ML20217E113
| ML20217E113 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9804270192 | |
| Download: ML20217E113 (68) | |
Text
_. . .
Dave Mor y S:vthern Nuclear i Mce President Op: rating.Coger.ny l Farley Project P.O. BoMf '*
i Birrningham. Alabama 35201 Tel 205.992.5131 1
SOUTHERNk L COMPANY April 21,1998 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant Radiolozical Environmental Operating Report for 1997 Ladies and Gentlemen:
The enclosed " Radiological Environmental Operating Report for 1997" is transmitted in accordance with the Joseph M. Farley Nuclear Plant Unit I and Unit 2 Technical Specifications Section 6.9.1.6 and 6.9.1.7.
If you have any questions, please advise.
Respectfully submitted, flh }N0"'
Dave Morey DNM/DAH/ cit:98078_. doc
Enclosures:
Subject Report xc: U. S. Nuclear Reculatory Commission Mr. L. A. Reyes, Region II Administrator Mr. T. M. Ross, FNP Senior Resident Inspector Mr. J. I. Zimmerman, NRR Project Manager State of Alabama Mr. K. E. Whatley State of Georcia Mr. J. C. Hardeman, Jr.
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JOSEPH M. FARLEY NUCLEAR PLANT l RADIOLOGICAL ENVIRONMENTAL ;
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e TABLE OF CONTENTS Section and/o.- Title - Subsection Pane
- 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 4
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LIST OF FIGURES Figure Number Title Page Figure 2-1 REMP Stations Near the Plant Perimeter 2-8 Figure 2-2 REMP Stations 2 to 5 Miles from the Plant 2-9 Figure 2-3 REMP Stations Beyond 5 Miles frorn the Plant 2-10 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 1-131 Concentration in Milk 4-20 Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 4-22 Figure 4.5-2 Average Annual 1-131 Concentration in Forage 4-24 Figure 4.6-1 Average Annual 11-3 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 il
1 LIST OF TABLES Tatde Number Title Pane 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 41 Table 4-2 Reponing Levels 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 I-131 Concentration in Milk 4-21 Table 4.5-1 Average Annual Cs-137 Concentration in Forage 4-23 Table 4.5-2 . Average Annual I-131 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-137 Conce.itration in Game Fish 4-35 Table 4.9 Sediment Nuclide Concentrations 4-36 Table 5-1 Interlaboratory Comparison Program Results 5-3 iii l
LIST OF ACRONYMS Acronyms presented in alphabetical order.
Acronyan Definition A2LA American Association of Laboratory Accreditation 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 DifTerence 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 h
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1.0 INTRODUCTION
The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with Technical Specification (TS) 6.8.3.f and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 1997 are reponed herein in accordance with TS 6.9.1.6 and 6.9.1.7 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 alTected by plant operation (control stations) and at locations where radiological levels are more hkely 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 rated power output of 860 Megawatts electric (MWe) achieved initial criticality on August 9, 1977 and was declared
" commercial" on December 1,1977. Unit 2, also a 860 MWe 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 pre-operational 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 repod. 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 is provided in Section 4. The results of the Interlaboratory Comparison Program (ICP) are provided in Section 5. Conclusions are provided in Section 6.
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2.0 REMP DESCRIPTION A summary description of the REMP is provided in Table 2-1. This table summarizes the program's requirements as outlined in ODCM Table 4-1 by detailing 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 by delineating 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 identi6 cation 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 I and Unit Il 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 6rst 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 i approximately 15 miles northeast of the origin. The locations for the sampling l stations along the river are identiDed by the nearest River Mile (RM) which is the i
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 1
All laboratory analyses were performed by Georgia Power Company's Environmental Laboratory (EL) in Smyrna, Georgia. Since 1987, the EL has been accredited by the American Association of Laboratory Accreditation (A2LA) for radiochemistry. Accreditation is based upon internationally accepted critecia for laboratory competence (ISO /IEC Guide 25,1990, General Requirements for the Comoetence of Calibration and Testing Laboratories).
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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) Radiological Assessment Branch Technical Position, Revision 1, November 1979. Results for samples collected at any other locations are discussed in Section 4 under the particular sample type.
As indicated in ODCM 7.1.2.1, only the naturally occurring radionuclides which are also found in the plant's emuent releases are required to be reported. The radionuclide, Be-7, which occurs abundantly in nature is also found m the plants' liquid efTluent. No other naturally occwring radionuclides are found in the plants' liquid emuent releases. Therefore, the only radionuclides ofinterest 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 ofinterest for the other REMP samples. During 1997, Be-7 was not found in any of the REMP samples monitoring liquid releases.
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D/D/D/ 2 2 2 .
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4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various o sample types. Comparisons were made between the difference in mean values for pairs of station groups (e.g., indicator and control stations, or, indicator and community 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 1997 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 MDC's were achieved during laboratory sample analysis. Any anomalous results are explained within this report.
Results of interest were 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/l) Particulate (pC!/kg- (pCi/l) Leafy (pCi/kg-dry) or Gases wei) Vegetation (fCi/m3) (pCi/kg-wet)
Gross Beta 4 10 11-3 2000 (a) hin-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 1-131 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 j
(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.
l 4-1
I l Table 4-2 l
Reporting Levels (RL)
Analysis Water Airborne Fish Milk (pCi/l) Grass or (pCi/l) Particulate' (pCi/kg-wet) Leafy or Gases Vegetation (fCi/m3) (pCi/ka-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 f
(a) This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 30,000 may be used.
(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 weatber, equipment malfunction or other just reasons.
Deviations from conducting the REMP as described in Table 2-1 are summarized j in Table 4-3 along with their causes and resolutions.
4-2
I All results were tested for conformance to Chauvenet's criterion (G. D. Chase and l
J. L. Rabinowetz, Principles of Radioisofpoe 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 L determine the reason (s) for the difference. 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 werc F
excluded exclusively for failing Chauvenet's criterion. Data exclusions are discussed in this section under the appropriate sample type.
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l 4.1 Land Use Census in accordance with TS 6.8.3.f (ii) and ODCM 4.1.2, a land use census was conducted on June 5 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 locations of the nearest residence in each sector were the same as those found in last year's land use census. 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 l.2 none WSW 2.4 none W 0.9 none WNW 2.1 none NW l.5 none NNW 2.0 none The Ilouston 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 11ouston County was provided; there are no commercial dairy farms in Early County. Neither agent knew of privately cwned milk animals within 5 miles of FNP. In addition, field surveys were conoucted 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 identified, if the land
. use census identifies a location that yields a calculated receptor dose greater than I the one in current use. There were no changes in the 1997 census results and therefore no change in the controlling receptor was required. The current
. controlling receptor as described in ODCM Table 3-7 is a child in the SW Sector at 1.2 miles.
(
i 47 l l
4.2 Airborne As specified in Table 2-1 and shown in Figures 2-1 through 2-3, 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 <:ommunity stations. At each location, air is continuously drawn through a glass fiber filter to retain airborne particulate 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 prgvided in Table 3-1, the annual average peekly gross beta activity of 21.1 fCi/m for the indicator stations was 1.3 fCi/m less than that for the community -
stations and 0.5 fCi/m* less than that for the3 control stations. For each of these cases, the MDD was calculated as 2.0 fCi/m Since each of these difTerences is less than its MDD, there is not a statistically discernible difference between the average levels at the indicator stations and those for the other two station groups.
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 1980s, 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 impac The installation of new air monitoring equ,t faded away in approxima 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 a close agreement between the results for the indicator, control and community stations. This close agreement supports the position that the plant is not contributing significantly to the gross beta concentrations in air.
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$>&%> L 8
O mqr ,r 1
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l MDC --m--indicator --A-- Control --M--Community l e
4-9 i
l Table 4.2-1 Average Weekly Gross Beta Air Concentration Period Indicator - Control Community (fCi/m3) (fCi/m3) (fCi/m3)
Pre-op 90 92 91 1977 205 206 206 1978 125 115 115 1979 27.3 27.3 28.7 1980 29.7 2.8.1 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 l 1.0 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 I 1997 -21.I 21.6 22.4 -=
I e
4 10
1 l
During 1997, 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 mcident have faded. During, preoperation and the early years of operation, a i
. number of fission and activation products were detected. Du i the average levels for Cs-134 and Cs-137 were 22 and 9 fri/m'J ng preoperation
, respectively. Ig 1986, as a consequence of the Chernobyl incident, cesium levels of 3 to were found. The MDC and RL for Cs-134 are,50 andand10,000 the fCi/m,4 MDC and RL for Cs-137 are 60 and 20,000 fri/m respectively.
The historical trending of the annual detectable Cs-137 concentrations for the I 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 15
.~_
C E 10 '
3 e <
h d l
8 , \ ..
V !
0 *D: /:N : : :. : : :
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l + indicator -e- control --*-community l
. l i
l 4 11
l l
Table 4.2-2 Average Annual Cs-137 Concentration in Air Period Indicator Control Community (fCi/m3) (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 e
4 12
I Airborne I-131 was not detected in the charcoal canisters during 1997. In 1978, levcis between 40 and 50 fri/m' were found in a few samples and attributed to the Chinese wgapons tests; then after the Chemobyl incident, levels up to a few hundred fri/m were found in some samples. At no other times has airborne I-
. 131 been detected in the environmental samples. The MDC and RL for airborne I-13 I are 70 and 900 fCi/m3 respectively.
Table 4-3 lists REMP deviations which occurred during 1997. Not all of the deviations listed in Table 4-3 required data to be excluded from the calculation of the mean values. The following 4 sample results were excluded for failing Chauvenet's Criterion following equipment malfunctions:
- 1) When the air sample was collected at Station 1605 on 2/11/97, the volume totalizer was not registering. In addition, on 2/6/97 a power outage occurred which affected the sampler.;
- 2) On 3/12/97 Station 1605 was out of service for 42 minutes to replace the turbine totalizer assembly. There had been no indication of flow for 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />.
- 3) When the air sample was collected at Station 1605 on 3/25/97, the pump flow rate registered O. The pump was estimated to have been out of service for 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />.
- 4) When the air sample was collected at Station 1218 on 10/7/97 it was determined that the pump had not been running for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.
In addition to these 4 cases, no sampl ., were obtained at Station 1108 for the last 5 collection periods of the year de to no power being available.
j e
4-13
4.3 Direct Radiation Direct (external) radiation is measured with thermoluminescent dosimeters (TLDs) Two Panasonic UD-814 TLD badges are :) laced at each station. Each badge contains three phosphors com posed of ca cium 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 fonn 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. ,
l As provided in Table 3-1 the average quarterly exposure measured at the indicator j stations (inner ring) during 1997 was 2.3 and 1.4 mR greater than that acquired at l the community and control stations, respectively. The difference of 2.3 mR found I between the indicator and community stations is statistically discernible while that of 1.4 mR between the indicator and control stations is not since the difference is less than the MDD of 1.6 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 is only 1.1 mR greater. During preoperation, the average exposure at the indicator stations was 2.5 mR greater than that at the l community stations and the average over the period of operation is 2.7 mR I greater. This supports the position that the plant is not contributing significantly I to direct radiation in the environment. 1 e
I 4-14
Figure 4.3-1 I Average Quarterly Exposure from Direct Radiation
, 30 25
^ ' A 20 '
e us 15 10 , M i
/ 'r sr v we 5
0 Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l -+-indicator -e-control -*- community l J
4-15
Table 4.3-1 !
Average Quarterly Exposure from Direct Radiation Period Indicator Control Community (mR) (mR) (mR)
Pre-op 12.6 11.4 10.I 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 I984 18.3 16.9 15.3 1985 21.9 22.0 18.0 1986 17.8 17.7 15.I 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 I3.6 13.5 1993 17.4 15.9 15.6 I994 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 l 1.9 m
O 4-16
l The results for the Grst quarter at Station 0304 were excluded from the data set after failing to conform with Chauvenet's Criterion. These badges, which were on station for 49 days, were replacements which had been installed after Unding the regular badges missing during the mid quarter check.
Both badges at Station 0304 and Station 0505 were missing when collections were made at the end of the Grst quarter and both badges at Station 0304 were missing at the end of the second quarter.
The following TLD results were excluded from the data set because their standard j deviations were greater than 1.4: 0204A for the second quarter; and 0401B and l 02048 for the fourth quaner, in each of these cases, only the reading of the companion badge was used to determine the guarterly exposure for the station.
No reason was found for the high standard deviations. 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 abnormalities were discovered.
I 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 Chan Analysis. Founh 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 Hag to initiate an investigation.
To be conservative, readings with a standard deviation greater than 1.4 are deleted since the high standard deviation is interpreted as an indication of a suspect TLD.
0 4 17
1 4.4 Milk In accordance with Table 2-1, milk samples are collected biweekly from the Bmce Ivey Dairy (control station) which is located 12 miles west of the plant as shown in
. Figure 2-3. No indicator station (a location within 5 miles of the plant) is available. As discussed in Section 4.0, no milk animals were found in the 1997 land use census. Gamma isotopic and 1-131 analyses are performed on each sample as specified in Table 2-1.
l No man-made radionuclides were identified from the gamma isotopic analysis of l the milk samples during 1997. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/1, 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. It's 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 40 '
l 35 f\
1 1 \
o 30
- \
g 25
=
r ec a\
3 3 U
u
/ \ qi
! ,,, T / \ /\
, \ / \ / \
0- - \" :l'
): ' (
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97
\" . : : .
Year l --+-indkator --m-control Moc l 1
(.
4-18 f
l . _ _ _ _ - _ _ _ _ _ _ _ _ _
l Table 4.4-1 Average Annual Cs-137 Concentration in Milk i -
Period Indicator Control (pCi/l) (pCi/l)
Pre-op 32 18 l 1977 41 20 l 1978 15 17 1979 0 0 1980 0 0 1981 0 23 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 9
4-19
I-131 has not been detected in milk since 1986 and its presence 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 I and 3 pCi/1, respectively.
Figure 4.4-2 and Table 4.4-2 show the historical trending of the average annual
. detectable 1-131 concentration in milk samples.
Figure 4.4-2 Average Annual 1-131 Concentration in Milk 50 g< >
?.
I 30
.9 20 '
s 8 4 10 \ H
_ \\ 1. ./
x o . . . .
h.. . . . . . . .
I Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 l
Year l --+--indicator --s-Control MDC RLl l
l I
l
- O 4-20
Table 4.4-2 Average Annual 1-131 Concentration in Milk
. Period Indicator Control (pCiM) (pCiM)
Pre-op 41 14 1977 20 2.6 1978 30 11 1979 0 0 l
1980 0 0 1981 0 0 1982 0 0 1983 0 0 1984 0 0 1985 0 0 1986 0 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 I
O 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 as shown in Figure 2-1, and at one control station located approximately 18 miles west of the plant in Dothan as shown in Figure 2-3. Gamma isotopic analysis is performed on each sample.
During 1997, one sample at an indicator station showed Cs-137 at a level of 52.6 pCi/kg-wet which is below the MDC for Cs-137. This is the first time since 1994 that a manmade radionuclide was detected in a forage sample. During preo 3eration and the years of operation through 1986 (the year of the Chemobyl meicent), Cs-137 was typically found in about a third of the 35 to 40 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. 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 80 7,
e
$ 60, g ,, "\ u [ "
i ., \ / \ ;< A /\ u /
i ,, \\ / XN A V \ /\ l i ,, \ x/ h// '
\ /\ \ / H l 3
,, \ / \/ \ / \ V \ l 0 -
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l -+-Indicator --S-- Control MDCl E
h 4 22
Table 4.5-1 Average Annual Cs-137 Concentration in Forage Period . indicator Control (pCi/ka-wet) (pCi/ka-wet)
Pre-op 59.4 48.6 l 1977 25.0 0 1978 52.5 32.5 l 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 l 1988 33.6 31.7 1989 35.7 0 1990 56.0 0 1991 0 12.9 1992 0 43.0 j 1993 0 24.0 -
1994 0 24 l 1995 0 0 1996 0 0 1997 52.6 - 0
)
l l.
l.
4-23
During preoperation and in the early years of operation,1-131 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 I-131 are 60 and 100 pCi/kg-wet, respectively. Table 4.5-2 lists the average detectable results ofI-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 m vegetation samples since the 1986 Chernobyl accident.
Figure 4.5-2 Average Annual 1-131 Concentration in Forage 1000 900 O 800 l\
t
, 700 l \
m o 600 In \
s V \\
c 600 2 400-E I 8 300 l 200 100 - - ~~
j 0 " : ! !: : : : :
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l --+--indicator --m-- Control MDC RLl
\
4-24
Table 4.5-2 Average Annual 1-131 Concentration in Forage Period indicator Control (pCi/kg-wet) (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 I
These forage analyses results show a decided 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 ar seen in 1985 appeared at a significantly higher magnitude and I-131 reappeared. In the years following 1986, only Cs-137 has been found and in a decreasing fraction of the samples. By 1989, detectable results were usually found in only one sample, as was the case in 1997.
L I
1 4-25
4.6 Ground Water In the FNP environs, there are no true indicator sources of ground water. A well, located on the cast bank of the Chattahoochee River, about four miles south-southeast of the plant, which serves Georgia Pacific Paper Company as a source
, of potable water, is designated as the indicator station. A deep well located about 1.2 miles southwest of the plant, which supplies water to the nearest 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.
In 1983,1985, and 1986, Cs-134 was detected in one sample at levels ranging from 3 to 13 pCi/1. The MDC and RL for Cs-134 in water are 15 and 30 pCiM, respectively.
l During preoperation, Cs-137 was detected in two of the samples at levels of 15 and 17 pCi/1. Then in 1984 and 1985, Cs-137 was again detected in a few samples with levels ranging from 4 to 5 pCi/1. The MDC and RL for Cs-137 in water are 18 and 50 pCi/1, 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 2000 f 1800 1600 h 1400 c.
- 1200 o
j 1000 '
f 800 E l o 600 0
400 200 l l H J%
, O : : : : : "
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year j' l -+-indicator --o-control Mocj 1
4-26 l
l
Table 4.6-1 Average Annual 11-3 Concentration in Ground Water Period ludicator Control
. (pCi/I) (pCi/1)
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 O
4-27 L_______-___
1 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 throug1 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 not found in any of the composite samples collected during 1997. Figure 4.7-1 and Table 4.7-1 provide the historical trending of the detectable concentrations of tritium in surface water. The slightly clevated plot of the indicator stations is indicative of plant tritium contributions to surface water, although it is important to note that the annual average levels are at most 15% of the MDC and only 1.5% of the RL The MDC and RL for tritium in surface water are 3000 and 30,000, respectively.
4 28
Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 3000
. 2500 5
b**
8 j1500 s
'b 1M0 8
O
$00
/% H /\
o
' MH r I :
w /N q ,q hH\/g\
q, , ,
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l +1ndicator --o-control Moc l 1
- \
l i
I 4-29
Table 4.7-1 Average Annual 11-3 Concentration in Surface Water Period Indicator Control (pCiM) (pCiM)
Pre-op 200 170 1977 300 160 ;
1978 230 250 i 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 1
I e
4-30 l
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 a 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 speciDed in Table 2-1.
As provided in Table 3-1, Cs-137 was the only radionuclide ofinterest which was found from the gamma isotopic analysis in 1997. For the bottom feeding Gsh, it was found in each collection except for the March collection at the control station.
The average concentration for indicator samples was 10.9 pCi/kg-wet and the concentration for the single control sample was 7.7 pCi/kg-wet. (Note, the 3.2 pCi/kg-wet difTerence was not discernible since it was less than the calculated MDD of 3.7 3Ci/kg-wet.) For game Osh, Cs-137 was found only in the March collection at t;ie indicator station at a concentration of 25.9 pCi/kg-wet.
Ilistorically, Cs-137 has been found in approximately 30% of the bottom feeding fish samples and in 80% of the game Osh samples. Figures 4.8-1 & 4.8-2 and Tables 4.8-1 & 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 Osh, respectively. Since the early 1980s, values have generally decreased for both indicator and control groups and appear to be leveling out. The Cs-137 levels in these samples are attributed to the nuclear weapons tests and the Chernobyl incident.
l l
l l
l l
9 4-31
1 I
Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 250 O 200
!5 g160
?o 100 -
0 60 ,
( \
, /\/** \. . .
f' .;Nu%
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year
--o-control l --+-indicator Moc l e
4-32
Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish Period Indicator Control (pCi/kg-wet) (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-e 4-33
Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 350 1 1 O j[
dn 250 f\
1-S 150 C
1 8 100 50 ' L 0
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 96 96 97 Year
--+--indicator -e-Control MDC 1
I.
l 4-34 l 1
i l
Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish o Period Indicator Control (pCi/kg-wet) (pCi/kg-wet)
Pre-op 84 60 1977 95 48 1978 0 0 1979 11I 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 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.
l I
YEAR Nuclide Fish Type Indicator Control MDC (pCi/kg) (pCi/kg) (pCi/kg) 1978 Ce-144 Bottom Feeding 0 200 150 (a) 1981 Nb-95 130ttom Feeding 38 0 50 (b) 1982 Nb-95 Game 31 0 50 (b) 1986 Co-60 Game 25 0 130 (a) 1996 Annual Report to NRC for Environmental Radiation in Alabama, Alabama Department of Public Health, April 26,1997, page 142.
(b) 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 R.iver at a control station which is approximately 4 miles u 3 stream of the intake structure and at an indicator station which is approximate:y 2 miles downstream of the discharge structure as shown in Figure 2-2. A gamma isotopic analysis is perfonned on each sample as specified in Table 2-1. During 1997, no radionuclides ofinterest were detected.
Historically, Be-7, Cs-134, Cs-137, & 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 results for these nuclides along with their applicable MDC's 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 Control MDC (pCi/ka-dry) (pci/ka-dry) (pci/ka-dry)
Be-7 1985 535 945 655 (a)
Cs-134 1987 45 1989 48 150 1992 138 51 1993 94 105 Cs-137 1981 185 1985 97 180 1989 39 1994 29 11 1996 11.8 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 l
l
i i
Figure 4.9-1 i i
Average Annual Cs-134 Concentration in Sediment 160 140 s A 17 120 f
s_ 100 f \ '
c go i: .0 l l< \
i 8 40 o R IJ \
3
,0 /\ / \ l/ \
0: : : : : : : : : : : : : ;
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l -+-Indicmor --m-Control MDCl The positive results for Cs-134 appear mostly at the Control Station. Due to its relatively short halflife of approximately 2 years, the positive results may in part be attributed to the Chernobyl incident. The overall plotting of the positive results does not show any discernible trends.
l l'
l 4-37 I
i l
Figure 4.9-2
, Average Annual Cs-137 Concentration in Sediment 200
. 180
$ 160 9
cm 140 l\
0 120 I
g 100 I
= /
j 80 I, E 60 8
" i \ l \
- I \ l \ I\ ><
0: : : : : - : : :
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 Year l -+--indicator --m-control Moc l Cs-137 appears to be trending down since the ceasing of above ground weapons I testing and the majority of the positive results appear at the control stations. l Therefore in general, the positive results can be attributed to the weapons tests and the Chernobyl incident.
G 4-38
5.0 INTERLABORATORY COMPARISON PROGRAM In accordance with TS 6.8.3.f(iii) and ODCM 4.1.3, the EL participates in an ICP which satisnes the requirements of Regulatory Guide 4.15, Revision 1, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Ef6uent Streams and the Environment", February 1979. The guide indicates that the ICP is to be conducted with the EPA (Environmental Protection Agency)
Environmental Radioactivity Laboratory Intercomparison Studies (Cross-check)
Program or an equivalent program, and that 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 conoucted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented Quality Assurance program and the capability to prepare Quality Control 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 cross check samples to the EL which performs the laboratory analyses in a normal manner. Each of the specined analyses is i performed three times. The results are then sent to Analytics who performs an !
evalu:: tion which may be helpful to the EL in the identification ofinstrument or procedural problems.
The accuracy of each result is measured by the noimalized 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 (counting statistics, calibration uncenainties, chemical yield etc.). The uncertainty of the reponed average is the standard deviation of the analysis results performed by the EL. The precision of each result is measured by the coef6cient of variation which is denned as the standard deviation divided by the reponed average. An investigation is undertaken whenever the absolute value of the normalized deviation is greater than 3 or whenever the coefTicient of variation is greater than 15%.
As required by ODCM 4.1.3.3 and 7.1.2.3, a summary of the results of the EL's 1 panicipation in the ICP is provided in Table 5-1 for: the gross beta analysis of an air Diter; the gamma isotopic analysis of an air Glter, a milk sample, and water samples; and the tritium analysis of water samples. Delineated in this table for each of the media / analysis combinations, are: the specinc 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 coemcients of variation expressed as a percentage. It may be seen from Table 5-1 that each of the results satis 6ed the acceptance criteria for the coemeient of variation, but 5 of the 41 results exceeded the acceptance criteria for normalized deviation. The outcomes of investigations into these 5 results are provided in subsequent paragraphs.
, The activity recoveries for Cs-134 from the gamma analysis in the December 11 air Glter and in the March 20 water sample were both low. The two primary gamma decay peaks at 604 and 795 kev cause a coincidence peak at 1399 kev 5-1
(the sum of the two primary peaks). The activity can be corrected by developing a correction factor for the summing effect.
The activity recoveries for Ce-141 from the gamma analysis in the same two samples were also low. The gamma decay peak for Ce-141 is 145 kev. The presence of the 144 KcV gamma from Fe-59 may affect the background calculation for Ce-141. The analysis may require extrapolating the background of the 145 kev peak and thus changing the area of the peak.
For the gamma analysis for 1-131 in the September 18 water sample: the questionable result was due to an electronic problem regarding pole zero in one of the detectors. The electronics have been recalibrated to reduce variation.
The results of these investigations have been used to identify interferences and instrument deficiencies which have been corrected.
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6.0 CONCLUSION
S This report confirms the licensee's conformance with the requirements of TS 6.8.3.f and Chapter 4 of the OIX'M during 1997. 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.
No discernible radiological impact upon the environment or the public as a consequence of plant discharges to the atmosphere and to the river was identified.
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