ML20029D327
| ML20029D327 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1993 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20029D326 | List: |
| References | |
| NUDOCS 9405050125 | |
| Download: ML20029D327 (82) | |
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ALABAMA POWER COMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT PARTB: RADIOLOGICAL JOSEPH M. FARLEY NUCLEAR PLANT l
l UNIT NO.1 LICENSE NO. NPF-2 AND l UNIT NO. 2 l
l LICENSE NO. NPF-8 PERIOD ENDING DECEMBER 31,1993 9405050125 940427 PDR ADOCK 05000348 R PDR
l ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL TABLE OF CONTENTS Section Tit!R flLQQ l Introduction 1 il Radiological Sampling and Analysis 2 111 Results and Discussion 6 IV Land Use Census and Interlaboratory Comparison 11 Program V Data Trends and Conclusions 12 l
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF FIGURES fim!La Ill!Q 1 Indicator Sampling Locations for Airborne / Direct Environmental Radioactivity at the Farley Nuclear Plant 2 Community (Indicator ll) Sampling Locations for Direct Radiation in the Farley Nuclear Plant Area 3 Control Sampling Locations for Airborne / Direct Environmental l Radioactivity in the Farley Nuclear Plant Area 4 Indicator and Control Sampling Locations for Waterborne Environmental Radioactivity in the Farley Nuclear Plant Area ii 1
RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES Table Title 1 Outline of Operational Radiological Environmental Monitoring Program for Farley Nuclear Plant During 1993 2 Required Detection Capabilities for Environmental Sample Analysis for Farley Nuclear Plant 3 Reporting Levels for Radioactivity Concentrations in Environmental )
Samples 4 Environmental Monitoring Program Deviations 1993 1
1993 1 Airborne: Particulates - Operational Radioactivity Summary 1993-2 Airborne: lodine - Operational Radioactivity Summary 1993-3 External Radiation - Operational Radioactivity Summary l 1993-4 Milk - Operational Radioactivity Summary 1 1
1993-5 Vegetation: Forage - Operational Radioactivity Summary i l
1993-6 Soil - Operational Radioactivity Summary 1993-7 Waterborne: Surface Water - Operational Rad oactivity Summary 1993-8 Waterborne: Ground Water - Operational Radioactivity Summary 1993-9 Sediment: River - Operational Radioactivity Summary
- 1993-10 Fish
- River (Game) - Operational Radioactivity Summary 1993-11 Fish: River (Bottom Feeding) - Operational Radioactivity Summary J
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF ATTACHMENTS Attachment Subiq91 1 Joseph M. Farley Nuclear Plant, Land Use Census, June 21, 1993 2 Plots of Selected Environmental Data iv
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l OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 l
- 1. Introduction The Joseph M. Farley Nuclear Plant, owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company (SNC),
located in Houston County, Alabama is approximately fifteen miles east of
, Dothan, Alabama on the west bank of the Chattahoochee River. Unit 1, a l
Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a rated power output of 860 megawatts electrical (MWe) achieved initial l
criticality on August 9,1977. The unit was declared " commercial" on l December 1,1977. Unit No. 2, also a 860 MWe Westinghouse PWR,
! achieved initial criticality on May 8,1981 and was declared " commercial" on July 30,1981.
Unit 11 was shutdown for its ninth refueling outage from September 24, 1993, through December 2,1993.
The Farley Nuclear Plant Environmental Monitoring Program is designed to I detect the effects, if any, of plant operation on environmental radiation
! levels. The sample collection and analysis schedule was implemented in 1977, and modified on July 1,1980, by adding 14 TLD stations. The program was further modified in April 1982, by Amendment No. 26 to the Unit I Technical Specifications. The program was changed a third time in 1989, with the addition of two more control TLDs and has continued through 1993 without further change. Indicator sampling stations are located, where practical, at locations where detection of the radiological effects of the plant's operation is thought to be most likely, where the samples collected should provide a significant indication of potential dose to 1 man, and where an adequate comparison of predicted radiologicallevels might be made with measured levels. The control stations are placed at locations where radiologicallevels are not expected to be significantly influenced by plant operation, i.e., at background locations. For some airborne radioactivity samples, community stations are located at the principal population centers between the indicator and the control stations (3-5 miles). Community TLDs were placed at locations approximately 1.2 miles southwest of the plant site (nearest occupied residence) and 8 miles west southwest of the plant site (City of Ashford, Alabama). A community air monitoring station is also located in the city of Ashford. Community stations could be used, if desired, as additional control stations, and alternatively, as indicator stations for the nearest population centers in the event of a major airborne release from the plant.
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- 11. Radioloalcal Samolina and Analysis To assess the environmentalimpact of plant operation, the Farley Nuclear Plant Environmental Monitoring Program monitors airborne, waterborne, ingestion and direct radiation pathways in the area surrounding the plant site Table 1 details the sample types, collection and analysis frequency and locations of indicator, community and control stations. For each sample type and location, one sample was collected and analyzed to meet Technical Specification requirements for Units I and ll. While no longer required by Technical Specifications,in situ soil monitoring was continued in 1993.
The samples were collected by Southern Nuclear's technical staff except for in sity soil measurements, fish and river sediment samples. The in situ soil measurements were collected by staff members of the University of Georgia (UGA), Center for Applied Isotope Studies, and the fish and river sediment samples were collected by Alabama Power Company (APCo) Environmental Field Services personnel. All sample analyses were contracted to UGA, except TLD's, which are read at the plant. The minimum detectable concentration (MDC), specified for the various samples and their respective analyses are given in Table 2. The reporting levels for radioactivity concentrations in environmental samples are provided in Table 3. Sampling and analysis deviations during 1993 are listed in Table 4.
To identify the locations of environmental monitoring stations, the area surrounding Farley Nuclear Plant is divided into sixteen radial sectors whose common origin is the point midway between the Unit I and Unit 11 plant vent stacks. This point is defined as "the plant site" Each sector of the resulting circle is numbered sequentially clockwise and the circle is oriented so that the centerline of sector 16 is due north. Each sampling point is identified by a four digit number. The first two digits indicate the sector number, and the last two digits indicate the distance, to the nearest mile, from the origin. For example, TLD station 0304 is located 4 miles east northeast of the plant site. Fish and sediment samplo points are identified by their " river mile" location. The Jim Woodruff Dam near Chattahoochee, Florida is designated as river mile zero, and the miles are numbered sequentially northward along the navigable portion of the river to Columbus, Georgia. River mile 41 is approximately three miles downstream of the plant site, and river mile 47 is approximately three miles upstream.
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I A. Airborne Particulates and lodine The airborne particulate and iodine monitoring stations shown in Figures 1 and 3 are equipped with FN 2108 air samplers manufactured by Science i 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. In March 1993, electrical surge protectors were installed on all air monitoring stations. A 47 millimeter particulate filter and a 50 millimeter F&J activated charcoal cartridge are installed in separate compartments of the combination filter holder, which is mounted vertically on the pump suction. Sampled air flows vertically from top to bottom, first through the particulate filter, then through the charcoal cartridge. To compensate for dust buildup on the sample 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 distribution of sampled airborne particulates over the entire filter disk. The totalizers are calibrated using the SAIC Model C-812 calibrator.
In September 1993, the Gelman VM-1 Metricel membrane filters, used for sampling airbome particulates since 1977, were replaced by Gelman A/E glass fiber filters. The reasons for the change are discussed in paragraph lll A, "Results and Discussion", and are documented in FNP Environmental incident Report No. ElR-93-007. The radiciodine collection filter used was the F&J model TE3C,50 millimeter cartridge, which contains triethylenediamine (TEDA) impregnated activated carbon.
Particulate filters and charcoal cartridges were collected weekly and sent to UGA for radioactivity analysis. Gross beta radioactivity measurements were performed on each air particulate filter using a Tennelec low background alpha-beta counting system. The filters from each station, composited at the end of each quarter, were analyzed for gamma emitters using a fifteen percent relative efficiency low background germanium lithium (Ge(Li)) detector and a Canberra 4096 channel computer-based multichannel analyzer (MCA).
All air monitoring station locations shown in Figures 1 and 3 have the capability of monitoring airborne iodine. Weekly routine samples m,re analyzed for 1-131 by UGA using a Canberra 1024 channel MCA and two 1" x 3" Nal detectors and matched photomultiplier tubes.
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1 B. External Radiation l For the continuous measurement of environmental gamma radiation, natural Lithium Fluoride (LiF) (TLD-700) chips, manuf actured by Harshaw Filtrol Chemical Company, were used. TLD packets, each containing four annealed LiF chips, were sealed in opaque mylar to produce a packet that was light-tight, weather-proof, and which had a low mass attenuation for radiation (approximately 50mg/cm2 ). On the plant site, all TLD packets were kept in a lead safe with 2-inch walls except for those receiving field exposure or those in the process of being exchanged.
At each extemal radiation monitoring station (shown in Figures 1-3), two ,
TLD packets, one changed and read quarterly and one changed and read annually, were exposed side-by-side on metal stakes at a height of one meter above the ground. For the computation of the net field doses, a log of all exposure periods was maintained for each TLD packet.
C. Milk The milk sample location is as indicated on Figure 3. All milk samples, collected bi-weekly, were analyzed by UGA for 1-1'11 and gamma emitters.
As a preservative for shipment,1 ml of 25 weight percent merthiolate (Thimerosal) solution was added to each one gallon sample. The I-131 concentration in each sample was determined by collection on anion exchange resin, elution with sodium hypochlorite, followed by organic extraction and counting, by beta-gamma coincidence, the resultant toluene-iodine solution in a low level liquid scintillation counter. Stable iodine carrier was added to each sample for determination of the radiochemical yield.
One liter of each sample was placed in a marinelli beaker and analyzed for gamma emitters using a 15 percent relative efficiency low background Ge(Li) detector and a Canberra 4096 channel computer-based MCA.
D. Vegetation: Forage i l
Monthly, forage was collected from indicator grass plots located near the )
air monitoring stations at the plant site perimeter in the SSE and N sectors, or alternate plots if needed, and from a control grass plot located near the air monitoring station in Dothan, Alabama. After drying and pulverizing, the samples were analyzed by UGA for gamma emitters using a 15 percent .
relative efficiency low background Ge(Li) detector and a Canberra 4096 l channel computer-based MCA. l l
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i E. Soil Annualin Sity gamma-ray spectroscopy measurements were made by UGA using a 10 percent relative officiency high purity germanium detector and gamma-ray spectroscopy system specially designed for field use.
Measurements were taken at the seven indicator locations and at the three community and two control (background) locations listed in Table 1. A i 1024 channel Canberra MCA interfaced to a Hewlett-Packard 9825A calculator was used for data storage and analysis.
F. Surface (River) Water l
Weekly, samples of water from the Chattahoochee River, upstream and downstream of the plant site at the locations shown in Figure 4 were collected on a semi-continuous basis with Instrumentation Specialties Company (ISCO) samplers. For each 28-day surveillance interval, one liter of each week's background and indicator samples were combined to make 4-liter composite samples which were sent to UGA for radioactivity analysis. Two liter aliquots from each 28-day composite were placed in trays lined with plastic film and evaporated to dryness at 100 C. The t residue (on plastic film) was folded to fit a petri-dish and analyzed for I gamma emitters using a 15 percent relative efficiency Ge(Li) low I background detector and a Canberra 4096 channel computer-based MCA.
l For each calendar quarter,75 milliliters (ml) of each week's indicator and background samples were combined to make a 975 milliliter composite sample for tritium analysis. Approximately 50 ml from each quarterly composite sample was distilled and a 25 ml aliquot taken for tritium analysis using a large volume (100 ml) Hewlett Packard 200 low background iquid scintillation counter.
G. Ground (Well) Water l
In the Farley Plant area there are no true indicator sources of groundwater.
A well which serves Georgia Pacific Paper Company as a scurce of potable water, located on the east bank of the Chattahoochee River about four miles south-southeast of the plant, was sampled quarterly as an indicator station. A deep well which supplies water to the Whatley residence located about 1.2 miles southwest of the plant was sampled quarterly as a control (background) station. Samples from both were sent to UGA for radioactivity analysis. An aliquot from each sample was taken for tritium analysis. After distillation,25 mi samples were analyzed using a large volume (100 mi) low background liquid scintillation counter. From the remainder of each sample, a two liter aliquot was taken and evaporated to dryness at 100 C in a tray lined with plastic film. The residue (on plastic film) was folded to fit a petri dish and analyzed for gamma emitters using a 15 percent relative efficiency Ge(Li) dete: tor and a Canberra 4096 channel computer-based MCA. ;
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l H. Fish (River) l Semi annually, two types of fish, game and bottom feeding, were collected from the Chattahoochee River at the locations shown in Figure 4, and sent i to UGA for gamma-ray spectroscopy analysis. All fish samples sent to j UGA consisted of fish fillets that had been split with Alabama Division of Radiation Control. These fish samples were coarsely chopped at UGA and l were analyzed for gamma emitters using a 15 percent relative efficiency low background Ge(Li) detector and 4096 channel Canberra computer based MCA.
- 1. Sediment (Rivar) 1 Semi-annually, sediment samples were collected from the Chattahoochee River at the locations shown in Figure 4. Approximately one kilogram of d
each sample was sent to UGA where it was dried, mixed, and analyzed for gamma emitters using a 15 percent relative efficiency low background j Ge(Li) detector and a Canberra 4096 channel computer-based MCA. One set of semi-annual sediment samples was split with Alabama Division of
- Radiation Control. ,
Ill. Results and Discussion No known atmospheric nuclear tests were conducted during 1993.
Attachment 2, Plots of Selected Environmental Data, is included as an enhancement to trending. In general, the mean annual concentrations of j frequently identified isotopes were chosen to be plotted. In cases where many 4 naturally occurring isotopes were identified, those chosen to be plotted were i from differing decay chains. Significant uptrends in the data were as follows: j (1) Atmospheric Tests, Peoples Republic of China 4
! September 17,1977 i March 14,1978
- December 14,1978 i October 15,1980 (2) Chernobyl Disaster, USSR, April 1986 4
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1 A. Airborne Particulates and lodines Analysis results of airborne particulate filters and charcoal cartridges are shown in Tables 1993-1 and 1993 2, and Attachment 2, pages 1-4. The 1993 results, while below pre-operational levels, showed expected increases in mean particulate Beta activity and mean particulate Beryllium-7 activity. The 1992 Annual Environmental l Operating Report documented step increases in these two parameters I following the installation of new air monitoring stations in May 1992.
The mean activities for these parameters in 1993 (0.021 pCi/m3 Beta, 0.061 pCi/m 3 Beryllium-7) were consistent with mean activities observed from June through December 1992 (0.022 pCi/m3 Beta, 0.057 pCi/m 3 Beryllium-7). The measured activities of these parameters are expected to stabilize at these levels and will be
. monitored for future trends.
As stated in Paragraph 11 A, in September 1993, the Gelman VM-1 Metricel membrane filters used for airborne particulate sampling since 1977 were replaced with Gelman A/E glass fiber filters. Following installation of the new air monitors in 1992, the membrane filters were found to clog and rupture occasionally. Ruptured filters were observed more frequently during the summer months, when high ambient temperatures and humidities prevailed. Review of product information 1 and literature documented a "high resistance to airflow" and
" brittleness" as undesirable characteristics of membrane filters and indicated that glass fiber filters are generally more desirable for use in sampling airborne particulates. The Gelman A/E glass fiber filter was selected for use in the FNP Radiological Environmental Monitoring Program (REMP) after comparison with other filters on the basis of 4
flowrate, particle size retention, and cost. This filter is also used by the other nuclear generating plants in the Southern Company for sampling airborne particulates. There have been no instances of damaged filters since the change, and analytical results have been
. more consistent, with less variance between sampling stations than previously observed.
Deviations from the Environmental Monitoring Program resulting from airborne particulate and iodine analysis are given in Table 4.
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I B. Extemal Radiation The results of the external radiation measurements are shown in Table 1993-3 and Attachment 2 page 5. Mean external gamma dose measured in 1993 was greater than in 1992 and slightly greater than during the pre-operational period. The doses measured at all stations in the fourth quarter of 1993 were generally greater than those measured in the third quarter by a factor of approximately 1.5. The higher fourth quarter results are not considered to be the result of plant operation since similar readings were obtained for indicator, control and community locations. The highest mean annual dose to a single ..
location,94.9 mrem, was measured at station RI-0401, located on the .
plant perimeter 0.8 miles east of the midpoint between the Unit I and Unit 11 plant vent stacks. Review of data and results for the entire year revealed elevated doses at that location in the second, third and fourth quarters. The observed increases are possibly due to disturbances in natural radiation fields and releases of Radon and other naturally occurring isotopes during river dredging operations conducted near station RI-0401. The mean extemal gamma doses for all stations are i consistent with previously observed annual variations, and no significant differences in indicator, community and control '
measurements were noted. ,
Deviations from the Environmental Monitoring Program resulting from extemal radiation measurements are given in Table 4. .
t C. Milk The milk analysis results are shown in Table 1993-4 and Attachment 2, pages 6-8. Lewis Dairy was used as the control location. There l were no indicator samples during 1993. The 1993 results are l consistent with those of previous years, and Potassium-40 was the j only isotope detected in milk samples. .
No deviations from the Environmental Monitoring Program resulted from milk sample analysis. ,
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a D. Vegetation Forage analysis results are shown in Table 1993-5 and Attachment 2, pages 9-12. The 1993 results are below pre-operational levels and consistent with the downward trends of recent years. The control sample collected November 30,1993 contained 24 pCi/kg Cesium 137 activity. This value is below pre-operationallevels and is not considered significant since Cesium 137 has been shown to be present in the soil throughout the area.
4 No deviations from the Environmental Monitoring Program resulted
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from forage sample analysis.
E. Soil The in nilu i soil analysis results are shown in Table 1993-6 and in Attachment 2, pages 13 and 14. The only man-made isotope found
- was Cesium 137 which has been present since the pre-operational period. Increases in mean Cesium 137 activity were observed at
- control and indicator stations, while decreases were observed at community stations. The measured activities are consistent with annual variations and the downward trends observed in the years since the cessation of atmosphere nuc' ear weapons testing.
- F. Waterborne (Surface Water)
The surfaae water analysis results are shown in Table 1993-7 and in Attachment 2, pages 15-17. The mean indicator Tritium activity was consistent with that observed in 1992 and higher than pre-operational levels. The activity was measured during all four quarters and was 4 highest in the fourth quarter. No activity was measured in control samples.
No deviations from the Environmental Monitoring Program resulted from surface water analysis, 9
t G. Waterborne (Ground Water)
The ground water analysis results are shown in Table 1993 8 and in Attachment 2, pages 18-20. No measurable activity from man-made isotopes was detected in ground water samples in 1993.
No deviations from the Environmental Monitoring Program resulted from ground water analysis.
H. River Sediment The river sediment analysis results are shown in Table 1993-9, and in Attachment 2, pages ?.1-24. Along with activity from a variety of naturally occurring isotopes, Cesium 134 activity was again measured in the fall control and indicator samples. Cesium 134 activity has been detected sporadically in previous control samples, and for the second consecutive year has been detected in the fall control and indicator samples. Review of 1992 and 1993 Semi-Annual Effluent Reports revealed that Cesium-134 activity in 1993 plant effluents was greater than in 1992, and was distributed uniformly in releases over all four quarters. The presence of Cesium-134 in only the fall samples in 1992 and 1993 is possibly due to the fact that in both yeais, the fall samples were collected after lengthy periods of dry weather, when the river level was lowered and the flowrates were greatly reduced. Such conditions favor the settling of more of the isotope from the water into sediment in the riverbed.
No deviations from the Environmental Monitoring Program resulted from river sediment analysis.
I. Game Fish (River)
The analysis results of edible portions of Chattahoochee River game fish are shown in Table 1993-10 and in Attachment 2, page 25.
Cesium 137 activity was detected in the spring indicator sample.
Detected activity was below pre-operational levels and consistent with established trends.
No deviations from the Environmental Monitoring Program resulted from game fish analysis.
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J. Bottom-Feeding Fish (River)
Analysis results of edible portions of Chattahoochee River bottomfeeding fish are shown in Table 1993-11 and in Attachment 2, page 26. Cesium-137 activity in the spring indicator sample was 208 pCi/kg. This value is greater than pre-operationallevels but well below the reporting level of 2000 pCi/kg. No activity other than Potassium-40 was measured in the fall samples. Review of 1992 and 1993 i Semi-Annual Effluent Reports revealed that Cesium-137 activity in plant effluents was greater in 1993 than in 1992, and that the Cesium- 1 137 activity released in 1993 was spread evenly over all four quarters.
The Cesium-137 activity released during the first two quarters of 1993 was also found to be greater than the same period in 1992. Since no Cesium 137 activity was measured in the fall samples, and since Cesium-137 activity was not measured at abnormal or unexpectedly high levels in other pathways monitored, the activity measured in the spring indicator sample is not considered significant.
No deviations from the Environmental Monitoring Program resulted from bottom feeding fish analysis.
IV. Land Use Census and Interlaboratory Comoarison Prooram A. Land Use Census and Milk Animal Survey The Land Use Census and Milk Animal Survey was completed on June 21,1993. The results are given in Attachment 1.
i No deviations from the Environmental Monitoring Program occarred as a result of the Land Use Census and Milk Animal Survey.
B. Interlaboratory Comparison Program
, During 1993, the University of Georgia Center for Applied Isotope Studies (UGA) was a participant in the EPA Crosscheck Program. The UGA EPA Program code designation is EA.
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V. Data Trends and Conclusion Review of the data trends from the pre-operational period through 1993 indicates that environmental radiation levels measured in all the pathways monitored in 1993 remained at background levels and were consistent with pre-l operational levels, except river water Tritium, river sediment Cesium-134 in the fall
! samples and bottom feeding fish Cesium-137 in the spring samples. The atmospheric weapons tests conducted by the People's Republic of China in October
- 1980, and the Chernobyl disaster in April 1986, produced measured increased in j background rad;ation, but the effects dissipated within two to three years following each event. Even though these levels were slightly higher, overall the data obtained l during 1993 demonstrated that contint ed operation of Farley Nuclear Plant has not harmed or caused any irreversible damage to the environment.
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TABLE 1 OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1993 Types of samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis AIRBORNE Particulates Continuous operation of sampler with Particulate sampler sample collection being performed once per 7 days. Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Indicator Stations: following filter change.
Perform gamma isotopic North Perimeter (N-0.8) analysis on each sample South Perimeter (SSE-1.0) when gross beta activity Plant Entrance (WSW-0.9) is >10 times the yearly River Intake Structure (ESE-0.8) mean of control samples.
Perform gamma isotopic analysis on composite Community Stations: (by location) sample at least once per 92 days.
Columbia, AL. (N-5)
Georgia Pacific Paper Co. (SSE-3)
Ashford, AL. (WSW-8)
Control Stations: ,
Blakely, GA. (NE-15)
Dothan, AL. (W-18)
Neals Landing, FL. (SSE-18) i Iodine Continuous sampler operation Radioiodine canister j with charcoal canister Indicator Stations: collection performed once Analyze at least once per 7 days. per 7 days for I-131.
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Plant Entrance - (WSW-0.9)
River Intake Structure (ESE-0.8)
Table 1 ENV/1 Page 1 of 5
TABLE 1.(con'd) l Types of samples i and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis i Community Stations:
Georgia Pacific Paper Co. (SSE-3)
Control Stations:
Blakely, GA. (NE-15)
Dothan, AL. (W-18)
Neals Landing, FL. (SSE-18)
Soil Annual in situ Ge(Li) gamma-ray Gamma Isotopic spectroscopy measurements.
Indicator Stations: Annually Seven Stations along the plant perimeter (NE-1.0, E-0.8, SSE-1.0, SSW-1.0, WSW-0.9, NNW-0.8 and N-0.8)
Community Stations:
Columbia, AL. (N-5)
Georgia Pacific Paper Co.(SSE-3)
Ashford, AL. (WSW-8)
Control Stations:
Blakely, GA. (NE-15)
Dothan, AL. (W-18)
DIRECT RADIATION At least once per 92 days Gamma dose Readout at least once per 92 days Table 1 Page 2 of 5 3
TABLE 1 (con'd)
Types of Samples and Sampling Type and Frequency sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis Indicator I Stations:
Sixteen stations, one in each meteorological sector along the plant perimeter (N-0.8, NNE-0.9, NE-1.0, ENE-0.9, E-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 sector at a distance of 3-5 miles (NNE-4, NE-4, ENE-4, E-5, ESE-5, SE-5, SSE-3, S-5, SSW-4, SW-5, 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)
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 surface Water composite taken with propor- Monthly gamma isotopic tional semi-continuous sampler, analysis of each composite Indicator Station: having a minimum sampling fre- sample. Tritium analysis quency not exceeding two hours of each composite sample collected over a period s 31 days. at least once per 92 days.
, Paper Mill at Cedar Springs, GA (3 miles downstream of plant discharge, River Mile-40)
Table 1 Page 3 of 5 i
- . _ . . - . - . _ .. . - . ~ . . _ - . ~ ... .. . . . . - . . . - . . . _ ._ . . . .. . ..
TABLE 1 (con'd)
Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis Control Station:
Upstream of Andrews Lock and Dam
(=3 miles upstream of plant intake, River Mile-47)
Ground Water Grab sample taken at least Gamma isotopic and tritium once per 92 days. analyses of each sample Indicator Station: once per quarter.
Paper Mill at Cedar Springs, GA, Well (SSE-4)
Control Station:
Whatley Residence, Well (SW-1.2)
River Sediment Grab sample taken at least Gamma isotopic analysis once per 184 days. of each sample twice per year.
Indicator Station:
Downstream of plant discharge at Smith's Bend (River Mile - 41)
Control Station:
Upstream of plant discharge at Andrews Lock & Dam Reservoir (River Mile - 47) 1 Table 1 Page 4 of 5
TABLE 1 (con'd)
Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis INGESTION Milk Control Staton:
Lewis Dairy At least once per 16 days Gamma isotopic and I-131 Avon, AL. (WSW-14) analysis of each bi-weekly sample when animals are on pasture.
Fish Indicator Station: One sample each of the following Gamma isotopic analysis species at least once per each on edible portions once season (March 15 - May 15 and per season.
September 15 - November 15)
- 1. Game Fish
- 2. Bottom Feeding Fish Downstream of plant discharge in vicinity of Smith's Bend (River Mile - 41)
Control Station:
Upstream of plant discharge in Andrews Lock & Dam Reservoir (River Mile - 47)
Forace Grab sample cut from green Gamma isotopic analysis forage at least once per 31 (which includes I-131) days. of each monthly sample.
I Indicator Station:
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Control Station:
j Dothan, AL. (W-18) Table 1 Page 5 of 5
TABLE 2 REOUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS FOR FARLEY NUCLEAR PLANT VALUES FOR THE MINIMUM DETECTABLE CONCENTRATIONfMDC)*
Airborne Particulate Water or Gas Fish Milk Food Products Sediment Analysis (DCi/1) f oCi/m3) (DCi/ka. wet _1 foci /11 (pCi/ko. wet) (DCi/ko. dry)
Gross beta 4 0.01 NA NA NA NA H-3 2000 NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58, 60 15 NA 130 NA NA NA Zn-65 30 NA 260 NA NA NA Zr-95 30 NA NA NA NA NA Rb-95 15 NA NA NA NA NA I-131 l' O.07 NA 1 60 NA i
Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 J Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA Table 2 Page 1 of 2 4
1
! l TABLE 2 (con'd) l l
l
'The MDC is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical l separation):
MDC = 4.66 Sm E V 2.22 Y exp (-lat)
Where:
MDC is the "a priori" lower limit of detection as defined above (as picoeurie per unit mass or volume).
S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
E is the counting efficiency (as counts per transformation).
V is the sample size (in units of mass or volume).
2.22 is the number of transformations per minute per picoeurie.
Y is the fractional radiochemical yield (when applicable).
l 1 is the radioactive decay constant for the particular radionuclide.
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples). ,
i l
The value of S used in the calculation of the MDC for a detection j system shall be based on the actual observed variance of the l l
background counting rate or of the counting rate of the blank samples !
! (as appropriate) rather than on an unverified theoretically predicted l variance. In calculating the MDC for a radionuclide determined by gamma-ray spectroscopy, the background shall include the typical contributions of other radionuclides normally present in the samples
( (e.g., Potassium-40 in milk samples). Typical values of E, V, Y and At shall be used in the calculations.
'The MDC's for Tritium, Gross beta, and Radioiodine were obtained using blank background (a priori), whereas, for gamma-ray spectroscopy actual sample backgrounds were used (a posteriori).
74DC for drinking water.
Table 2 Page 2 of 2
TABLE 3 REPORTING LEVELS FOR RADIOACTIVITY CONCEFiTRATIONS 195 ENVIRONMENTAL SAMPLES Airborne Particulate Water or Gas Fish Milk Food Products Analysis foci /11 foci /m') foci /ko. wet) foci /1) foci /ko. wet)
H-3 2 x 10' NA NA NA NA Mn-54 1 x 10' NA 3 x 10' NA NA Fe-59 4 x 10 2 NA 1 x 10' NA NA Co-58 1 x 10' NA 3 x 10' NA NA Co-60 3x 10 2 NA 1 x 10' NA NA Zn-65 3 x 10 2 NA 2x 10' NA NA Zr/Nb-95 4 x 10 2 NA NA NA NA 2
I-131 2 x 10' 9x 10-' NA 3 x 10' 1x 10 Cs-134 3x 10' 1 x 10' 1 x 10' 6 x 10' 1 x 10' Cs-137 5 x 10' 2x 10' 2 x 10 3 7 x 10' 2 x 10' Ba/La-140 2x 10 2 NA NA 3 x 10 2 NA
- For drinking water samples.
Annual ENV Report /4(7)
Table 3 Page 1 of 1
L i
TABLE 4 ,
l ENVIRONMENTAL MONITORING PROGRAM DEVIATIONS 1993 DATE/ TIME COMPONENT CAUSE OF DEVIATION RESOLUTION REMARKS O2-23-93/1320 Air Monitor 0701 Loss of electrical power Work Request 267409 submitted. Monitor out of service for approximately Power restored 02-24-93/1230. 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />. Insufficient sample volume
' to meet lodine-131 MDC. ,
t 07-06-93/1300 TLD Stake 0304 Destroyed by vandals Replaced stake, instalied new TLD. No second quarter TLD readings for this i location. I 07-07-93/2200 Air Monitor 1601 Loss of electrical power due to lighting Damage repaired, power restored 07- Monitor out of service for approximately I
! strike on pole supplying power to 08-93/0800. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
monitor.
i 07-27-93/1028 Air Monitor 0718 Overload circuit breaker tripped after Reset circuit breaker. Monitor out of service for approximately i approximately 79 hours9.143519e-4 days <br />0.0219 hours <br />1.306217e-4 weeks <br />3.00595e-5 months <br /> operation. 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.. Insufficient sample volume to meet lodine-131 MDC.
2 08-24-93/0805 Air Monitor 1218 Exhaust filter cover vibrated loose and Replaced and secured cover. Insufficient sample volume to meet detached from pump assembly after inspected other monitors to preclude lodine-131 MDC.
I 97.4 m3 sample collected. reoccurrence.
08-24-93/1207 Air Monitor 0215 Clogged particulate filter. Replaced filter, inspected and retumed Insufficient sample volume to meet monitor to service. Replace lodine-131 MDC.
- membrane filters with glass fiber filters. .
i i 08-24-93/1259 Air Monitor 1605 Clogged particulate filter. Replaced filter, inspected and returned insufficient sample volume to meet monitor to service. Replaced lodine-131 MDC. "
membrane filters with glass fiber filters.
4 08-24-93/1329 Air Monitor 1101 Clogged particulate filter. Replace filter, inspected and retumed Insufficient sample volume to meet monitor to service. Replaced lodine-131 MDC.
membrane filters with glass fiber filters.
t
- . . - , - - . v. i
l l
AIRBORNE: PARTICULATES OPERATIONAL RAD'OACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT 1.!Cl NSE NOS. NPF-2 AND NPF-8 Ilot1STON cot!N'lY ALAllAMA StfMMARY RI PORT 11 TOM 10171 TO 123193 M/ )
I AIK ARTN1't.ATU titl4 unu Meters
'- l t OMMUN TY
^
~ CONTROL ~
~
TYP . And ~~A ITNDicATOR- - ~~~ ~1NDICATORTOCATION' I TOTAL LOCATIONS Will! IllGilFST ANN 11AL MEAN ll) CATIONS LOCATIONS l I
NI! MILERS Of sowis st. NAME AN AI.YSIS M on a, MEAN MIN MAX _ oisTrscE MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX j P Hili)R M ED c o 4 4 niun now c o c e c o ilE? 40 r T) 0i l [0 0575 0.042 d in,9 55E PERIM 01)m7 554 0 0<is 1 0 0r,40 0 05 0 09 0 0ril 2 H42 0 076 16 16 1.0 MI. SSE 4 4 12 12 12 12 Ill .TA 520 0 002 0.0191 0 004 0.0t>3 SSE PERIM. 0 0218 0 005 0 (wa 0 0224 0 4Nvi 0 054 0.0223 0 005 0 094 208 208 1.0 MI. SSE 52 52 156 156 156 156 CN-134 40 0 002 <MDC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 10 0 0 0 12 0 12 CS-137 40 O tuu <MDC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 16 0 0 0 12 0 12 1131 40 o th)1 <MDC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 16 0 0 0 12 0 12 i
l 1
Aler;n - [k tericdnc l I re m Alcantremerus Wuh IneaaNe A uru s Ordy.
t 6 N,> bnroutme . Inomalvu s Afeawremerus ik j>>rteriIattring 1Ju s l'crni.
tin Alcan Aluumum iktectabh Coru cruraturn Calcsalate.1l'< r ~ls.ble 2 nf Iid.s licjuuri tra Number of Alcawrements Wsth IWrectuNr A ucuy only tI>> IoralNumber oJ Afeawrcmcrus Ialen.
TABLE 1993-1 Page 1 of 1 l
AIRBORNE: LODINE- OPERATIONAL RADIO ACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSli NOS. NPF-2 AND NPF-8 IlOl1STON CotJNTY AI.AllAMA SilMMARY RFPORT IROM 10191 TO 123191 (4; l AIR 10lblNK I WI nanc Meerro TYPE And ~ ~ ALL ~ ND CATOR~- - ~~ IND PATUR LOCATIUM COMMUNITY ~ -- ' ~ ~ TONTROL~ ~- ~~
'l O I AL L.OCATIONS Willi filGIIEST ANNUAL Ml!AN LOCATIONS IJ) CATIONS NL.! Mill RS Of soutui. NAME ANAL.YS15 won ni MEAN MIN MAX pas 14scE Ml!AN MIN MAX MEAN MIN MAX MEAN MIN MAX peril)RMhl) c o 4.d oturevios c o_ c o c 0 TTI31 41c, 0 040 aiDc NA NA NA GiDC NA NA (MDC NA NA UTDC NA NA 0 20H 0 0 0 $2 0 156 l
l l
5 i
1
.Ti~in LWirrndncJ l rom Alcamicirwms Wah lk teaahie ,L uvu s onir
< A) k Nonnounne tnomalous Alcanrements RrjwortcJ lhnng Ilu s l'enad.
(10 Afran Almimum IWiectaNe Conceruranon CakulatcJ l'er t able lof Ilus Report tro Mmber of Alcamremeras With IViet table Aateus Only Ith 1,,tal Number o f Alcamicmcrus ialcn.
TABLE 1993-2 l l
Page l of 1 l
EXTERNAL RADIATION: OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICliNSli NOS. NPF-2 AND NPF-8 IlOUSTON COUN~lY ALAllAMA
SUMMARY
RI PORT I' ROM 10193 TO 121193 (41
} AMDAE tMREMo lYl'h And ALL INDICA' LOR INDICATOR LOCATION COMMUNil Y CON 1ROL
'lOTAL LOCATIONS Wrill IllGill;ST ANN 11Al, MEAN 1.OCATIONe i OCATIONS NUMill RS Of sowns rs. NAMii AN Al.YSIS umm MEAN MIN MAX pasTr%cr MEAN MIN MAX MiiAN MIN MAX MEAN MIN MAX PF RI ORMED c o 4 4 osmmow c o e o e o ANNUAL 40 NA 59.30r>3 44.5 94 9 l'LAN'l Pt RIM. 94.'Mui 94.9 94.9 51.6722 .t4.7 52.1 51.5167 43.8 63 1 16 16 0.8 MI. E 1 1 18 18 6 6 PLANT PERIM. 23 8250 26.4 15.6113 9.2 32 4 15.9250 9.1 27.4 QUARTlR 159 NA 17.3*k. 10A 29 6 18.8 64 64 0 8 MI. E 4 4 ?) 71 24 24 S U M ( 1. ) 40 NA : 69.St>25 55.7 95.3 Pl ANT PI RIM 95.%W 95.3 95.3 62.4722 52.1 76 63.7t m 52.5 74 16 16 0 8 MI. E I 1 18 18 6 6 r
(
Alcan . IMer?runnii rom Alcamremerus Wuh (Mecsable Actwny only.
1 A b No Nonrounne Arvemalous Alcanorements Rep rted Ikring Ihis Persud t B> Alcan Afimmum Irrectable t 'oru entranon raiculated l'er 1abic 2 of flu s Reprt.
(C) Number of Afcamrrmems With IVicctable Actnity Only.
t(H lotal Numbcr of Alcamremerus laten.
< Ei sum of the i vur %ariers TABLE 1993-3 Page 1 of 1 l
l l
l - - - . _ . _ - . _ __ __ - _ _ . _ _ . _ . , ,
MILK: OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICl NSli NOS. NPIL2 AND NPIL8 IlOUSTON COUNTY AIAllAMA
SUMMARY
RfiPORT l^ ROM 10191 TO 123193 (A>
Mif f[_l;f _ -__ _ _ _ ___ _ _ _ ,__[,_ _ _ ,_ _ _ _ _ _ _ _ _ . _
FYPh And _ . . . . . . . . . . _All. INDICAlOR INDICAIOR LOCATION _COMMUNilY_ ___ CONIROL TOTAL. l OCATIONS Willi lilGilEST ANNIIAI. MEAN l.OCATIONS I OCATIONS Ntf MilliRS Of sowisa NAMIi AN Al.YSIS win ni MEAN MIN MAX Damsct MEAN MIN MAX MiiAN MIN MAX MEAN MIN MAX PI RIT)RMf;D c o A.4 piuttvios e o e o c o ISA-140 26 47. 4m NA NA NA NA NA NA NA NA NA NA (MDC NA NA 0 0 0 0 0 0 0 h CS-134 26 13.462 NA NA NA NA NA NA NA NA NA NA <MDC NA NA 0 0 0 0 0 0 0 M CS 137 26 11.49 NA NA NA NA NA NA NA NA NA NA <MDC NA NA 0 0 0 0 0 0 0 26 I-131 26 0.243 NA NA NA NA NA NA NA NA NA NA (MDC NA NA 0 0 0 0 0 0 0 26 K-40 26 102 423 NA NA NA NA NA NA NA NA NA NA 1336.15 10'N) 15.4) 0 0 0 0 0 0 26 26 IA-140 2t- 9%2 NA NA NA NA NA NA NA NA NA NA (MDC NA NA 0 0 0 0 0 0 0 26
- ~
Alcan - Ik ternurwd I rom Elcawenwrus Wuh twics tune A tivit y Oriv.
l t A 6 No Nonroutine Anomalous Afcamremerus Rcforted iJunne ilu s l'enod.
l uIn Atcan Aluumum Ik-tectahic ('onceruration Calculated l'er 1able 2 of Ilus Rcport er) Number of Alcawements With Ik tectahic Actway only.
ilh 1vta! Number of Alcawements lakert TABLE 1993-4 Page 1 of 1 )
I
_ _ _ - - - _ - _ _ _ - - - - - - - _ - - _ - _ .__ _-_ J
l l
l VEGETATION: FORAGE- OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT 1.lCENSE NOS. NPl'.2 AND NI't" 8 IlOUSTON COUNTY AI.AllAMA
SUMMARY
RI'P()RT IROM 10193 T 123191 m; j 1
FORLF tEo 4kl AG 88 f.To , .
l
~~ ~
l YPh And~ ~~Al [IN DIUA h AI'~ ' iNDIUXEUK 1AA)Al10N ~ ~ . ~ UO'MMUNifY ' ~ ~~ CONTROL ~
'l OTAI. 1.OCATIONS WITil lilGilEST ANNtfAI MEAN 1.OCAT10NS LOCATIONS NUMHl:RS Of %owi%rt NAMIi AN Al.YSIS wim si Ml!AN MIN MAX pmr%cr Ml!AN MIN MAX MiiAN MIN MAX MiiAN MIN MAX PI RI ORMl:D c D ue ninnvio% c o c D c D 111 .-7 39 87.179 en4.807 Ps 2iw Ssh PI RIM. 710.7mi 337 1920 NA NA NA t>72.153 172 19eio 26 26 1.0 Mt. SSE 13 13 0 0 13 13 CS 114 39 14.744 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 26 0 0 0 0 0 13 CS-137 39 11.949 <MDC NA NA NA (MDC NA NA NA NA NA 24 0(WM) 24 24 0 26 0 0 0 0 1 13 1 131 39 14 795 <MDC NA NA NA (MDC NA NA NA NA NA <MDC NA NA 0 26 0 0 0 0 0 13 K 40 39 112 128 4w12 30 2310 6920 NORTil PI RIM. 5010.76 3200 (n20 NA NA NA 4920.7t> .NN) 6110 26 26 0 8 MI. N 13 13 0 0 13 13 A C. 225 2 42 (WW) 54 0fM10 39 69 SSli Pl'. RIM. ti9 tM100 (W fn NA NA NA NA NA NA 2 2 1.0 Mt. % E I 1 0 0 0 0 l
)
l t
l l
hican - IvierrruncJ l rom Mea.narcervras it' ads letet sable kuva r Iinis i A t b N<mrounne Aromalous Mea.naremerus Rep,rted iMrmg iJus l'ersoJ.
Ilh Mcan Mm:mam IVsectable Corn crutration ('als ulated I'cr Iabic lof flus Report.
tC1 N.mber of Meanarcrwus If'ith Iksectable kuvity Ihdv.
(l1o TotalNumber of 3iean.rerrvoas Taten.
II p 3fean !!'rt'l)ry Ratio for 1993 was 5 19 TABLE 1993-5 Page 1 of 1
SOIL: OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 ANI) NPI'-8 liOUSTON COUNTY AIAllAMA StJMMARY RI PORT FROM 10191 TO 123191 (A) 5011. (IN %ITTI tWl'KG-1)Mr TT PE And ALL INL)lCAlOR INDICA' LOR LOCA'llON COMMlJNITY CON 1'ROL TOTAL 1 OCATIONS WIBl lilGilEST ANNilAl, MEAN !.OCATIONS I OCATIONS NLJMilERS Of som a NAME ANALYSIS wo n, MEAN MIN MAX pier 4%cr Ml!AN MIN MAX MEAN MIN MAX MEAN MIN MAX PI RI ORMED c o 4 4 ninEtTios c o c o c o AC-22^ 12 145 417 15n9.57 954 2^50 PLAN 1' Pl. RIM. 2x50 00 2a50 2850 10% 6td. 9% ll N) 1575AM) 1240 Ivl0 7 7 0 8 MI. E 1 1 3 3 2 2 111-212 10 340 (xW) 1018.33 611 1650 NE PERIM. 1650 00 1650 1650 715tN m 715 715 838.500 741 9M 6 6 1.0 Mt. NE I 1 1 2 2 2 111-214 12 101.750 16M 23 1070 2620 PI ANT PERIM. 2070 00 2620 2620 1236.333 959 1440 1410 00 1140 ItN) 7 7 OA MI. E I 1 3 3 2 2 rs 137 12 220x3 111 142 56 262 PLANT PI RIM 262Am 2t 2 262 134 6ts,7 A0 227 161.500 154 169 7 7 0 8 Mt. WNW 1 1 3 3 2 2 K 40 12 22&Ox3 Sv000 1020 14WO Pl ANT PERIM 14M O 14'M N) 14 *x) 1570d m 10'O 2070 1905 0s) 1070 2740 7 7 0.s MI. E 1 1 2 3 2 2 Pil-212 12 123.750 10'2.14 583 1910 NE Pl RIM. 1940 00 1910 1930 661 Aum 5* 773 1019.50 749 1290 7 7 1.0 MI. NE I 1 3 3 2 2 Pil 214 12 149 000 1510 00 llw 2670 PLANT PERIM 2670 00 26?O 2670 1160 lm 1040 1580 1690 00 1440 1940 7 7 0.5 MI. E 1 1 3 3 2 2 R A.226 539 0n0 619Am til 9 619 PI ANT PERIM. 619Axw) 619 619 659.tN m 659 659 615 000 635 635 1 1 0.9 MI. WSW I i 1 1 1 I l i
l T1.-20s 12 51
- N1 586.571 3 L4 10x0 NE PI RIM. 10x0 00 10x0 10x0 462.3433 331 386 50n.500 399 614 7 7 10 MI. NE 1 1 3 3 2 2 Alcan DetermouNli rom . flea mremnus Wuh IWics table A uvit y Univ.
ul) No Nonroutine Anomalous Afrasttremcrus Refterted Iburing ihis l*criod.
n in Afcan Afudmum IWicciable Concemr.tuon Cakulated l'er iable 2 of 1 Jus Rciv rt.
tt 1 Number of Alca.mrcments inth Iktectable Activity Only 4I)) 1 oral Number of Areawrements Talcrt TABLE 1993-6 Page 1 of 1
WATERBORNE: SURFACE WATER OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT l.lCENSli NOS. NPlu2 AND NPI-8 IlOUSTON Col 1NTY Al.AllAMA
SUMMARY
Rf PORT I ROM 10194 TO 121191 (A>
. . .- .?? ' .!_ !!-_ ._. .. .
.'L h%. .
TYPE And. _ _ . . - . .All INI)lCA' LOR INDICA' LOR 1.OCATION .COMMUNilY CONTRW Tul'AL LOCATIONS WTni filGilEST ANNilAL MEAN 1.OCATIONS I OCATIONS NUMilERS Of souisat NAMli AN Al.YSIS umm MEAN MIN MAX DisTrsca MiiAN MIN MAX MiiAN MIN MAX Ml!AN MIN MAX PI RIORMED c o And DiknTloN C D C D C D it A-140 2r > 1s615 <MDC NA NA NA <MDC NA NA NA NA NA (MDC NA NA 0 13 0 0 0 0 0 13 C0 5^ 26 3 9ta2 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 Co m 26 3.942 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 CS 134 24 4 hx5 <MDC NA NA NA <MDC NA NA NA NA NA <MD( NA NA 0 13 0 0 0 0 0 13 CS- 137 26 40M <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 ,
1 l
lb59 26 K462 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 13 0 0 0 0 0 13 l l
IA 140 26 3 'ta <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 13 0 0 0 0 0 13 l l
M N-54 2n 4 000 <MDC NA NA NA < MI)C NA NA NA NA NA < MI)C NA NA l 0 13 0 0 0 0 0 13 l l
Nil 95 26 4 2f.9 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 TRITil f M s 100 000 1 A 750 229 569 GPPC 3e 750 229 569 NA NA NA <MDC NA NA j 4 4 RIV. MI. 40 4 0 0 0 4 l
/N f.5 26 x x44 <MDC NA NA NA <MDC NA i NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 ZR 95 2n 7.4 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 11
~
Mn Ik ternuncJ J rum .tfcasuremerus Wuh IJetectable A, uvu y unir.
(. I) No Nonrouune Anomalous Alcantremerus Rc;wrte i Ikinng 1 his l'eriod iIn Afcan Afinimurn IWtectable Conccruration CalculateJ I*er Table 2 of 1hn Re;vrt
!C> Nwnber of S1cautremaus With IWtectable Actwasy Uniy.
tih lvial Number of Sfeantremous laLert TABLE 1993-7 Page 1 <.f 1 1
i WATERBORNE: GROUND WATER - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT I ICF.NSl! NOS. NPF-2 AND NPF-8 IlOUSTON COUNTY Al.AHAMA
SUMMARY
Ri? PORT FROM 10193 TO 123193 u>
l GRUCNib WMER til EI.I.s 4I% I_I.6 liPh And ALL INDICAIOR ANDICATOR LOCAllON COMMUNITY CONIROL
'I OTAl . LOCATIONS WrDI lilGliF.ST ANNUAL MI!AN l.OCATIONS 1 OCATIONS NUMBl!RS Of soulut. NAMli ANALYSIS winsi MiiAN MIN MAX DisTocr Ml!AN MIN MAX MiiAN MIN MAX MliAN MIN MAX Pl RI ORMl(D c o Aw pi m Tion c o e o e o ilA-140 8 lx.125 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 CO-5A 8 3.750 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 CO M h 4.125 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 US- 131 R 4 375 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 l CS- 137 8 4.125 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 1 E59 8 7.S75 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 1-131 8 0.2% <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 lA-140 x 3 230 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 MN54 8 3375 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 NB45 8 4im <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 TRil LUM s 100 WWI <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 ZN -65 x 8 575 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 1
/.R -95 8 6 475 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 I
Alcan - (Wierndru J I rom Alcamrenwous With (ktectable kiivit y only i A t No Nontounne Anornalous Alcanirenwnts Ret >ricJ lhreng ihis l'eriod.
t H) Sican Studnuam IWiectable Conceruranon CalculascJ Per Table 2 of finis Re;vrt.
tr) Nun +ct a f Alcamrenwrus Wuh (Wiectable kuva y Unly.
l t!)) 1 oral Number of Siea.niremcrus Takcrt TABLE 1993-8 l Page 1 of 1 1
i l
l
SEDIMENT: RIVER OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT l.lCENSli NOS. NPF.2 AND NPF-8 IlOUSTON COUNTY ALAllAMA
SUMMARY
RI: PORT I ROM 10193 TO 123193 M;
^
4ElblMENT tRil liko tWi> Ato-llR}~s .
TYPh And A1..L IN DICA l'UR INDICAlOR 1,0CAllON COMMUNITY CONI'ROL
,. TOTAL. LOCATIONS WITil llIGilEST ANNUAL Ml!AN I.OCATIONS I OCATIONS NUMIIERS Of sowiut. NAME ANAL.YSIS uncini MEAN MIN MAX DisTocx MEAN MIN MAX MEAN MIN MAX MiiAN MIN MAX PI RI ORMI D c o 4.a otur Tion c o e o c o AC-22X 4 (2Muo l014.50 wi 1120 SMI l'll'S lihND 1014 50 909 1120 NA NA NA 1935 00 1690 2180 2 2 R IV. MI. 41 2 2 0 0 2 2 111-212 4 620.500 1235 00 1190 1280 SMITii'S ilEND 1235 00 1190 12A0 NA NA NA 2135.00 1850 2420 2 2 RIV. M1. 41 2 2 0 0 2 2 111214 4 79.750 564.500 539 590 SMITi l'S ilEND 5tA500 539 590 NA NA NA 10*) 00 9W) 11(N) 2 2 RIV. MI. 41 2 2 0 0 2 2 h CS- 134 4 41.500 940m0 44 94 S Ml lll'S ilEN D 94 0mM 94 94 NA NA NA 1051mW) 105 105 4 1 2 RIV. MI. 41 1 1 0 0 1 2 l
2 CS 137 4 42.250 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 K-40 4 316.500 2555.00 25T0 2530 SMITi l'S ilEN D 2555.00 100 2ho NA NA NA 2t>45 00 1760 3510 2 2 RIV. MI. 41 2 2 0 0 2 2 l
) Pll-212 4 M 250 955.500 881 10.M SM ITi l'S ilEN D 955.500 881 1010 NA NA NA 1825.00 1490 2160 l 2 2 RIV. M t. 41 2 2 0 0 2 2 Pil 214 4 82.5m) 579.500 562 597 S MITi l'S ilEN D 579.500 562 597 NA NA NA 10'O.00 94 1210 2 2 RIV. MI. 41 2 2 0 0 2 2 RA.226 4 Sw 250 s941n)0 594 894 sMITil'S ilEND A94 000 894 894 NA NA NA 1335 00 1160 1510 1 2 RIV. M I. 41 1 1 0 0 2 2
'II. 20x 4 44.250 tid 591 352 375 SMITi l'S ilEN D 363.500 352 375 NA NA NA 7191mni 645 793 2 2 RIV. M t. 41 2 2 0 0 2 2 Alcan Iktermirwd I rom Mcamremous Wah Ik tet table Activity only \
t A > No Nontoutine Anomalous Afeamremous Referred Imring 1 his Pernod.
t'Ho Alcan Afuumum ik tectable Conceruration Calculated Per Table 2 0f This Retort t C) Number af Aieamicments With Ik tectable Activtty Only.
tIH luta! Number of Afeasurements Taken.
TABLE 1993-9 Page 1 of 1 i
l i
FISH: RIVER (GAME)-OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPl4 IlOUSTON COUNW ALAllAMA
SUMMARY
RI' PORT lROM 10193 TO 123193 M/
FISH 4GAMEI qN I A'G if ET TIMES ITI'E And ALL INDICAIOR INDICAIOR LOCAllON COMMUNI'lY CONIKOL TOTAL LOCATIONS WITil IIIGIIEST ANNUAL MEAN LOCATIONS I OCATIONS NUMilERS of sowisa NAME ANALYSIS wim a, MU.AN MIN MAX Din 4%cF. M EAN MIN MAX MEAN MIN MAX MEAN MIN MAX PFRI ORMI D c o raa ntura'rio% e o e o e o TO-5s 4 24 W <MDr NA NA NA (MDC NA NA NA NX NA (MDC NA NT 0 2 0 0 0 0 0 2 CO M) 4 30.250 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CS 134 4 28 250 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CS 1 U 4 23.500 M Otax) 34 34 SMITI PS lil:ND 34 Dixx) 34 34 NA NA NA <MDC NA NA 1 2 R IV. M t. 41 1 1 0 0 0 2 l
2 lb 59 4 59.250 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 1
2 K 40 4 195.250 290030 2630 3170 SMITil S ilEND 2wx)00 26.41 3170 NA NA NA 2645 00 2160 3130 2 2 RIV. Mt. 41 2 2 0 0 2 2 i MN-54 4 2W) <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA i 0 2 0 0 0 0 0 2
/N 65 4 60.500 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA O 2 0 0 0 0 0 2 i
Mean - lxterr?urwd I rom Mea.mremerus Wuh twice table At uvu v ortiv
( A t No Nonrotaine Anomalous Mea.mremnus Rcjn.rted thrtng 1lu s l'eriod.
t14 Mean Muumum IVtectable Conceruratwn rakulatcJ l'cr Table lof Ilus Retu>rt t C) Number of Meamicrrwnts With (ktertable Actn ny only.
4I>> 1ota' Number of Mcamremerus Takat TABLE 1993-10 l Page 1 of 1 l
l
s l.
, FISH: RIVER (BOTTOM FEEDING) OPERATIONAL RADIOACTIVITY
SUMMARY
I JOSEPH M. r~%FY NUCL11R PLANT LICENSE NOS. NPF-2 AND NPF-8 ~" Y"'NTY ALAllAMA
SUMMARY
REPORT IKOM no '
123193 rm
._. _ _ - - _. ._!_? '__. _. Y
..lYPi: And. ALL INDICA' LOR INDICAlOR LOCA'IR)N COMM uni l'Y CONTROL TOTAL LOCATIONS WM11 IIIGIIEST ANNUAL. MEAN LOCATIONS LOCATIONS NUMilERS Of %ourut. NAME ANALYSIS waxw MEAN MIN MAX oisTAmt Ml!AN MIN MAX MEAN MIN MAX MliAN MIN MAX PI RI ORMED c o 4.a Distrnow c o e o c o
( O 53 4 24 (M ut < MIX' NA NA NA < MI)C NA NA NA NA NA < Mix NA NA 0 2 0 0 0 0 0 2 CO M 4 26 750 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 2 0 0 0 0 0 2 CS-114 4 27.250 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CS - 137 4 3 250 20N(01 2th 20x SM fl'I t'S ill:ND 20s tum 20x 20x NA NA NA <MDC NA NA 1 2 RIV. MI. 41 1 1 0 0 0 2 lb59 4 66.750 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 K-40 4 152ANM) 2590 00 2550 26.4 SMfill'S ill ND 2590 00 2550 26 % NA NA NA 2460 00 2400 2520 2 2 RIV. MI. 41 2 2 0 0 2 2 M N-54 4 21.5tni <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 ZN -65 4 57.500 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 3Tiun InscrrruncJ l rom Atcasurements with twicaabic /aivu r orar q Al No Nonroutine Anomalous Alcamrements RcfortcJ lauring Tius l'criod.
(10 Afcan Afunmum ik tectable Concentration CakulatcJ l'er Table 2 of Tius Retort-t C) Number ol A1casurcments Wuh Ik tectable .ktivaty Only
{lb 1otal Number of Atcawremems Talert TABLE 1993-11 Page 1 of 1
l ATTACRMENT 1 JOSEPH M. FARLEY NUCLEAR PLANT LAND USE CENSUS JUNE 21, 1993 I. PURPOSE l
As required by FNP Technical Specifications 3.12.2 and 4.12.2, the annual land use census was completed on June 21, 1993. The purpose
! of the census was l
l l A. To identify, within a five mile radius of FNP, the location of the l
resident nearest the plant site in each sector. As used in the Land Use Census report, the termo "FNP" and " plant site" are interchangeable, and are defined as the point midway between the l Unit One and Unit Two plant vent stacks.
B. To identify within a five mile radius of FNP, the number and location of milk animals in each sector. As used in the Land Use census report, the term " milk animal" is defined as a cow or goat whose milk is obtained for human consumption.
! C. To determine, using results obtained in parts A and B above, if
! changes to the Offsite Dose Calculation Manual (ODCM) and/or the milk sampling program are necessary.
II. METHOD Using topographic maps obtained from the U. S. Geological Survey (USGS) and highway maps obtained from the Alabama Highway Department and the Georgia Department of Transportation, field surveys were conducted in each sector out to five miles from the plant site.
Information gained from residents interviewed during the surveys was used to establish or confirm the location of the resident nearest the plant site in each sector, and to determine whether milk animals were present in any sector within five miles of the plant site. The Houston County, Alabama, livestock agent and the Early County, Georgia, extension agent were contacted for assistance in locating commercial dairy farms or privately owned milk animals within five miles of the plant site. The results of the surveys are shown in Table 1.
Attachment 1 ENV/1 Page 1 of 4
III. RESULTS l l
A. NEAREST RESIDENT LOCATIONS l l
The location of the resident nearest the plant site in each sector is plotted on a USGS topographic map maintained by the environmental staff. The 1993 surveys revealed one change from the 1992 surveys. The residence identified in the 1992 surveys as nearest the plant site in sector six was unoccupied during the 1993 surveys. The 1993 surveys identified a trailer l approximately 300 feet north of the 1992 location and the same j linear distance from the plant site as the nearest occupied I residence in sector six. I B. MILK ANIMAL SURVEY Mr. Mickey Fourakers, Early County, Georgia, Extension Agent I stated that there are no commercial dairy farms in Early County, and that he knew of no privately owned milk animals within five miles of the plant site. Field surveys conducted along Georgia Highways 62, 370, 273 and 363, and Early County Roads 26, 103, 28, 270, 81 and 248 produced no evidence of milk animals.
l Mr. Ricky Hudson, Houston County, Alabama Livestock Agent, I provided a list of commercial dairy farms in Houston County, and stated that he knew of no privately owned milk animals within five miles of the plant site. Field surveys conducted along Alabama highways 52 and 95, and Houston County, Roads 75, 33, 42 and interconnecting secondary roads produced no evidence of milk animals.
There are three commercial dairy farms, all more than 5 miles from the plant cite, in the vicinity of FNP:
Ray Lewis Dairy Rt. 1 Ashford, AL 14 miles west southwest of the plant site; Ray Lewis, owner Green Valley Farms Webb, AL 1
12 miles west of the plant site; Bruce Ivey, owner Robert Weir and Sons Dairy Seminole County, GA 14 c4les south southeast of the plant site; Robert Weir, owner The current milk control sample location is Ray Lewis Dairy.
Since milk animals have not been located within five miles of the plant site, no milk indicator sample is collected.
Attachment 1 ENV/1 Page 2 of 4 l l
1
I Although milk animals have not bsen found within five miles of
- the plant site, the following itema have boon noted
- 1. As reported'in 1992'and previous surveys, Mr. Thomas Dean of Gordon, Alabama, keeps milk goats for his personal use at his residence six miles south of the plant site. Mr.
Dean was interviewed and the location of his residence and the presence of the goats confirmed.
- 2. A Holstein bull reported approximately 1.2 miles west southwest of the plant site in the 1992 surveys has been removed.
- 3. A mixed-breed Guernsey cow observed in 1992 at the residence of Mrs. Mary Esther Allums in Early County, Georgia, three miles east southeast of the plant site has been removed.
- 4. A herd of approximately 20 goats observed in Gordon, Alabama, 5.1 miles south of the plant site were removed in July 1992.
IV. CONCLUSIONS A. There is no occupied residence in any sector closer to the plant site than currently assessed by the ODCM.
B. In sector 6, although the location of the reside.sa .;sarest the plant site has changed, the linear distance from the plant site to the nearest resident is the same as that reported in 1992.
C. There are currently no milk animals within five miles of the plant site.
D. No changes to ODCM are required.
E. No change to the milk sampling program is necessary.
Attachment 1 ENV/1 Page 3 of 4
i TABLE 1 OF ATTACHMENT 1 JOSEPH M. FARLEY NUCLEAR PLANT LAND USE CENSUS AND MILK ANIMAL SURVEY l 1
JUNE 21, 1993 4
DISTANCE IN MILES TO NEAREST i RADIAL SECTORS RESIDENT MILK ANIMAL l 22.5 DEGREES EACH 1992 1993 1992 1993 REASON FOR CHANGE INDIVIDUALS INTERVIEWED North Northeast (01) 2.5 2.5 >5 >5 N/A *Mrs. C. H. Freeman Ms. Susan Herring Northeast (02) 2.4 2.4 >5 >5 N/A Mrs. Barbara Kirkpatrick
- Mr. Judson Freemau !
- East Northeast (03) 2.4 2.4 >5 >5 N/A *Mr. Jim Donaldson East (04) 2.8 2.8 >5 >5 N/A *Mr. Booker T. Spivey East Southeast (05) 2.8 3.0 >5 >5 N/A *Mrs. Mary Esther Allums Southeast (06) 3.4 3.4 >5 >5 Note 1 *Ms. Kathryn Smith Mrs. David Smith Mr. Harold Smith South Southeast (07) >5 >5 >5 >5 N/A Note 2 South (08) 4.3 4.3 >5 >5 N/A *Mrs. Francha Brown Mrs. Thomas Dean l South Southwest (09) 2.9 2.9 >5 >5 N/A *Ms. Pricilla Wilson Ms. Lula Mae McGriff
- Southwest (10) 1.2 1.2 >5 >5 N/A *Mr. Maurice Gilbert i West Southwest (11) 2.4 2.4 >5 >5 N/A
- r. Jimmy Daughtry Mr. Ray Lewis
. West (12) 1.3 1.3 >5 >5 N/A *Mr. Tommy Respress j Mr. Lester Smith West Northwest (13) 2.1 2.1 >5 >5 N/A *Mr. William coulson Northwest (14) 1.5 1.5 >5 >5 N/A *Mrs. Amanda Ryals Mr. Blake Jernigan North Northwest (15) 2.0 3.3 >5 >5 N/A *Mrs. Thomas Steely i
North (16) 2.6 2.6 >5 >5 N/A *Mr. Tony Knighton i ONearest Resident in Sector d
Note 1: New location. 1992 lecation unoccupied. l Note 2 No resident within 5 miles in sector 7. Georgia Pacific Paper Co. (GPPC) loccted in l sector 7, 3.9 miles from plant site. Air sampler, aurface water sampler. TLD located l on CPPC plant site. l l
l Attachment 1 Annual ENV Report /19 Page 4 of 4
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