ML031210205
| ML031210205 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle, Farley  |
| Issue date: | 04/28/2003 |
| From: | Beasley J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-0938 | |
| Download: ML031210205 (69) | |
Text
ENCLOSURE 2 Joseph M. Farley Nuclear Plant Annual Radiological Environmental Operating Report for 2002
JOSEPH M. FARLEY NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2002 SOUTH ERN NZ COMPANY Energy to Serve You r World'
TABLE OF CONTENTS Section and/or Title Subsection Page List of Figures ii List of Tables iii List of Acronyms iv 1.0 Introduction 1-1 2.0 REMP Description 2-1 3.0 Results Summary 3-1 4.0 Discussion of Results 4-1 4.1 Land Use Census 4-7 4.2 Airborne 4-8 4.3 Direct Radiation 4-14 4.4 Milk 4-18 4.5 Forage 4-22 4.6 Ground Water 4-26 4.7 Surface Water 4-28 4.8 Fish 4-31 4.9 Sediment 4-36 5.0 Interlaboratory Comparison Program (ICP) 5-1 6.0 Conclusions 6-1 i
LIST OF FIGURES Figure Number Title Page Figure 2-1 REMP Stations Near the Plant Perimeter 2-9 Figure 2-2 REMP Stations 2 to 5 Miles from the Plant 2-10 Figure 2-3 REMP Stations Beyond 5 Miles from the Plant 2-11 Figure 4.2-1 Average Weekly Gross Beta Air Concentration 4-9 Figure 4.2-2 Average Annual Cs-137 Concentration in Air 4-11 Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 4-15 Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 4-18 Figure 4.4-2 Average Annual I-13 1 Concentration in Milk 4-20 Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 4-22 Figure 4.5-2 Average Annual I-131 Concentration in Forage 4-24 Figure 4.6-1 Average Annual H-3 Concentration in Ground Water 4-26 Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 4-29 Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-32 Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 4-34 Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 4-37 Figure 4.9-2 Average Annual Cs-137 Concentration in Sediment 4-38 ii
LIST OF TABLES Table Number Title Page Table 2-1 Summary Description of Radiological Environmental Monitoring Program 2-2 Table 3-1 Radiological Environmental Monitoring Program Annual Summary 3-2 Table 4-1 Minimum Detectable Concentrations (MDC) 4-1 Table 4-2 Reporting Levels (RL) 4-2 Table 4-3 Deviations from Radiological Environmental Monitoring Program 4-4 Table 4.1-1 Land Use Census Results 4-7 Table 4.2-1 Average Weekly Gross Beta Air Concentration 4-10 Table 4.2-2 Average Annual Cs-137 Concentration in Air 4-12 Table 4.3-1 Average Quarterly Exposure from Direct Radiation 4-16 Table 4.4-1 Average Annual Cs-137 Concentration in Milk 4-19 Table 4.4-2 Average Annual
- -131 Concentration in Milk 4-21 Table 4.5-1 Average Annual Cs-1 37 Concentration in Forage 4-23 Table 4.5-2 Average Annual I-13 1 Concentration in Forage 4-25 Table 4.6-1 Average Annual H-3 Concentration in Ground Water 4-27 Table 4.7-1 Average Annual H-3 Concentration in Surface Water 4-30 Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-33 Table 4.8-2 Average Annual Cs-1 37 Concentration in Game Fish 4-35 Table 4.9 Sediment Nuclide Concentrations 4-36 Table 5-1 Interlaboratory Comparison Program Results 5-3 iii
LIST OF ACRONYMS Acronyms presented in alphabetical order Acronym Definition APCo Alabama Power Company ASTM American Society for Testing and Materials CL Confidence Level EL Georgia Power Company Environmental Laboratory EPA Environmental Protection Agency FNP Joseph M. Farley Nuclear Plant ICP Interlaboratory Comparison Program MDC Minimum Detectable Concentration MDD Minimum Detectable Difference MWe MegaWatts Electric NA Not Applicable NDM No Detectable Measurement(s)
NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual Po Preoperation PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile TLD Thermoluminescent Dosimeter TS Technical Specification iv
1.0 INTRODUCTION
The Radiological Environmental Monitoring Program (REMP) for 2002 was conducted in accordance with Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 2002 are reported herein in accordance with Technical Specification (TS) 5.6.2 and ODCM 7.1.
The objectives of the REMP are to:
- 1) Determine the levels of radiation and the concentrations of radioactivity in the environs and;
- 2) Assess the radiological impact (if any) to the environment due to the operation of the Joseph M. Farley Nuclear Plant (FNP).
The assessments include comparisons between results of analyses of samples obtained at locations where radiological levels are not expected to be affected by plant operation (control stations) and at locations where radiological levels are more likely to be affected by plant operation (indicator stations), as well as comparisons between preoperational and operational sample results.
FNP is owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company.
It is located in Houston County, Alabama approximately fifteen miles east of Dothan, Alabama on the west bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a licensed core thermal power output of 2775 MegaWatts thermal (MWt), achieved initial criticality on August 9, 1977 and was declared "commercial" on December 1, 1977.
Unit 2, also a 2775 MWt Westinghouse PWR, achieved initial criticality on May 8, 1981 and was declared "commercial" on July 30, 1981.
The preoperational stage of the REMP began with initial sample collections in January of 1975. The transition from the preoperational to the operational stage of the REMP was marked by Unit 1 initial criticality.
A description of the REMP is provided in Section 2 of this report. An annual summary of the results of the analyses of REMP samples is provided in Section 3.
A discussion of the results, including assessments of any radiological impacts upon the environment and the results of the land use census are provided in Section 4.
The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.
1-1
2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1.
This table summarizes the program as it meets the requirements outlined in ODCM Table 4-1. It details the sample types to be collected and the analyses to be performed in order to monitor the airborne, direct radiation, waterborne and ingestion pathways, and also delineates the collection and analysis frequencies. In addition, Table 2-1 describes the locations of the indicator, community and control stations as described in ODCM Table 4-4 and the identification of each sample according to station location and analysis type.
The stations are also depicted on maps in Figures 2-1 through 2-3.
The location of each REMP station for gaseous releases is described by its direction and distance from a point midway between the Unit 1 and Unit 2 plant vent stacks. The surrounding area is divided into 16 azimuthal sectors which are centered on the major compass points; each sector is numbered sequentially clockwise and oriented so that the centerline of sector 16 is due north. Each sampling station is identified by a four digit number. The first two digits indicate the sector number, and the last two digits indicate the distance from the origin to the nearest mile.
For example, air monitoring station 0215 is located approximately 15 miles northeast of the origin. The locations for the sampling stations along the river are identified by the nearest River Mile (RM) which is the distance along the navigable portion of the Chattahoochee River upstream of the Jim Woodruff Dam near Chattahoochee, Florida. The approximate locations of the plant discharge and intake structures are at RM 43.5 and 43.8, respectively.
The samples are collected by the plant's technical staff, except for fish and river sediment samples which are collected by APCo Environmental Field Services personnel.
All laboratory analyses were performed by Georgia Power Company's Environmental Laboratory (EL) in Smyrna, Georgia.
2-1
TABLE 2-1 (SHEET 1 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t~)
Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
AIRBORNE Particulates Continuous sampler operation with sample Particulate sampler: Analyze for gross collection weekly.
beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite sample y location) quarterly.
Indicator Stations:
River Intake Structure PI-0501 (ESE-0.8)
South Perimeter PI-0701 (SSE-1.0)
Plant Entrance PI-1 101 (WSW-0.9)
North Perimeter PI-1601 (N-0.8)
Control Stations:
Blakely GA (NE-15)
PB-0215 Neals Landing, FL PB-0718 (SSE-1 8)
Dothan, AL(-
PB-1218 Community Stations:
GA Pacific Paper Co.
PC-0703 (SSE-3)
Ashford, AL PC-i 108 (WSW-8)
Columbia, AL (N-5)
PC-1605
TABLE 2-1 (SHEET 2 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
Iodine Continuous sampler operation with sample Radioiodine canister: Analyze each collection weekly sample for I-131 weekly._
Indicator Stations:
River Intake Structure 11-0501 (ESE-0.8)
South Perimeter 11-0701 (SSE-1.0)
Plant Entrance II-1101 (WSW-0.9)
North Perimeter II-1601 (N-0.8)
Control Station:
Blakely, GA (NE-15)
IB-0215 Neals Landing, FL IB-0718 (SSE-18)
Dothan, AL (W-18)
IB-1218 Community Station:
GA Pacific Paper Co.
IC-0703 (SSE-3)
DIRECT RADIATION TLD Quarterly Gamma dose: Read each badge
____________________________quarterly Indicator Stations:
Plant Perimeter (NNE-0.9)
RI-0101 (NE-1.0)
RI-0201 (ENE-0.9)
RI-0301 (E-0.8)
RI-0401 (ESE-0.8)
RI-0501
TABLE 2-1 (SHEET 3 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
(SE-1. 1)
RI-0601 (SSE-1.0)
RI-0701 (S-1.0)
RI-0801 (SSW-1.0)
RI-0901 (SW-0.9)
RI-1001 (WSW-0.9)
RI-1101 (W-0.8)
RI-1201 (WNW-0.8)
RI-1301 (NW-1.1)
RI-1401 (NNW-0.9)
RI-1501 (N-0.8)
RI-1601 Control Stations:
Blakely, GA (NE-15)
RB-0215 Neals Landing, FL RB-0718 (SSE-18)
Dothan, AL (W-15)
RB-1215 Dothan, AL (W-18)
RB-1218 Webb, AL RB-1311 (WNW-1)
Haleburg, AL (N-12)
RB-1612 Community Station By sector (NNE-4)
RC-0104 (NE-4)
RC-0204 (ENE-4)
RC-0304 (E-5)
RC-0405 (ESE-5)
RC-0505 (SE-5)
RC-0605 (SSE-3)
RC-0703
TABLE 2-1 (SHEET 4 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I'j Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
(S-5)
RC-0805 (SSW-4)
RC-0904 (SW-5)
RC-1005 (WSW-4)
RC-1 104 (W-4)
RC-1204 (WNW-4)
RC-1304 (NW-4)
RC-1404 (NNW-4)
RC-1504 (N-5)
RC-1605 Of Special Interest:
Nearest Residence RC-1001 (SW-1.2)
City of Ashford, AL RC-1 108 (WSW-8.0)
WATERBORNE Aliquots taken with proportional semi-Surface Water continuous sampler, having a minimum Gamma isotopic analysis of each 4 week sampling frequency not exceeding two composite sample. Tritium analysis for hours, collected weekly for 4 week each quarterly composite.
composites and quarterly composites Indicator Station:
Paper Mill, (-3 miles WRI downstream of plant discharge, RM 40)
Control Station:
Upstream of WRB Andrews Lock and dam (-3 miles upstream of the plant intake, RM 47)
TABLE 2-1 (SHEET 5 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
Ground Water Grab sample quarterly Gamma isotopic, I-13 1 and tritium analyses of each sa mple quarterly_
Indicator Station:
Paper Mill Well WGI-07 (SSE-4)
Control Station:
Whatley Residence WGB-10 Well (SW-1.2)
River Sediment Grab sample semiannually Gamma isotopic analysis of each sample semiannually Indicator Station:
Downstream of plant RSI discharge at Smith's Bend (RM 41)a Control Station:
Upstream of plant RSB discharge at Andrews Lock & Dam Reservoir (RM 48)a INGESTION Milk Grab sample biweekly Gamma isotopic and I-13 1 analyses of each samplbieekly Control Station:
Robert Weir Dairy MB-0714 Donaldsonville, GA (SSE-14)
TABLE 2-1 (SHEET 6 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and Collection Frequency Type and Frequency of Analysis with Sample Types Identification and Locations (sector-miles)
Fish Grab sample semiannually for Game Fish Gamma isotopic analysis on the edible and Bottom Feeding Fish portions of each sample semiannually Indicator Stations:
Downstream of plant FGI & FBI discharge in vicinity of Smith's Bend (RM 4 1)b Control Station:
Upstream of plant FGB & FBB discharge in Andrews Lock &
Dam Reservoir (RM 4 8 )b Forage Grab sample from forage every 4 weeks.
Gamma isotopic analysis of each sample
_ every 4 weeks.
Indicator Station:
South Southeast FI-0701 Perimeter (SSE-1.0)
North Perimeter FI-1601 (N-0.8)
Control Station:
Dothan, AL (W-18)
TABLE 2-1 (SHEET 7 of 7)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NOTATIONS
- a. These collections are normally made at river mile 41.3 for the indicator station and river mile 47.8 for the control station; however, due to river bottom sediment shifting caused by high flows, dredging, etc., collections may be made from river mile 40 to 42 for the indicator station and from river mile 47 to 49 for the control station.
- b. Since a few miles of river water may be needed to obtain adequate fish samples, these river mile positions represent the approximate locations about which the catches are taken. Collections for the indicator station should be from river mile 37.5 to 42.5 and for the control station from river mile 47 to 52.
00
E Radiological Environmental Sampling Locations Indicator Control Community REMP Stations Near the TLD A
A k
Plant Perimeter Other 0
0*
TLD & Other 0Figure 2-1 2-9 coW
Radiological Environmental Sampling Locations Indicator Control Community REMP Stations 2 to 5 TLD A
A A
Miles From the Plant Other O
0 0I TLD & Other a
0 Figure 2-2 2-10 COTL
Radiological Environmental Sampling Locations Indicator Control Community REMP Stations Beyond TLD A
A k
5 Miles From the Plant Other 0*
TLD & Other a
a 9
Figure 2-3 2-1 1 CO2'
3.0 RESULTS
SUMMARY
In accordance with ODCM 7.1.2.1, the summarized and tabulated results for all of the regular samples collected for the year at the designated indicator, community and control stations are presented in Table 3-1. The format of Table 3-1 is similar to Table 3 of the Nuclear Regulatory Commission (NRC) Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program" Revision 1, November 1979. Results for samples collected at locations other than those listed in Table 2-1 are discussed in Section 4 under the particular sample type.
As indicated in ODCM 7.1.2.1, the results for naturally-occurring radionuclides that are also found in the plant's effluent releases must be reported along with man-made radionuclides. The radionuclide, Be-7, which occurs abundantly in nature has been found in the plant's liquid effluent. No other naturally occurring radionuclides are found in the plants' liquid effluent releases. Therefore, the only radionuclides of interest in the samples monitoring liquid releases (surface water, fish, and river sediment) are the man-made radionuclides and Be-7, while only the man-made radionuclides are of interest for the other REMP samples. During 2002, Be-7 was not found in any of the REMP samples monitoring liquid releases.
3-1
TABLE 3-1 (SHEET 1 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama It~)
Medium or Type and Minimum Indicator Indicator Location with the Community Control Pathway Total Detectable Locations Highest Annual Mean Locations Locations Sampled Number of Concentration Mean (b),
Mean (b),
Mean(b),
(Unit of Analyses (MDC) (a)
Range Name Distance Mean (b),
Range Range Measurement)
Performed (Fraction)
& Direction Range (Fraction)
(Fraction)
(Fraction)
Airborne Gross Beta 10 16.8 North 18.8 16.8 18.0 Particulates 525 5-32 Perimeter 5-32 6-33 5-42 (fCi/m3) 0.8 miles, N (52/52)
(158/158) 16/ 56)
Gamma Isotopic 40 I-131 70 NDM(c)
NA(d)
NDM NDM (0/16)
(0/12)
(0/12)
Cs-134 50 NDM NA NDM NDM (0/16)
(0/12)
(0/12)
Cs-137 60 NDM NA NDM NDM (0/16)
(0/12)
(0/12)
Airborne 1-131 70 NDM NA NDM NDM Radioiodine 420 (0/211)
(0/53)
(0/156)
(fCi/m3)
Direct Gamma NA 14.2 PIt. Perimeter 21.1 11.9 12.6 Radiation Dose 11-22 0.8 miles 20-22 10-16 10-16 (mR/91 days) 159 (64/64)
E (4/4)
(71/71)
(24/24)
Milk (pCi/i)
Gamma Isotopic 26 Cs-134 15 NA NA NA NDM (0/26)
Ba-140 60 NA NA NA NDM (0/26)
La-140 15 NA NA NA NDM
__ (0/26) 1-131 1
NA NA NA NDM 26 (0/26)
TABLE 3-1 (SHEET 2 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama It-,
Medium or Type and Minimum Indicator Indicator Location with the Community Control Pathway Total Detectable Locations Highest Annual Mean Locations Locations Sampled Number of Concentration Mean (b),
Mean (b),
Mean(b),
(Unit of Analyses (MDC) (a)
Range Name Distance Mean (b),
Range Range Measurement)
Performed (Fraction)
& Direction Range (Fraction)
(Fraction)
(Fraction)
Forage Gamma (pCi/kg wet)
Isotopic 42 1-131 60 NDM NA NA NDM (0/28)
(0/14)
Cs-134 60 NDM NA NA NDM (0/28)
(0/14)
Cs-137 80 NDM NA NA NDM (0/28)
(0/14)
Ground Water H-3 2000 NDM NA NA NDM (pCi/l) 8
_.A 04
_(
I-131 1
~
(0/4)?
Gamma Isotopic 8
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
TABLE 3-1 (SHEET 3 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farlcy Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Indicator Location with the Community Control Pathway Total Detectable Locations Highest Annual Mean Locations Locations Sampled Number of Concentration Mean (b),
Mean (b),
Mean(b),
(Unit of Analyses (MDC) (a)
Range Name Distance Mean (b),
Range Range Measurement)
Performed (Fraction)
& Direction Range (Fraction)
(Fraction)
(Fraction)
(0/4)
(0/4)
(0/4)
(0/4)
Surface Water H-3 3000 598 Ga Pacific 598 NA NDM (pCi/l) 8 567-628 Paper Co.
567-628 (0/4)
(2/4)
RM 40 (2/4 Gamma Isotopic 28 Be-7 124 (e)
(0/14)
(0/14)
(0/14)
(0/14)
(0/14)
(0/14)
(0/14)
(0/14)
TABLE 3-1 (SHEET 4 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama I;13 Medium or Type and Minimum Indicator Indicator Location with the Community Control Pathway Total Detectable Locations Highest Annual Mean Locations Locations Sampled Number of Concentration Mean (b),
Mean (b),
Mean(b),
(Unit of Analyses (MDC) (a)
Range Name Distance Mean (b),
Range Range Measurement)
Performed (Fraction)
& Direction Range (Fraction)
(Fraction)
(Fraction) 1-131 15 (f)
(0/14)
Cs-134 15 NDM NA NA NDM (0/14)
(0/14)
Cs-137 18 NDM NA NA NDM (0/14)
(0/14)
Ba-140 60 NDM NA NA NDM (0/14)
(0/14)
La-140 15 NDM NA NA NDM (0/14)
(0/14)
Bottom Gamma Feeding Fish Isotopic (pCi/kg wet) 4 Be-7 655 (e)
(0/2)
(0/2)
(0/2)
(0/2)
(0/2)
(0/2)
Cs-134 130 NDM NA NA NDM (0/2)
(0/2)
Cs-137 150 NDM NA NA NDM (0/2)
(0/2)
TABLE 3-1 (SHEET 5 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Medium or Type and Minimum Indicator Indicator Location with the Community Control Pathway Total Detectable Locations Highest Annual Mean Locations Locations Sampled Number of Concentration Mean (b),
Mean (b),
Mean(b),
(Unit of Analyses (MDC) (a)
Range Name Distance Mean (b),
Range Range Measurement)
Performed (Fraction)
& Direction Range (Fraction)
(Fraction)
(Fraction)
Game Fish Gamma (pCi/kg wet)
Isotopic 4
Be-7 655 (e)
(0/2)
(0/2)
(0/2)
(0/2)
(0/2)
(0/2)
Cs-134 130 NDM NA NA NDM (0/2)
(0/2)
Cs-137 150 NDM NA NA 10.1 (0/2) 10.1 - 10.1 (1/2)
River Shoreline Gamma Sediment Isotopic (pCi/kg dry) 4 Be-7 655 (e)
(0/2)
Cs-134 150 NDM NA NA NDM (0/2)
(0/2)
Cs-137 180 NDM NA NA NDM (0/2)
(0/2)
TABLE 3-1 (SHEET 6 of 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Farlcy Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama NOTATIONS
- a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3 (Table 4-1 of this report). The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.
- b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location that are detectable is placed in parentheses.
- c. No Detectable Measurement(s).
- d. Not Applicable.
- e. The EL has determined that this value may be routinely attained under normal conditions. No value is provided in Table 4-1 of this report.
- f. If a drinking water pathway exists, a value of 1 pCi/l would be used. See note b of Table 4-1 of this report.
4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations, or, community and control stations) and the calculated Minimum Detectable Difference (MDD) between these pairs, at the 99% Confidence Level (CL).. The MDD was determined using the standard Student's t-test. A difference in the mean values which was less than the MDD was considered to be statistically indiscernible.
The 2002 results were compared with past results, including those obtained during preoperation.
As appropriate, results were compared with their Minimum Detectable Concentrations (MDC) and Reporting Levels (RL) which are listed in Tables 4-1 and 4-2 of this report, respectively. The required MDCs were achieved during laboratory sample analysis. Any anomalous results are explained within this report.
Results of interest are graphed to show historical trends. The data points are tabulated and included in this report. The points plotted and provided in the tables represent mean values of only detectable results. Periods for which no detectable measurements (NDM) were observed, or periods for which values were not applicable (e.g., milk indicator, etc.), are plotted as and listed in the tables as O's.
Table 4-1 Minimum Detectable Concentrations (MDC)
Analysis Water Airborne Fish Milk Grass or Sediment (pCi/I)
Particulate (pCi/kg)
(pCi/l)
Leafy (pCi/kg) or Gases wVet Vegetation dry (fCi/m3)
(pCilkg) wet Gross Beta 4
10 H-3 2000 (a)
Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1 (b)70 1
60 Cs-134 15 50 130 15 60 150 Cs-137 18 60 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/l may be used.
(b) If no drinking water pathway exists, a value of 15 pCi/l may be used.
4-1
Table 4-2 Reporting Levels (RL)
Analysis Water Airborne Fish Milk (pCi/1)
Grass or (pCi/l)
Particulate (pCi/kg) wet Leafy or Gases Vegetation (fCi/m3)
(pCi/kg) wet H-3 20,000 (a)
Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 700 1-131 2 (b)900 3
100 Cs-134 30 10,000 1000 60 1000 Cs-137 50 20,000 2000 70 2000 Ba-140 200 300 La-140 100 400 (a) This is the 40 CFR 141 value for drinking water samples.
exists, a value of 30,000 maybe used.
If no drinking water pathway (b) If no drinking water pathway exists, a value of 20 pCi/l may be used.
Atmospheric nuclear weapons tests from the mid 1940's through 1980 distributed man-made nuclides around the world. The most recent atmospheric tests in the 1970's and in 1980 had a significant impact upon the radiological concentrations found in the environment prior to and during preoperation, and the earlier years of operation. Some long-lived radionuclides, such as Cs-137, continue to have some impact.
Significant upward trends also followed the Chernobyl incident, which began on April 26, 1986.
In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule are permitted if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or other just reasons.
Deviations from conducting the REMP as described in Table 2-1 are summarized in Table 4-3 along with their causes and resolutions.
4-2
All results were tested for conformance with Chauvenet's criterion (G. D. Chase and J. L. Rabinowitz, Principles of Radioisotope Methodology, Burgess Publishing Company, 1962, pages 87-90) to identify values which differed from the mean of a set by a statistically significant amount. Identified outliers were investigated to determine the reason(s) for the variation. If equipment malfunction or other valid physical reasons were identified as causing the variation, the anomalous result was excluded from the data set as non-representative. No data were excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.
4-3
TABLE 4-3 (SHEET 1 of 3)
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLE(S) 12/11/01-01/08/02 WRB River water sampling was not Sampler float trip error, Rearranged tubing to allow performed for about 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> caused by near-freezing better drainage and repositioned (from 12-25-2001/0530 to 12-temperatures.
sampler behind wall to help 26-2001/1230).
protect from cold weather.
12/11/01-01/08/02 WRB River water sampling was not Autosampler lost power Battery was replaced; performed for about 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> due to battery losing its autosampler batteries were (from 01-01-02/0330 to 01 charge.
serviced to establish an 02/1220).
expected life of 3 to 5 years.
01/01/02-01/08/02 PB-0215 and Air sampling was not performed Sample pump fuse blown, Fuse and sample pump motor IB-0215 for about 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.
due to pump motor were replaced and sampler binding.
returned to service.
02/12/02-02/19/02 PB-0215 and Correct air sample volume was Malfunction of sampler Sample pump turbine assembly IB-0215 not determined.
flow measuring device.
was replaced and sampler returned to service.
02/26/02-03/01/02 WRB Nonrepresentative water sample Subfreezing weather Sampler program was modified was collected during this period.
affected flow through to indicate longer tube length, sample line.
which helps prevent ice clogging by increasing line flushing and sampling time.
Sampling STP was modified to address weather effect.
02/26/02-03/05/02 PB-0718 and Air sampling was not performed Loss of power to sample Sampler restarted automatically IB-0718 for about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
pump due to local power upon restoration of power to interruption.
sampler.
04/09/02-04/16/02 PC-1 108 Insufficient volume of air was Loss of power to sample Fuse was replaced and sampler sampled (less than 20% of pump due to blown fuse.
returned to service.
normal sample volume).
TABLE 4-3 (SHEET 2 of 3)
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLE(S) 04/02/02-04/30/02 WRB Nonrepresentative water sample Float trip caused sampler to Alarm was cleared to resume was collected.
overfill thereby spilling part operation and the sampler was of sample.
replaced the following day.
04/30/02-05/07/02 PI-0501 and Air sampling was not performed Power to sample pump was Sampler automatically II-0501 for about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
turned off during restarted upon restoration of maintenance of heat power. PM task planning was detectors.
modified to note that the power source was shared by air sampler 0501.
04/30/02-05/07/02 PB-0718 and Air sampling was not performed Loss of power to sample Sampler resumed operation IB-0718 for about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
pump due to local power upon restoration of power.
interruption.
05/14/02-05/21/02 PI-1601 and Insufficient volume of air was Loss of power to sample Fuse was replaced and sampler II-1601 sampled (less than about half of pump due to blown fuse.
returned to service.
normal sample volume).
05/28/02-06/04/02 PB-1218 and Insufficient volume of air was Loss of power to sample Fuse was replaced and sampler IB-1218 sampled (less than about 25% of pump due to blown fuse.
returned to service.
normal sample volume).
06/11/02-06/18/02 PI-1601 and Insufficient volume of air was Sample pump motor Sample pump was replaced II-1601 sampled (less than about half of tripped.
and satisfactory operation normal sample volume).
confirmed.
Quarter 2, 2002 RC-405 Direct radiation dose was not TLD support pole was down TLD support pole was erected determined for this station.
and TLD missing at end of and new TLD attached.
quarter.
TABLE 4-3 (SHEET 3 of 3)
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM COLLECTION AFFECTED DEVIATION CAUSE RESOLUTION PERIOD SAMPLE(S) 07/16/02-07/23/02 PI-1101 and Air sample was not continuously Loss of power to sample Fuse was replaced and sampler 11-1101 collected throughout sample pump due to blown fuse.
returned to service.
period.
07/30/02-08/06/02 PC-I 108 Air sample was not continuously Air sampler was inoperative Fuse and sample pump were collected throughout sample due to blown fuse caused by replaced and sampler returned period.
sample pump binding.
to service.
09/17/02-10/15/02 WRB River water sampler missed 19 Loss of power to sampler Battery replaced and system of about 113 aliquots which due to dead battery.
observation increased to resulted in a nonrepresentative confirm satisfactory operation.
sample Quarter 3, 2002 RC-1204 TLD was not on station for TLD was discovered TLD was replaced and complete sampling period.
missing second week of replacement remained on quarter.
station for rest of quarter.
11/12/02-12/10/02 WRI River water sampler missed 10 Inadequate power to the Sample pump and battery were of about 83 aliquots which sample pump due to low replaced and sampler returned resulted in a nonrepresentative battery. (Pump was noisy to service.
sample.
and may have been pulling excessive current.)
4.1 Land Use Census In accordance with ODCM 4.1.2, a land use census was conducted during the month of June, 2002. The land use census is used to determine the locations of the nearest permanent residence and milk animal in each of the 16 compass sectors within a distance of 5 miles. A milk animal is a cow or goat producing milk for human consumption. The 2002 survey revealed no changes from the 2001 survey. No milk animals were found within a 5 mile distance. The census results are tabulated in Table 4.1-1.
Table 4.1-1 LAND USE CENSUS RESULTS Distance in Miles to the Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL N
2.6 none NNE 2.5 none NE 2.4 none ENE 2.4 none E
2.8 none ESE 3.0 none SE 3.4 none SSE none none S
4.3 none SSW 2.9 none SW 1.2 none WSW 2.4 none W
1.3 none WNW 2.1 none NW 1.5 none NNW 2.0 none The Houston County, Alabama and the Early County, Georgia Extension Agents were contacted for assistance in locating commercial dairy farms and privately owned milk animals within 5 miles of the plant. A list of commercial dairy farms in Houston County was provided; there are no commercial dairy farms in Early County. Neither agent knew of privately owned milk animals within 5 miles of FNP. In addition, field surveys were conducted in the plant vicinity along the state and county highways and the interconnecting secondary roads.
No milk animals were found within 5 miles of the plant.
ODCM 4.1.2.2.1 requires a new controlling receptor to be determined, if the land use census identifies a location that yields a calculated receptor dose greater than the one in current use. Neither current sampling locations nor the controlling receptor were affected by the 2002 land use census results. The current controlling receptor as described in ODCM Table 3-7 remains a child in the SW Sector at 1.2 miles.
4-7
4.2 Airborne As specified in Table 2-1 and shown in Figures 4.2-1 and 4.2-2, airborne particulate filters and charcoal canisters are collected weekly at 4 indicator, 3 control and 3 community stations. Particulate filters are collected at all of the stations while the charcoal canisters are collected at all but 2 of the community stations. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulates and, as appropriate, an activated charcoal canister is placed in series to adsorb radioiodine.
Each particulate filter is counted for gross beta activity.
A quarterly gamma isotopic analysis is performed on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for I-131.
As provided in Table 3-1, the 2002 annual average weekly gross beta activity was 16.8 fCi/m3 at the indicator stations and 18.0 fCi/m3 at the control stations.
However, the difference of 1.2 fCi/m3 between the two averages is not statistically discernible since the MDD for these two average values is 1.7 fCi/m3.
As shown in Table 3-1, the 2002 annual average weekly gross beta concentration was 16.8 fCi/m3 at community stations. Although the community stations average was 1.2 fCi/m3 less than the average for the control stations, the difference is not statistically discernible since it is less than the MDD of 1.8 fCi/m3 between the two averages.
Due to the weapons tests during preoperation and the early years of operation, the average gross beta concentrations were 5 to 10 times greater than those currently being measured. By the mid 1 980s, the readings had diminished to about half the current levels. These annual averages approximately doubled as a consequence of the Chernobyl incident in 1986; this impact faded away in approximately 2 years.
The installation of new air monitoring equipment in 1992 yielded an approximate factor of 2 increase in the readings. Since then, the levels have been fairly flat.
The historical trending of the average weekly gross beta air concentrations for each year of operation and the preoperational period at the indicator, control and community stations is plotted in Figure 4.2-1 and listed in Table 4.2-1. In general, there is close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plant's contribution to gross beta concentration in air is insignificant.
4-8
Figure 4.2-1 Average Weekly Gross Beta Air Concentration 1000 0
I--
10 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year l
--N-Indicator A
Control Community E
d E
d Cof i
4-9
Table 4.2-1 Average Weekly Gross Beta Air Concentration Period Indicator Control Community (fCi/m3)(fCi/m3)(fCil m
Pre-op 90 92 91 1977 205 206 206 1978 125 115 115 1979 27.3 27.3 28.7 1980 29.7 28.1 29.2 1981 121 115 115 1982 20.0 20.4 21.0 1983 15.5 14.1 14.5 1984 10.2 12.6 10.5 1985 9,0 9.6 10.3 1986 10.5 15.8 12.5 1987 9.0 11.0 17.0 1988 8.0 8.0 10.0 1989 7.0 7.0 8.0 1990 10.0 10.0 10.0 1991 9.0 10.0 8.0 1992 15.0 17.9 18.5 1993 19.1 22.3 22.4 1994 19.0 20.0 19.0 1995 21.7 22.9 21.6 1996 20.3 22.3 23.5 1997 21.1 21.6 22.4 1998 20.6 19.3 22.0 1999 20.5 22.1 25.2 2000 20.9 20.8 23.6 2001 16.3 17.2 17.3 2002
- 16.8 18.0.
16.8 4-10
During 2002, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters.
This has generally been the case since the impact of the weapons tests and the Chernobyl incident have faded.
During preoperation and the early years of operation, a number of fission and activation products were detected. Durin3g preoperation, the average levels for Cs-134 and Cs-137 were 22 and 9 fCi/m, respectively.
In 1986, as a consequence of the Chernobyl incident, Cs-134 and Cs-137 levels of 3 to 4 fCi/m3 were found. The MDC and RL for Cs-134 are 50 and 10,000 fCi/m3 and the MDC and RL for Cs-137 are 60 and 20,000 fCi/m3 respectively.
The historical trending of the annual detectable Cs-137 concentrations for the indicator, control and community stations is provided in Figure 4.2-2 and Table 4.2-2. The trend has been generally downward since preoperation and no positive results have been observed since 1988.
Figure 4.2-2 Average Annual Cs-137 Concentration in Air 20 V
15 E
C
- 0. 10 2
C 0
0 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 Year 90 91 92 93 94 95 96 97 98 99 00 01 02
=
Cd5 l
+
Indicator Control
-- *-- Community I
4-11
Table 4.2-2 Average Annual Cs-137 Concentration in Air Period Indicator Control Community l_(fCi/m3) l (fCi/m3)
(fCi/m3)
Pre-op 8
13 7
1977 3.0 3.0 3.0 1978 4.0 5.0 5.0 1979 2.0 0
2.0 1980 1.0 2.0 1.8 1981 2.8 3.2 2.6 1982 1.7 0
1.0 1983 1.0 0
1.0 1984 0
1.5 0
1985 1.0 1.0 1.0 1986 3.3 3.4 2.7 1987 0
0 0
1988 0
0 1
1989 0
0 0
1990 0
0 0
1991 0
0 0
1992 0
0 0
1993 0
0 0
1994 0
0 0
1995 0
0 0
1996 0
0 0
1997 0
0 0
1998 0
0 0
1999 0
0 0
2000 0
0 0
2001 0
0 0
2002 0AD 0
0-4-12
Airborne 1-131 was not detected in the charcoal canisters during 2002. In 1978, levels between 40 and 50 fCi/m3 were found in a few samples and attributed to the Chinese weapons tests; then after the Chernobyl incident, levels up to a few hundred fCi/m3 were found in some samples.
At no other times has airborne 1-131 been detected in the environmental samples. The MDC and RL for airborne 1-131 are 70 and 900 fCi/m3 respectively.
Table 4-3 lists REMP deviations that occurred during 2002.
Not all of the deviations listed in Table 4-3 required data to be excluded from the calculation of the mean values.
For air samples, five air filter sample results and four air charcoal sample results were excluded for failing Chauvenet's Criterion following equipment malfunctions:
For the period 2/12 - 2/19, Station 0215 experienced a malfunction of the sampler flow measuring device, resulting in the inability to correctly determine sample volume.
For the period 2/26 - 3/5, Station 0718 experienced short run time due to a power supply failure.
For the period 4/9 - 4/16, Station 1108, which has an air particulate filter but no charcoal filter, experienced short run time due to a blown fuse.
For the period 5/14 - 5/21, Station 1601 experienced short run time due to a blown fuse.
For the period 5/28 - 6/4, Station 1218 experienced short run time due to a blown fuse.
4-13
4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors composed of calcium sulfate crystals (with thulium impurity). The gamma dose at each station is based upon the average readings of the phosphors from the two badges. The two badges for each station are placed in thin plastic bags for protection from moisture while in the field. The badges are nominally exposed for periods of a quarter of a year (91 days). An inspection is performed near mid-quarter to assure that all badges are on-station and to replace any missing or damaged badges.
Two TLD stations are established in each of the 16 sectors, to form 2 concentric rings. The inner ring stations are located near the plant perimeter, as shown in Figure 2-1, and the outer ring stations are located at distances of approximately 3 to 5 miles from the plant, as shown in Figure 2-2. The stations forming the inner ring are designated as the indicator stations. The 6 control stations are located at distances greater than 10 miles from the plant, as shown in Figure 2-3. Stations are also provided which monitor special interest areas: the nearest occupied residence (SW at 1.2 miles), as shown in Figure 2-1, and the city of Ashford (WSW at 8 miles), as shown in Figure 2-3. The 16 outer ring stations and the 2 special interest stations are designated as community stations.
As provided in Table 3-1, the average quarterly exposure measured at the indicator stations (inner ring) during 2002 was 1.5 mR greater than that acquired at the control stations. Although this small difference is greater than the MDD of 1.17 mR and is therefore statistically discernible, it is consistent with the difference between indicator and control station locations observed during preoperation. The difference of 0.7 mR found between the control stations and community stations is not statistically discernible since the difference is less than the MDD of 0.96 mR.
The historical trending of the average quarterly exposures in units of mR at the indicator, control and community locations are plotted in Figure 4.3-1 and listed in Table 4.3-1. During preoperation the average exposure at the indicator stations was 1.2 mR greater than that for the control stations, but the average over the entire period of operation was only 1.1 mR greater.
During preoperation, the average exposure at the control stations was 1.3 mR greater than that at the community stations and the average over the period of operation is 1.5 mR greater. This supports the position that the plant is not contributing significantly to direct radiation in the environment.
Table 4-3 lists the REMP program deviations that occurred in 2002.
Two deviations involved measurement of direct radiation.
However, only one deviation led to the loss of direct radiation data. The TLDs at station RC-405 were missing at the end of the second quarter. Since no data was available for this station, the results for this station are excluded for the second quarter. Early in the third quarter, the TLDs at station RC-1204 were discovered missing. The missing TLDs were replaced for the remainder of the third quarter. The results obtained with the replacement badges passed Chauvenet's Criterion. Therefore, this data was retained in the data base.
4-14
Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 30 25 20 E
2 15 0
0
- w. 10 5
0 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year I
+ Indicator Control Community I
coG 4-15
Table 4.3-1 Average Quarterly Exposure from Direct Radiation Period l Indicator (mR) l Control (mR) l Community
_________J___
____j J
(mR)
Pre-op 12.6 11.4 10.1 1977 10.6 12.2 10.6 1978 15.0 13.5 12.0 1979 20.3 18.7 15.2 1980 21.9 21.6 18.5 1981 16.5 14.9 14.5 1982 15.5 14.7 13.0 1983 20.2 20.2 17.4 1984 18.3 16.9 15.3 1985 21.9 22.0 18.0 1986 17.8 17.7 15.1 1987 20.8 20.0 18.0 1988 21.5 19.9 18.5 1989 18.0 16.2 15.3 1990 18.9 16.4 15.8 1991 18.4 16.1 16.1 1992 16.1 13.6 13.5 1993 17.4 15.9 15.6 1994 15.0 13.0 12.0 1995 14.0 12.5 11.8 1996 14.2 12.7 11.9 1997 15.3 13.9 11.9 1998 16.2 14.6 13.9 1999 14.7 13.4 12.6 2000 15.5 14.1 13.5 2001 14.9 13.4 12.7 2002 14.1..
L.
12.6' 11.9 4-16
The standard deviation limit of 1.4 is calculated using a method developed by the American Society for Testing and Materials (ASTM) (ASTM Special Technical Publication 15D, ASTM Manual on Presentation of Data and Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976). The calculation is based upon the standard deviations obtained by the EL with the Panasonic UD-814 badges during 1992. This limit serves as a flag to initiate an investigation.
To be conservative, readings with a standard deviation greater than 1.4 are excluded since the high standard deviation is interpreted as an indication of unacceptable variation in TLD response.
The TLD results from the following stations were excluded from the data set because their standard deviations were greater than 1.4:
Quarter 1 - None Quarter 2 - None Quarter 3 - RB-0215B, RB-1218A, RC-1 108A Quarter 4 - RC-1204A For the four TLD stations where these badges were located, only the reading of the companion badge was used to determine the quarterly exposure for the station.
The affected badges were visually inspected under a microscope and the glow curve and test results for the anneal data and the element correction factors were reviewed. No reason was found for the high standard deviations.
4-17
4.4 Milk In accordance with Table 2-1, milk samples are collected biweekly from a control location. No indicator station (a location within five miles of the plant) has been available for milk sampling since 1987.
As discussed in Section 4.0, no milk animals were found within five miles of the plant during the 2002 land use census.
Gamma isotopic analyses were performed on each sample as specified in Table 2-1. No man-made radionuclides were identified from the gamma isotopic analysis of the milk samples during 2002. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. The historical trending of the average annual detectable Cs-137 concentration in milk samples is shown in Figure 4.4-1 and Table 4.4-1.
Cs-137 has not been detected in milk since 1986. Its presence at that time is attributed to the Chernobyl incident.
The earlier detectable results were attributed to the weapons tests.
Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 45 35 G
30-
.2 1 5 -
0 00 0
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year C 07 Indicator Control
-MDC 4-18
Table 4.4-1 Average Annual Cs-137 Concentration in Milk Period Indicator
[
Control l
(pCiIl) t (pCi/l)
Pre-op 32 18 1977 41 20 1978 15 17 1979 0
0 1980 0
0 1981 0
23.0 1982 0
0 1983 0
0 1984 0
0 1985 0
0 1986 0
16.5 1987 0
0 1988 0
0 1989 0
0 1990 0
0 1991 0
0 1992 0
0 1993 0
0 1994 0
0 1995 0
0 1996 0
0 1997 0
0 1998 0
0 1999 0
0 2000 0
0 2001 0
0
- .2002 0
0 4-19
As specified in Table 2-1, each sample was analyzed for I-13 1, which has not been detected in milk since 1986. The presence of 1-131 at that time is attributed to the Chernobyl incident. The earlier detectable results were attributed to the weapons tests. The MDC and RL for 1-131 are 1 and 3 pCi/l, respectively. Figure 4.4-2 and Table 4.4-2 show the historical trending of the average annual detectable I-131 concentration in milk samples.
Figure 4.4-2 Average Annual 1-131 Concentration in Milk 40 U
Ya l-a~20-0 10 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year Indicator
-U-F-Control IVDC RL A
d Ot 4-20
Table 4.4-2 Average Annual 1-131 Concentration in Milk Period Indicator Control
__(pCiII)
J(pCi/i)
Pre-op 41 14 1977 20 2.6 1978 30 11 1979 0
0 1980 0
0 1981 0
0 1982 0
0 1983 0
0 1984 0
0 1985 0
0 1986 0
5.0 1987 0
0 1988 0
0 1989 0
0 1990 0
0 1991 0
0 1992 0
0 1993 0
0 1994 0
0 1995 0
0 1996 0
0 1997 0
0 1998 0
0 1999 0
0 2000 0
0 2001 0
0 20021 00 -____-
_:0. -:::
4-21
4.5 Forage In accordance with Table 2-1, forage samples are collected every 4 weeks at two indicator stations on the plant perimeter, and at one control station located approximately 18 miles west of the plant, in Dothan. Gamma isotopic analyses are performed on each sample.
No manmade radionuclide was found in forage at an indicator or control station during 2002. During preoperation and the years of operation through 1986 (the year of the Chernobyl incident), Cs-137 was typically found in about a third of the 35 to 40 forage samples collected per year. In 1987 and 1988 the number dropped to about a seventh of the total samples and from 1989 through 1994, it was only found in one or two samples every year. Since 1994, Cs-137 has been detected in only two samples, one indicator and one control. The MDC and RL for Cs-137 in forage are 80 and 2000 pCi/kg wet, respectively. Table 4.5-1 presents the average detectable results of Cs-137 found in forage over the life of the plant and Figure 4.5-1 shows the historical trending of this data.
Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 90 I
I I
80 4'
70 4-0 7 50
.0 40 0
50 10 0
II II II II II II
.I I
I I
I I
_I L 9
~_ABAt Ir_
i t I I_
I _ I I Ir I -_
i-t
.1 M.
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year l +-Indicator Control MDC 4-22 C(Ci~
Table 4.5-1 Average Annual Cs-137 Concentration in Forage Period 1
Indicator Control l_
(pCiLkg) wet J
(pCi/kg) wet Pre-op 59.4 48.6 1977 25.0 0
1978 52.5 32.5 1979 37.2 32.8 1980 36.2 35.9 1981 32.1 43.1 1982 25.0 33.1 1983 16.8 23.6 1984 19.9 22.8 1985 22.2 9.5 1986 41.2 36.2 1987 46.8 0
1988 33.6 31.7 1989 35.7 0
1990 56.0 0
1991 0
12.9 1992 0
43.0 1993 0
24.0 1994 0
24 1995 0
0 1996 0
0 1997 52.6 0
1998 0
22.7 1999 0
0 2000 0
0 2001 0
0 2002
.0-0 4-23
During preoperation and in the early years of operation, I-131 was found in 10%
to 25% of the forage samples at very high levels which ranged from around 100 to 1,000 pCi/kg wet.
In 1986 (Chernobyl incident), 1-131 reappeared after not having been detected for 3 years. The MDC and RL for 1-131 are 60 and 100 pCi/kg wet, respectively. Table 4.5-2 lists the average detectable results of I-131 found in forage over the life of the plant and Figure 4.5-2 plots the historical trending of this data.
I-131 has not been detected in forage samples since the 1986 Chernobyl accident.
Figure 4.5-2 Average Annual 1-131 Concentration in Forage 1000 900 4-Sa) 0)
C.,
0.
0 (U
B.6-0 C0 C.
800 700 600 500 400 BAA l
I I I I I --
I I I_____1
__ __ _ _ _ _I g~~
I 300MM
_f ffI a
_ _ _i
_ _ _ _i
_ _ _ _i i
200 100 0
1I. II[-
A I
I I I I I _ _ 4 -
I I I I I I I _ _ I I I I Po 77 78 79 80 81 82 83 84 85 86 87 88 Year 89 90 91 92 93 94 95 96 97 98 99 00 01 02
+
Indicator
-d-Control MDC RL I 4-24 GIC
Table 4.5-2 Average Annual 1-131 Concentration in Forage Period 1
Indicator 1
Control l
(pCi/kg) wet l
(pCi/kg) wet Pre-op 405 486 1977 971 654 1978 220 240 1979 0
0 1980 0
0 1981 21.4 0
1982 46.4 0
1983 0
0 1984 0
0 1985 0
0 1986 184 0
1987 0
0 1988 0
0 1989 0
0 1990 0
0 1991 0
0 1992 0
0 1993 0
0 1994 0
0 1995 0
0 1996 0
0 1997 0
0 1998 0
0 1999 0
0 2000 0
0 2001 0
0 2002:
0 0
These forage analyses results show the impact of the weapons tests during preoperation and the early years of operation and of the Chernobyl incident in 1986 and for a few years afterwards. The impact is reflected by the number of different radionuclides detected, the fraction of samples with detectable results, as well as the magnitude of the results. During preoperation and for the first few years of operation, 11 different radionuclides from fission and activation products were detected. By 1985, only 2 different radionuclides were detected and the fraction of samples with detectable results had diminished. In 1986, the same two nuclides as seen in 1985 appeared at a significantly higher magnitude and 1-131 reappeared. In the years following 1986, only Cs-137 has been found in forage and it has been found in a decreasing fraction of the samples.
4-25
4.6 Ground Water In the FNP environs, there are no true indicator sources of ground water. A well, located about four miles south-southeast of the plant on the east bank of the Chattahoochee River, serves Georgia Pacific Paper Company as a source of potable water and is designated as the indicator station. A deep well located about 1.2 miles southwest of the plant, which supplies water to the Whatley residence, is designated as the control station. Samples are collected quarterly and analyzed for gamma isotopic, 1-131 and tritium as specified in Table 2-1. No radionuclides were found in ground water samples in 2002.
In 1983, 1985, and 1986, Cs-134 was detected in single samples at levels ranging from 3 to 13 pCi/l. The MDC and RL for Cs-134 in water are 15 and 30 pCi/l, respectively.
During preoperation, Cs-137 was detected in two of the samples at levels of 15 and 17 pCi/l. Then in 1984 and 1985, Cs-137 was again detected in a few samples with levels ranging from 4 to 5 pCi/l. The MDC and RL for Cs-137 in water are 18 and 50 pCi/I, respectively.
1-131 has never been detected in ground water samples. Tritium has not been detected in any sample since 1983. There have been no radionuclides detected in any of the ground water samples since 1986. The MDC and RL for tritium are 2,000 and 20,000 pCi/l, respectively.
Figure 4.6-1 and Table 4.6-1 show the historical trending of the average annual detectable tritium concentration in ground water.
Figure 4.6-1 Average Annual H-3 Concentration in Ground Water 2500 2000 0.4) 10900 X;EEWSWRN 1500 0 00 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year l +Indicator Control MDC 4-26 C) I
Table 4.6-1 Average Annual H-3 Concentration in Ground Water Period Indicator Control l
(pCiEl)
I (pCi/l)
Pre-op 150 240 1977 0
0 1978 0
240 1979 0
0 1980 124 0
1981 264 0
1982 240 0
1983 360 341 1984 0
0 1985 0
0 1986 0
0 1987 0
0 1988 0
0 1989 0
0 1990 0
0 1991 0
0 1992 0
0 1993 0
0 1994 0
0 1995 0
0 1996 0
0 1997 0
0 1998 0
0 1999 0
0 2000 0
0 2001 0
0 2002 0
4-27
4.7 Surface Water As specified in Table 2-1 and shown in Figure 2-2, water samples are collected from the Chattahoochee River at a control station approximately 3 miles upstream of the intake structure and at an indicator station approximately 4 miles downstream of the discharge structure. Small quantities are collected during the week at periodic intervals using automatic samplers. For each station, one liter from each of four consecutive weekly samples is combined into a composite sample which is analyzed for gamma emitters.
In addition, 0.075 liters is collected from 13 consecutive weekly samples for each station to form composite quarterly samples which are analyzed for tritium.
No detectable results have been found from these gamma isotopic analyses since 1988. During preoperation and in every year of operation through 1988 (except 1979 and 1980), a few samples showed at least one of nine different activation or fission products at levels less than or on the order of their MDCs.
During preoperation, Cs-137 was found in about 3% of the samples. From 1981 through 1988, it was found in about 15% of the samples. Cs-134 was found in about 15%
of the samples from 1981 to 1986. All of these gamma emitters are attributed to the weapons tests and the Chernobyl incident.
As shown in Table 3-1, tritium was found in two of the composite samples collected at the indicator station during 2002. The average concentration was 598 pCi/I. No tritium was found at the control station during 2002. Therefore, this small tritium concentration, which is about 2% of the RL, may be attributed to plant releases.
Historical trending of the detectable concentrations of tritium in surface water is provided in Figure 4.7-1 and Table 4.7-1. The slightly elevated plot of the indicator stations is indicative of plant tritium contributions to surface water, although it is noteworthy that the annual average levels are less than 10% of the MDC and less than 1% of the RL. The MDC and RL for tritium in surface water are 3000 and 30,000, respectively.
As shown in Table 4-3, there were six deviations involving surface water sampling in 2002. However, none of deviations resulted in excluded data.
4-28
Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 3500 3000 2500
.2 0
2000----
0 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 9 Year l + Indicator
- Control MDC 8 99 00 01 02 4-29
Table 4.7-1 Average Annual H-3 Concentration in Surface Water Period 1
Indicator 1
Control l
(pCi/l)
J (pCi/l)
Pre-op 200 170 1977 300 160 1978 230 250 1979 169 135 1980 221 206 1981 294 162 1982 300 132 1983 434 111 1984 333 152 1985 351 105 1986 478 272 1987 291.8 116.5 1988 293.3 0
1989 253.8 0
1990 166 0
1991 122 0
1992 360.5 134 1993 388.8 0
1994 0
0 1995 257 0
1996 386 0
1997 0
0 1998 415 0
1999 314 0
2000 424 212 2001 252 0
-:2002
'598 0
4-30
4.8 Fish Two types of fish (bottom feeding and game) are collected semiannually from the Chattahoochee River at a control station several miles upstream of the plant intake structure and at an indicator station a few miles downstream of the plant discharge structure. These locations are shown in Figure 2-2. Gamma isotopic analysis is performed on the edible portions of each sample as specified in Table 2-1.
As provided in Table 3-1, Cs-137 was the only radionuclide of interest that was found from the gamma isotopic analysis of fish samples in 2002.
No radionuclides were detected in bottom feeding fish. In one game fish sample, collected at the control location, Cs-137 was detected at a concentration of 10.1 pCi/kg-wet. No radionuclides were detected in game fish samples collected at the indicator station. Since no radionuclides were detected in fish samples collected at the indicator station, no Cs-137 in fish should be attributed to plant releases.
Historically, Cs-137 has been found in approximately 30% of the bottom feeding fish samples and in 80% of the game fish samples. Figures 4.8-1 and 4.8-2 and Tables 4.8-1 and 4.8-2 provide the historical trending of the average annual detectable concentrations of Cs-137 in pCi/kg wet in bottom feeding and game fish, respectively. Since the early 1980s, values have generally decreased for both indicator and control groups, with the exception of the bottom feeding fish collected at the indicator station in 1993. While some contribution from the plant cannot be ruled out, most of the Cs-137 in these samples may be attributed to the nuclear weapons tests and the Chernobyl incident, as evidenced by the normally close agreement between the control and indicator station results.
4-31
Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 3.
0
.X C0.
4-0 Ca) 0C0 200 150-100 0
1 1 m 1 I I
I I
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year 91 92 93 94 95 96 97 98 99 00 01 02 I
+ Indicator Control MDC 4-32 cy3
Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish Period Indicator l
Control l
(pCi/kg) wet l
(pCi/kg) wet Pre-Op 69 48 1977 0
0 1978 0
0 1979 38 30 1980 92 90 1981 96 106 1982 51.5 39.0 1983 0
0 1984 0
19 1985 0
0 1986 28 25 1987 25 19 1988 25.5 22.0 1989 0
0 1990 0
0 1991 0
0 1992 0
0 1993 208 0
1994 15.9 10.3 1995 0
14.2 1996 16.4 9.9 1997 10.9 7.7 1998 0
0 1999 19.2 0
2000 0
0 2001 9.8 0
- .2002 i
0-0 4-33
Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 50 C.
0 10 1010 50 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 Year
+-Indicator
- Control MDC cr
4-34
Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish Period Indicator l
Control (pCi/kg) wet l
(pCi/kg) wet Pre-op 84 60 1977 95 48 1978 0
0 1979 111 83.5 1980 289 316 1981 189 126 1982 76 77 1983 57 56.5 1984 42 26 1985 84 44 1986 51 35 1987 83 46 1988 42 33 1989 38 29 1990 28 0
1991 36 24 1992 32.5 28 1993 34 0
1994 19 16 1995 17.9 18.2 1996 19.6 23.1 1997 25.9 0
1998 52 20 1999 36.9 15.9 2000 22.9 12.5 2001 22.4 12.3 2002
-0; 10.1:
Radionuclides of interest other than Cs-137 have been found in only a few samples in the past. The following table provides a summary of the results in pCi/kg wet compared with the applicable MDCs.
YEAR Nuclide Fish Type Indicator Control MDC (pCilkg)
(pCilkg)
(pCi/kg) 1978 Ce-144 Bottom Feeding 0
200 1981 Nb-95 Bottom Feeding 38 0
50 (a) 1982 Nb-95 Game 31 0
50 (a) 1986 Co-60 Game 25 0
130 (a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report) 4-35
4.9 Sediment River sediment samples are collected semiannually on the Chattahoochee River at a control station which is approximately 4 miles upstream of the intake structure and at an indicator station which is approximately 2 miles downstream of the discharge structure as shown in Figure 2-2. A gamma isotopic analysis is performed on each sample as specified in Table 2-1.
During 2002, no radionuclides of interest were detected.
Historically, Be-7, Cs-134, Cs-137, and Nb-95 have been detected in some samples. These positive results were generally for samples collected at the control station. A summary of the positive historical results for these nuclides along with their applicable MDCs in units of pCi/kg dry is provided in Table 4.9. Cs-134 and Cs-137 data are plotted in Figures 4.9-1 and 4.9-2, respectively.
Table 4.9 Sediment Nuclide Concentrations Nuclide YEAR Indicator (pCi/kg)
Control (pCi/kg)
MDC (pCi/kg)
Be-7 1985 535 945 655 (a)
Cs-134 1987 0
45 150 1989 0
48 1992 138 51 1993 94 105 Cs-137 1981 0
185 180 1985 0
97 1989 0
39 1994 29 11 1996 11.8 0
Nb-95 1981 52 113 50 (a)
(a) Determined by the EL. Not defined in ODCM Table 4-3 (Table 4-1 of this report).
4-36
Figure 4.9-1 160 140
-n 120 0
Q. 100 C0 80
= o I.-
A -
CD 6
C) 0 U
40 20 0
Average Annual Cs-134 Concentration in Sediment I I I1 I1 I
I I
t I~,
t I
b I
I InL Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year 91 92 93 94 95 96 97 98 99 00 01 02 l
Indicator
-Control MDC The positive results for Cs-134 appear mostly at the control station. Due to its relatively short half-life of approximately 2 years, the positive results may be attributed to the Chernobyl incident. The overall plotting of the positive results does not show any discernible trends.
4-37 C1-
Figure 4.9-2 200 180 160 140 0
Q 120 0
- . 100 c 80 0
O 60 0
0 40 20 0
Average Annual Cs-137 Concentration in Sediment I I II I I I
I I
I
_I I
I I I
I I I I
I I
I I I I
t
__s_____I I
I I
I I
\\ _
I I
I I
A Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year 91 92 93 94 95 96 97 98 99 00 01 02 Il Indicator
-d Control MDC Cs-137 appears to be trending down since the ceasing of above ground weapons testing and the majority of the positive results appear at the control stations.
Therefore in general, the positive results can be attributed to the weapons tests and the Chernobyl incident.
4-38
=
C\\(D
5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with ODCM 4.1.3, the EL participates in an ICP that satisfies the requirements of Regulatory Guide 4.15, Revision 1, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", February 1979. The guide indicates the ICP is to be conducted with the Environmental Protection Agency (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check) Program or an equivalent program, and the ICP should include all of the determinations (sample medium/radionuclide combinations) that are offered by the EPA and included in the REMP.
The ICP is conducted by Analytics, Inc. of Atlanta, Georgia.
Analytics has a documented Quality Assurance (QA) program and the capability to prepare Quality Control (QC) materials traceable to the National Institute of Standards and Technology. The ICP is a third party blind testing program which provides a means to ensure independent checks are performed on the accuracy and precision of the measurements of radioactive materials in environmental sample matrices.
Analytics supplies the crosscheck samples to the EL which performs the laboratory analyses in a normal manner.
Each of the specified analyses is performed three times. The results are then sent to Analytics who performs an evaluation which may be helpful to the EL in the identification of instrument or procedural problems.
The samples offered by Analytics and included in the EL analyses are gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples.
The accuracy of each result is measured by the normalized deviation, which is the ratio of the reported average less the known value to the total error. The total error is the square root of the sum of the squares of the uncertainties of the known value and of the reported average. The uncertainty of the known value includes all analytical uncertainties as reported by Analytics. The uncertainty of the reported average is the propagated error of the values in the reported average by the EL.
The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation of the reported result divided by the reported average.
An investigation is undertaken whenever the absolute value of the normalized deviation is greater than three or whenever the coefficient of variation is greater than 15% for all radionuclides other than Cr-51 and Fe-59. For Cr-51 and Fe-59, an investigation is undertaken when the coefficient of variation exceeds the values shown as follows:
Nuclide Concentration
- Total Sample Activity Percent Coefficient (pCi) of Variation Cr-51
<300 NA 25 Cr-51 NA
>1000 25 Cr-51
>300
<1000 15 Fe-59
<80 NA 25 Fe-59
>80 NA 15
- For air filters, concentration units are pCi/filter.
For all other media, concentration units are pCi/liter (pCi/l).
5-1
As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's participation in the ICP is provided in Table 5-1 for: the gross beta and gamma isotopic analyses of an air filter; gamma isotopic analyses of milk samples; and gross beta, tritium and gamma isotopic analyses of water samples. Delineated in this table for each of the media/analysis combinations, are: the specific radionuclides; Analytics' preparation dates; the known values with their uncertainties supplied by Analytics; the reported averages with their standard deviations; and the resultant normalized deviations and coefficients of variation expressed as a percentage.
It may be seen from Table 5-1 that all results were acceptable for precision, with one exception. The analysis of I-131 in a water sample prepared on 03/14/2002, exceeded the coefficient of variation acceptance criterion of 15%. The outcome of the investigation into the result that failed to meet ICP acceptance criterion is provided in the following paragraph.
The precision deviation was from the determination of 1-131 in water by gamma spectroscopy. The precision result (16.8%) was outside the upper control limit (15%). The variation of the gamma spectroscopy values was due to the low level of activity on the count date. The sample was shipped from Analytics on 03/14/02, and received at the EL on 03/20/02. The sample was counted on 03/21/02 through 03/25/02. During the counting period, the sample activity ranged from 33 pCi/l to 24 pCi/l. This level of activity is measurable by gamma spectroscopy with MDC of 15 pCi/l. The following corrective actions were implemented by the EL to reduce delays in analysis:
- 1) Alternate payment options were established with the supplier to prevent delays in sample shipments.
- 2) Steps have been taken to minimize the time between sample availability at Analytics and analysis by the EL.
The second quarter 2002 ICP samples were received and analyzed within three days of shipment and the results indicate excellent accuracy (104%) and precision (8.5%) for I-131.
As shown in Table 5-1, two analysis results failed to meet the acceptance criterion for accuracy, which is a normalized deviation no greater than three. The analysis of Cs-134 in a milk sample prepared on 03/14/02 exceeded the acceptance criterion for accuracy. Further, the analysis of Cs-134 on an air sample prepared on 09/12/02 failed the accuracy acceptance criterion.
The outcomes of investigations into the causes contributing to these accuracy failures are discussed in the following paragraph.
The accuracy problem with Cs-134 was determined in an investigation in 2001 to be the summing of the two major gamma peaks from Cs-134, thereby underestimating the sample activity.
As discussed in "The Joseph M. Farley Nuclear Plant Annual Radiological Environmental Operating Report for 2001,"
correction curves were developed from existing intercomparison data to correct for the summing loss. The Cs-134 results in 2002 indicate additional corrective action is required to address this problem.
Further investigation revealed that gamma spectroscopy efficiency curves are determined with standards containing radionuclides that cover the energy spectrum.
However, the standards do not contain Cs-134. As a corrective action, the gamma system will be calibrated in 2003 with standards that include Cs-1 34.
5-2
TABLE 5-1 (SHEET 1 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GROSS BETA ANALYSIS OF AN AIR FILTER (pCi/filter)
Analysis or l Date l Reported Known Standard I Uncertainty Percent Coef Normalized Radionuclide Prepared lAverage I Value I Deviation EL lAnalytics (3S) of Variation ifDeviation Gross Beta l 09/12/02 73.5 1 74 l 2.97 l
1.33 4.00
-0.15 GAMMA ISOTOPIC ANALYSIS OF AN AIR FILTER (pCilfilter)
Analysis or Date Reported Known l Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 09/12/02 106 111 3.21 2.00 3.02
-1.32 Co-58 09/12/02 70 67 3.27 1.00 4.67 0.88 Co-60 09/12/02 102 103 3.27 1.67 3.20
-0.27 Cr-51 09/12/02 176 158 16.06 2.67 9.12 1.11 Cs-134 09/12/02 77 91 2.46 1.67 3.19
-4.72 Cs-137 09/12/02 90 88 3.52 1.33 3.91 0.53 Fe-59 09/12/02 74 62 4.27 1.00 5.77 2.74 Mn-54 09/12/02 117 106 4.33 1.67 3.70 2.37 Zn-65 09/12/02 150 130 7.53 2.33 5.02 2.54 GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or Date
[Reported Known Standard Uncertainty l Percent Coef l Normalized Radionuclide l Prepared l Average l Value I Deviation EL l Analytics (3S) l of Variation l Deviation Ce-141 03/14/02 306 326 10.71 4.00 3.50
-1.75 Co-60 03/14/02 146 158 5.55 2.00 3.80
-2.04 Cr-51 03/14/02 285 267 41.74 3.33 9.12 1.11 Cs-134 03/14/02 105 122 4.00 1.67 3.81
-3.92 Cs-137 03/14/02 265 266 9.50 3.33 3.59
-0.10
TABLE 5-1 (SHEET 2 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF A MILK SAMPLE (pCi/liter)
Analysis or Date Reported Known Standard lUncertainty Percent Coef Normalized Radionuclide Prepared Average I Value I Deviation EL Analytics (3S) of Variation Deviation Fe-59 03/14/02 113 116 12.1 1.33 10.71
-0.25 1-131 03/14/02 92 92 12.21 1.00 13.28 0.00 Mn-54 03/14/02 221 224 8.69 2.67 3.93
-0.33 Zn-65 03/14/02 226 221 13.27 2.67 5.87 0.37 GROSS BETA ANALYSIS OF WATER SAMPLE (pCi/liter)
Analysis or Date Reported Known Standard Uncertainty 1 Percent Coef Normalized Radionuclide Prepared Average Value Deviation EL Analytics (3S) of Variation Deviation Gross Beta 03/14/02 292 287 8.66 4.67 3.00
-0.10 06/13/02 281 280 8.22 4.67 9.00 0.06 GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or Date Reported Known Standard Uncertainty Percent Coef Normalized Radionuclide Prepared Average I Value Deviation EL Analytics (3S) of Variation Deviation Ce-141 03/14/02 244.0 242 10.87 4.00 4.45 0.17
_ 06/14/02 87.0 83.0 8.36 4.00 9.61 0.43 Co-58 06/14/02 97.0 93.0 7.23 1.00 7.45 0.55 Co-60 03/14/02 118.0 117.0 44.56 3.33 20.44 0.45 06/14/02 118.0 115.0 5.60 2.00 4.75 0.50 Cr-51 03/14/02 218.0 242 41.31 4.00 17.07 0.00
_ 06/14/02 209.0 218.0 33.74 3.33 16.14
-0.27 Cs-134 03/14/02 82.0 91.0 4.58 1.67 5.59
-1.85 1 06/14/02 1
102.01 111.0 1 4.2 1 1.67 1 4.12
-1.99
TABLE 5-1 (SHEET 3 of 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS GAMMA ISOTOPIC ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or Date lReported Known Standard Uncertainty l Percent Coef l Normalized Radionuclide Prepared Average I Value Deviation EL Analytics (3S) of Variation Deviation Cs-137 03/14/02 206.0 197.0 9.31 3.33 4.52 0.91 06/14/02 76.0 84.0 6.45 3.33 8.49
-1.10 Fe-59 03/14/02 91.0 86.0 11.76 1.33 12.93 0.42 06/14/02 90.0 75.0 8.79 1.33 9.77 1.69 1-131 03/14/02 62.0 61.0 10.43 1.00 16.82 0.10 06/14/02 98.0 94.0 8.36 1.00 8.53 0.48 Mn-54 03/14/02 172.0 166.0 8.10 2.67 4.71 0.70 06/14/02 93.0 88.0 6.56 2.67 7.05 0.71 Zn-65 03/14/02 174.0 164.0 15.06 2.67 8.66 0.65 06/14/02 177.0 166.0 14.53 2.67 14.63 0.74 TRITIUM ANALYSIS OF WATER SAMPLES (pCi/liter)
Analysis or Date
[Reported Known Standard I Uncertainty l Percent Coef Normalized Radionuclide Prepared Average Value
[Deviation EL Analytics (3S) of Variation Deviation H-3 03/24/02 10721 10026 173 167.01 3.00 2.07 06/14/02 7710 6970 [
165.0 116.3 5.00 1.85 vt
6.0 CONCLUSION
S This report confirms the licensee's conformance with the requirements of Chapter 4 of the ODCM during 2002. It provides a summary and discussion of the results of the laboratory analyses for each type of sample.
All of the radiological levels were low and are generally trending downward.
In 2002, there were two instances for which the indicator station readings were statistically discernible from the control station readings.
These instances are discussed in the following paragraphs.
Tritium was detected in surface water at the indicator station at a concentration of 598 pCi/I, which is approximately 2% of the RL. No tritium was detected at the control station. Therefore, this tritium concentration must be attributed to plant releases.
Although no drinking water pathway via surface water exists in the plant vicinity, a potential dose from tritium in the drinking water pathway was calculated using the methodology in the FNP ODCM. This dose was calculated assuming that a person regularly consumed drinking water from the river downstream, near the indicator station for surface water sampling. Under these assumed circumstances, the potential dose to such an individual would be about 4.6E-2 mrem in a year. This dose would be approximately 1.5% of the annual dose limit for the total body, due to liquid effluents.
Direct radiation measured at the indicator stations was 1.5 mR higher than the direct radiation measured at the control stations. Although this small difference is statistically discernible, it is consistent with the difference between indicator and control station locations observed during preoperation.
This dose would contribute only 1.5% of the annual dose limit if a person were continuously present at the location of the indicator stations over a one-year period.
No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was established for any other REMP samples.
6-1