ML20087H498
| ML20087H498 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1994 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| References | |
| NUDOCS 9505030185 | |
| Download: ML20087H498 (62) | |
Text
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4 South 3rn Nucl ar Optrating Company g o Post Offico Box 1295 Birmingham. Alabama 35201 Telephone (205) 863-5131 I
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- o. e morey Southern Nudear Operating Company Vice President Farley Project the Southem electnc System April 26,1995 l Docket Nos.:50-348 l 50-364 l
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U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington,DC 20555 l
- Joseph M. Farley Nuclear Plant Annual Environmental Operatina Report -Radiolonical Ladies and Gentlemen:
l The enclosed " Annual Environmental Operatmg Report, Part B: Radiological" for 1994, is transnitted in accordance with the Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 Technical Specifications Section 6.9.1.8 and 6.9.1.9.
If you have any questions, please advise.
Respectfully submitted,
()} b%4u Dave Morey WHO/ cit:enviorad. doc l
Enclosure cc: Mr. S. D. Ebneter Mr. B. L. Siegel w/o Mr. T. M. Ross 9505030185 941231 PDR ADDCK0500g8
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'i ALABAMA POWER COMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT !
PART B: RADIOLOGICAL i
JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO.1 LICENSE NO. NPF 2 AND ,
UNIT NO. 2 LICENSE NO. NPF-8 :
F PERIOD ENDING DECEMBER 31,1994 ,
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- ANNUAL ENVIRONMENTAL OPERATING REPORT
! PART B: RADIOLOGICAL 1
! TABLE OF CONTENTS l
l Section Tit!g Page
, I introduction 1 i
11 Radiological Sampling and Analysis 2 i
. lll Results and Discussion 7 IV Land Use Census and Interlaboratory Comparison 11 1 Program V Data Trends and Conclusions 11 i
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l RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ,
c LIST OF FIGURES Fiaure Titig >
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! 1 Indicator Sampling Locations for Airborne / Direct Environmental ,
Radioactivity at the Farley Nuclear Plant l 2 Community (Indicator 11) Sampling Locations for Direct Radiation in the Farley Nuclear Plant Area ,
3 Control Sampling Locations for Airborne / Direct Environmental Radioactivity in the Farley Nuclear Plant Area ,
4 Indicator and Control Sampling Locations for Waterborne Environmental Radioactivity in the Farley Nuclear Plant Area l
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES' Table lit!R 1 Outline of Operational Radiological Environmental Monitoring Program for Farley Nuclear Plant During 1994 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 1994 -
1994-1 Airbome: Particulates - Operational Radioactivity Summary 1994-2 Airborne: lodins - Operational Radioactivity Summary 1994-3 External Radiation - Operational Radioactivity Summary 1994-4 Milk - Operational Radioactivity Summary 1994-5 Vegetation: Forage - Operational Radioactivity Summary 1994-6 Soil - Operational Radioactivity Summary 1994-7 Waterborne: Surface Water - Operational Radioactivity Summary i 1994-8 Waterborne: Ground Water - Operational Radioactivity Summary 1994-9 Sediment: River - Operational Radioactivity Summary )
1994-10 Fish: River (Garne) - Operational Radioactivity Summary j 1994-11 Fish: River (Bottom Feeding) - Operational Radioactivity Summary l
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RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF ATTACHMENTS I
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Attachment Subiect ;
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1 Joseph M. Farley Nuclear Plant, Land Use Census ,
1 2 Plots of Selected Environmental Data i
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4 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM i
JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2
- 1. Introduction l The Joseph M. Farley Nuclear Plant, owned by Alabar.1a 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 Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a rated power output of 860 megawatts electrical (MWe) achieved initial
! criticality on August 9,1977. The unit was declared " commercial" on 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 I was shutdown for its twelfth refueling outage from March 5,1994 l through April 24,1994.
The Farley Nuclear Plant Environmental Monitoring Program is designed to detect the effects, if a'ny, 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 i 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 i 1989, with the addition of two more control TLDs and has continued l through 1994 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 man, and where an adequate comparison of predicted radiologicallevels might be made with measured levels. The control stations are placed at I locations where radiological levels 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 l
principal population centers between the indicator and the control stations (3-5 miles). Community TLDs were placed at locations approximately 1.2 l 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. Radioloaical 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 I locations of indicator, community and control stations. For each sample type l and location, one sample was collected and analyzed to meet Technical Specification requirements for Units I and 11. tr} sihl i soil monitoring was i discontinued in 1994 as it is no longer required by Technical Specifications. )
The samples were collected by Southern Nuclear's technical staff except for fish and river sediment samples. The fish and river sediment samples were collected by Alabama Power Company (APCo) Environmental Field Services personnel. All sample analyses were contracted to the Georgia Power Environmental Lab. 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 i samples are provided in Table 3. Sampling and analysis deviations during ,
1994 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 il 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 rption 0304 is located 4 miles east northeast of the plant site. Fish and sediment sample 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 apprcximately three miles upstream.
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A. Airbome Particulates and lodine ,
i l The airborne particulate and iodine monitoring stations shown in Figures 1 .
! and 3 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 l
microprocessor based air volume totalizer, an open faced combination filter holder and a thermostatically contro!!ed exhaust fan, all mounted in a ,
ventilated aluminum weather house. in March 1993, electrical surge l
[ 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 i 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 i 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.
Particulate filters and charcoal cartridges were collected weekly and sent to l GPC lab for radioactivity analysis. Gross beta radioactivity measurements were performed on each air particulate filter using a low background gas flow proportional counting system. The filters from each station, i composited at the end of each quarter, were analyzed for gamma emitters '
using either a twenty percent or forty percent relative efficiency EG & G l intrinsic germanium detector system, l f
l All air monitoring station locations shown lii Figures 1 and 3 have the i capability of monitoring airborne iodine. Weekly routine samples were j analyzed for 1-131 by the GPC Environmentallab using either a twenty l percent or forty percent relative efficiency EG & G intrinsic germanium detector system.
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B. External Radiation Environmental TLDs are processed for external radiation using Panasonic UD-814 TLDs and UD-710A TLD readers. Replicate (3) elements of CaSO, .
encased in 860 mg 'em2 of plastic and lead are used as the primary detector. Each field location contains two TLDs, therefore utilizing six l
elements of CaSO. Each badge is permanently sealed in a 10 mg/cm2 plastic bag to protect it from moisture. The mean and standard deviation is reported for each badge and field location. 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.
1 At each external radiation monitoring station (shown in Figures 1-3), two TLDs changed and read quarterly, were exposed side-by-side on metal I stakes at a height of one meter above the ground. For the computation of J the net field doses, a log of all exposure periods was maintained for each J TLD packet.
l C. Milk The milk sample location is as indicated on Figure 3. All milk !amples, ;
collected bi-weekly, were analyzed by GPC for I-131 and gan ra emitters. I As a preservative for shipment,1 ml of 25 weight percere r" uthiolate 1 (Thimerosal) solution was added to each one gallon sample until November 22,1994. Starting with the November 22 sample, the milk was no longer l chemically preserved, but was maintained cold and shipped via over night !
express. The elimination of the preservative removed the need for I correction for its addition in the analytical process, as well as making the preservation process consistent with Plants Vogtle and Hatch, whose milk samples are also analyzed at the Georgia Power Lab. The 1-131 concentration in each sample was determined by collection on anion l exchange resin, elution with sodium perchlorate, folicwed by precipitation !
as silver iodide and counting on a beta-gamma coincidence counter or the low background gas flow proportional counter. Stable iodide carrier was added to each sample for determination of the radiochemical yield. The concentration of stable iodine present in the sample before carrier addition was also determined and accounted for in the chemical yield determination.
One liter of each sample was placed in a marinelli beaker and analyzed for gamma emitters using either a twenty percent or forty percent relative l efficiency EG & G Ortec intrinsic germanium detector system. l l
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D. Vegetation: Forage I
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. Vegetation samples were chopped to a smaller size, mixed well, then an approximate 200g sample aliquot of the wet sample was placed in a 0.45 liter marinelli beaker and analyzed for gamma emitters using either a twenty percent or forty percent !
relative efficiency EG & G Ortec intrinsic germanium detector system.
E. Surface (River) Water Weekly, samples of water from the Chattahoochee River, upstream and i 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 GPC Environmental Lab for radioactivity analysis. One liter of each sample was placed in a marinelli beaker and analyzed for gamma emitters using either a twenty percent or forty percent relative efficiency EG & G Ortec intrinsic germanium detector system.
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. River water quarterly composite samples were analyzed for tritium by distilling an aliquot of the sample along with sodium hydroxide and potassium permanganate. An aliquot of the distilled sample was mixed with liquid scintillation cocktail and analyzed for tritium on a Beckman LS7800 Liquid Scintillation Counter with the window settings and sample size optimized for tritium.
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F. Ground (Well) Water in the Farley Plant area there are no true indicator sources of groundwater.
!- 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, 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 the GPC lab for radioactivity analysis. Ground water samples were analyzed for tritium by distilling an aliquot of the sample along with sodium hydroxide and potassium permanganate. An aliquot of the distilled sample was mixed with liquid scintillation cocktail and analyzed for tritium on a Beckman LS7800 Liquid Scintillation Counter with the window settings and sample '
size optimized for tritium. Ground water samples were analyzed for low level 1-131 by precipitating one liter of sample as palladium iodide and I counting the final palladium iodide precipitate on a beta-gamma coincidence counter or the low background gas flow proportional counter. One liter of each sample was placed in a marinelli beaker and analyzed for gamma emitters using either a twenty percent or forty percent relative efficiency EG & G Ortec intrinsic germanium detector system.
G. Fish (River)
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
! to GPC for gamma-ray spectroscopy analysis. All fish samples sent to GPC consisted of fish fillets that had been split with Alabama Division of Radiation Control. These fish samples were chopped to a smaller size, mixed well, then an approximate 450g aliquot of the sample was placed in a 0.45 liter marinelli beaker and analyzed for gamma emitters using either a i twenty percent or forty percent relative efficiency EG & G Ortec intrinsic j germanium detector system.
l H. Sediment (River)
Semi-annually, sediment samples were collected from the Chattahoochee River at the locations shown in Figure 4. Approximately one kilogram of each sample was sent to the GPC lab where it was dried, ground and mixed and an approximate 450g aliquot was placed in a 0.45 liter marinelli l beaker and analyzed for gamma emitters using either a twenty percent or forty percent relative efficiency EG & G Ortec intrinsic germanium detector system.
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Ill. Results and Dis _cussion No known atmospheric nuclear tests were conducted during 1994 Attachment 2, Plots of Selected Environmental Data,is included as an enhancement to trending. In general, the mean annual c ncentrations of frequently identified isotopes were chosen to be plotted. in cases where many !
naturally occurring isotopes were identified, those chosen to be plotted were ;
from differing decay chains. Significant uptrends in the data were as follows:
(1) Atmospheric Tests, Peoples Republic of China:
September 17,1977 March 14,1978 December 14,1978 October 15,1980 (2) Chernobyl Disaster, USSR, April 1986 A. Airborne Particulates and lodines Analysis results of airborne particulate filters and cartridges are shown in Tables 1994-1 and 1994-2, and Attachment 2, pages 1-4. The 1994 results remained oelow pre-operational levels, and showed a slight decrease in mean Beta activity while Beryllium-7 activity continued to increase. The 1992 Annual Environmental Operating Report documented step increases in these two parameters following the installation of new air monitoring stations in May 1992. The mean activities for these parameters in 1994 (0.019 pCi/m3 Beta,0.076 pCi/m3 Beryllium-7) were consistent with mean activities observed from June through December 1992 (0.021 pCi/m3 Beta,0.061 pCi/m3 Beryllium-7). As expected, these parameters appear to be stabilizing and will continue to be monitored for future trends.
The nominal MDC values for all parameters except charcoal cartridge 1-131 showed increases after contracting the analyses to the Georgia Power Environmental Lab beginning in January 1993. All MDC values remained well within ODCM requirements.
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l As stated in Paragraph 11 A, in September 1993, the Gelman VM-1 i Metricel membrane filters used for airborne particulate sampling since 1977 were replaced with Gelman A/E glass fiber filters. Following l installation of the new air monitors in 1992, the membrane filters were found to clog and rupture occasionally. Ruptured filters were observed
- mere frec;uently during the summer months, when high ambient
- temperatures and humidities prevailed. Review of product information l and literature documented a "high resistance to airflow" and i " 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 cf flowrate, particle size retention, and cost. This filter is also used by the other nuclear generating plants in the Southern Company for sampling airbo ne 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.
B. Extemal Radiation The results of the external radiation measurements are shown in Table 1994-3 and Attachment 2 page 5. Mean extemal gamma exposure measured in 1994 was less than in 1993 and slightly greater than during the pre-operational period. The highest mean annual exposure to a single location,87.0 mR, was again measured at station Rl-0401, located on the plant perimeter O.8 miles east of the midpoint between the Unit i and Unit il plant vent stacks. This represents a decrease from the 1993 value (94.9 mPl. The mean external gamma exposures l for all stations are consistent with previously observed annual
! variations, and no significant differences in indicator, community and l control measurements were noted.
l Deviations from the Environmental Monitoring Program resulting from
! external radiation measurements are given in Table 4.
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C. Milk The milk analysis results are shown in Table 1994-4 and Attachment 2, pages 6 8. Through 1993 Lewis Dairy had been used as the control location. In December 1993 Mr. t.ewis indicated that he no longer wished to allow milk sampling. In January 1994 an agreement was reached with Mr. Bruce Ivey, owner of Ivev Dairy (Green Valley Farms),
Webb, Alabama to allow sampling at his dairy. Beginning February 14, 1994 all control milk samples were from Ivey Dairy. There were no indicator samples in 1994. The 1994 results are consistent with those
. of previous years, and Potassium-40 was the only isotope detected in milk samples.
No deviations from the Env;ionmental Monitoring Program resulted from milk sample analysis.
D. Vegetation Forage analysis results are shown in Table 1994-5 and Attachment 2, pages 9-12. The 1994 results are below pre-operationallevels and consistent with the downward trends of recent years. The control samples collected August 2,1994 and October 24,1994 contained 25.2 pCi/m3 and 21.8 pCi/m3 Cs-137 activity. These values are below pre-operationallevels and are not considered significant since Cesium 137 has been shown to be present in the soil throughout the area. Mean Beryllium-7 activity increased in bott- e indicator and control samples but remained well below preope il levels.
No deviations from the Environmental Monitorirs .Wram resulted from forage sample analysis.
E. Soil The in situ soil analysis was discontinued in 1994 since there is no requirement that this be performed.
F. Waterborne (Surface Water)
The surface water analysis results are shown in Table 1994-7 and in Attachment 2, pages 1517. In years prior to 1994 the indicator samples (and occasionally the control sample) have shown tritium levels greater than MDC. Also prior to 1994, the MDC for tritium was approximately 100 pCi/l. In 1994, all tritium samples were shown to be less than an MDC of 271.5 pCi/l. Although the MDC for 1994 is higher than previous years, it is less than the levels of tritium which were measured in the indicator samples in both 1992 and 1993 (see Attachment 2, page 15), and still considerably lower than the ODCM requirement of 2000 pCill (drinking water pathway limit).
Deviations from the Environmental Monitoring Program occurred on 7-5-94 and 8-16-94 and are given in Table 4.
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l G. Waterborne (Ground Water)
The ground water analysis results are shown in Table 1994-8 and in l Attachment 2, pages 18-20. No measurable activity from man-made l l
isotopes was detected in ground water samples in 1994. j l
No deviations from the Environmental Monitoring Program resulted from ground water analysis.
H. River Sediment River Sediment results are shown in Table 1994-9 and in Attachment 2, pages 21-24. Activity from several naturalisotopes was identified l in both the control and indicator samples. Cesium-137 was identified j in both the Spring and Fall indicator samples and in the Spring control sample. The identified presence of Cesium-137 can be attributed to l the fact that the nominal MDC for Cesium 137 decreased from 42.25 l pCi/m3 in 1993 to 6.3 pCi/m3 in 1994 when the Georgia Power
! Environmental Lab began contracting the analyses. The mean Cesium-i 137 activity for 1994 (29 pCi/m3) is below the nominal MDC for 1993 l (42.25 pCi/m3).
No deviations from the Environmental Monitoring Program resulted from river sediment analysis.
- 1. Game Fish (River)
The analysis results of edible portions of Chattahoochee River game fish are shown in Table 1994-10 and in Attachment 2, page 25.
Cesium 137 activity was detected in both the spring and fallindicator and background samples. Detected activity was below pre-operational levels and consistent with established trends.
No deviations from the Environmental Monitoring Program resulted j from game fish analysis. !
J. Bottom-Feeding Fish (River) j Analysis results of edible portions of Chattahoochee River bottom-feeding fish are shown in Table 1994-11 and in Attachment 2, page
- 26. Cesium-137 activity was detected in the spring and fallindicator sample. Detected activity was below pre-operationallevels and consistent with current trends.
No deviations from the Environmental Monitoring Program resulted from bottom feeding fish analysis.
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I IV. Land Use Census and Inte. laboratory Comparison Proaram l
A. Land Use Census and Milk Animal Survey l
l l The Land Use Census and Milk Animal Survey was completed on June l 17,1994. The results are given in Attachment 1.
l No deviations from the Environmental Monitoring Program occurred as a result of the Land Use Census and Milk Animal Survey.
B. Interlaboratory Comparison Program During 1994, the Georgia Power Environmental Lab as a participant in the EPA Crosscheck Program. The Georgia Power Environmental Lab EPA Program code designation is MO. l V. Data Trends and Conclusi.p_q l
l Review of the data trends from the pre-operational period through 1994 l l
indicates that environmental radiation levels measured in all the pathways J l monitored in 1994 remained at background levels and were consistent with pre-I operational levels. Cesium-137 was idt.:ntified in river sediment, and game and l l bottom feeding fish but is not significant because Cesium-137 is known to occur in the environment, and was shown at levels below the MDCs of previous years.
It is noteworthy that the contract lab changed in 1994 from the University of Georgia to the Georgia Power Environmental Lab. As a result, MDCs of some analyses showed changes over MDC trends of previous years. All MDCs remained i well below ODCM required limits. All data collected in 1994 continue to !
demonstrate that operation of Farley Nuclear Plant has had no detrimental affect on the environment.
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INDICATOR SAMPLING LOCATIONS FOR AIRBORNE / DIRECT ENVIRONMENTAL RADIOACTIVITY AT THE FARLEY NUCLEAR PLANT FIGURE 1 1
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s 1 CONTROL SAMPLING LOCATIONS FOR AIRBORNE / DIRECT 4 ENVIR.ONNENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA FIGURE 3 s *
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e so..m .m..nsmo stoiMm x nss Ano stoiMm @snounowmi INDICATOR AND CONTROL SAMPLING LOCATIONS FOR WATERBORNE ENVIRONMENTAL RADI0 ACTIVITY i
IN THE FARLEY NUCLEAR PLANT AREA FIGURE 4 i
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TABLE 1 OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL - ;
MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1994 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 por 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 /> i 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)
Iodine Continuous sampler operation Radiciodine canister 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)
I Plant Entrance - (WSW-0.9) l River Intake Structure (ESE-0.8)
Table 1 Page 1 of 5 i
, _ _ _ -__.._ _____ I
TABLE 1 (c@n d) [
Types of samples ,
and Sampling Type and Frequency.
Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis Community Stations: ,
I Georgia Pacific Paper Co. (SSE-3) y Control Stations:
Blakely, CA. (NE-15) 'I Dothan, AL. (W-18)
Neals Landing, FL. (SSE-18) i DIRECT RADIATION At least once per 92 days Gamma dose Readout at least once per 92 days Indicator I Stations:
Sixteen stations, one in each meteorological l
, sector along the plant perimeter (N-0.8, I
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:
I i 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).
l Special Interest Stations: ,
. Occupied residence nearest the plant site (SW-1.2)
City of Ashtord, AL (WSW-8.0) a Table 1 4 Page 2'of 5 o
TABLE 1 (con'd)
Types of samples ,
and Sampling Type and Frequency sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis Control Stations:
Blakely, GA. (NE-15)
Neals Landing, FL. (SSE-18)
Dothan, AL. (W-18)
Dothan, AL. (W-15)
Webb, AL. (WNW-ll)
Haleburg, AL. (N-12)
WATERBORNE Surface Wateg 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)
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 Stations once per quarter.
Paper Mill at Cedar Springs, GA, Well (SSE-4)
Control Station:
Whatley Residence, Well (SW-1.2)
Table 1 Page 3 of 5
TAILE 1 (con'd) .
Types of Samples .
and .
Sampling Type and Frequency sampling Locations and of ,
(Distances Given in Miles) Collection Frequency Analysis River Sediment Grab aample taken at least Gamma isotopic analysis once per 184 days. of each sample twice per year. l Indicator Station:
Downstream of plant discharge at Smith's Bend (River Mile - 41)
Control Station:
i Upstream of plat.t discharge at Andrews Iock & Dam Reservoir (River Mile - 47)
INGESTION Milk Control Staton Ivey Dairy (Green Valley Farms) At least once per 16 duys Gamma isotopic and I-131 Webb, AL. (W-12) analysis of each bi-weekly sample when animals are on pasture.
Fish Indicator Station: one sample each of the following Gamma isotopic analysis l species at least once per each on edible portions once
- season (March 15 - May 15 and per season.
September 15 - November.15)
.. Game Fish
- 2. Bottom Feeding Fish Downstream of plant discharge in vicinity of Smith's Bend (River Mile - 41)
Table 1 Page 4 of 5
. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ . _. . _ _ __ __ .~. .._ .. . . _ .
i
. I TABLE 1 (con'd) ,
Types of Samples .
and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis l
Contrei Stationt Upstream of plant discharge
! in Andrews Lock & Dam Res=rvoir (River Mile - 47)
Foraae Grab sample cut from green Gamma isotopic analysis forage at least once per 31 (which includes I-131) days, of each monthly sample.
Indicator stations
, North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Control Station:
Dothan, AL. (W-18) l i I i
t' i
b
, Table 1 4
- Page 5 of 5 f
4
_ . . _ - .. _ . - ._....._. - ._ __ . _ . ..._..._.-..-_.-....m ._ _----- . - . . . _ . - - _ .. - . . . _ - . ...m- __ - .m -._._..m... .
TABLE 2 1
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 fDCi/1) i pCi /m') fDCi/ka. wet) fpCi/11 (pC1/ko. wet) ipCi/ko. dryl 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 Nb-95 15 NA FA- NA NA NA I-131 l' O.07 NA 1 60 NA Cs-134 15 0.05 130 15 60 150 i
Cs-137 18 0.06 150 18 80 180 i Ba-140 60 NA NA 60 NA NA i
La-140 15 NA NA 15 NA NA Table 2
{
Page 1 of 2 4
- . . _ . _ . _ _ _ _ _ _ . - . _ . _ _ _ - . . _ _ _ _ _ - - _ _ . _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ , m_ . , . _ , , - - _ , - _ _ .- .- __
i
, TABLE 2 (con'd)
'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 separation, the MDC for a given radionuclide is determined as follows:
l +- l' 2.71 + 3.29 R, l
l MDC =
t, j st, tv I I E V 2.22 x 10' Y e" !
I l where: l MDC= the apriori MINIMUM DETECTABLE CONCENTRATION (pCi per unit l mass or volume).
2.71 = the square of the standard normal variate (1.645) for the 95 percent confidence level.
I 3.29 = Two times the standard normal variate (1.645) for the 95 percent conficence
! level.
R$ = the background counting rate, or the counting rate of a blank sample, as i
appropriate (counts per minute). l
- t. = the length of the sample counting period (minutes).
ta = the length of the background counting period (minutes).
E= the counting efficiency (counts per disintegration).
V= the sample size (units of mass or volume).
2.22 X 10' = the number of disintegrations per minutes per pCi.
Y= the fractional radiochemical yield, when applicable.
A= the radioactive decay constant for the given radionuclide (h '). Values of A used in effluent calculations should be based on decay data from a recognized and current source.
At = for effluent samples, the elapsed time between the midpoint of sample collection and the time of counting (h); for environmental samples, the
- elapsed time between the end of sample collection and the time of counting (h).
6 Where values were reported as < MDC, the MDC was calculated using actual sample background (a posteriori).
- MDC for drinking water.
Table 2 Page 2 of 2
~
TABLE 3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES -
Airborne Particulate Water or Gas Fish Milk Food Products Analysis iDCi/1) (DCi/ml) fDCi/ko. wet) (DCi/1) iDCi/ko. wet)
H-3 2 x 10' NA NA NA NA Mn-54 1 x 10' NA 3 x 10* NA NA 2
Fe-59 4x 10 NA 1x 10' NA NA Co-58 1 x 10' NA 3 x 10' NA NA 2
Co-60 3x 10 NA 1x 10' NA NA Zn-65 3 x 10 2 NA 2 x 10' NA NA Zr-95 4 x 10 2 NA NA NA NA 2
Nb-95 7x 10 NA NA NA NA I-131 2 x 10' 9x 10 NA 3x 10' 1 x 10 2 Cs-134 3 x 10' 1x 10' 1x 10' 6 x 10 3 1 x 10' Cs-137 5x 10' 2x 10' 2x 10' 7x 10 8 2x 10' Ba-140 2x 10 2 NA NA 3 x 10 2 NA 2
La-140 1x 10 NA NA NA NA
'For drinking water samples.
a Table 3 Page 1 of 1
t
. i t
. l TABLE 4 ENVIRONMENTAL MONITORING PROGRAM DEVIATIONS 1994 DATE/ TIME COMPONENT CAUSE OF DEVIATION RESOLUTION REMARKS
- 3-15-94/1542 Air monitor 1605 Surge protector tnpped af ter Breaker was reset, tripped again, Monitor out of service for approximately approximately 52:59 hours of surge protector was replaced. 116 hours0.00134 days <br />0.0322 hours <br />1.917989e-4 weeks <br />4.4138e-5 months <br /> first trip, approximately 10 ,
operation. hours the second time. ,
G-5 94/* Community TLD 1504 TLD and stake missing Stake and TLD replaced. No data for first quarter. Average of quarters 2,3,4 was used for computer trending.
5-9-94/0829 Air monitor 0718 Air monitor found not running, sample Surge protector was reset. Monitor elfectively out of service volume / time lost._ 171:31 hours.
5-31-94/0812 Air monitor 1108 Air morutor found tripped af ter 95:00 Surge protector reset. Monitor out of service 72:52 hours.
hours. Sample volume of 264.5 m* met minimum requirement.
l 7 5-94/0804 Air monitor 1108 Morutor found tripped af ter 151:32 Reset breaker. Monitor out of service 17:51 hours.
hours due to severe weather.
7-5-94/1553 Background River Sampler removed from Andrews Dam Sampler replaced on 7-12-94 af ter No background river water sample for water sample due to severe flooding. flood waters receded. week of 7-5-94 -+ 7-12 94 7-5-94/1830 Indicator TLDs TLDs RI-0101, RI-0201, RI-0301, RI- TLDs were collected on 7-11-94 af ter Although no TLDs were lost, they were 0401, RI-0501, RI-0601, R!-0801, RI- flood waters receded. collected greater than 92 days after 0901, RI-1401, RI-1501, inaccessible installation.
due to flooding.
7-12-94/0820 Air monitor 1108 Monitor tnpped af ter 22:16 hours due Monitor reset and restarted. Monitor out or service for 145:57 hours.
to severe weather. Required Gross Beta MDC of 0.01 pCi/m* met despite low sampfe volume.
7-12 94/0902 Air monitor 0718 Monitor tripped af ter 95:05 hours due Monitor was reset and returned to Monitor our of service 71:08 hours.
to severe weather and loss of power service.
due to flooding.
7-12-94/1125 Air monitor 1605 Monitor tripped after 148:09 hours Monitor reset and returned to service. Monitor out of service 14:40 hours.
due to se'rere weather.
7-12-94/1233 Air monitor 1601 Monitor tripped af ter 153:59 hours. Monitor reset and returned to service. Monitor out of service 8:25 hours.
7-12-94/1320 Air monitor 0701 Morwtor found to have been New pump and totalizer insta!!ed, Monitor retumed to service 7-14-94 submerged during flooding. electncal power reestablished. 0755 af ter being OOS for 186:23 hours.
"No time recorded Page 1 of 2
TABLE 4 ENVIRONMENTAL MONITORING PROGRAM DEVIATIONS 1994 DATE/ TIME COMPONENT CAUSE OF DEVIATION RESOLUTION REMARKS 7-26-94/1315 Air monitor 1601 Power loss during thunderstorm Power restored and monitor returned Monitor out of service 246:40 hours.
caused sampler to stop af ter 150:30 to service 7-29-94/1538.
hours.
8-16-94/0910 River indicator sample Sample supply tubing vibrated out of Sample supply tubing secured to Missing sample volume made up with receptacle resulting in no sample. receptacle. the next weeks' sample.
9-20-94/0711 Air monitor 1601 Ouick connect fittings on biter holder Filter holder was reinstalled properly. Review of Beta particulate results not completel/ coupled allowing some indicated activity within expected range.
air to bypass filters.
12-13 94,'0812 Air monitor 1108 Monitor found sampling at 35 Ipm Flow rate adjusted. Pump changed Total sample volume of 347.9 M' was
(< required minimum) out 12-22-94/1415. sufficient to meet required MDCs.
12-20-94/1420 Air monitor 1601 Sample pump found not running. Due Pump was replaced. 235.98 M' sample collected, unable to to blown fuse on pump. determine how long pump was inoperable because the timer continued to run. All MDC requirements were met on analysis of filters.
I Page 2 of 2
i AIRBORNE: PARTICULATES-OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPI'2 AND NPF4 IlOUSTON COUNTY ALABAMA
SUMMARY
REPORT IROM 10194 TO 123194 to P 4MitTLMb5 tn I Ceek Makrb .
TYP i And AU INDICATGT- - INDTCATORIDCATION CDMMUNITY~ CONTROL TOTAL LOCATIONS Wml IIIGilEST ANNtfAL MEAN LOCATIONS LOCATIONS NUMBERS Of howtut. NAME ANALYSIS uman MEAN MIN MAX cisTA%cs MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX PERFORMED c o And raiarcnos c D c o c o BE7 40 0 016 0,07ts 0 0527 0.0945 NOR Di PLRIM 0 0nl 0.0t43 0.0945 0 073 0.04o4 0 4ws 0 077 0.0552 00 %
16 16 OE M1. N 4 4 12 12 12 12 BETA 519 0.004 0.019 0 007 0.036 SSE PERIM. 0.020 0.012 0.032 0.019 0 064 0 035 0.020 0.006 0 046 i 51 156 156 156 156 l 207 207 1.0 MI. SSE 51 C3 134 40 0.002 <MDC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 16 0 0 0 12 0 12 CS-137 40 0.002 < M DC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 16 0 0 0 12 0 12 J
1131 40 0 004 < M DC NA NA NA <MDC NA NA <MDC NA NA <MDC NA NA 0 16 0 0 0 12 0 12 i
l l
1 l
l l
i l
i i
J i
.I Mean - Desernune7Trom Meamremerus with skircuable Actnuy only.
(A) No Nornroutine Anarrwlous Meamrements Repwned LLnng Tha Period.
(B) hfcan Minimum skiectable Concentration Calculated Per Table 2of This Repon.
(C) Number ol Meamremerus Whh Ektectable Activity Only.
(D) TotalNurnber of Meamremens Taken.
TABLE 1994-1 Page 1 of 1
AIRBORNE: LODINE-OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF4 ilOUSTON COUNTY ALABAMA
SUMMARY
REPORT IROM 10lH TO 1231H lo AIR Ittibiht duMA Alekr6
~TYPEXT ~AlflNDICATok TNDTAToRToCATlotF~-~~~ ~ CDMMUN11Y CONiuOL -'~-,
TOTAL LOCATIONS Willi lilGilEST ANNilAL MEAN LOCATIONS LOCATIONS NUMBERS Of houtsrt NAME ANALYSIS MDcias MEAN MIN MAX pasTocs MEAN MIN MAX MEAN MIN MAX MiiAN MIN MAX PERFORMED e o A.a piarrnos e o e o e o 1-131 415 0.02.5 <MDC NA NA NA (MDC NA NA <MDC NA NA <MDC NA NA 0 207 0 0 0 52 0 156 Mean Determined From Meausrements Whh Iktectable Actisity Only.
(A) No Nontouzine Anomalous Measuremems Reported During This Perwd.
(B) Mean Minimurn Detectable Concentration Cakulated Per Table 2of This Report (C) Number of Measttremems With Detectable Activvy Only.
(D) TotalNumber of Measurements Taken TABLE 1994-2 Page 1 of 1
I EXTERNAL RADLATION: OPERATIONAL RADIOACTMTY
SUMMARY
JOSF.PH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF4 IlOUSTON COUNTY AIAllAMA
SUMMARY
RL; PORT IROM 10194 TO 123194 (m
~
EAMhtM forRJ TYPE And All INDICNIOR INDICATOR LOCAllON COMMUNITY CONTROL
%TITI l1101113T ANNUAL MFAN LOCATIONS 1.OCATIONS TOTAL LOCATIONS NUMBERS Of mouts4L NAME MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX ANALYSIS wto si MFAN MIN MAX omoct e o c o e o PERf'ORMED c o 4 4 omenom 20 83 23.7 12 9 25 1365 13 9.6 15 65 QUARlLR 160 NA 15 10'2 23.7 Pl.AN I PLRIM. 22 71 72 24 24 6t 64 0.8 MI. E 4 4 87.5 67.5 47 38.7 53 1 50 41.2 61 SUM (E) 40 NA 58 45 1 87.5 PIANT PERIM. 87.5 0.8 MI, E 1 1 18 18 6 6 16 16 l
l l
)
l l
i l
l Mean Ikterrmned f rom Meamrements H un ik,ectable A uvuy Only (A) No Nontoudne Anomakuus Meamremens Regened Dunng This renod.
(B) Mean Minimum Iktectable Concentrancm Cakulased Per Table 2 of This Reymrt.
(C) Number of Meamrements With Iktecsable Actn1ty Only.
(D) Total Number of Measurements Taken TABLE 1994-3 (E) Sum of the Four Quaners.
Page 1 of 1
, MILK: OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF 2 AND NPIt8 IlOUSTON COUNTY AIAllAMA
SUMMARY
REPORT FROM 10194 TO 123194 to AtIIK (PCIIL) ~
^ '
'IYPE And ALL INDICATOR INDICATOR LOCATION COMMUN TIY CONTROL lOTAL LOCAT10NS WTDI IllGilEST ANNUAL MEAN I OCATIONS LOCATIONS NUMBERS of hownsrt NAME ANALYSIS Miosa MEAN MIN MAX binrscr MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX PERFORM ED c o 4 4 tumrlos c o e o e o BA 140 26 27 NA NA NA NA NA NA NA NA NA NA <MDC NA NA 0 0 0 0 0 0 0 26 CS-134 26 5 82 NA NA NA NA NA NA NA NA NA NA <MDC NA NA 0 0 0 0 0 0 0 26 CS 137 26 8.50 NA NA NA NA NA NA NA NA NA NA <MDC NA NA 0 0 0 0 0 0 0 26 1131 26 0 73 NA NA NA NA NA NA NA NA NA NA <MDC NA NA
' 0 0 0 0 0 0 0 26 K-40 26 163 NA NA NA NA NA NA NA NA NA NA 1350 1200 1540 0 0 0 0 0 0 26 26 ,
l LA 140 26 8.83 NA NA NA NA NA NA NA NA NA NA <MDC NA NA l 0 0 0 0 0 0 0 26 l
l l
l Mean Ikserrruned irom Mcamrements With Iktectable Actanty Only.
(A)No Norvourine Anomalous Afcasurements Regened ikring Tfus Pcnod.
IB) Afcan Afinimwn Detectable Conceruration Calculated Per Table 2 of This Report.
(C) Nwnber of Afeomrcments With [ktectable Actnhy Only.
IDJ TotalNwnbcrof Alcasuremcrus ToLert TABLE 1994-4 Page 1 of 1
, VEGETATION: FORAGE-OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF 2 AND NPF4 ilOUSTON COUNTY A!AllAMA
SUMMARY
REPORT FROM 10194 TO 123194 m
. FORME (WilEGMETp .
. ,,7 7_.. . _ . . _ . _ . __
.. __ COMMUNilY CON IROL- ~ ~ ~~ ~
TOTAL LOCATIONS WTill lilGilEST ANNUAL MEAN LOCATIONS 1 OCATIONS NUMBERS Of somut. NAME ANALYSIS mesi MEAN MIN MAX MsT ort MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX PERI ORMED c o 4 4 oimm% e o e o e o AC-22a Tf' 73 TMDC NA RA NA <MDC fiA tW NA NA NA <MDC NA NA 0 26 0 0 0 0 0 13 BE-7 39 360 1032 125 2750 SSE PERIM. 1065 125 2t.80 NA NA NA 812 256 2150 25 20 1.0 Mi SSE 13 13 0 0 13 13 CS-134 39 12 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 26 0 0 0 0 0 13 CS-137 39 17 <MDC NA NA NA <MDC NA NA NA NA NA 24 21.8 25 2 0 26 0 0 0 0 2 13 I
l131 39 16 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 26 0 0 0 0 0 13 K-40 39 516 4077 1950 7470 NORlll PERIM 4246 2&M 7470 NA NA NA 4622 2/4K) 8140 26 26 0.8 MI. N 13 13 0 0 13 13 l
l l
Alcan Ikscrrruned t rom Mea.surements Wuh Lktectable Actsnty Only (A) No Nonroutine Anomalous Meamrerrents Repried During This Period.
(B) Mean Minimum Eksectable Conceruration Calculated Per Table 2cf This Repet (C) Number of Meamrements With Ikoectable Actinzy Only (DJ TotalNumber of Meamrements Toten TABLE 1994-5 Page 1 of 1
. SOIL: OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT 1.lCENSE NOS. NPF-2 AND NPF4 IlOUSTON COUNTY ALABAMA
SUMMARY
REPORT FROM 10194 TO 123194 e 4; Mill fl% Allt's II1likio-11RYo ,
'jwiEAnd - ~ '~ ~ALONDICATolE ~ ~~ ~ INDICA'l Olt TUCATION COMM UNIN~~ ~ ~ ~ CONTROL ~-~ --
TOTAL LOCATIONS Wml lilGilEST ANNUAL MIMN 1.OCATIONS 1.OCATIONS NUMBL R5 of somut. NAME ANALYSIS m w.a. MEAN MIN MAX onTocr MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX
, PI RIORMI D c o and Dikscrios e o c o C D NONE O NA NA NA NA NA NA NA NA NT NA NA hA NA NA NA NA 0 0 NA NA NA NA Alcan . lkscrnned itorn Afcasuremerus Wuh Iktectable Actmty Only (A)No Nonroutme Anomalous Alcasuremerus Rep >rted Dunng This Penod.
(B) Afean Attrumum Detectable Concentranon Calculated Per 7'abk 20f This Rep >rt (C) Number of Alcawcmcrus With Dctect.abk Activity Only.
(DJ TotalNumbcr of Meawcments ToLen TABLE 1994-6 Page 1 of 1
l
- WATERBORNE: SURFACE WATER- OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF 2 AND NPF4 IlOUSTON COUNTY ALABAMA
SUMMARY
REPORT IROM 10194 TO 123194 (N M M ist f. n .4 tut 4WMb IVPE And ALL INDICAUTR INDICAIUR LOU TION ~ ~~TUTdhjUNTIY CURIKUI TOTAL LOCATIONS Wml IllGilEST ANNUAL MEAN 1 OCATIONS LOCATIONS j
l NUMBERS Of moert. NAME ANALYSIS MEAN MIN MAX mffA m MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX l wucis>
o e o e o e o PERFORMED c A.4 muscrm NA NA NA <MDC NA NA NA NA NA <MDC NA NA BA 140 26 25 <MDC 0 0 0 0 0 13 0 13 l <MDC NA l CO-58 26 6.26 <MDC NA NA NA <MDC NA NA NA NA NA NA 0 0 0 0 0 13 0 13 1 NA <MDC NA NA COM 26 8.35 <MDC NA NA NA <MDC NA NA NA NA l 0 0 0 13
! 0 13 0 0 i
NA NA <MDC NA NA NA NA NA < M DC NA NA CS 134 26 5.46 <MDC NA 0 0 0 0 0 13 0 13 CS 137 26 6.98 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 0 0 0 0 13 l 0 13 NA NA <MDC NA NA NA NA NA <MDC NA NA l'Ii-59 26 14 <MDC NA l 13 0 0 0 0 0 13 0
l I 131 26 7.75 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 l
1A 140 26 8.73 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 MN-54 26 6.99 <MDC NA NA NA < MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 0 0 0 13 NB-95 26 6.82 <MDC NA NA NA <MDC NA NA NA NA NA (MDC NA NA 0 13 0 0 0 0 0 13 TRmUM 8 272 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 7M5 26 14 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
l 0 13 0 0 0 0 0 13 I
ZR-95 26 11 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 13 0 0 . 0 0 13 Mean - Determined from Meawements n uh Eksecsable Actmty Only.
(A) No Nontexaine Anomalous Meaucments Rrported skring This Penod.
(B) Mean Minimum DetectaMe Concerwration Cakulated Per Table 2 of This Report (C) Number of Measurements Wuh Ektectable Activisy only.
(D) Total Number of Meawements Taka TABLE 1994-7 Page 1 of 1
l t
. WATERIORNE: GROUND WATER. OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF 2 AND NPF.8 IlOUSTON COUNTY ALABAMA l
SUMMARY
REPORT IROM 10194 TO 123194 (N 4.RtM Ah n GER sn fekt (It1 Lp lYPE And A1.L LNDICA1DR INDICAlVR LOCATION COMMUNITY CON'IROL l TOTAL LOCATIONS %Till filGilEST ANNUAL MEAN LOCATIONS LOCATIONS I
l NUMBERS Of how!NAL NAME MEAN MIN MAX pastoct MEAN MIN MAX MFAN MIN MAX MEAN MIN MAX l ANALYSIS wocasi c o e o e o e o )
PERFORMED A.4 twarrww NA NA NA < M DC NA NA NA NA NA <MDC NA NA BA 140 8 24 < M DC 0 4 0 0 0 0 0 4 l
CO 58 8 6.41 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 4 0 0 0 0 0 4 I
l CO44 8 9.03 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA ;
4 0 0 0 0 0 4
)
I 0 l CS 134 8 5.73 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 4 0 0 0 0 0 4 l
CS 137 8 6.51 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 FE 59 8 13 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 l 131 8 0.73 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
0 4 0 0 0 0 0 4 l
l 1A 140 8 8.79 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 MN-54 8 6.84 <MDC NA NA NA <MDC NA NA NA NA NA < M DC NA NA 0 4 0 0 0 0 0 4 NB 95 8 6.76 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 TRmUM 8 267 <MDC NA NA NA <MDC NA- NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 4 ZN45 8 12 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 4 0 0 0 0 0 A ZA95 8 10 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l
l 0 4 0 0 0 0 0 4 Mean Daernuned from Meawemenu Wuh IksectaNe Acusvy %y.
(A) No Nontoutine Anomalms Meawements Reponed Ikaing Tha Perwd.
(B) Mean Minimum Dctectable Concerwradon Cakulated Per Tame 2 of This Report (C) Number of Meawements Whh Detectable Activity Only (D) TotalNumber of Meausremenu Taken TABLE 1994-8 Page 1 of 1
. SEDIMENT: RIVER-OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF4 IlOUSTON COUNlY ALABAMA
SUMMARY
REPORT I ROM 10194 TO 123194 (o
~
KII>I ul \frRIsi-Kr IN 1 Mi-DkYp TYPE And ALL INDICATOR INDICATOR LOCATION COMMUNITY CONTROL TOTAL LOCATIONS Wml filGilEST ANNUAL MEAN I OCATIONS LOCATIONS NUMBERS Of wow %at NAME ANALYSIS wucia, MEAN MIN MAX mmscs MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX Pl:RFORMED C o And NRF.CMO% C D C D C D T 228 4 30 700 70a 812 SMml S HEND 700 708 812 NA NA NA 900 539 l >()
2 2 RIV. MI. 41 2 2 0 0 2 2 BI-212 4 76 607 568 686 SMmi'S HEND 607 568 646 NA NA NA 644 418 60 2 2 RIV. MI. 41 2 2 0 0 2 2 Bl.214 4 19 549 459 639 SMmi'S HEND 549 459 639 NA NA NA 545 355 7.4 2 2 RIV. M1. 41 2 2 0 0 2 2 CS 134 4 7.39 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 CS 137 4 6.30 29 12.4 46 2 SMmi'S BEND 29 12.4 46.2 NA NA NA 11 11 11 2 2 RIV. MI. 41 2 2 0 o 1 2 K-40 4 112 4670 *t)?0 5670 SMmi's BEND 4870 4070 5670 NA NA NA 3505 2640 43 0 2 2 RIV. MI. 41 2 2 0 0 2 2 PB 212 4 16 457 72.4 841 SMmi'S BEND 457 72.4 641 NA NA NA 647 53.6 1240 2 2 RIV. MI. 41 2 2 0 0 2 2 PB-214 4 22 SM 495 660 SMml's BEND 588 495 660 NA NA NA 620 404 635 2 2 RIV. MI. 41 2 2 0 0 2 2 RA-226 4 205 1164 Wo 1330 SMml S BEND 1164 998 1330 NA NA NA 1292 804 IN 2 2 RIV. MI. 41 2 2 0 0 2 2
'IL 208 4 9 00 275 237 312 SMmi's BEND 275 237 312 NA NA NA 32 21 43 1 2 2 RIV. Mt. 41 2 2 0 0 2 2 t
Mean Iktennined from Meawemems Wuh IMectable Actinty Only.
M) No Nontourine Anomalous Meawemems Repnned Ikring TIus Period.
tB) Mean Minimum Iklectable Concemration Calculated Per Table 2cf This Report (C) Number of Meamrcmens With Iklectable Acmity Only.
IDJ TotalNumber of Meamremens Takert TABLE 1994-9 Page 1 of 1
. FISH: RIVER (GAME) OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF.2 AND NPF-8 IlOUSTON COUNTY ALABAMA I
SUMMARY
REPORT I' ROM 10194 TO 123194 to iI AII st ~ tAID IN *I Mi n F.$ TIA%CEp lYPE And ALL INDICATOR INDICATOR LOCATION COMMUNITY CON ~IKOL TOTAL LOCATIONS WH11 lilGilEST ANNUAL MEAN LOCATIONS LOCATIONS NUMBERS Of hownsrt. NAME ANALYSIS wims: MFAN MIN MAX onsTascr MEAN MIN MAX MEAN MIN MAX MEAN MIN MAX PE RFORMED c o 4 4 ciasx tio% c o e o e o C0-56 4 7.54 < MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CO-60 4 9.00 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CS 134 4 4 45 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 CS 137 4 5 00 19 17.3 21.6 SM mi'S BEND 19 17.3 21.6 NA NA NA 16 14 6 17.5 2 2 RIV. MI. 41 2 2 0 0 2 2 FE-59 4 '4 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 u o 2 K40 4 112 2930 2MO 3020 SMml'S BEND 2930 2A40 3020 NA NA NA 3155 2950 3360 I
2 2 RIV. MI. 41 2 2 0 0 2 2 M74 54 4 5.33 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 7365 4 16 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 l
Mean . Ekterrruned From Meamrements Wuh Lktectable Actnnty Only.
tA) No Nonroutine Anornalous Mcamrements Reprned During This Period.
IB) Mean Minimum Detectable Concentration Calculated Per Table 2of This Report (C) Number of Meamrements Wuh [Wiectable kinhy Only.
(D) TotalNumber of Meamrements Takert TABLE 1994-10 Page 1 of 1
l I
, FISH RIVER (BOTTOM FEEDING) OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF4 IlOUSTON COUNTY ALAHAMA
SUMMARY
REPOPT IROM 10194 TO 123194 (S l flSil 180110M FEEDWATa tWI4G N ET TiswEl lYPE And All INDICAlDR INDICATOR IDCA110N COMMUNITY CONIROL TOTAL ? OCATIONS Wml lilGilF5F ANNUAL MEAN LOCAT10NS IDCAT10NS NUMBERS Of houluL NAME ]
ANALYSIS utrian MEAN MIN MAX DisToct MEAN; MIN MAX MEAN MIN MAX MiiAN MIN MAX PERFOR MED C o A J ferr71o* C D C D C O CO-56 4 6.13 <MDC NA NA NA < M DC NA NA NA NA NA (MDC NA NA l
i 0 2 0 0 0 0 0 2 l l I l
l C040 4 7.86 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA l l
0 2 0 0 0 0 0 2 l CS 134 ? 4W < MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA
! 0 2 0 0 0 0 0 2 0
(5 137 C 6.10 15.9 15.9 15.9 SMI111'S BEND 15.9 15.9 15 9 NA NA NA 103 103 10.3 1 2 RIV. MI. 41 1 1 0 0 1 2 IE59 4 10 ch4DC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2 K-40 4 112 2730 2410 3050 SMFIll3 BEND 2730 2410 3050 NA NA NA 2700 2610 2790 2 2 RIV. MI. 41 2 2 0 0 2 2 l l
MM-54 4 6.87 <MDC NA NA NA <MDC NA NA NA "
.A NA <MDC NA NA !
0 2 0 0 0 0 0 2 ZN45 4 12 <MDC NA NA NA <MDC NA NA NA NA NA <MDC NA NA 0 2 0 0 0 0 0 2
(
Mean Lxserrmned from Mcamremems K uh Iktecuabic kunty Only (A) No Nonrounne Anomalous Menrem:nts Repurned skring Tha Perud
!B) Mean Minimum Eksectable Concewradon Caknda ed Per Tabk 2 ol TIus Repet (C)Numberof Meawements WithIksectable ActiNyOnly (D) Tout Number of Meamrements Taken TABLE 1994-11 Page 1 of 1
FNP-0-STP-799 RTYPE GB.05 JOSEPH M. FARLEY NUCLEAR PLANT LAND USE CENSUS JUNE 17, 1994 I. PURPOSE As required by offsite Dose Calculation Manual (ODCM) section 4.1.2, the annual land use census was completed on June 17, 1994. The purpose of the census was:
To identify, within a five mile radius of FNP, the location of the A. ,
resident nearest the plant site in each sector. As used in the Laad Use Census report, the terms "FNP" and " plant site
- are interchangeable, and are defined as the point midway between the 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 h and B above, if changes to the 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 cbtained 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 J
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 withir five miles of the plant site. The Houston County, Alabama, livu- .3ck agent and the Early County, Georgia, extension agent werv evatacted 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 Page 1 of 4
FNP-0-STP-799 [
RTYPE G8.05 !
III. RESULTS A. NEAREST RESIDENT LOCATIONS 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 1994 surveys revealed one change from the 1993 surveys. The residence identified in the 1993 surveys as nearest the plant site in sector eleven was found unoccepied during the 1994 surveys. The 1994 surveys identified a house approximately 700 feet north of the 1993 location and the same linear distance from the plant site as the nearest occupied residence in sector eleven. The location of the controlling receptor continues to be in the southwest sector (sector 10) at 1.2 miles, as indicated in ODCM Table 3.7. l I
B. MILK ANIHAL SURVEY ;
Mr. Mickey Fourakers, Early County, Georgia, Extension Agent ;
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. ield surveys conducted along Georgia r
Highways 62, 370, 273 and 363, and Early County Roads 26, 103, 28, 270, 81 and 248 produced no evidence of milk animals.
Mr. Ricky Hudson, Houston County, Alabama Livestock Agent, 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 site, in the vicinity of FNP: ,
Ray Lewis Dairy Rt. 1 Ashford, AL 14 miles west southwest of the plant site; Ray Lewis, owner Ivey Dairy (Green Valley Farms)
Webb, AL 12 miles west of the plant site; Bruce Ivey, owner Robert Weir and Sons Dairy Seminole County, GA 14 miles south southeast of the plant site; Robert Weir, owner Attachment 1 Page 2 of 4
- - . . . ~ . .. - -. .-.
I FWP-0-STP-799 RTYPE G8.05 f
. 1 I
Since milk animals have not been located w'ithin five miles of. I the plant site, no milk indicator sample is collected. In February, 1994, the milk control sample location was changed to ;
Ivey Dairy (Green Valley Farms). .,
As reported in 1993 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. Mrs. Dean was ;
interviewed and the location of his residence and the presence ;
of the goats confirmed. j IV.- CONCLUSIONS A. There is no occupied residence in any sector closer to the plant !
site than currently assessed by the ODcM.
l B. In sector 11, although the location of the resident nearest the ;
plant site has changed, the linear distance from the plant site to l l
-the nearest resident is the same as that reported in 1993. !
l I I C. There are currently no milk animals within five miles of the plant ,
site.
D. No changes to ODCM are required. j E. No change to the milk sampling program is necessary. !
i 5
i l i t
i i
i i
l l
Attachment 1 Page 3 of 4
4
- FNP-0-STP-799 RTYPE G8.05 TABLE 1 OF ATTACllMENT 1 JOSEPH M. FARLEY NUCLEAR PLANT LAND USE CENSUS AND MILK ANIMAL SURVEY JUNE 17,1994 Distance In Miles To Nearest Resident Milk Animal Radial Sectors 22.5 Degrees Each 1993 1994 1993 1994 Reason For Change Indhiduals Inteniewed North Northeast (01) 2.5 2.5 >5 >5 N/A *Mr. C. H. Freeman Mrs. Art Freeman Northeast (02) 2.4 2.4 >5 >5 N/A *Mr. Judson Freeman East Nonheast (03) 2.4 2.4 >5 >5 N/A *Mrs. Jim Donaldson East (04) 2.8 2.8 >5 >5 N/A *Mrs. Booker T. Spivey Mrs. Anna Grier
- Mrs. Mary Esther Allums l East Southeast (05) 3.0 3.0 >5 >5 N/A Southeast (06) 3.4 3.4 >5 >5 N/A Mr. David Smith Note 3 l
l South Southeast (07) >5 >5 >5 >5 N/A Note 2 i
i l
South (08) 4.3 4.3 >5 >5 N/A *Mrs. Francha Brown )
i Mrs. Thomas Dean South Southwest (09) 2.9 2.9 >5 >5 N/A Ms. Lula Mac McGriff Note 3 l
Southwest (10) 1.2 1.2 >5 >5 N/A *Mr. Maurice Gilbert West Southwest (11) 2.4 2.4 >5 >$ Note 1 Mni. Terry Martin Note 3 l West (12) 1.3 1.3 >5 >5 N/A *Mr. Alfred Respress West Northwest (13) 2.1 2.1 >5 >5 N/A *Mrs. William C aulsen Northwest (14) 1.5 1.5 >5 >5 N/A *Mrs. Amanda Ryals North Northwest (15) 3.3 3.3 >$ >5 N/A *Mrs. Tnomas Steely North (16) 2.6 2.6 >5 >5 N/A *Mr. Tony Knighton
' Nearest Resident in Sector l
Note 1: New location. 1994 location unoccupied.
- Note 2
- No resident within 5 miles in sector 7. Georgia Pacific Paper Co. (GPPC) located in sector 7,3.9 miles from plant l site. Air sampler, surface water sampler, TLD located on GPPC plant site.
i Note 3: Unable to contact nearest resident in this sect 7. Personal observation of residence location and inteniews with
! neighbors or other residents indicate no milk animals present.
Attachment 1 Page 4 of 4 l
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