ML20206B557
| ML20206B557 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1998 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NEL-99-0174, NEL-99-174, NUDOCS 9904290290 | |
| Download: ML20206B557 (70) | |
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, Da;o Morey S:uthern N:cf r:r Vice President Op: rating Comp:ny. inc.
farley Project Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 SOUTHERN April 21, 1999 COMPANY Energy to Serve hur World" i
Docket Nos. 50-348 NEI-99-0174 50-364 U. S. Nuclear Regulatory Commission NITN: Document Control Desk Wa Egina. D. C. 20555 l
Joseph M. Farley Nuclear Plant Radiolonical Environmental Oocratina Report for 1998 i
Laacs and Ga=*h-The enclosed "Ra&ological Psvironmental Operating Report for 1998", is transmitted in accordance with the Joegh M. Farley Nuclear Plant Unit 1 and Unit 2 Technical Specificataons Section 6.9.1.6 and 6.9.1.7.
If you have any questions, please advise.
Respectfully submitted, ftlstet Dave Morey / / JIID/ahl: rden. doc
/
Enclosure [$ y,c,t.55 9904290290 981231 PDR ADOCK 05000348 R PDR _
Page 2 U. S. Nuclear Rag =1-*ary Comnussion cc: hitharn Nnetaar Oneratine Comnany Mr. L. M. Stinson, General Manager - Farley U. S. Nnetaar Remilmfarv Cammi==ina Wa=hinatan D. C. Mr. J. I. Zi.mmm n, Licmsing Project Manager - Farley U. S. Nuclear Reentatory Commissian Reaion II Mr. L. A. Reyes, Regional Admmistrator Mr. T. P. Johnson, Senior Resident Inspector - Farley State of Alabama Mr. K. E. Whatley, Department of Public Health, Division of Radiation Control State ofGeorgia Mr. J. L. Setser, Department of Natural Resourocs v
l JOSEPH M. FARLEY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 1998
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l TABLE OF CONTENTS I i l I 1 Section and/or Title Subsection Page l 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 l 4.1 Land Use Census 4-8 4.2 Airborne 4-9 4.3 Direct Radiation 4-15 4.4 Milk 4-19 4.5 Forage 4-23 4.6 Ground Water 4-27 4.7 Surface Water 4-29 4.8 Fish 4-32 4.9 Sediment 4-37 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 2-8 Figure 2-2 REMP Stations 2 to 5 Miles from the Plant- 2-9 Figure 2-3 REMP Stations Beyond 5 Miles from the Plant 2-10 Figure 4.2-1 Average Weekly Gross Beta Air Concentration 4-10 Figure 4.2-2 Average Annual Cs-137 Concentration in Air 4-12 Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 4-16 Figure 4.4-1 Average Annual Cs-137 Concentration in Milk 4-19 Figure 4.4 2 Average Annual 1-131 Concentration in Milk 4-21 Figure 4.5-1 Average Annual Cs-137 Concentration in Forage 4-23 Figure 4.5-2 Average Annual 1-131 Concentration in Forage 4-25 Figure 4.6-1 Average Annual H-3 Concentration in Ground Water 4-27 Figure 4.7 1 Average Annual H-3 Concentration in Surface Watc- 4-30 Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-33 Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 4-35 Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 4-38 Figure 4.9-2 Average Annual Cs-137 Concentration in Sediment 4-39 I l l l
l I \ e n 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 Ixvels (RL) 4-2 Table 4-3 Deviations from Radiological Environmental Monitoring Program 4-4 Table 4.1-1 Land Use Census Results 4-8 Table 4.2-1 Average Weekly Gross Beta Air Concentration 4-11 Table 4.2-2 Average Annual Cs-137 Concentration in Air 4-13 Table 4.3 1 Average Quarterly Exposure from Direct Radiation 4-17 Table 4.4-1 Average Annual Cs-137 Concentration in Milk 4-20 Table 4.4-2 Average Annual 1-131 Concentration in Milk 4-22 Table 4.5-1 Average Annual Cs-137 Concentration in Forage 4-24 Table 4.5-2 Average Annual 1-131 Concentration in Forage 4-26 Table 4.6-1 Average Annual H-3 Concentration in Ground Water 4-28 Table 4.7-1 Average Annual H-3 Concentration in Surface Water 4-31 Table 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 4-34 Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish 4-36 Table 4.9 Sediment Nuclide Concentrations 4-37 Table 5-1 Interlaboratory Comparison Program Results 5-3 i I l l iii )
r LIST OF ACRONYMS Acronyms presented in order of first appearance Acronym Definition A2LA American Association ofl2boratory Accreditation APCo Alabama Power Company ASTM American Society for Testing and Materials CL Confidence Level EL Georgia Power Company Environmental 12boratory 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 Reponing Level RM River Mile TLD Thermoluminescent Dosimeter TS Technical Specification l 4 iV
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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 1998 are reported herein in accordance with TS 6.9.l.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 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 Com 3any (APCo) and operated by Southern Nuclear Operating Company. It is ocated 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 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 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 IJnit I and Unit 11 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 nonheast 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 performe<1 by Georgia Power Company's Environmental Laboratory (EL)in Smyrna Georgia. Since 1988, the EL has been accredited by the American Association of Laboratory Accreditation (A2LA) for radiochemistry. Accreditation is based upon internationally accepted criteria for laboratory competence (ISO /IEC Guide 25,1990, General Requirements for the Comnetence of Calibration and Testing Liboratories). 1 i
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o 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 reponed aloog with man-made radionuclides. The radionuclide, Be-7, which occurs abundantly in nature is also found in the plant's liquid effluent. No other naturally occurring radionuclides are found in the plants' liquid effluent 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 1998, Be-7 was not found in any of the REMP samples monitoring liquid releases. 3-1
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- 4.0 DISCUSSION OF RESULTS Included in this section are evaluations of the laboratory results for the various sample types. Cuuparisons 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 1998 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 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/l) Particulate (pCi/kg) (pCi/l) Leafy (pCi/kg) or Gases wet Vegetation dry (fCi/m3) (pCi/kg) wet Gross Beta 4 10 H3 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 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 l 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. l 4-1 L
n Table 4-2 ; i Reporting Levels (RL) Analysis Water- . Airlmrne Fish Milk (pCi/l) Grass or (pCi/l)' Particulate (pCi/kg) wet I esfy 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 I Zn-65 300 20,000 1 Zr-95 400 Nb-95 700 ) l-131 2 (b) 900 3 100 Cs-134 30 10,0(X) 1000 60 1000 ) Cs-137 50 20.000 2000 70 2000 i Ba-140 200 300 Li-140 100 400 (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 Chemobyl 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 1 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 enterion. Data exclusions are discussed in this section under the appropriate sample type. i 4-3
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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 j 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 l Distance in Miles to the Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL N 2.6 None i NNE 2.5 none , NE 2.4 none ENE 2.4 none _ E 2.8 none ! ESE 3.0 none l SE 3.4 none l SSE none none l 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 Houston County, Alabama and the Early County, Georgia Extension Agents were contacted for assistance in locating commercial dairy fanns 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 corrmercial 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. There were no changes in the 1998 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. 4-8
'4.2 Airborne As specified in Table 2-1 and shown in Figures 4.2-1 and 4.2-2, airborne paniculate filters and charcoal canisters are collected weekly at 4 indicator, 3 control and 3 community stations. Particulate filters are collected at all of the ,
I 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 airbome particulate and, as appropriate, an activated charcoal canister is placed in series to adsort radioiodine. Each particulate filter is counted for gross beta activity. A quanerly gamma j isotopic analysis is performed on a composite of the air particulate filters for each i station. Each charcoal canister is analyzed for I-131. As provideq in Table 3-1, the 1998 annual average weekly 3 gross beta activity was l 20.6 fCi/m at the indicator stations 3 and 19.2 fCi/m at the control stations. ! However, the difference of 1.4 fCi/m between the two averages is n t statistically I discemible since the MDD for these two average values is 1.6 fCi/m As shown in Table 3-1, the 1998 annual average weekly gross beta concentration was 22.0 fCi/m 3at community stations. Although the community stations 3 average was only 2.8 fCi/m higher than the average for the control stations, the difference is greater than the MDD of 1.9 fCi/m', between the two averages. Therefore, the difference between the community stations average gross beta concentration and the control stations average is statistically discernible. 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 Chemobyl incident in 1986; this impact faded away in ap proximately 2 years. The installation of new air monitonng equipment in 1992 yie:ded an approximate factor of 2 increase in the readings. Since t ben, the levels have been fairly flat. The historical trending of the average weekly gross beta air concentrations far each year of operation and the p,reoperational period at the indicator, contro' and commumty 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's contribution to gross beta concentration in air is insignificant. 4-9
Figure 4.2-1 Average Weekly Gross Beta Air Concentration 1000
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Table 4.21 Average Weekly Gross Beta Air Concentration Period . Indicator Control . Community (fC1/m3) (fCi/m3) (fCi/m3) Pre-op 90 92 91 1977 205 206 2% 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
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During 1998, 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. During 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/m' were found. The MDC and RL for Cs-134 are 50 and 10,000 fCi/m 3 3 and the MDC and RL for Cs-137 are 60 and 20,000 fCi/m 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 E 15 b g I I
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o Table 4.2-2 Average Annual Cs-137 Concentration in Air Period Indicator Control Community (fCUm3) (fCi/m3) (fCl/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 p; t1998) -
- 01 :0L 0' 4-13
Ai borne I-131 was not detected in the charcoal canisters during 1998. In 1978, 3 nevels between 40 and 50 fCi/m 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/m' 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 I-131 are 70 and 900 fCi/m3 n:spectively. Table 4-3 lists REMP deviations that occurred during 1998. 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 the following sample results were excluded for failing Chauvenet's Criterion following equipment malfunctions:
- 1) For the sample, period 2/17 - 2/24, the air filter (gross beta) sample collected at station 1605 was inadequate due to incorrect installation of the filter (off-center in the filter holder).
- 2) Air sampling Station 0718 experienced low sample volume collection for the penod 6/23-6/30, due to a totalizer trip. This problem affected both the air filter and the charcoal canister results.
- 3) Air sampling Station 0703 experienced low sample volume collection for the period 7/7 - 7/14, due to a totalizer trip. This problem affected both the air filter and the charcoal canister results.
- 4) Air sampli,ng Station 0703 experienced low sample volume collection for the penod 7/21 - 7/28, due to a totalizer tri). This problem affected both the air filter and the charcoal canister resu ts.
- 5) Air sampli,ng Station 0718 experienced low sample volume collection for the penod 8/18 - 8/25, due to a totalizer trip. This problem affected both the air filter results and the charcoal canister results.
- 6) Air sampling Station 0215 experienced low sample volume collection for the period 8/25 - 9/1, due to a totalizer trip. This problem affected both the air filter results and the charcoal canister results.
In the cases above a total of 11 sample results were excluded. In addition to the cases discussed above, no samples were obtained at Station 1108 from 12/30/97 to 1/27/98, the first 4 collection periods of the year, due to lack of electrical power while the Ashford substation was being upgraded. Station i108 is not equipped with a charcoal canister, therefore, only air filter results were affected. In all, a total of 15 air sample results were excluded or unavailable as discussed in Table 4-3. l i l 4-14 r.
4.3 Direct Radiation Direce u d) radiation is measured with thermoluminescent dosimeters (TLF > W 7anasonic UD-814 TLD badges are placed at each station. Each bad;r sa. three phosphors composed of calcium sulfate crystals (with thub m unn= v). The gamma dose at each station is based upon the average readings of . e hosphors from the two badges. The two badges for each station are placei m @ plastic bags for protection from moisture while in the field. The badgesrr wninally 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 i distances greater than 10 miles from the plant, as shown in Figure 2-3. Stations I 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 1998 was 1.6 mR greater than that acquired at the control stations. This dose is not significant when compared to applicable limits for a .nember of the public and is consistent with previous years results. Although this difference is small, it is equal to the MDD and is therefore statistically discernible. However, 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 1.1 mPs. , l The historical trending of the average quarterly exposures in units of mR at the i 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 1.6 mR greater. This supports the position that the plant is not contributing significantly to direct radiation in the environment. 4-15
f Figure 4.3-1 Average Quarterly Exposure from Direct Radiation 30 25
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Table 4.3-1 l Average Quarterly Exposure from Direct Radiation j Period Indicator (mR) Control (mR) Community (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 4 1990 18.9 16.4 15.8 1991 18.4 16.I 16.1 4 1992 16.I 13.6 13.5 I 1993 17.4 15.9 I 5.6 l
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.c As described in Table 4-3, the direct radiation measurements taken at Station 0201 during the first quaner duviated from the radiological environmental monitoring program requirements. These two TLDs, which were on station for 14 days, were replacements that had been installed after the initial badges were lost due to flooding of the Chattahoochee River. The results for the first quarter at Station 0201 were excluded from the data set after failing to conform to Chauvenet's criterion.
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. 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 following TLD results were excluded from the data set because their standard deviations were' greater than 1.4: For the first quaner, badge 1101A; for the second quaner, badge 0405B; for the third quarter, badges 0201 A, 0301 A, i10' 0104B,14048, and 0718B; and for the founh quaner, badge 0401B. In eacn these cases, only the reading of the companion badge was used to deternane 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. 4-18
4.4 Milk In accordance with Table 2-1, milk samples are collected biweekly from a control location. Until mid-November the control location was the Bruce Ivey Dairy 12 miles west of the plant. Between the milk sample collection on November 17 and the planned collection on December 1, this dairy ceased operation. A replacement milk sample control station was established 14 miles SSE of the plant at the Robert Weir Dairy, as shown in Table 2-1. During 1998,23 biweekly samples were collected from the Bruce Ivey Dairy and one sample was collected from the Robert Weir Dairy. Two samples were missed due to the unavailability of milk samples, as shown in Table 4-3. 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 1998 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 1998. 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. 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 Cciscentration in Milk 45 1 " 40 35
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-+--indicator -G-Control MDC
) 4-19
Table 4.4-1 Average Annual Cs-137 Concentration in Milk Period Indicator Control (pCi/l) (pCi/l) Pre-op 32 18 1977 41 20 1978 15 17 1 1979 0 0 I 1980 0 0 l 1981 0 23.0 I 1982 0 0 l 1983 0 0 l 1984 0 0 I 1985 0 0 1986 0 16.5 ; 1987 0 0 l 1988 0 0 1989 0 0 1990 0 0 1991 0 0 1992 0 0 1993 0 0 1994 0 0 l 1995 0 0 i 1996 0 0 1997 0 0 1998 - s: Lt O - > 20^ 4-20
As specified in Table 2-1, each sample was analyzed for 1-131, which 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 I-131 concentration in milk samples. Figure 4.4-2 Average Annual 1-131 Concentration in Milk 50
.i i 40 '
5 S 7 30
.e lii b
E 20 8 o i ' 10 ( U
\/ \\
u 3 / xs 0 - : : : : Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year l --+--indicator Control MDC RL l 4-21
1 i Table 4.4-2 i Average Annual I-131 Concentration in Milk ! Period - Indicator - Control (pCi/l) (pCi/I) Pre-op 41 14 : I 1977 20 2.6 1978 30 11 1979 0 0 1980 0 0 1981 0 0 i 1982 0 0 1983 0 0 1984 0 0 I 1985 0 0 j 0 1986 5.0 1987 0 0 1988 0 0 , 1989 0 0 1990 0 j 1991 0 , 1992 0 . 1993 0 1 1994 0 v i 1995 0 0 1996 0 0 l 1997 0 0 l
.1993 s
=Om e -
- e 0.; l l
, 4-22
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. During 1998 Cs-137 was found at the control station in one sample at a level of 22.7 pCi/kg wet. This is only the second time since 1994 that a manmade radionuclide was detected in a forage sample. No manmade radionuclide was found in forage at an indicator station during 1998. During preoperation ar.d 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 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 90 80 f70 s g 60, R "\ n I
)I o
.i .3, \ /\ x A / \ n A 1,,, \\ l k% k V \ /\ l \
i
",, \ "I %U '
\ n \ / H I \v
,, \ / \/"
\ / \ V \ l X O
V V
\ /
\.J J' Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 63 94 95 96 97 98 Year
--+-Indicator Control MDC 4-23
Table 4.5-1 Average Annual Cs-137 Concentration in Forage Period Indicator Control (pCi/kg) wet (pCl/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.I 1982 25.0 33.I 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 -01~ - 22.7 :
4-24 l
O During preoperation and in the early years of operation, I-131 was found in 10'7e 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 of I-131 found in forage over the life of the plant and Figure 4.5-2 plots the historical trending of this data. 1-131 has not been detected in vegetation samples since the 1986 Chernobyl accident. Figure 4.5-2 Average Annual 1-131 Concentration in Forage 1000 I ! 900
- 800 It 3
8 700 l O 600 l} s C 500 u l' \' '\ E 400' \\ 1! l 300 b 200 100
\g f
A g 0 .- d " Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year l -+--Indicator --G-- Control MDC RLl 4-25
Table 4.5-2 Average Annual I-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 I84 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
-1998s >
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 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 1998. 4-2.6
4.6 Ground Water in the FNP environs, there are no true indicator sources of ground water. A well, located on the east 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 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 1998. In 1983,1985, and 1986, Cs-134 was detected in one sample 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/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/1, 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 O S y 1500
.9 lii 23 1000 8
o 500 0 .
) .
Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year
--+-Indicator Control MDC l 4-27
Tcble 4.6-1 Average Annual H-3 Concentration in Ground Water Period Indicator Control (pCi/l) (pCi/I) 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
.gggg; .,
, .:n 0:: m ;nu <
I l i i 4-28
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 one of the composite samples collected at the indicator station during 1998 at a concentration of 415 pCi/1, which is about 1.4% of the RL. No tritium was found at the control station during 1998. If during 1998 an adult individual had eaten 26 kg of fish taken near the indicator station and 64 kg of garden vegetation taken from the nearest irrigated gardens located approximately 26 miles downstream from the plant, the resulting dose to the total body of the individual due to tt: tium in the river water would be about 2.3E-4 mrem, which is less than 0.01% of the annual limit for doses due to liquid effluents. The annual consumption of fish and garden vegetation and the dose calculation methodology are from " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," NRC Regulatory Guide 1.109, Revision 1, October 1977. 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 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. l. 4-29
Figure 4.7-1 Average Annual H-3 Concentration in Surface Water 3500 3000 2500- - . s
@2000
'il f1500 8
$1C00 0
500 1 " ir-0 . , , Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year
-+--indicator Control MDC 4-30
Table 4.7-1 Average Annual H-3 Concentration in Surface Water Period Indicator Control (pCi/l) (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 lit 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- 132 0 1992 360.5 134 1993 388.8 0 1994 0 0 1995 257 0 1996 386 0 1997 0 0 1998- :415' O. 4-31
e 4.8 Fish r 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 specified 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 1998. For the bottom feeding fish, no Cs-137 was found. For game fish, Cs-137 was found in all control and indicator samples. For the indicator station the 1998 concentration is slightly higher than in recent years. The average Cs-137 concentration for game fish samples from the indicator station was 52.4 pCi/kg wet. The average for samples taken from ) the control station was 20.0 pCi/kg wet. However, the 32.4 pCi/kg wet difference
-was not discernible since it was less than the calculated MDD of 269.3 pCi/kg-wet.
/
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. l l l l 4-32
I l Figure 4.8-1 Average Annual Cs-137 Concentration in Bottom Feeding Fish 250
** 200 k
^
tn , 150 k C ,
.j '
J S 100 ' c V \ l 8 1 b 50, I ' l 0 : : Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year
-+-Indicator Control MDCl 4-33
n 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 ' I977 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 i 1988 25.5 22.0 1989 0 0 ; I990 0 0 I991 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 4 1998s w 0:,, .
~ 0 :--
4-34
Figure 4.8-2 Average Annual Cs-137 Concentration in Game Fish 350 l I 300 g 250 q cL 200 k
.i3 150 I h
E I
$ 100 50 - '
l ( l Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year
-indicator -G-Control MDC i
l l 4-35
Table 4.8-2 Average Annual Cs-137 Concentration in Game Fish Period . Indicator Control (pCi/ka) wet (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.I 1997 25.9 0 e1998 % ' ' " > < f52: we , * - v 20 - ' 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 (pCi/kg) (pCi/kg) (pCi/ka) 1978 Cc-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) l 4-36 rby -
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 1998, no radionuclides ofinterest 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 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 (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). 4-37 l
e Figure 4.9-1 Average Annual Cs-134 Concentration in Sediment 160 140 , 3 120
- l h' S100
-i 80 l /
\ /
"8' v ll h)[
, /\ / \ //
0: : : : : : : : : : :
/ V \. . :/
1 Po 77 78 79 80 81 82 83 84 85 66 87 88 89 90 91 92 93 94 95 96 97 98 Year l --+-Indicator Control MDCl 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 in part be attributed to the Chernobyl incident. The overall plotting of the positive results does not show any discernible trends. 4-38
Figure 4.9-2 i Average Annual Cs-137 Concentration in Sediment l 200 II 180 160 I T:n g 140 o S 120 i l ia o , 80 8 8 So ,l \ O f I\ 40
,, > I \ n 1 0 .
. 1 J \..
. .bDR.
l Po 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 Year l --+--indicator -G-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 Chernobylincident. 4-39
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 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 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 conducted by Analytics, Inc. of Atlanta, Georgia. Analytics has a documented QA (Quality Assurance) program and the capability to prepare QC (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 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 ofinstrument or procedural problems. 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 (counting statistics, calibration uncertainties, chemical yield etc.). The uncertainty of the reported average is the standard deviation of the analysis results performed by the EL. The precision of each result is measured by the coefficient of variation, which is defined as the standard deviation divided by the reponed 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%. 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 analysis of an air filter; the gamma isotopic analysis of an air filter, milk, and water samples; and the tritium analysis of water samples. Delineated in this table for each of the media / analysis combinations, are: the specific radionuclides: Ana'ytics' 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. For 1998. Co-58 was not available to Analytics, Inc., from radionuclide suppliers. Therefore, Co-58 was not included in the crosscheck samples supplied to the EL by Analytics, Inc. For this reason, no results for Co-58 were included in Table 5-1 for gamma isotopic analyses of the air filter, milk or water samples. It may be seen from Table 5-1 that of the 39 samples analyzed all results were satisfied for normalized deviation, with one exception. The analysis of I-131 in a j water sample prepared on 03/12/98 exceeded the normalized deviation 5-1
acceptance criterion of three. Also of the 39 analysis results, five exceeded the acceptance criterion of 15% for the coefficient of variation. The outcomes of investigations into these six results that failed to meet ICP acceptance criteria are provided in subsequent paragraphs. The activity recovery for the gamma analysis of 1-131 in water for the sample prepared on 03/12/98 exceeded the accuracy control limit. The sample was received on 03/16/98 but was not analyzed unti! 04/20/98. The level of activity by the analysis date was 3 pCi, which was not accurately measurable by gamma spectroscopy. Corrective actions consist of analyzing future intercomparison samples for gamma emitting radionuclides within one week of sample receipt. For the gamma isotopic analysis of Cr-51 in a water sample prepared on 03/12/98, the gamma isotopic analysis of Cr-51 in a water sample prepared on 06/11/98, the gamma isotopic analysis of Fe-59 in a water sample prepared on 03/12/98, the gamma isotopic analysis of Cr-51 in a milk sample prepared on 06/11/98, and the gamma isotopic analysis of Fe-59 in a milk sample prepared on 06/11/98, the coefficient of variation exceeded the control limit of 15%. Therefore, these analyses were investigated. The investigation revealed that the gamma isotopic analysis software indicated poor peak shapes and large counting uncertainties. The poor peak shapes were attributed to several factors including activity level, detector efficiency, and the gammas per disintegration for these radionuclides. The samples also contained higher energy gamma emitters that produced an increased background. The impact on analytical results caused by these problems was reflected in the large total measurement uncertainties reported for the five analyses in question. For each of these five samples, the 2 sigma uncertainty was greater than 20%, with the uncertainties for the five analyses ranging from 26% to 60%. The corrective action for gamma isotopic analyses with large measurement uncertainties entailed evaluating analyses of radionuclides with 2 sigma measurement uncertainties greater than 20%. The evaluation included statistical analysis of performance evaluation gamma spectroscopy samples to determine the appropnaie pn: cision limit. The evaluation found for Cr-51, as the concentration decreased and the total sample activity increased, the percent coefficient of variation in historical sample results also increased. As the total sample activity increased, the background for the 320 kev peak of Cr-51 also increased. At lower concentrations, the elevated background increased the uncertainty and the percent coefficient of variation for this radionuclide. For Fe-59 the evaluation found as the concentration decreased the percent coefficient of variation in historical sample results increased. As a result of this evaluation the precision limits for Cr-51 and Fe-59 have been revised as follows: Nuclide Concentration Total Sample Activity Percent Coefficient (pCi/ Liter) (pCl) of Variation Cr-51 <300 >1000 25 Cr-51 NA <1000 15 Fe-59 <80 NA 25 Fe-59 >80 NA 15 5-2
f en oo feoo'n f en oo Cit a Cia t Cita t t t nir nir nir ea c ea c 1 9 9 5 7 1 6 ea c 2 7 3 6 9 2 3 8 rV 5 0 rV 6 2 9 8 0 9 %.5 rV 3 3 1 7 3 8 3 8 6 ef ef 1 7 9 5 7 5 5 5 ef 0 6 0 4 0 4 8 9 5 Po 3 Po 1 Po 2 2 1 i d d d e zno e zn e zn i l i l o i l o ait ait ait mia rv 5 mia rv 8 8 2 7 8 6 2 6 8 6 2 2 0 6 0 6 mia rv 7 5 3 7 9 0 3 0 6 6 1 8 5 5 4 6 3 2 oe 0- ) oe 00 0 0 2 1 ) oe 0 0 0 0- 0 0 0 0 0-S ND r e ND - - - r e ND - T ) r t l i l t L e i f / i U t
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i C C l S i f dn dn p dn F / i ro ( p ro ( ro R C ait ait E ait p da ni v R da ni v 9 7 9 8 7 8 6 5 L da 9 8 2 1 8 ni v 0 6 78 6 5 6 6 5 M ( ae 7 1 E ae 6 2 3 1 7 0 0 4 P ta e I. 7 A R t SD T t SD 3 2 6 7 9 6 5 9 8 M SD 1 3 6 0 6 3 4 6 0 3 R E 1 L 1 A 1 1 1 T I l
)
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- S Y 5 O I t
nn L t nn Y t nn S L E C Y i aw t o A iwa t o A iwa t o L Y L r N r n r n C en e 7 7 3 7 7 N e 3 7 7 3 7 3 7 A R A cK A cK 6 6 3 6 6 A cK 3 6 6 3 6 3 6 O N nf C n 4 1 2 3 n 2 0 2 2 1 T T A Uo 1 I Uof 3 1 1 3 C I Uo f 1 1 1 1 A P P ll A O O R T O E T T B B O O A S S S n I n I n L R S weu A weu A we O ol na M ol na 5 0 6 9 6 0 2 6 olu na 2 6 5 3 2 5 0 9 7 E R 7 2 9 7 7 3 0 6 7 M 3 0 4 4 2 9 7 9 6 T G KV 5 M KV 2 1 2 1 1 1 M KV 1 1 1 1 N I l A A G G d 8 d 8 8 8 8 8 8 8 8 d 8 8 8 8 8 8 8 8 8 e e e r 9 .r 9 9 9 9 9 9 9 9 r 9 9 9 9 9 9 9 9 9 ep a / 4 ep
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;! !i{l f f en en oo oo Cita Cits t t :
nir nir ea 9 8 5 9 6 9 7 4 22 06 09 32 29 5 55 28 89 20 c e c a rV 2 6 5 1 4 I 0 5 I. rV 7 5 ef 6 2 8 6 8 6 . 7 4 0 6 4 6 5 8 0 6 1 7 ef 4 7 Po 1 2 I 1 1 Po 0 2 d d e zn e i o zn l ait i l o ait mi a rv 0 8 9 8 1 9 3 9 5 8 2 8 I. 4 3 3 9 7 4 2 7 2 6 7 0 3 5 5 4 5 8 0 8 5 4 mia rv 6 2
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)
2 O S P f R R M e P E d ~ 2 T ee A d ee N A t s ra S t g T O or R ra or E S W pe 4 9 3 7 6 E pe 0 0 E I ev 2 4 6 4 9 2 5 8 5 2 1 8 7 8 6 0 2 6 ev 7 6 H R F RA 9 4 1 1 1 1 2 1 8 6 7 6 1 5 7 0 3 1 2 T RA 9 2 A 1 1 1 O 1 1 5 3 S A ll ( P S W 1 M I y F y
- S t 5 O Y nn O t
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6 ar / / DP 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 DP 6 9 0 0 e e rid ri d ol c ol c su su in s yo 4 4 7 1 i sn l i 1 5- 9 0 5 3 3 4 yo ad 5- 5- 6- 6- 1 1 1 1 l i na n - - - 3 ad 3-r e o n s s c 1 na AR C M F C Z C C C l AR 1 1 { t
6.0 CONCLUSION
S , I Thir, report confirms the licensee's conformance with the requirements of TS 6.8.3.f and Chapter 4 of the ODCM during 1998. It provides summaries of data collection activities nd a discussion of the results of the laboratory analyses of the samples. All of the radiological levels were low and are generally trending downward. At community air sampling stations, 3 the annual average weekly gross beti concentration was 2.8 fCi/m greater than the average for control stations. Although this difference was very small, it was statistically discernible, since it 3 was greater than the MDD of 1.9 fCi/m between the two averages. However, the close agreement between the results for the indicator, community, and control stations supports the position that the plant's wntribution to gross beta concentration in air is insignificant. As measured by TLDs, the average quarterly direct radiation result found at indicator stations was 1.6 mR greater than that measured at control stations. l Although this difference was small, it was equal to the MDD and was, therefore, statistically discemible. However, this dose is not significant when compared to applicable dose limits for a member of the public and is consistent with previous years results. The tritium in river water downriver from the plant discharge structure was indicative of plant releases. The consequent dose due to this concentration of ' tritium in river water was shown to be less than 0.01% of the ODCM limit for liquid effluent releases. This dose is not significant and is consistent with previous years results. 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. :
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