.00E+00l 1
l lZN-65 78l 0.00E+00l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
l l
l l
l lNS-95 78l 0.00E+00l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l I
I I
I I
lZR-95 78l 0.00E+00 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26)l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l l
l l
1 I
i lI131 78l 15.
] 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l 1
I I
I I
lLL1-131 78l 1.0 l 0.00E+00(
0/ 52)l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
l lCS134 78l 15.
l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26)l 0
O.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00 0.00E+00 l l209(7.0MiSSW) l l
l CS-137 78l 18.
I 2.8
(
1/ 52) l 2.8
(
1/ 26) 0.00E+00(
0/ 26)l 0
l l
2.8
-- 2.8 2.8
-- 2.8 0.00E+00--0.00E+00l l
l 1
lBALA140 78 'l 15.
l 0.00E+00(
0/ 52) ll 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26)l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0...................................................................,,...........................................................
ard range based upon detectable measurements only tion Cf detectable measurements at specified locations is indicated in parentheses, (Fraction) range irdicates no detectable activity measurements LD is equal to 0, then LLD is not required by Selected Licensee Commitments tion 209 a Woods Dairy (7.0 Mi SSW) 3fon 219 s Pursley Dairy (6.0 Mi SW) tion 221 = Oates Dairy (13.0 Mi NW)
l TABLE B.6 BROADLEAF VEGETATION Environmental Radiological Monitoring Program Suunary "ame af Fccility
- Catawba Nuclear Station Docket Nusber
- 50-413,414 kocationcfFacility
- York County, S.C.
Reporting Period 1 JAN 1994 through 31-0EC-1994 hine Report Generated : 12 JAN 1995 09:43:16 Database Name
- $ DISK 1 (USER.ASC3CNS94.SAF;104 p...............................................................................................................................
l l
Location with Highest Mean l l; No. of Mediun cr Type & Total Lower All Indicator
-~~~~~------~~~~----l Non-P:thway Number of Limit of Locations Name,DistanceandDirectionl Control Locations Routine Sampled l
Analyses Detection Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction)
Report (Units) l Performed (LLD) l Range Code Range Range Meas.
3...............................................................................................................................
DLEAFVEGETl l
l l
/ WET /KG) l l
l 217 (10.0 Mi SSE)
I I
I cations lMN-54 32l 0.00E+00 0.00E+00(
0/ 24) l 0.00E+00(
0/ 8) I' O.00E+00(
0/ 8) 0 l
0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 ll 0.00E+00- 0.00E+00 l
l l
CO-58 32 0.00E+00l 0.00E+00(
0/ 24)l 0.00E+00(
0/ 8) 0.00E+00(
0/ 8)l 0
j 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 0.00E+00-- 0.00E+00 l
l l
llFE-59 32 l 0.00E+00 0.00E+00(
0/ 24)l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 8) 0
]
l l
0.00E+00-0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00 ~ 0.00E+00 I
l CO-60 32 l 0.00E+00 0.00E+00(
0/ 24) 0.00E+00(
0/ 8) 0.00E+00(
0/ 8) 0 l
0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 l
.. ZN-65 32l 0.00E+00 0.00E+00(
0/ 24)l 0.00E+00(
0/ 8)
, 0.00E+00(
0/ 8) 0 l
l 0.00E+00~ 0.00E+00 l; 0.00E+00 - 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l
l l
h L
lNe-95 32l 0.00E+00 0.00E+00(
0/ 24) 0.00E+00(
0/ 8) 0.00E+00(
0/ 8) l 0
l 0.00E+00~ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ 0.00E+00 I
, ZR-95 32l 0.00E+00 0.00E+00(
0/ 24)l 0.00E+00(
0/ 8) l 0.00E+00(
0/ 8) 0 l
l 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l
l lI131 32 60.
0.00E+00(
0/ 24) 0.00E+00(
0/ 8) l 0.00E+00(
0/ 8) 0 l
0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00-- 0.00E+00 l
l lCS*134 32 '
60.
0.00E+00(
0/ 24)!
0.00E+00(
0/ 8)l 0.00E+00(
0/ 8) l 0
'Il O.00E+00 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l
226 (0.5 Mi S) l CS-137 32 80.
66.
(
7/ 24) 70.
( 4/ 8) l 0.00E+00(
0/ 8) 0 21.
~ 1.23E+02 31.
~ 1.17E+02 0.00E+00-- 0.00E+00 l
BALA 140 32 l 0.00E+00 1 0.00E+00(
0/ 24)l 0.00E+00(
0/ 8) 0.00E+00(
0/ 8) 0 l
O.00E+00-0.00E+00l 0.00E+00~ 0.00E+00 1 0.00E+00 ~ 0.00E+00 i and range based upon detectable measurements only f' tion cf detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements LD is equal to 0, then LLD is not required by Selected Licensee Conunitments tion 200 m Site Boundary (0.6 Mi NNE) l tion 201 s Site soundary (0.5 Mi NE) tion 217 s Rock Hill Substation (10.0 Mi SSE)
. tion 226 s Site soundary (0.5 Mi S)
i TABLE B.7 SHORELINE SEDIMENT i
l Environmental Radiological Monitoring Program Sunnary lame of Facility
- Catawba Nuclear Station Docket Number
- 50-413,414
.ocation af Facility : York Cou1ty, S.C.
Reporting Period : 1-JAN 1994 through 31-DEC-1994
'ime Report Generated : 12 JAN 1995 09:43:16 Database Name ~
$0!SK1:(USER.ASC]CNS94.SAF;104 l
l
'. Location with Highest Mean l No. of ledlun er Type & Total l Lower l
All Indicator Non-P;thway Number of l Limitofl Locations Name, Olstance and Direction Control Locations Routine Sampled Analyses l Detection l Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l
Code Range Range ll Meas.
IENT l
- l l
J il l
'0RY/KG) l 215 (4.1 Mi NME) l 208 (0.5 Mi S)
- tions l
MN 54 6
0.00E+00l 49.
(
2/ 4) l 49.
(
2/ 2) l 0.00E+00(
0/ 2) 0 l
l 45.
53.
l 45.
53.
l 0.00E+00 - 0.00E+00 i
fl 208 l
l Co-58 6
0.00E+00 8.78E+02(
2/ 4) 8.78E+02(
2/ 2)l 0.00E+00(
0/ 2) l!
0 8.61E+02 - 8.95E+02 8.61E+02--8.95E+02l 0.00E+00-* 0.00E+00 i
FE-59 6
0.00E+00l 0.00E+00(
0/ 4)l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2)l 0
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00-0.00E+00l l
12m i
I co-60 6i 0.00E+00 5.09E+02(
2/ 4) l 5.09E+02(
2/ 2)l 0.00E+00(
0/
2)l 0
4.65E+02 - 5.54E+02 4.65E+02--5.54E+02l 0.00E+00 - 0.00E+00 I
ZN 65 6l 0.00E+00 l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2) 0 ll 0.00E+00-0.00E+00l 0.00E+00-- 0.00E+00 0.00E+00 0.00E+00 1
1 l
lNs-95 6 l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) 0.00E+00(
0/ 2) l 0
j 0.00E+00 - 0.00E+00 0.00E+00 0.00E+00 ll 0.00E+00-- 0.00E+00 ZR-95 6
0.00E+00 0.00E+00(
0/ 4) 0.00E+00(
0/ 2) 0.00E+00(
0/ 2) l 0
0.00E+00 - 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00 - 0.00E+00 I
1 131 6
0.00E+00 0.00E+00(
0/ 4) 0.00E+00(
0/ 2) 0.00E+00(
0/ 2) 0 i
0.00E+00. 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00 0.00E+00 ll 208 CS 134 6l 1.50E+02l 27
(
1/ 4) 1.
27.
(
1/ 2) 0.00E+00(
0/ 2) 0 ll l
27.
27.
27.
27.
0.00E+00 - 0.00E+00 l
208 CS 137 6
1.80E+02l 88.
(
3/ 4) 1.25E+02(
2/ 2) 0.00E+00(
0/ 2) 0 l
l 14.
-- 1.26E+02 1.24E+02-1.26E+02 0.00E+00-- 0.00E+00 l l
l BALA 140 6) 0.00E+00l 0.00E+00(
0/ 4) 0.00E+00(
0/ 2) ll 0.00E+00(
0/ 2) 0 l
l l
0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00
.................................................................................................l...............................
and range based upon detectable measurements only
- fon of detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements A is equal to 0, then LLD is not required by Selected Licensee Conunitments
- fon 208 s Discharge Canal (0.5 Mi S)
- fon 210 s Ebenezer Access (2.4 Mi SE)
)fon215sRiverPointe(4.1MiNNE) l
i TABLE B,8 FISH l
Environmental Radiological Monitoring Program Summary Name Cf Facility Catawba Nuclear Station Docket Ni.srber
- 50-413,414 location tf Facility : York County, S.C.,
Reporting Period 1-JAN-1994 through 31 DEC-1994 I
Time Report Generated : 12-JAN 1995 09:43:16 Database Name
$ DISK 1:(USER.ASC]CNS94.SAF;104 I
l l
l Location with Highest Mean l lNo.of Medlun er l Type & Total Lower l
All Indicator l------------------------------
l Non-Pcthway l
Nunber of Limitofl Locations l Name, Distance and Direction Control Locations l Routine Sampled l
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction)
Report (Units) l Performed l (LLD) l Range l
Code Range l
Range Meas.
l l
l l
l l
- / WET /KG) l l
l l
l216(4.0MiNNE) l
\\
l l
l208(0.5 mis) l l
) cations lMN-54 12l 1.30E+02l 23.
(
1/ 6) l 23.
(
1/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 23.
23.
l 23.
23.
l 0.00E+00--0.00E+00l l
l l
12m I
I lCo-58 12l 1.30E+02l 92.
(
3/ 6) l 92.
( 3/ 6) 0.00E+00(
0/ 6) l 0
l l
l 60.
--1.21E+02l 60.
- 1.21E+02 0.00E+00-0.00E+00l l
1 I
I I
lFE-59 12l 2.60E+02l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
l l
12m I
I lCO-60 12 l 1.30E+02l 38.
(
3/ 6) l 38.
(
3/ 6)l 0.00E+00(
0/ 6) l 0
l l
12.
-- 77.
l 12.
77.
l 0.00E+00--0.00E+00l 1
I I
I I
lZN-65 12l 2.60E+02l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 l I
I I
I I
N8-95 12l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) 0 l
l 0.00E+00 - 0.00E6 C 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l 1
i l
lZR-95 12l 0.00E+00l 0.00E+00(
0/ 6) 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00 - 0.00E+00 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l l
l l
I i
lI-131 12l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6)l 0.00E+00(
0/ 6) l 0
l l
0.00E+00-- 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00-- 0.00E+00 '
I I
lCS-134 12l 1.30E+02[ 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) 0.00E+00(
0/ 6) 0 l
l l 0.00E+00--0.00E+00l 0.00E+00 - 0.00E+00 0.00E+00-- 0.00E+00 ll l
l 1
l20s I
lCS-137 12l 1.50E+02l 27.
(
6/ 6) l 27.
( 6/ 6) l 0.00E+00(
0/ 6) 0 l
7.5 39.
l 7.5 39.
l 0.00E+00- 0.00E+00 l
I I
lBALA-140 12l 0.00E+00l 0.00E+00(
0/ 6)l 0.00E+00(
0/ 6)l 0.00E+00(
0/ 6) l 0
l
\\
l 0.00E+00--0.00E+00l 0.00E+00 - 0.00E+00 0.00E+00-- 0.00E+00
..................................................................................................l.......................l........
i and range based upon detectable measurements only
- tion of detectable measurements at specified locations is indicated in parentheses, (Fraction) i range indicates no detectable activity measurements
.LD is equal to 0, then LLD is not required by Selected Licensee Consnitments ition 208 e Discharge Canal (0.5 Mi S) ition 216 = Mighway 49 Bridge (4.0 Mi NNE)
TABLE B.9 DIRECT GAMMA RADIATION (TLD) t I
-l Environmental Radiological Monitoring Program Summary lane cf Facility
- Catsube Nuclear Station Docket Number
- 50-413,414
.ocition cf Facility York County, S.C.
Reporting Period : 1*JAN.1994 through 31-DEC-1994 time Report Generated : 18 JAN-1995 16:09:25 Database Name
- SDISIC1:(USER.ASC3CNS94.SAF;104 l
l Location with Highest Mean LNo.of ledium or l Type & Total Lower l
All Indicator
- - - ~ ~ ~ ~. ~.. ~ ~ ~ ~.. ~. ~
L Non.
P;thway l Number of Limit of Locations Name, Distance and Direction Control Locations l Routine Sampled Analyses Detection,
Mean (Fraction) l Location Meen (Fraction)
Mean (Fraction)
Report (Units)
Performed l (LLD)
.l Range l
Code Range R& Age Nees.
T RAD-TLD l
l l
ITR) l l
l*SeeBelow
.I 207 (0.9 mi WNW) l citions mR/0TR 157 0.00E+00 18.
( 145/ 145) 22.
( 4/ 4) l 16.
( 12/ 12) 0 8.1 27.
l 6.7 22.
l 27.
13.
~
and rtnge based upon detectable measurements only
- fon cf detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements D is equal to 0, then LLD is not required by Technical Specifications
- ions:
ilta Boundary (0.6 MI NNE) 232 4-5 Mi radius (4.1 Mi NE) litz Boundary (0.5 Mi NE) 233 4-5 Mi radius (4.0 Mi ENE) ilts Boundary (0.4 Mi ESE) 234 4 5 Mi radius (4.5 MI E)
- its Boundary (0.5 Mi SSW) 235 4-5 Mi radius (4.0 Mi ESE) ilt2 Boundary (0.3 Mi SW) 236 4 5 Mi radius (4.2 Mi SE) lita Boundary (0.7 MI WNW) 237 4-5 Mi radius (4.8 Mi SSE) ilts Bomdery (0.9 Mi WWW) 238 4-5 Mi radius (4.2 Mi S) ilt2 Bo mdary (0.9 Mi NNW) 239 4 5 Mi radius (4.6 Mi SSW)
CONTROL (10.0 Mi SSE) 240 4 5 Mi radius (4.1 Mi WSW) ilte Boundary (0.7 Mi W) 2414-5 Mi radius (4.7 Mi WSW)
'Its Boundary (0.6 Mi E) 242 4-5 Mi radius (4.6 Mi W) its Boundary (0.7 Mi SE) 243 4 5 Mi radius (4.6 Mi WNW) its Boundary (0.5 Mi S) 244 4-5 Mi radius (4.1 Mi NW) its Boundary (0.5 Mi WSW) 245 4 5 Mi radius (4.2 MI WNW) its Boundary (0.6 Mi W) 246 SPECIAL INTEREST (8.1 Mi ENE) its Bomdery (0.8 MI NW)
- 247 CONTROL (7.5 Mi ESE)
-5 Mi radius (4.4 Mi W) 248 SPECIAL INTEREST (7.0 Mi SSE) 5 Mi radius (4.2 Mi NME) 249 SPECIAL INTEREST (8.1 Mi S) its Boundary (0.6 Mi ENE) 250 SPECIAL INTEREST (10.3 Mi WSW)
It2 Bomdary (0.6 Mt SSE)
- 251 CONTROL (9.8 MI WNW)
TABLE B.10 FOOD PRODUCTS (CROPS)
Environmental Radiological Monitoring Program Sumnary ne of Facility
- Catawba Nuclear Station Docket Number 50-413,414 tation cf Facility : York County, S.C.
Reporting Period : 1 JAN 1994 through 31 DEC 1994 ne Report Generated : 12 JAN-1995 09:43:16 Database Name
- $0!SK1 (USER.ASC1CNSO4,SAF;104 h
Location with Highest Mean No. of diue er Type & Total Lower All Indicator Non-
- - ~ ~ ~ - - - ~ ~ - - - - - - - - - -
ethway Number of Limitofl Locations Name, Oistance and Ofrection Control Locations Routine unpled Analysee DetectionI Mean (Fraction)
Location Mean (Fraction)
Mean (Fraction) l Report Jnits) l Performed ll (LLO) l Range ll Code Range l
Range l Mees.
I L
ET/KG) l l
No control location l
1
'1 tion MN 54 11 0.00E+00 0.00E+00(
0/ 11) l 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) 0 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l 1
l Co-58 11 0.00E+00 0.00E+00(
0/ 11) l 0.00E+00(
0/ 11) 1 0.00E+00(
0/ 0) 0 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 I
I FE-59 11l 0.00E+00l 0.00E+00(
0/ 11) 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) 0 l
l 0.00E+00~ 0.00E+00 l
0.00E+00~ 0.00E+00 ll 0.00E+00~ 0.00E+00 l
l l
L Co-60 11l 0.00E+00 'l 0.00E+00(
0/ 11) 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) 0 l
l 0.00E+00 ~ 0.00E+00 '
O.00E+00~ 0.00E+00 l 0.00E+00-- 0.00E+00 '
l l
l ZN-65 11l 0.00E+00 0.00E+00(
0/ 11) 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) l-0 l
l 0.00E+00 - 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l
l NS-95 11 0.00E+00 1 0.00E+00(
0/ 11)
O.00E+00(
0/ 11) 0.00E+00(
0/ 0) l 0
0.00E+00 ~ 0.00E+00 1
0.00E+00~ 0.00E+00 '
O.00E+00~ 0.00E+00 I
l l
ZR 95 11 0.00E+00il 0.00E+00(
0/ 11) l 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) 0 l
0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 I
l 131 11l 60.
0.00E+00(
0/ 11) 0.00E+00(
0/ 11)l 0.00E+00(
0/ 03 0
l 0.00E+00~ 0.00E+00 0.00E+00 - 0.00E+00 l 0.00E+00~ 0.00E+00 l
l CS 134 11 '
60.
0.00E+00(
0/ 11) l 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) 0 L
0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 CS-137 11 80.
0.00E+00(
0/ 11) 0.00E+00(
0/ 11) l 0.00E+00(
0/ 0) 0 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 ~ 0.00E+00 BALA-140 11 0.00E+00 0.00E+00(
0/ 11) 0.00E+00(
0/ 11) 0.00E+00(
0/ 0) l 0
i l
0.00E+00-- 0.00E+00 l 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 '
nd range based upon detectable measurements only on cf detectable measureannts at specified locations is indicated in parentheses, (Fraction) ange ina:c;tes no detectable activity measurements la equel to 0, then LLO is not regJired by Selected Licensee Consmitments on 253 = Irrigated garden at the Cloninger Residence (Z.1 Mi SSE) 9
CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSES 1.
SAMPLING DEVIATIONS The following deviations from sampling requirements occurred during 1994:
Sample Scheduled Actual Type Location Collection Collection Deviation Reason Action Dates Dates Air 200 12/28-1/4/95 12/28 -1/4/95 Sample did not collect for Loss of power.
York Electric called to restore Particulates full 7 day period.
- power, and Air 201 2/9-2/16/94 2/9 - 2/16/b4 Sample did not collect for Power supply On 2/8, collection sampler was Radioiodines full 7 day period.
shut down for changed out and left on so it unknown would start up when power was reason.
restored.
6/22 -6/29/94 6/22 -6/27/94 Sample did not collect for Blown fuse.
Replaced fuse.
full 7 day period.
205 4/6 -4/13/94 4/6 -4/8/94 Sample did not collect for Blown fuse.
Replaced air sampler.
full 7 day period.
212 3/23 -3/30/94 3/23-3/26/94 Sample did not collect for Blown fuse.
Replaced fuse.
full 7 day period.
3/30 -4/6/94 3/30 -4/2/94 Sample did not collect for Blown fuse.
Replaced sampler LVAS #10 with full 7 day period.
LVAS #17 due to 2 blown fuses in a row.
6/15 - 6/22/94 6/15 -6/21/94 Sample did not collect for Motor failure.
Replaced sampler #16 with full 7 day period.
sampler #9.
10/26 -11/2/94 10/26-10/27/94 Sample did not collect for Sampler Replaced air sampler.
full 7 day period.
malfunction.
217 5/25-6/1/94 5/25 -5/28/94 Sample did not cc!!ect for Blown fuse.
Replaced fuse and tagged full 7 day period.
sampler #12.
APPENDIX C-1
}
Sample Scheduled Actu 1 Type Location Collection Collection Deviation Reason Action Dates Dstes Surface 208 6/8 - 6/22/94 6/8 - 6/15/94 Sample did not collect for Pump failure due to CNS notified on 6/23 to Water entire 2 week period.
clogged / corroded replace or repair pump.
intake screen.
Abbreviated sample co!!ected.
6/22 - 7/6/94 7/6/94 No sample available.
Pump failure due to Work request submitted.
clogged / corroded Collected grab sample.
intake screen.
7/6 - 7/20/94 7/20/94 No sample available.
Pump failure due to Interval sampler installed.
clogged / corroded Grab collected.
intake screen.
7/20 -8/3/94 8/3/94 No sample available.
Pump failure due to Grab collected.
clogged / corroded intake screen.
9/28 -10/12/94 10/12/94 No sample available.
Pump failure due to Hose crimped on sampler, clogged / corroded Grab collected.
intake screen.
211 6/22 - 7/6/94 7/6/94 No sample available.
Pump inoperable.
Work request submitted.
Grab collected.
7/6 - 7/20/94 7/20/94 No sample available.
Pump inoperable.
Work request submitted.
Grab collected.
7/20 -8/3/94 8/3/94 No sample available Sampler malfunction.
Reset sampler. Collected grab sample.
11/23 -12/7/94 12/7/94 Sample did not collect for Pump not repaired Collected abbreviated entire 2 week period.
until 12/7/94.
sample.
kkkg
$hubh '$
mp -
Y^
~
~ ' - W ~ '
1 Drinking 214 10/12 -10/26/94 10/26/94 No sample available Pump failed.
Pump was replaced. Grab Water sample was collected.
I 218 11/9 -11/23/94 11/23/94 Nn sample available Plant personnel Opered supply valve.
isolated tank.
Collected grab sample.
APPENDIX C-2
usnn,, nam,,nrmo^cntmenesnnAom il.
UNAVAILABLE ANALYSES The following unavailable analyses occurred during 1994:
Sample Scheduled Type Location Collection Deviation Reason Action Dates 206 12/30/93 -3/31/94 Unavailable for analysis.
TLD was found on ground on 2/6/94.
Replaced with 2nd Otr. TLD.
TLD Could not be processed.
228 6/27-9/29/94 Unavailable for analysis.
Missing at time of collection.
Replaced with 4th Otr. TLD.
238 12/30/93 -3/31/94 Unavailable for analysis.
Missing at time of collect!on.
Replaced with 2nd Otr. TLD.
APPENDIX C-3
1994 CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX D ANALYTICAL DEVIATIONS There were no analytical deviations for 1994.
APPENDIX D-1
1994 CNS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANALYSIS RESULTS This appendix includes all of the sample analysis reports (SAR's) generated from each sample medium for 1994.
Appendix E is located separately from this report and is archived at Duke Power's Environmental Center environmental data master file.
APPENDIX E-1
I E
(
)
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