ML20140E959
| ML20140E959 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1996 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9705020014 | |
| Download: ML20140E959 (49) | |
Text
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.1 D:v: Mor:y S;uthern Nuclear Vice President Operating Comp:ny Farley Project RO. Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 April 25, 1997 ggg COMPANY Energy to Serve YourWorld" Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant Radiological Environment.a!Operatina Report for 1996 Gentlemen:
The enclosed " Radiological Environmental Operating Report for 1996", 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, b
Dave Morey DNM/WHO s
Enclosure:
Subject Report xc: U. S. Nuclear Reculaton Commission Mr. L. A. Reyes, Region II Administrator f
Mr. T. M. Ross, FNP Senior Resident Inspector Mr. J. I. Zimmerman, NRR Project Manager f
State of Alabama Mr. K. E. Whatley h OO /
State of Geornia l
Mr. J. C. Hardeman, Jr.
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ALABAMA POWER COMPANY RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 1996 JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO. I r
LICENSE NO. NPF-2 t
AND UNIT NO. 2 LICENSE NO. NPF-8 I
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
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l TABLE OF CONTENTS SECTION TITLE PAGE I
INTRODUCTION 1
11 PROGRAM DESCRIPTION 2
Ill LABORATORY ANALYSIS RESULTS 7
i IV OTHER ACTIVITIES 14 V
CONCLUSIONS 17 l
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT i
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LIST OF FIGURES' 4
Figure Iitic 1
Indicator Stations for Monitoring Gaseous Releases 2
Community (Indicator II) Stations for Monitoring Gaseous Releases 3
Control Stations for Monitoring Gaseous Releases j
4 Indicator and Control Stations for Monitoring Liquid Releases i
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES Iahle Title 1
SUMMARY
DESCRIPTION OF REMP 2
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3
ANNUAL
SUMMARY
OF REMP RESULTS 4
INTERLABORATORY COMPARISON PROGRAM RESULTS i
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l ACRONYMS A2LA American Association of Laboratory Accreditation APCo Alabama Power Company ASTM American Society for Testing and Materials CL Confidence Level EL Environmental Laboratory i
EPA Environmental Protection Agency FNP Joseph M. Farley Nuclear Plant l
IPC Interlaboratory Comparison Program l
MDC Minimum Detectable Concentration i
MDD Minimum Detectable Difference MWe Megawatt electric NA Not Applicable NDM No Detectable Measurement (s)
NRC Nuclear Regulatory Commission l
ODCM Offsite Dose Calculation Manual l
PWR Pressurized Water Reactor l
QA Quality Assurance QC Quality Control l
REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SAIC Science Applications International Corporation TLD Thermoluminescent Dosimeter TS Technical Specifications l
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JOSEPH M. FARLEY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL OPERATING IEPORT I.
INTRODUCTION The Radiological Environmental Monitoring Program (REMP) for the Joseph M.
Farley Nuclear Plant (FNP) is conducted in accordance with Technical Specifications (TS) 6.8.3.f and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP activities for 1996 are reported herein in accordance with TS 6.9.1.6 and 6.9.1.7, and ODCM 7.1.
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The objectives of the REMP are to ascertain the levels of radiation and concentrations of radioactivity in the environs of FNP and to assess any radiological impact upon the environment due to plant operation.
The bases for such an assessment include appropriate comparisons between the i
results of the radiological analysis of REMP samples obtained at control stations (locations where radiological levels are not expected to be significantly affected by plant operation, that is, locations at background levels) with those at indicator stations (locations where it is anticipated that radiological levels are more likely to be affected by plant operation, such as, the plant perimeter), and comparisons between results obtained during preoperation with those obtained during operation. The preoperational stage of the REMP was conducted from its initiation in January 1975 until initial criticality of Unit I. Some samples are also collected at community stations which consist of population centers and other areas ofinterest; these stations are generally located in-between the indicator and the control stations.
FNP is owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company. It is located in Ilouston 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.
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Unit 2 was shutdown for its eleventh refueling outage from October 12 through December 18. There were no other significant outages during the year.
A description of the REMP - the samples to be analyzed, the locations for sampling, the sampling equipment and how the laboratory analyses of the samples are to be performed - is provided in Section II. The laboratory analysis results are discussed in Section III. Other REMP activities, the results of the land use census and the Interlaboratory Comparison Program (IPC), are presented in Section IV.
l Conclusions are stated in Section V.
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l II.
PROGRAM DESCRIPTION l
A summary description of the REMP is provided in Table 1. This table portrays the program in the manner by which it is being regularly carried out. Table 1 summarizes the programs requirements as outlined in ODCM Table 4-1 by j
l detailing the sample types for monitoring the airborne, direct radiation, waterborne and ingestion pathways and delineating the collection and analysis l
l frequencies. Table 1 also describes the locations of the indicator, community and control stations as spelled out in ODCM Table 4-4. The sampling locations are l
also depicted on maps in Figures 1 through 4.
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The location of each environmental monitoring station which monitors gaseous l
releases is described by its direction and distance from the point midway between the Unit I and Unit 11 plant vent stacks. The area surrounding this origin 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 l
monitoring station 0215 is located approximately 15 miles northeast of the origin.
l The locations for the sampling stations along the river are identified by the nearest l
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.
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In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule as set forth in Table 1 are permitted if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or otherjust reasons. All deviations which occurred from implementing the REMP during this reporting period are listed in Table 2 along with their cause and resolution.
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 sample analyses are 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. The A2LA is a nonprofit, nongovernmental, public service, membership society dedicated to the formal recognition of competent laboratories and related activities. Accreditation is based upon internationally accepted criteria for laboratory competence. (ISO /IEC l
Guide 25,1990, " General Requirements for the Competence of Calibration and Testing Laboratories")
A.
Airborne Particulates and Iodine The airborne particulate and iodine monitoring stations are equipped with FN-210B air samplers manufactured by Science Applications International Corporation (SAIC). Each air sampler is a modular unit consisting of a sample pump, regulator valve assembly, a microprocessor based air volume totalizer, an open faced combination filter holder and a thermostatically controlled exhaust fan, all mounted in a ventilated aluminum weather house. The air monitoring stations are also equipped with electrical surge protectors.
Sampled air flows vertically from top to bottom, first through a 47 millimeter Gelmin A/E glass fiber particulate filter, then through a 50 milihneter F&J activated charcoal cartridge which are installed in separate compadments of the combination filter holder. To compensate for dust buildup on the sarnple filters, the regulator valve assembly, located downstream of the combination filter holder, maintains a constant sample flowrate over a wide range of pressure differentials across the filters. The design of the filter holder allows uniform l
distribution of airborne particulates over the filter disk. The totalizers are l
calibrated using the SAIC Model C-812 calibrator.
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Charcoal cartridges and/or particulate filters are collected weekly at 4 indicator, 3'
3 community and 3 control stations as shown in Figures * ' and 3, respectively.
l Gross beta radioactivity measurements are performed on. :. air particulate filter using a low background gas flow proportional counting system. A gamma j,
isotopic analysis is performed quarterly _ on a composite of the particulate filters for each station using either a twenty percent or forty percent efficiency EGG-Ortec intrinsic germanium detector system.. The charcoal filters are analyzed for l
I-131 using the germanium detector system.
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Direct Radiation i
i Direct (external) radiation is measured utilizing Panasonic UD-814
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thermoluminescent dosimeters (TLDs) and a Panasonic UD-710A reader. Each j
TLD badge contains 3 phosphors which are composed of calcium sulfate (with 2
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thulium impurity) crystals and are encased in 860 mg/cm ofplastic and lead.
2 Each badge is sealed in a 10 mg/cm plastic bag to protect it from moisture L
while in the field. On the plant site, all TLD packets which are not in the field i
are kept in a lead safe with 2-inch walls.
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Two TLD stations are established in each of the 16 sectors forming two L
concentric rings. The stations comprising the inner ring, located near the plant i
perimeter and shown in Figure 1, are designated as the indicator stations. The j
community stations shown in Figure 2 consist of the outer ring stations which are located at approximate distances between 3 and 5 miles, plus 2 special interest areas, namely the nearest occupied residence (SW at 1.2 miles) and the.
City of Ashford (WSW at 8 miles). Each of the 6 control stations shown in Figure 3 are more than 10 miles from the plant.-
. At each TLD station, two TLD badges are exposed side-by-side. The badges are
,l nominally exposed for periods of a quarter of a year (91 days). For the i
computation of the net field doses, a log of all exposure periods is maintained l
for each TLD packet.
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Milk i
A milk sample is collected biweekly from one control station, the Bruce Ivey Dairy (Green Valley Farms) in Webb, Alabama which is located about 12 miles west of the plant as shown in Figure 3. As bome out by the results of the land use census, no indicator stations for milk are available. The samples are kept at a low temperature and shipped to the EL via overnight express. Gamma isotopic and I-131 analyses are performed on each sample.
The I-131 concentration in each sample is determined by collection on anion exchange resin, elution with sodium perchlorate, followed by precipitation as silver iodide and counting on a beta-gamma coincidence counter or a low background gas flow proportional counter. Stable iodide carrier is added to each sample for determination of the radiochemical yield. The concentration of stable iodine present in the sample before carrier addition is also determined and accounted for in the chemical yield determination. One liter of each sample is placed in a marinelli beaker and analyzed for gamma emitters using the germanium detector system.
D.
Forage Forage samples are collected monthly from 3 grass plots. The 2 indicator stations are on the plant perimeter as shown in Figure 1 and the control station is in Dothan about 18 miles west of the plant as shown in Figure 3. Aner the samples are chopped to a smaller size and mixed well,200 gram aliquots are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system.
E.
Ground Water In the FNP environs, there are no true indicator sources of ground water. A well which serves Georgia Pacific Paper Company as a source of potable water, located on the east bank of the Chattahoochee River about four miles south-southeast of the plant, is designated as the indicator station. A deep well which supplies water to the Whatley residence located about 1.2 miles southwest of the plant is designated as the control station. Samples are collected quarterly from each of these stations.
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Gamma isotopic, I-131 and tritium analyses are performed on each sample. The.
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gamma isotopic and tritium analyses are performed in the same manner as O
described below for surface water. The low level I-131 analysis is performed by l
precipitating one liter of sample as palladium iodide and counting the final palladium iodide precipitate on a beta-gamma coincidence counter or the low i
background gas flow proportional counter.
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Surface Water Water samples are collected from the Chattahoochee River at control and indicator stations which are respectively almost 3 miles upstream of the intake structure and almost 4 miles downstream of the discharge structure; these -
stations are shown in Figure 4. Using ISCO (Instrumentation Specialties Company) samplers, small aliquots are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. For each station, one liter from each of the collections for four consecutive weeks are combined to make composite samples for a 28 day interval. One liter of each of these composite samples is placed in a~ marinelli beaker and analyzed for gamma emitters using the germanium detector system.
The quarterly composite sample for each' station is composed of 75 ml from each of the weekly collections. An aliquot from each of the composite samples is distilled after mixing with sodium hydroxide and potassium permanganate, a liquid scintillation cocktail is then added and the analysis for tritium is conducted on a Beckman LS7800 Liquid Scintillation Counter.
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Fish-i Two types of fish, bottom feeding and game, are collected semiannually from the Chattahoochee River at a control location which is several miles upstream of the plant and at a indicator location which is a few miles downstream of the plant. These locations are shown in Figure 4. A gamma isotopic analysis is performed on the edible portions of each sample. The fillets from each species collected at a station are chopped to a smaller size and mixed well,450g aliquots -
are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system.
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River Sediment Sediment samples are collected semiannually from the shoreline of the Chattahoochee River at a control station which is approximately 3 miles i
upstream of the intake structure and at an indicator station which is approximately 2 miles downstream of the discharge structure. A gamma isotopic analysis is performed on each sample. After each sample is dried, ground and well mixed, aliquots are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system.
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III.
LABORATORY ANALYSIS RESULTS 1
In accordance with ODCM 7.1.2.1, summarized and tabulated results of the laboratory analyses for all of the regular samples collected for the year at the designated indicator, community and control stations are presented in Table 3 in a format similar to that found in Table 3 of the Nuclear Regulatory Commission (NRC) Radiological Assessment Branch Technical Position, Revision 1, November 1979. Since no reportable occurrences were called for during the year, the column entitled " Number of Reportable Occurrences" has been excluded from Table 3.
In accordance with ODCM 4.1.1.2.2, only the naturally occurring radionuclides which are found in the plant's effluent releases need be reported. The only J
naturally occurring radionuclide found in the plant's efHuent releases is Be-7.
Hence, the radionuclides ofinterest for the samples monitoring liquid releases (surface water, fish and river sediment) are man-made radionuclides plus Be-7, while only man-made radionuclides are ofinterest for the other REMP samples.
During 1996, Be-7 was not detected in any of the samples monitoring liquid releases.
An interpretation and evaluation, as appropriate, of the laboratory results for each type sample are included in this section. Relevant comparisons are made between the difference in average values for different station groups (such as the indicator and control stations or the indicator and community stations) and the calculated Minimum Detectable Diffeience (MDD) between these groups at the 99 perc>at Confidence Level (CL). The MDD is determined using the standard Student's t-test. A difference in the average values which is less than the MDD is considered to be statistically indiscernible.
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Pertinent results are also compared with past results including those obtained during preoperation. The results are examined to perceive any trends. To provide perspective, a result might also be compared with its Reporting Level (RL) or Minimum Detectable Concentration (MDC) whose nominal values are found in ODCM Tables 4-2 and 4-3, respectively. During the year there were no failures in the laboratory analyses for any of the samples in attaining the MDCs required by ODCM Table 4-3.
All results are tested for conformance to Chauvenet's criterion (G. D. Chase and J.
L. Rabinowetz, Princinles of Radioisotone Methodology, Burgess Publishing Company,1962, pages 87-90) to flag any values which might differ from the others in its set by a relatively large amount. Identified outliers are investigated to determine reason (s) for deviation from the norm. If the deviation is due to an equipment malfunction or other valid physical reason, the anomalous result is deemed non-representative and excluded from the data set. No datum is excluded for failing Chauvenet's criterion only. Any exclusions are discussed in this section under the appropriate sample type.
The series of detonations of nuclear devices in weapons tests conducted on the mainland of China prior to and during preoperation, and the early years of operation had a significant impact upon the radiological levels found in some of the samples for several years afterwards. These atmospheric tests occurred on:
January 7,1972; March 13,1972 September 26,1976; November 17,1976; September 17,1977;
. March 14,1978; December 14,1978; and October 15,1980.
Significant uptrends in the results also followed the Chernobyl incident in the Ukraine which began on April 26,1986 1
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A.
Airborne Particulates and Iodines As seen in Table 3, the annual average weekl gross beta activity of 20.3 7
3 fCi/m for the indicator stations is 3.2 fCi/m less than that for the 3
community stations and 2.0 fCi/m less than that for the control stations.
3 For each of these cases, the MDD was calculated as 1.5 fCi/m. Since each of these differences is greater than its MDD, there is a discernible difference between the average levels at the indicator stations and those for the other two station groups.
During preoperation and the early years of operation the average gross beta readings were 5 to 10 times greater than those currently being obtained. By the mid 1980s, the readings had diminished to about half the current levels.
These annual averages about doubled with the Chernobyl incident in 1986; this impact faded away after a year or two. The installation of new air monitoring equipment in 1992 brought a step increase in the readings, roughly by a factor of two. Subsequently, the levels have been fairly flat.
During 1996, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters for each station. This has generally been the case after the impact of the weapons tests and the Chernobyl incident had faded away. During preoperation and the early years of operation, a number of fission and activation products were detected at low levels. For example, during preoperation, the average positive levels for Cs-134 and Cs-137 were 22 and 3
9 fCi/m, respectively. For 1986, as a consequence of the Chernobyl 3
incident, cesium levels of around 3 or 4 fCi/m were found. It might be 3
noted that the MDC for Cs-134 and Cs-137 are 50 and 60 fCi/m.
Airborne 1-131 is not normally detected in the charcoal canisters and 1996 was no exception. In an early year of operation (1978), levels between 40 3
and 50 fCi/m were found in a few samples; then after the Chernobyl i
3 incident, levels up to a few hundred fCi/m were found in a number of samples. At no other times has airbome I-131 been detected in the environmental samples.
Listed in Table 2 are a number of deviations which occurred during the year. In each case, the affected samples were tested for conformance with l
Chauvenet's Criterion; in one case, the particulate filter collected December 24 at Station 1108, the criterion was not satisfied; the result for that sample j
was thus deemed nonrepresentative and excluded from the data set.
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External Radiation As indicated by Table 3, the average quarterly exposure of 14.21 mR acquired at the indicator stations was 2.31 and 1.55 mR greater than that for the community and control stations, respectively. Each of these differences is discernible as each is greater than the MDDs calculated as 0.91 mR between the indicator and community stations, and 1.49 mR between the indicator and control stations.
These differences between the station groups for 1996 are typical, of but slightly less than those found in recent years. For example, during the previous 6 years (1990 through 1995), the average quarterly exposure at the indicator stations was 2.50 and 2.05 mR greater than that at the community and control stations, respectively.
The results for the second quarter at Station 0405 were excluded from the data base after failing to conform with Chauvenet's Criterion. The second quarter results for Station 1504 and the fourth quarter results for Stations 0405 and 0505 are also not in the data base because the badges at these stations were lost in the field. The details for these deviations are provided in Table i.
The result for TLD badge 0104A exposed during the first quarter was excluded from the data base because the standard deviation was greater than 1.4. In cases like this, the reading for the companion badge only is used to determine the quarterly doses for the station.
The standard deviation limit of 1.4 was calculated using a method developed by the American Society for Testing and Materials (ASTM). (ASTM Special Technical Publication ISD, ASTM Manual on Presentation of Data and Control Chart Analysis. Fourth Revision, Philadelphia, PA, October 1976) The calculation was based upon the standard deviations obtained by the EL with the Panasonic UD-814 badges during 1992. This limit serves as a flag to evoke 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.
No reason was found for the high deviation obtained with TLD badge 0104A for the first quarter. It was visually inspected under a microscope; the glow curve and test results for the anneal data and the element correction factors were reviewed.
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Milk Not since the early years of operation have any positive results been found from either the gamma isotopic or the I-131 analyses. During preoperation, some results for I-131 were over a hundred pCi/1, while the average positive results for Cs-137 were around 30 pCi/l. In the second year of operation (1978), the average positive results were 21 and 16 pCi/l for I-131 and Cs-137, respecti.<ly. During these periods, positive results were found in only about a fifth of the samples. The MDC and RL for I-131 are 1 and 3 pCi/1, respectively; for Cs-137,18 and 70 pCi/1.
D.
Vegetation No man-made radionuclides were detected from the gamma isotopic analysis of the forage samples during 1995 and 1996. In 1994, Cs-137 was found in two samples at the control station; the average level was 24 pCi/kg wet. Since 1986, only Cs-137 has been found; since 1988, it has been found in only one or two samples each year out of the 35 to 40 samples collected.
During preoperation, the early years of operation and in 1986 (the year of the Chernobyl incident), Cs-137 was found in about a third of the samples and the levels were about 10 times greater than those found in recent years.
The MDC and RL for Cs-137 in forage are 80 and 2000 pCi/kg wet, respectively.
In these earlier periods, I-131 was found at very high levels which ranged from around 100 to 1500 pCi/kg dry. The MDC and RL for I-131 are 60 and 100 pCi/kg wet, respectively. In 1978,1980 and 1981, a number of fission and activation products were also found in the forage samples.
There has been a steady decline in the number of radionuclides detected, their level and the frequency at which they are found.
E.
Ground Water As usual, no radionuclides were detected from any of the analyses (gamma isotopic,I-131 and tritium) of the samples. During preoperation and through 1983, tritium was found at levels of a few hundred pCi/l in a few of the samples each year. The MDC and RL of tritium is 2000 and 20,000 pCi/l, respectively.
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Surface Water As usual no positive results were found from the gamma isotopic analysis of the samples collected during 1996. Prior to 1987 low levels of Cs-134 and
. Cs-137 were detected in some of the samples.
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. As may be seen from Table 3, tritium was found in only two of the 8 l
samples collected; both at the indicator station. The levels of 360 and 412 pCi/l are typical of the results found in the past. Generally speaking the l
annual average levels at the indicator station have been a little greater (by i
one to two hundred pCi/l) than those at the control station.' The highest
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annual level in the past was around 500 pCi/1. In general, there appears to
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be a slight downward trend in the levels as well as the frequency at _which positive results are found. Tritium was detected in only one sample during j
1995 and none in 1994 (the only year in which there were no detectable results).
Beginning in 1996, a small quantity of acid was added to the liquid effluent samples to preclude plateout. Since this practice was not followed with the 1
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environmental surface water samples, it is possible that some radionuclides
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may have not been detected; this might be con.sidered to be a deviation. A l
procedure change has been made to assure the prevention of any plateout in l
the future. There were also deviations regarding the collections at the l
control station on four occasions and at the indicator station on two occasions. Details are given in Table 2.
G.
Fish I
i As may be seen from Table 3, Cs-137 was the only radionuclide ofinterest 3
which was found from the gamma isotopic analysis. -For the bottom feeding fish, it was found in only one of the two samples collected at each station; i
the levels at the indicator and control stations were 16.4 and 9.9 pCi/kg wet, l
respectively. For the game fish, it was found in each sample. The average l
level at the indicator station of 19.6 pCi/kg wet was 3.5 pCi/kg wet less than that found at the control station; this difference is not discernible since it is less than the MDD of 20.7 pCi/kg wet.
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Over the years, Cs-l ? - is been found in about 85% of the game fish samples but in only ae.id 30% of the bottom feeding fish samples. Every year (except one) the 4verage levels for the game fish have been greater than those for the bottom feeding fish, typically about 50% greater. During preoperation, the levels were about 5 times greater than the current levels; during 1980 and 1981, they were an order of magnitude greater.
On only a few occasions in the past have radionuclides ofinterest other than Cs-137 been found. In 1986 (the year of the Chernobyl incident), Co-60 was found at a level of 25 pCi/kg wet in one of the two game fish samples collected at the indicator station. In 1982, Nb-95 was found at a level of 31 pCi/kg wet in one of the 3 game fish samples from the indicator station. In 1981, Nb-95 was found at a level of 38 pCi/kg wet in one of the 2 bottom feeding samples from the indicator station. The impact of the weapons test was strong during the early eighties.
As may be seen in Table 1, the location of the indicator station is specified as RM 41. The collections during 1996 were made between RM 42 and 43 as no fish were found at RM 41. A review of past records showed that during 1995, collections were made between RM 42.5 and 43. Details of these deviations are provided in Table 2. The ODCM is to be modified to provide upstream as well as downstream stretches of the river of a few miles from which control as well as indicator fish samples may be collected.
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Sediment During 1996, Cs-137 was found in one of the two samples collected at the indicator station; the level was 11.8 pCi/xg dry. The MDC for Cs-137 in i
sediment is 180 pCi/kg dry. No other radionuclides ofinterest were detected.
In previous years, Be-7, Nb-95, Cs-134 and Cs-137 have been detected in only a few samples. Except for two of each of the cesium isotopes, these positive results were for samples collected et the control station. Be-7 was detected only once, in 1985 at a level of 945 pCi/kg dry; its MDC is 655 l
pCi/kg F Nb-95 was also detected only once,in 1981 at a level of 113 pCi/kg dry; its MDC is 50 pCi/kg dry. Cs-134 has been detected six times at levels ranging from 45 to 138 pCi/kg dry;its MDC is 150 pCi/kg dry.
Cs-137 has been detected seven times at levels ranging from 11 to 185 pCi/kg dry; its MDC is 180 pCi/kg dry. No trend is recognized from these data.
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IV.
OTHER ACTIVITIES l
A Land Use Census i
l An annual land use census as required by TS 6.8.3.f(ii) and ODCM 4.1.2 was conducted on June 5,1996 to determine the locations of the nearest milk animal and the nearest permanent resident in each of the 16 meteorological sectors, within a distance of 5 miles. A milk animal is a cow or goat producing milk for human consumption. No milk animals were found within a distance of 5 miles. In the NNW sector, the location of the l
nearest resident changed from 3.3 to 2.0 miles; the location of the nearest resident in the other sectors remained the same.
l The Houston County, Alabama Livestock Agent and the Early County, l
Georgia Extension Agent were contacted for assistance in locating commercial dairy farms and privately owned milk animals within 5 miles of the plant. A list of commercial dairy farms in Houston County was provided; there are no commercial dairy farms in Early County. Neither agent knew of privately owned milk animals within 5 miles of FNP. In addition, field surveys were conducted in the plant vicinity along the state i
and county highways and the interconnecting secondary roads. No milk animals were located within 5 miles of the plant.
l ODCM 4.1.2.2.1 requires a new controlling receptor in ODCM 3.4.3, if the land use census identifies a location which would yield a calculated dose greater than that currently being calculated. The only land use census result that could precipitate a new controlling receptor is the location of the new nearest resident in the NNW sector.
The current controlling receptor as described in ODCM Table 3-7 is a child in the SW Sector at 1.2 miles receiving dose via the inhalation, ground plane, vegetable garden and cow meat pathways. The new nearest resident in the NNW sector receives dose only though the inhalation and ground plane pathways; in addition the dose received though each of these two pathways would be less than that received by the current controlling receptor since the dispersion and deposition parameters for the mixed mode i
and ground plane releases at the location of the new nearest residence in the NNW sector are each less than those of the current controlling receptor as shown in ODCM Tables 8-2 through 8-5. Thus, the land use census confirms the validity of the current controlling receptor.
l l
\\
i 14 l
B.
Interlaboratory Comparison Program l
l In conformance with ODCM 4.1.3, the EL participates in an ICP which i
satisfies the requirements of Regulatory Guide 4.15, Revision 1, " Quality l
Assurance for Radiological Monitoring Programs (Normal Operations) -
l Effluent Streams and the Environment", February 1979. The guide l
indicates that the ICP is to be conducted with the EPA's (Environmental l
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 both offered by the EPA and included in the REMP. The ICP had been conducted utilizing the EPA program through the end of 1995 when it became unavailable to utilities.
Like the EPA program, the replacement ICP which was initiated at the beginning of 1996 is a third party blind testing program which provides a means to ensure independent checks are performed on the precision and i
accuracy of the measurements of radioactive materials in environmental sample matrices. It includes essentially the same determinations with the same frequencies that had been utilized with the EPA program.
The replacement 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 in a manner that ensures tracability to the National Institute of Standards and Technology.
Analytics provides the cross check samples to the EL who performs the laboratory analyses and sends their results to Analytics for statistical J
analyses. The documented evaluations provided by Analytics can be helpful to the EL in identifying any instrument or procedural problems.
Reported herein, as required by ODCM 4.1.3.3 and 7.1.2.3 is a summary of the results of the EL's participation in the ICP. Summarized in Table 4 are the results obtained during 1996 for: the single analyses of beta-ray and gamma-ray emitters in air filters and gamma-ray emitters in milk; and the two analyses for tritium and gamma-ray emitters in water samples.
Delineated in Table 4 for each of the media / analysis combinations are: the specific radionuclides, Analytics's preparation dates, the known values, the expected precisions, the average results obtained with their standard deviations, and the resultant normalized deviations and normalized ranges.
The normalized deviations and normalized ranges are calculated using the methodology of the EPA program.
15
i i
l' The normalized deviation from the known value provides a measure of the J
central tendency of the data (accuracy). The normalized range is a measure of the dispersion of the data (precision). An absolute value of 3 standard -
i l
deviations for the normalized deviation and for the normalized range was j'
established by the EPA as the control limit. An absolute value of 2 standard
' deviations was established by the EL as the warning limit. Investigations are undertaken whenever any value exceeds the warning or control limits.
i
[
The program supplied by Analytics, although simil'ar to the EPA's, did 1
l possess differences that posed problems in the analyses. These differences p
are outlined below along with the investigative determinations and any planned corrective actions.
[
The control limits of the normalized deviation for both Sr-89 and Sr-90 were exceeded in the analysis for the beta-ray emitters in air filters. The
~
activity recovery for both radionuclides was low. QC spikes were prepared to evaluate the self absorption curves. The curves were found to be valid.
The cross-check water sample for Sr-89/90 (used for the effiuents program)
]
was analyzed with excellent results; these accurate results indicate a processing problem with the air filters. The air filters were packaged with a plastic wrap. The wrap was not dissolved with the filter. In the future, the l
filter wrap will be processed with the filter; also, the counting time may be increased.
5 The warning and control limits for the normalized deviation of the analysis for gamma-ray emitters in air filters were exceeded for one and three of the radion"clides, respectively. The Analytic's air filters contained nine gamma-ray emitters whereas Cs-137 was the only the gamma-ray emitter in the EPA air filters. The standard used in calibrating the detectors was recounted and the activity recovery exceeded 95%. Geometry differences were ruled outJ The background corrections for the germanium detectors are being reviewed as a possible source of bias.
16
I Regarding the analysis for the gamma-ray emitters in milk: the warning limit for the normalized deviation was exceeded for one radionuclide while the control limit was exceeded for three radionuclides; the warning and control limits for the normalized range were each exceeded for one radionuclide. For the two analyses of the gamma-ray emitters in water: the warning and control limits for the normalized deviation were each exceeded for three radionuclides; the warning and control limits for the normalized range were respectively exceeded for one and two of the radionuclides.
Each milk and water sample contained the same nine gamma-ray emitters as the air filters. Analytics provided diluted one liter samples of milk and I
water. The one liter sample may be replaced with a 4 liter sample to improve the statistics. The background corrections for the germanium detectors are being reviewed as a possible source of bias, l
A low concentration ofI-131 was also present in the milk sample but not in the water samples. The concentration was substantially reduced by decay j
due to the 5 days in transit from Analytics to the EL. The level had become too low for detection by the gamma detectors; it could have been detected by the chemical separation process, however. With the EPA samples, the activity had always been sufficient for measurement by the gamma detectors. Plans for a larger sample and longer counting times will improve the probability of detecting I-131 on the gamma counters.
V.
CONCLUSIONS This report confirms the licensee's conformance with the requirements of TS 6.8.3.f and Chapter 4 of the ODCM during 1996. A summary and discussion of the results of the laboratory analyses for each type sample were presented.
All of the radiological levels were low and generally trending downward. No radiological impact upon the environment or to the public as a consequence of plant discharges to the atmosphere and to the river was recognized.
17
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Figure 4
TABLE 1-
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathways Sampling Type and Frequency f
with and of
-l
)
. Sample Types and Locations Collection Frequency Analysis
[
I AIRBORNE 1
i i
Particulates Continuous sampler operation with Particulate sampler:
sample collection once per 7 days.
Indicator Stations:
Analyze for gross beta River Intake Structure (ESE-0.8) radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> -
l South Perimeter (SSE-1.0) following filter change.
l Plant Entrance (WSW-0.9)
Perform gamma isotopic
. North Perimeter (N-0.8) analysis on each sample when gross beta activity Community Stations:
is >10 times the yearly
[
Georgia Pacific Paper Co. (SSE-3) mean ofcontrol samples.
l Ashford, AL. (WSW-8)
Perform gamma isotopic Columbia, AL. (N-5) analysis on composite i
(by location) sample at t
Control Stations:
least once per 92 days.
l Blakely, GA. (NE-15)
[
Neals Landing, FL. (SSE-18)
Dothan, AL. (W-18) i i
l Iodme Continuous sampler operation with Radioiodine canister:
sample collection once per 7 days.
i Indicator Stations:
Analyze for I-131 at
[
River Intake Structure (ESE-0.8) least once per 7 days.
l South Perimeter (SSE-1.0)
J Plant Entrance (WSW-0.9) j North Perimeter (N-0.8) f I
i Page1of5 h
=.
TABLE 11 l
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathways Sampling Type and Frequency with and of Sample Types and Locations Collection Frequency Analysis t
2 Community Station:
j Georgia Pacific Paper Co. (SSE-3)
Control Stations:
Blakely, GA. (NE-15)
Neals Landing, FL. (SSE-18) l Dothan, AL. (W-18)
DIRECT RADIATION At least once per 92 days.
Gamma dose:
Indicator I Stations:
Readout at least once Sixteen stations, one in each meteorological per 92 days.
sector alcng the plant perimeter (N-0.8, NNE-0.9, NE-1.0, ENE-0.9, F,-0.8, ESE-0.8, SE-1.1, SSE-1.0, S-1.0, SSW-1.0, SW-0.9, WSW-0.9, W-0.8, WNW-0.8, NW-1.1, and NNW-0.9).
[
Indicator II(Community) Stations:
Sixteen stations: At least one in each meteorological l
sector at a distance of 3 to 5 miles (NNE-4, NE-4, ENE-4, E-5, ESE-5, SE-5, SSE-3, S-5, SSW-4, SW-5, I
WSW-4, W-4, WNW-4, NW-4, NNW-4, and N-5).
Special Interest Stations:
Occupied residence nearest the plant site (SW-1.2)
)
City of Ashford, AL (WSW-8.0) l Page 2 of 5
=
=
1 TABLE 1 i
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t
Exposure Pathways Sampling Type and Frequency -
with and of Sample Types and Locations Collection Frequency.
Analysis i
Control Stations:
Blakely, GA. (NE-15)
Neals Landing, FL. (SSE-18)
Dothan, AL. (W-18)
- Dothan, AL. (W-15)
Webb, AL. (WNW-11)
Haleburg, AL.(N-12)
WATERBORNE Etrface Water Composite taken with proportional Monthly gamma isotopic semi-continuous sampler, having a analysis ofeach composite Indicator Station:
minimum sampling frequency not sample. Tritium analysis Paper Mill,(3 mile downstream exceeding two hours, cellected over of each composite sample of plant discharge, RM 40) a period s 31 days.
at least once per 92 days.
Control Station:
Upstream of Andrews Lock and Dam l
(-3 miles upstream of plant intake, RM 47) t Ground Water Grab sample taken at least Gamma isotopic and tritium i
once per 92 days.
analyses of each sample Indicator Station:
once per quarter.
Paper Mill. Weil, (SSE-4) i Control Station:
Whatley Residence Well (SW-1.2) j Page 3 of 5 I
- -. =
TABLE 1 I
1
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
Exposure Pathways Sampling Type and Frequency with and
-of Sample Types and Locations Collection Frequency
. Analysis l
i River Sediment Grab sample taken at least Gamma isotopic analysis of l
once per 184 days.
each sample twice per year
?
Indicator Station:
Downstream of plant discharge at Smith's Bend (RM 41)
Control Station:
Upstream of plent discharge j
at Andrews Lock & Dam Reservoir (RM 47) f INGESTION r
hhlk At least once per 16 days.
Gamma isotopic and I-131 analyses ofeach biweekly j
Control Station:
sample when animals are on Ivey Dairy (Green Valley Farms) pasture; otherwise monthly.
Webb, AL. (W-12)
{
-f i
Eish One sample for each of the following Gamma isotopic analysis Control Station:
species at least once per each season on edible portions once.
i Downstream of plant discharge in (03/15 - 05/15 and 09/15 - 11/15) per season.
j vicinity of Smith's Bend (RM 41)
- 1. Game Fish
- 2. Bottom Feeding Fish.
i Control Station:
Upstream of plant discharge in Andrews Lock & Dam Reservoir (RM 47)
Page 4 of 5
TABLEl
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -
Exposure Pathways -
Sampling Type and Frequency -
with and of' Sample Types and Locations Collection Frequency Analysis Forage Grab sample from green forage Gamma isotopic analysis at least once per 31 days.
(which includes I-131)
Indicator Station:
of each monthly sample.
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
(
Control Station:
Dothan, AL. (W-18) t
)
i I
.E i
i i
i i
Page 5 of 5 l
i i
TABLE 2 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATEfflME SAMPLES /
DEVIATION CAUSE RESOLUTION of Discovery STATIONS 12-27-95 / 0930 Surface Water /
Eight aliquots were not drawn at The collection schedule was Procedure was changed to permit a WRI & WRB each of the stations; consequently, delayed one day due to the greater number of aliquots to be monitoring was not performed for holidays. Samplers had drawn drawn.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
the maximum number of samples for which they were programmed.
02-06-96/1219 Airborne Monitoring was not performed for Power was offin the area due to Power was restored to the area.
Particulate /
2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
extremely cold weather.
PC-1108 02-20-96/1310 Airborne Monitoring was not performed for Power was oirwhile breaker Power was restored.
Particulates and 36 minutes.
work was performed.
Radioiodine /
PI-0701 & 1101 and II-0701 &
1101 02-27-96/0933 Airbome Monitoring was effectively not The particulate filter appeared to Installed new particulate filter and Particulate and performed for about 2.5 days.
have become clogged reducing charcoal cartridge, and observed Radioiodine /
the air flow to effectively zero.
air flow.
PC-0703 and IC 0703 03-12-96/ 1256 Airborne Monitoring was not performed for Power was lost due to a Power was restored after Particulate and about 8 days.
lightning strike after operating installation of a lightning arrestor.
Radioiodine /
for only 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />. Restart was PI-1601 and II-delayed 2 days awaiting the 1601 installation of a lightning arrestor.
Page1of4
TABLE 2 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATE/ TIME SAMPLES /
DEVIATION CAUSE RESOLUTION of Discovery STATIONS 03-26-96/ I150 Airborne Monitoring was not performed for Pump was not running as fuse Pump was replaced.
Particulate and a few hours.
had blown.
Radiciodine /
PI-l101 and II-1101 04-02-96 / 0755 Airborne Monitoring was not performed for Power was lost probably due to Power was restored.
Particulate and about 5 days.
lightning strike after operating Radiciodine /
for about 4 days. Restart was PI-1601 and II-achieved on 04/04/96.
1601 05-14-96 / 1025 TLDs / RC-0405 Direct radiation exposure results Both TLD badges were found to Replacement badges were installed A&B for 42 days were lost.
be missing when checked in mid to monitor direct radiation quarter.
exposure for the remainder of the 2nd quarter.
07-03-96/0735 TLDs / RC-1504 Direct radiation exposure results Both TLD badges were missing Regular badges were installed to A&B for 2nd quarter were lost.
at end of quarter; it appeared monitor direct radiation exposure they had been run over by a for the next quarter.
mower.
07-09-96/ 1135 Surface Water /
Monitoring was not performed for Insufficient volume collected Replaced tubing, restarted WRB 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />.
due to split pump tubing.
sampling. Increased frequency for the routine replacement of pump tubing.
07-23-96/0943 Surface Water /
Monitoring was not performed for Supply tubing to sampler Attached tubing securely using a WRI about 2 days.
became unattached.
hose clamp.
08-27-96/0848 Airborne Monitoring was not performed for Breaker was found tripped.
Reset breaker and observed pumps Particulate and about 2.8 days.
performance.
Radioiodine /
PB-0718 and IB-0718 Page 2 of 4
a TABLE 2 i
DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DATFIFIME SAMPLES /
DEVIATION CAUSE RESOLUTION of Discovery STATIONS 09-24-96 / 1144 Surface Water /
Monitoring was not performed for Very little sample collected due A fresh battery was installed.
WRB 1 week.
to dead battery; a depleted rather than a fresh battery had been inadvertently installed.
10/15/96/ 1012 Airborne Monitoring was not performed for A general power outage in the Power was restored to the area.
Particulate and about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
area occurred.
Radioiodine /
PC-0703 and IC-0703 t
12-24-96/ 0620 Airborne Monitoring was not performed for Power was offin the area due to Power was restored to the area.
Particulate / PC-about 6.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
cold weather.
I108 12-24-96/ 1130 Surface Water /
Five aliquots were not drawn; Battery was dead as it had been A fresh battery was installed. The l
WRB consequently, monitoring was not charged for an insufficient time.
charging period for batteries was performed for about 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
increased.
i 12-31-96 / 0914 TLDs / RC-0405 Direct radiation exposure results Both TLD badges at these The nearby areas were searched to A & B and RC-for 4th quarter were lost.
stations were missing at the end no avail. Regular badges were 0505 A & B of the quarter; they were installed to monitor direct probably stolen.
radiation exposure for the next quarter.
04-03-95, Bottom Feeding Collections were outside location Fish were not present at the An ODCM change which is to be 09-26-95,
& Game Fish /
specified in ODCM.
location specified in ODCM.
submitted will provide a stretch of 04-16-96, and 09 FBI & FGI the river of a few miles from 18-96 which fish samples may be collected.
Page 3 of 4
TABLE 2 DEVIATIONS FROM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
~
DATEfrIME SAMPLES /
DEVIATION CAUSE RESOLUTION of Discovery STATIONS 01/16,02/13, Surface Water /
Sample preparation inadequate to Procedural inadequacy Sample preparation procedure was 03/12,04/09, WRI & WRB assure prevention of plateout of revised to add a small quantity of 05/07,06/04, possible radionuclides in samples.
acid to preclude plateout.
07/02,07/30, 08/27,09/24, 10/22,11/19, and 12/17/96 Page 4 of 4 t
~.+-
TABLE 3 (SHEET 1 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 ilouston County, Alabama Type and Minimum Indicator Indicator Location With Community Control Total Number Detectable Locations Highest Annual Mean Locations Locations ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction) 3 AIRBORNE PARTICULATES (fri/m )
Gross Beta 10 203 Pit. Perim.
22.7 23.5 223 530 8-37 0.8 miles 8-37 11-44 8-450 (212/212)
N (53/53)
(158/159)
(159/159)-
Gamma Isotopic 40
.1-131 70 NDM(c)
NA (d)
NDM NDM (0/16)
(0/12)
(0/12)
Cs-134 50 NDM NA NDM NDM (0/16)
(0/12)
(0/12)
Cs-137 60 NDM NA NDM NDM (0/16)
(0/12)
(0/12) 3 AIRBORNE RADIOIODINE (fCi/m )
l-131 70 NDM NA NDM NDM 424 (0/212)
(0/53)
(0/159)
,u
___._m,_
m
- a
.m
.o......
.m.
TABLE 3 (SHEET 2 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 i
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama j
I Type and Minimum Indicator Indicator Location With Community Control Total Number Detectable Locations Highest Annual Mean Locations Locations ofAnalyses Concentration Mean (b), hnge Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction) -
(Fraction)
DIRECT RADIATION (mR/91 days)
Gamma Dose NA 14.2 Plt. Perim.
21.5 11.9
.12.7 160 10-23 0.8 miles 20-23 9-14 10-16 (64/64)
E (4/4)
(68/72)
(24/24)
MILK (nCI/1)
Gamma lsotopic 27 Cs-134 15 NA NA NA NDM l
(0/27)
Ba-140 60 NA NA NA NDM (0/27) l La-140 15 NA NA NA NDM (0/27) 1-131 1
NA NA NA NDM 27 (0/27) t
[
t i
TABLE 3 (SIIEET 3 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Nue: ear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Type and Minimum -
Indicator Indicator Location With Community Control Total Nuaber Detectable Locations Highest Annual Mean Locations Locations of Analyses.
Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction)
FORAGE (oCi/kg wet)
I Gamma Isotopic 39 l-131 60 NDM NA NA NDM t
.(0/26)
(0/13)
Cs-134 60 NDM NA NA NDM (0/26)
(0/13) j Cs-137 80 NDM NA NA NDM (0/26)
(0/13) f GROUND WATER (oCi/1) 11-3 2000 NDM NA NA NDM j
8 (0/4)
(0/4)
T I-131 I
(0/4)
(0/4) f I
i
\\
TABLE 3 (SHEET 4 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROCRAM
SUMMARY
FOR 1996 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Type and Minimum
_ Indicator Indicator Location With Community
. Control Total Number Detectable Locations flighest Annual Mean Locations Locations ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction)
Gamma Isotopic 8
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
(0/4)
~.
...~. - - - - - ~ - -....
e TABLE 3 (SHEET 5 OF 10) a RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMARi FOR 1996 Farley Nuclear Plant. Docket Nos. 50-348 and 50- M4 Houston County, Alabama Type and Minimum Indicator Indicater Location With Community Control l
Total Number Detectable Locations Highest Annual Mean Locations Locations ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range i
Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction)
[
i Cs-137
(0/4)
(0/4) l
[
(0/4)
SURFACE WATER (oCi/l) j H-3 3000 386 Paper Co.
386 NA NDM 8
360-412 3 miles 360-412
. (0/4)
(2/4)
Downstream (2/4)
Gamma Iso:apic i
26 be-7 124 (e)
(0/13)
(0/13)
(0/13)
(0/13) 1
'l
^.
' TABLE 3 (SHEET 6 OF 10) l 1
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 f
Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama p
Type and Minimum Indicator Indicator Location With Community Control i
Total Number Detectable Locations Hinhest Annual Mean Locr. tie as Imcations ofAnalyses Concentration
- ean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
~ (Fraction) f 2
[
(0/13)
(0/13)
[
[
13)
(0/13) f Zn-65 30 NDM NA NA NDM I
(0/13)
@/13)
(0/13)
(0!!3) t-:31 15 NDM NA NA NDM i
(0/13)
(0/13) i Cs-134 15 NDM NA NA NDM (0!!3)
(0/13) l 1
I Cs-137 18 NDM NA NA NDM (0/13)
(0/13)
}
(0/13)
(0/13)
?
_... _... ~. _ _.... _ _. _ - - - - - - -- - - _ - - _ - - _ - - - - - - - --- - - - - - - -. - - - - - - - - - - - - - - _
?
o TABLE 3 (SHEET 7 OF 10)
).
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama j
h Minimum
. Indicator Indicator Location With Community Control f
Type and
' Detectable Locations Ilighest Annual Mean -
Locations Locations
-}
Total Number ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range l
Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction)
{
(0/13)
(0/13) i BOTTOM FEEDING FISil(oCi/kg wet) f Gamma Isotopic 4
Be-7 655 (e)
(0/2)
(0/2)
[
(0/2)
(0/2) i i
i (0/2)
(0/2)
(0/2)
(0/2)
(0/2);
(0/2)
Zn-65
- (0/2) i I
.i f
F 4
.m m.-
-. ma m
--w..-e
..-n
-.m.----
m
.-m..r,-
... -. -~.
TABLE 3 (SHEET 8 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Nuclear Piant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Type and
. Minimum Indicator Indicator Location With Community Control TotalNumber Detectable Locations Hichest Annual Mean Locations Locations L
ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range
[
Performed (MDC)(a)
(Fraction)
& Direction (Fraction)
(Fraction)
(Fraction)
Cs-134 130 NDM NA
-NA NDM
[
(0/2)
(0/2)
[
t Cs-137 150 16.4 Smith's Bend 16.4 NA 9.9 l
16.4-16.4 2 miles 16.4-16.4 9.9-9.9 (1/2)
Downstream (1/2)
(1/2)
GAME FISH foci /kn wet)
.[
t Gamma Isotopic
[
4 9e-7 655 (e)
(0/2)
(0/2)
[
- NA
-NDM (0/2)
(0/2)
I Fe-59 260 NDM NA NA NDM (0/2)
(0/2)
Co-58 130 NDM NA NA
'NDM f
(0/2)
(0/2) j l
(0/2)
{
i l
L e
I
TABLE 3 (SHEET 9 OF 10)
RADIOLOGICAL ENVIRONMENTA'L MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama f
. Type and Minimum Indicator Indicator Location With Community Control Total Number Detectable Locations Hichest Annual Mean Locations Locations e
ofAnalyses Concentration Mean (b), Range Name, Distance Mean (b), Range Mean (b), Range Mean (b), Range f
Performed (MDC)(a)
(Fraction)
& Direction (Fraction)'
(Fraction)
(Fraction) l 1
(0/2)
(0/2)
Cs-134 130 NDM NA NA NDM (0/2)
(0.72)
[
l Cs-137 150 19.6 Smith's Bend 19.6 NA 23.1 I8-21 2 miles 18-21 20-26 (2/2)
Downstream (2/2)
(2/2)
RIVER SilORELINE SEDIMENT (oCi/kg drv)
I Gamma Isotopic
[
4 i
Be-7 655 (e)
(0/2) i i
(0/2)
(0/2)
Cs-137 180 11.8 Smith's Bend 11.8 NA NDM l
11.8-11.8 2 miles 11.8-11.8
[
(1/2)
Downstream (1/2) t i
I,
. ~
TABLE 3 (SHEET 10 OF 10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1996 Farley Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama i
NOTATIONS a.
The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by i
ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori (after the fact) MDCs are generally lower than the values listed. There were no MDC values during the year which were greater than the values listed in this column.
b.
Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location which is detectable is placed in parenthesis.
c.
No Detectable Measurement (s),
d.
Not Applicable.
e.
The EL has determined thu this value may be routinely attained under normal conditions. No value is provided in ODCM Table 4-3.
l l
l I
1
TABLE 4 (SHEET I OF 3)
+
INTERLABORATORY COMPARISON PROGRAM RESULTS Specific Date Known Expected
- Reported Standard Normalized Normalized I
Radionuclide Prepared Value Precision.
AYcIage Deviation Deviation Range Beta-ray Emitters in Air Filters (pCi/ filter)
Sr-89
'09/26/96 132.0 7.00 107.0 5.70
-5.05 0.97 t
6 Sr-90 09/26/96 53.0 5.00 42.0 1.41
-3.11 0.30
[
Gamma-ray Emitters in Air Filters (pCi/ filter) i 4
Cr-51 12/12/96 211.0 11.00 190.0 6.80
-3.31 0.69 i
Mn-54 12/12/96 204.0 10.00 205.0 1.70 0.17 0.19 Fe-59 12/12/96 49.0 5.00 54.0 3.90 1.73 0.92
- Co-58 12/12/96 120.0 6.00 115.0 4.00
-1.45 0.73 1
Co-60 12/12/96 109.0 5.50 104.0 2.10
-1.57 0.45 Zn-65 12/12/96 92.0 5.00 99.0 4.70 2.42 1.19
[
Cs-134 12/12/96 173.0 9.00 138.0
.2.60
-6.73 0.33 i
Cs-137 12/12/96 192.0 10.00 182.0 2.80
-1.73 0.29 l
Ce-141 12/12/96 274.0 14.00 244.0 3.70
-3.70 0.31 l
t I
I 1
_..~..
'r.
j i
TABLE 4 (SIIEET 2 OF 3) t INTERLABORATORY COMPARISON PROGRAM RESULTS i
i Specific Date Known Expected Reported Standard Normalized
' Normalized
[
Radionuclide Prenared Value Precision Averane Deviation Deviation Range P
Gamma-ray Emitters in Milk (pCi/1) f Cr-51 06/19/96 563.0 28.00 561.0 43.68
-0.12 2.52 Mn-54 06/19/96 300.0 15.00 299.0 10.50
-0.12 0.83 Fe-59 06/19/96 77.0 5.00 95.0 1.80 6.24 0.39 Co-58
'06/19/96 93.0 5.00 90.0 2.40
-1.04 0.39 Co 06/19/96 84.0 5.00 78.0 5.14
-2.08 1.14 Zn-65 06/19/96 58.0 5.00 79.0 26.87 7.27 10.86 Cs-134 06/19/96 166.0 8.30 151.0 26.70
-3.13 0.19 Cs-137
% /19/96 410.0 20.50 398.0 144.60
-1.01 0.60 l
Cc-141 06/19/96 215.0 10.75 206.0 4.16
-1.45 0.41
-?
i Tritium in Water (pCill) i 11-3 06/19/96 4915.0 491.50 4930.0 64.55 0.05 0.17 12/12/96 2686.0 268.60 2687.0 106.90 0.01 0.35 i
m..
TABLE 4 (SHEET 3 OF 3)
INTERLABORATORY COMPARISON PROGRAM RESULTS Specific Date Known Expected Reported Standard Normalized Normalized Radionuclide Prepared Value Precision Average Deviation Deviation Range Gamma-ray Emitters in Water (pCi/1)
Cr-51 03/12/96 322.0 16.10 323.0 17.00 0.11 1.48 09/26/96 646.0 32.00 596.0 50.51
-2.70 3.83 Mn-54 03/12/96 31.0 5.00 32.0 1.73 0.35 0.39 09/26/96 239.0 12.00 227.0 16.52
-1.73 1.93 Fe-59 03/12/96 83.0 5.00 89.0 3.50 2.08 2.85 09/26/96 50.0 5.00 66.0 81.90 5.54 1.09 Co-58 03/12/96 48.0 5.00 49.0 6.00 0.35 0.85 09/26/96 174.0 9.00 159.0 5.51
-2.89 0.70 Co-60 03/12/96 76.0 5.00 75.0 2.65
-0.35 0.63 09/26/96 151.0 8.00 148.0 5.29
-0.65 0.72 i
Zn-65 03/12/96 97.0 5.00 96.0 9.29
-0.35 1.44 09/26/96 93.0 5.00 91.0 10.26
-0.69 3.50 Cs-134 03/12/96 58.0 5.00 55.0 5.00
-1.04 0.27 09/26/96 295.0 15.00 257.0 2.31
-4.39 0.32 Cs-137 03/12/96 64.0 5.00 62.0 5.00
-0.69 1.43 09/26/96 225.0 11.00 214.0 13.80
-1.73 1.78 Ce-141 03/12/96 88.0 5.00 83.0 5.00
-1.73 1.28 09/26/96 423.0 2100 382.0 12.12
-3.38 0.68
-