ML20210C838
| ML20210C838 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1986 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NT-87-0176, NT-87-176, NUDOCS 8705060336 | |
| Download: ML20210C838 (47) | |
Text
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ALABAMA POWER COMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOIOGICAL JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO. 1 LICENSE NO. NPF-2 AND UNIT NO. 2 LICENSE NO. NPF-8 PERIOD ENDING DECEMBER 31, 1986 o
Annual ENV Report /2 B705060336 861231 DR ADOCK O 38
[
AttiUAL ENVIRONMENIAL OPERATING REPORT PART B: RADIOIOGICAL TABLE OF CCNI1!NIS I
Section Title Page I
Introduction 1
II Radiological Sanpling and Analysis 2
III Results and Discussion 5
IV Land Use Census and Interlaboratory Comparison 10 Program V
Data Trends and Conclusions 10 I
l i
RADIOIOGICAL ENVIR0tatENTAL OPERATING REPORT LIST OF FIGURES Figure Title Page 3.12-1 Indicator Sampling Locations for Airborne 11 Environmental Radioactivity at the Farley Nuclear Plant.
3.12-2 Connunity (Indicator II) Sampling Locations for 12 Airborne Radioactivity in the Farley Nuclear Plant Area.
3.12-3 Control Sampling Locations for Airborne 13 Environmental Radioactivity in the Farley Nuclear Plant Area.
3.12-4 Indicator and control Sampling Locations for 14 Waterborne Environmental Radioactivity in the Farley Nuclear Plant Area.
11
RADIOIOGICAL ENVIROME!NTAL OPERATING REPORT 4
LIST OF TABLES Table Title Page 1
Scope of Operational Radiological Environmental 15 Monitoring Program at the Farley Nuclear Plant During 1986 2
Outline of Operational Radiological Environmental 16 Monitoring Program for Farley Nuclear Plant During 1986 3
Detection Capabilities for Environmental Sample 21 Analysis for Farley Nuclear Plant 4
Reporting Levels for Radioactivity Concentrations 23 in Environmental Samples 5
Sampling and Analysis Deviations During 1986 24 F010-1 Airborne: Particulates and Iodine - Operational 28 Radioactivity Summary Fol0-2 External Radiation - Operational Radioactivity 29 Summary F010-3 Milk - Operational Radioactivity Summary 30 F010-4 Vegetation: Forage, Vegetables and Fruits -
31 Operational Radioactivity Sumary F010-5 Soil - Operational Radioactivity Summary 33 F010-6 Waterborne: Surface and Ground Water - Operational 34 Radioactivity Sumary F010-7 Sediment: River - Operational Radioactivity 37 Summary F010-8 Fish: River - Operational Radioactivity Summary 38 111
RADIOIDGICAL ENVIRONMI!NTAL OPERATING REPORT LIST OF ATTACIDENTS Attachment Title Page 1
Land Use Survey for Radiological Environmental 40 Monitoring Program, Joseph M. Farley Nuclear Plant, July 23-30, 1986 iv
OPERATIONAL RADIOf4GICAL DNIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 I.
Introduction
%e Joseph M. rarley Nuclear Plant, owned and operated by Alabama Power Company (APCo), located in Houston County, Alabama is approximately fifteen miles east of Dothan, Alabama on the west j
bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a rated power output of 860 megawatts electrical (MNe) achieved initial criticality on August 9, 1977. We unit was declared "comercial" on December 1,1977. Unit No. 2, also a 860 PMe Westinghouse PWR, achieved initial criticality on May 8, 1981 and was declared "comercial" on July 30, 1981.
During 1986, Unit No. I was shut down for a scheduled refueling outage from October 3 through December 2.
Unit No. 2 was shut down for a scheduled refueling outage from April 6 through May 27.
%e sample collection and analysis schedule for the operational off-site radiological environmental monitoring program implemented in May 1977 and as modified on July 1, 1980 with the addition of 14 TLD stations was continued during 1986 for both Units No. 1 and 2.
The program was further modified effective April 1982 to reflect Amendment No. 26 to the Unit 1 Technical Specifications issued March 1, 1982. h is program was designed to monitor any radioactivity contribution to the environs from the plant through either the airborne or waterborne pathways. %e type of samples monitored, and number and type of sampling stations are shown in l
Table 1. Indicator sanpling stations are located, where practical, i
at locations where detection of the radiological effects of the l
plant's operation is thought to be most likely, where the sanples collected should provide a significant indication of potential dose to man, and where an adequate comparison of predicted radiological levels might be made with measured levels. H e control stations are placed at locations where radiological levels are not expected to be significantly influenced by plant operation, i.e., at background locations. For some airborne radioactivity samples, comunity stations are located at the principal population centers between the indicator and the control stations (3-8 miles). These in normal operation could be used, if desired, as additional control stations, and alternatively, as indicator stations in the nearest population centers in the event of a major airborne release of radioactivity from the plant.
1
II.
Radiological Sampling and Analysis A detailed outline of the operational radiological sampling and analysis activities for the environmental program to meet the requirements of the Unit 1 and 2 Technical Specifications is given in Tables 1 and 2.
For each parameter only one sample was collected and one analysis performed to meet the specifications for both Units No. 1 and 2.
he samples were collected by APCo's technical staff except for the in situ high purity germanium (HP(Ge)) gasuna-ray spectroscopy measurements of soil. %e latter was made by staff members of the University of Georgia (UGA), Center for Applied Isotope Studies. All sample analyses were contracted to UGA. %e minimum detectable concentration (MDC), specified for the various samples and their respective analyses are given in Table 3.
he. reporting levels for radioactivity concentrations in environmental samples are provided in Table 4.
Sampling difficulties and/or deviations from the sampling schedule during 1986 are listed in Table 5.
A.
Airborne Particulates and Iodine All airborne particulate and iodine monitoring stations shown in Figure 3.12-1 through 3.12-3 were equipped with Roots vacuum punps wp/ min (1.5ft,/ min).ich operated continuously at a flow rate of approximately 0.0 m
The particulates were collected on Gelman Metricel 47m (or equivalent) filters.
In series with, but downstream of the particulate filters, F&J 50 m (or equivalent) activated charcoal cartridges were used for collection of iodine.
We Roots system has the sample collector mounted outside of the cabinet horizontally to the ground with a Singer gas meter measuring the cumulative air flow. The gas meters were calibrated against a certified flow meter. Both the 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. We filters from each station, composited at the end of each quarter, were analyzed for gama 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 3.12-1 through 3.12-3 have the capability of monitoring airborne iodine. Weekly routine samples were analyzed for I-131 by UGA using a Canberra 1024 channel MCA and two 1" x 3" NaI detectors and matched photomultiplier tubes.
2
B.
External Radiation For the continuous measurement of environmental gama radiation, natural Lithium Fluoride (Lir) (TLD-700) chips, manufactured 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,andwhichhadalp).massattenuationfor radiation (approximately 50mg/cm 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 external radiation monitoring station, shown in Figures 3.12-1, 3.12-2, and 3.12-3, 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 background sample location remained as indicated on Figure 3.12-3.
All milk samples, collected bi-weekly, were analyzed by UGA for I-131 and gamma emitters. As a preservative for shipment, 1 ml of 25 weight percent merthiolate ( himerasol) solution was added to each one gallon sample. We 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-gama 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.
A one liter quantity of each sample was placed in a marinelli beaker and then 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 Monthly, forage was collected from indicator grass plots located near the air monitoring stations at the plant site perimeter in sectors 7 (SSE) and 16 (N), or alternate plots if needed, and from a control grass plot located near the air monitoring station in Dothan. 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 channel computer-based MCA.
I 3
E.
Soil Annual in situ gamma-ray spectroscopy measurements were made by UGA using a~ID percent relative efficiency high purity germanium detector and gama-ray spectroscopy system specially designed for field use. Measurements were taken at the seven indicator locations and at the five community and control (background) locations listed in Table 2.
A 1024 channel Canberra MCA interfaced to a Hewlett-Packard 9825A calculator was used for data storage and analysis.
F.
Surface Water: River Water Samples of water from the Chattahoochee River, above and below the plant site at the locations shown in Figure 3.12-4 were collected on a semi-continuous basis with Instrumentation Specialties Company (ISCO) samplers. Monthly composites were sent to UGA for radioactivity analysis. N o liter aliquots from each monthly composite were placed in trays lined with plastic film and evaporated to dryness at 100'C. The residue and plastic film was folded to fit a petri-dish and analyzed for gamma emitters using a 15 percent relative efficiency Ge(Li) low background detector and a Canberra 4096 channel computer-based MCA.
At the end of each quarter, for each sampling location, the balance of the three monthly composites were combined to give a quarterly composite sample. Approximately 50 m1 from each quarterly composite sample was distilled and a 25 ml aliquot taken for tritium analysis using a large volume (100 ml) low background liquid scintillation counter.
G.
Groundwater: Well Water In the Farley Plant area there are no true indicator sources of groundwater. A well which serves Great Southern 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 on a quarterly basis and designated 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 on a quarterly basis and designated 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 ml samples were analyzed using a large volume (100 ml) 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 and film was folded to fit a petri dish and analyzed for gamma emitters using a 15 percent relative efficiency Ge(Li) detector and a Canberra 4096 channel computer-based liCA.
4
H.
Fish: River Semi-annually, two types of fish, game and bottom feeding, were collected from the Chattahoochee River at the locations shown in Figure 3.12-4, and sent to UGA for gamma-ray spectroscopy a-analysis. Both semi-annual fish samples sent to UGA consisted of fish fillets that had been split with Alabama Bureau of Radiological Health. 'Ihese fish samples were coarsely chopped at UGA and were analyzed for gama emitters using a 15 percent relative efficiency low background Ge(Li) detector and 4096 channel Canberra computer-based MCA.
I.
Sediment: River Semi-annually, sediment samples were collected from the Chattahoochee River at the locations shown in Figure 3.12-4.
Approximately one kg of sample was sent to UGA where it was dried, mixed, and analyzed for gama emitters using a 15 percent relative efficiency low background Ge(Li) detector and a Canberra 4096 channel computer-based MCA.
III. Results and Discussion During the operational period, no known atmospheric, nuclear tests were conducted.
Identifiable radioactivity effects from the last test conducted by the Peoples Republic of China on October 16, 1980, were minimally existent during 1986.
Special sampling was performed during this operational period as a result of the Chernobyl Nuclear Power Plant accident in the U.S.S.R. which was announced to the public world-wide on April 29, 1986. This additional sampling was performed in response to United States Nuclear Regulatory Comission I. E. Information Notice No. 86-32 and in conjunction with the United States Environmental Protection Agency (USEPA) Eastern Environmental Radiation Facility, Montgomery, Alabama. Special samples of air particulates and iodine, rain water, milk, forage, and soil were collected during the period from May 5, 1986 through June 2, 1986. Evidence of increased activity in these samples was observed on May 12, 1986, and reached a peak between May 13 - May 15, 1986. The effects of this release of airborne radioactivity were evidenced in the environs of Farley Nuclear Plant for approximately five months.
The data for samples are presented in Sections III.A through H.
The samples obtained during this period of time were analyzed by the USEPA, Montgomery, Alabama, and the Center for Applied Isotopes Studies, University of Georgia.
5
I For measurements involving radioactivity concentrations by volume or mass the designation " minimum detectable concentration" (MDC) is defined in Table 3.
For measurements involving a quantity of radioactivity or radiation that is independent of the sample volume or mass the designation
" lower limit of detection" (LLD) is used to denote the limit of detection applicable at the 95 percent confidence level. %e LLD is defined as "the smallest amount of sample activity that will yield a net count for which there is confidence at a predetermined level that activity is present". Its application is limited to measurement systems which denote a limiting detection capability I
without respect to the size of sample and/or radiochemical yield and to measurments which by their nature do not involve concen-trations, e.g. radiation dose rates (mrad /hr., mrad /qtr., etc.)
A.
Airborne Particulates and Iodine The results of the radioactivity analyses of airborne particulate filters and iodine charcoal cartridges are shown in Table E010-1. These analyses include special samples obtained primarily during the month of May, 1986, due to the Chernobyl Nuclear Power Plant accident in Russia. In addition to routine sampling, special air samples of particualte filters and iodine charcoal cartridges were obtained from sector 1218 located in Dothan, Alabama, every 1 to 2 days from May 12 through May 30, 1986. The air monitoring station in sector 1218 was temporarily deleted as a " routine" sample point so that this station could be designated as the "Chernobyl" monitoring station. %ese samples were analyzed by Center for Applied Isotopic Studies, University of Georgia.
An air particulate filter was changed daily at the air monitoring station in sector 0901, Farley Nuclear Plant site, and analyzed by USEPA, Montgomery, Alabama. The first indications of increased airborne activity was evidenced on May12,19p6. This activity reached a peak on May 13 with of Cs-134, and 0.05) pciAn'0.140 pCi/m, of I-131, 0.043 pCiAn 3
1.53 pCi/m of gross beta, of Cs-137. Airborne activity began declining on 1:ay 16 and continued through June 5, at which time identifiable airborne radioactivity from this accidental release was not observed in routine air sampling at Farley Nuclear Plant and the surrounding area.
6
. We gross beta and gasuna-ray spectroscopy data for the air particulate filter composites and iodine cartridges showed a slight increase of beta gansna, Cs-134,.Cs-137, and I-131 in indicator and control samples as compared to 1985. However, the comununity and control values were approximately the same or in some instances higher than indicator values for all parameters. It is presumed that this incretse in activity is attributable to the Chernobyl release.
B.
External Radiation
%e results of the external radiation measurements using.TLD packets, each containing four Lir chips, are shown in Table ro10-2. As found during the preoperational measurement period and during 1985, the data reflects the differences in site specific soil radioactivity. %e exposures recorded by annual TLDs in 1986 were lower than that observed in 1985 and duriag the preoperational period. Exposures recorded by quarterly TLDs in 1986 were either less than or equal to that recorded in 1985, however, they were slightly higher than that observed during the preoperational period. Also evident in 1986 as in previous years, the exposure recorded by annual TLDs were less than the sum of the exposure from the four.
quarterly TLDs.
1 C.
Milk We results from the radioactivity analyses of milk are shown in Table E010-3. Milk from the Silcox Dairy was sampled.
Except for special milk samples obtained in May 1986, only naturally occurring radioactive isotopes were detected for all analyses. Special milk samples were taken May 9 through May 19 in response to the Chernobyl accident. We highest concentration of I-131 in all special milk samples obtained was 12.40 pCi/1. The activity of I-131 decreased to 2.13 pCi/l in the June 2 routine sample. We June 16 sample contained 0.53 pci/l of I-131, and returned to non-detectable levels by June 30.
In addition to the detection of I-131, Cs-137, and La-140 were also observed in milk samples during 1986 whereas no manmade activity was observed in milk in 1985. The observation of manmade activity was concurrent with the elevated activities noted following the Chernobyl release.
7
D.
Vegetation Forage was the only vegetation sampled during this operational period. %e radioactivity analysis results are shown in Table F010-4. Forage, as during the preoperational period, continued to be a very effective and sensitive indicator of airborne radioactivity. %is fact was further substantiated by the indication of radioactivity in three additional forage sanples taken May 20 through May 22 following the Chernobyl accident.
I-131 was detected in all three special samples with the greatest amount, 1000 pCi/kg, obtained May 21.
I-131 was also indicated in the routine sample taken in June in a decreased amount of 240 pCi/kg and was non-detectable in the July sample. Cs-134 and Cs-137 were also noted in all three samples with 118 pCi/kg and 224 pCi/kg, respectively in the May 21 sample. In the. routine June sample, Cs-124 and Cs-137 were found in increased amounts of 184 pCi/kg and 282 pCi/kg, respectively, and was also indicated in decreased quantities in the July sample. By August, Cs-134 was below MDC whereas Cs-137 remained detectable until October.
%e average I-131, Cs-134, and Cs-137 quantities were higher in 1986 than in 1985 as a result of the effects of the Chernobyl accident.
Indicator I-131 and Cs-137 values were greater than the control values, however, the indicator values for Cs-134 were less than controls. %e appearance of manmade radioactivity in forage samples coincided with the occurrence of and may therefore be attributed to the Chernobyl accident.
E.
Soil he results of the in situ HP(Ge) gansna-ray spectroscopy analysis of soil duFing this operational period are shown in Table fol0-5. %e only man-made radioactivity found in all measurements was Cs-137. During the preoperational period, the fission products Zr-95, Nb-95 and Cs-134 were seen at most of the locations in addition to Cs-137. The 1986 levels of Cs-137 found at indicator locations were not significantly different from control locations. The 1986 levels of Cs-137 were approximately the same as the 1985 period and lower than the preoperational period.
F.
Waterborne: Surface and Ground Water h e results of radioactivity analysis of surface and ground water are shown in Table FO10-6. Traces of Cs-134 and Cs-137 were found in river water control and indicator samples.
The indicator values for both Cs-134 and Cs-137 were lower than 3
the control values. 'Ihese cesium values were consistent with those observed in 1985 and lower than the values observed during the preoperational period.
'Ihe average surface water indicator tritium level was higher than the control, higher than that observed in 1985 and higher than that observed during the preoperational period. It should be noted also that the average control tritium value for 1986 was higher than that observed in 1985, and in all previous operational and preoperational periods. 'Ihe actual FNP tritium contribution to the river (indicator - control) was lower than that observed in 1985, 1983, 1982 and approximately the same as 1981 and 1984.
h tritium analyses of all ground water samples, indicator and control, were less than the MDC.
Rain water was collected during May, 1986, to monitor radioactivity from Chernobyl. Seven samples were collected from sectors 0501, 0701, 1101, and 1601 on the Farley Nuclear Plant site during the period of May 8 through June 2, 1986.
h May 12 sample revealed the first indication of radioactivity, 290 pCi/1 of I-131, and was the greatest concentration observed in all samples. I-131 activity returned to non-detectable levels by the May 28 sample.
G.
Sediment: River
'Ihe results of radioactivity analysis of sediment samples from the Chattahoochee River are shown in Table F010-7. W re were no manmade isotopes detected in any sediment sample.
H.
Fish: River The results of gamma-ray spectroscopy analysis of the edible portions of fish taken from the Chattahoochee River are shown in Table 7010-8. Cs-137 was found at low levels in both the indicator and control samples of game and bottom feeding fish.
'Ihe indicator Cs-137 levels for both bottom and game fish were higher than control values. However, the 1986 average indicator Cs-137 value was found to be lower than 1985 data and lower than the preoperational data. Additionally, the control Cs-137 value was found to be lower than the 1985 data and lower than preoperational levels.
9
I i
IV.
Land Use Census and Interlaboratory Comparison Program A.
Land Use Census he results of the July, 1986, Land Use Census are given in to this report.
.B.
Interlaboratory Comparison Program During 1986, the University of Georgia Center for Applied Isotope Studies (Ur.A) was a participant in the EPA Crosscheck Program. We UGA EPA Program code designation is EA.
Although Farley Nuclear Plant (ENP) also participates in the EPA crosscheck Program under code designation FU, none of the environmental analyses reported herein were performed by FNP.
V.
Data Trends and Conclusion A review of the 1986 environmental data indicated some changes in the parameters monitored when compared to previous years' data.
Increases of activity were observed in the analyses of airborne particulates and iodine, milk, forage, external radiation as measured by TLD, and tritium in river water.
The elevation of activity detected in airborne particulates and iodine, milk, and forage can be attributed to the effects of the Chernobyl accident as evidenced by the results of the special samples obtained following the accident. We elevated indicator and control river water tritium is presumed to be due to a lack of f a decreased river flow rate.
dilution by the river as a result p/sec; 1986 average river flow (1985 average f ver flow - 6027 ft i
rate - 5237 ft /sec). Since the actual picocurie / liter contribution to the river tritium concentrations by INP is less than or approximately the same as previous years, this constitutes no significant adverse trend. Therefore, data obtained during 1986 continued to demonstrate that there was no significant adverse impact on the environs surrounding Farley Nuclear Plant as a result of its operation.
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FISH AND SEDIMENT GROUND WATER FIGURE 3.12-4 INDICATOR AND CONTROL SAMPLING LOCATIONS FOR WATERBORNE ENVIRONMENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.
14
TABLE 1 SCOPE OF OPERATIONAL RADIOIDGICAL DNIRONMENTAL MONI'IORING PROGRAM AT DIE FARLEY NUCLEAR PLANT DURING 1986 Principle Type of Number of Sampling Stations Pathway Samples Indicator Community control Airborne Particulates 3
3 3
Airborne Iodine 3
1 3
External Radiation 16 18 4
Airborne Milk 1
Forage
- 2 1
b Soil 7
3 2
1 River Water 1
Groundwater 1
1 Waterborne 1
River Fish 1
1 River Sediment 1
- Forage sampling in lieu of vegetable and fruit. Vegetable and fruit sampling discontinued witF implementation of Unit 1 Technical Specification Upgrade (Amendment No. 26, issued March 1, 1982).
" Annual In Situ Gamma Measurements continued by choice of licensee during 1986.
15 Annual DN Report /3
TABLE 2 OUILINE OF OPERATIMAL RADIOIOGICAL E2NIRONMDTIAL MCNITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1986 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 as required by dust loading, but at least Analyze for gross beta once per 7 days.
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 (WSE-0.9) is >10 times the yearly River Intake Structure (ESE-0.8) mean of control samples.
Perform gamma isotopic analysis on composite Comunity Stations:
(by location) sample at least once per 92 days.
Columbia, AL. (N-5)
Great Southern 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 Analyze at least once Indicator Stations:
collection performed once per 7 days for I-131.
per 7 days.
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Plant Entrance - (WSW)-0.9 River Intake Structure (ESE-0.8)
Annual ENV Report /4 Page 1 of 5
TABLE 2 (con'd)
Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis 4
Community Stations:
I Great Southern Paper Co. (SSE-3) i l
Control Stations:
i Blakely, GA. (NE-15)
Dothan, AL. (W-18)
Neals Landing, FL. (SSE-18)
- I Soil Annual in situ Ge(Li) ganana-ray nanuna Isotopic
^
spectroscopy measurements.
Annually i
Indicator Stations:
Seven Stations along the plant perimeter (N-0.8, NE-1.0, E-0.8, t
SSE-l.0, SSW-1.0, WSW-0.9, and tam-0.8)
Community Stations:
4 j
Columbia, AL. (N-5) i Great Southern Paper Co.(SSE-3) j Ashford, AL. (WSW-8)
I Control Stations:
i j
Blakely, Ga. (NE-15)
Dothan, Al. (W-18) 4 I
DIRECT RADIATION At least once per 92 days nanuna dose Readout at least once per 92 days i
i 1
j Annual ENV Report /4 Page 2 of 5 i
TABLE 2 (con'd)
Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis Indicator I Staticns:
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, SSN-1.0, SW-0.9, WSW-0.9, W-0.8, WrM-0.8, IE-1.1, and NNW-0.9).
Indicator II (Community) Stations:
Eighteen stations, one in each meteorological sector at a distance of 4-5 miles (NNE-4, NE-4, ENE-4, E-5, ESE-5, SE-5, SSE-3, S-5, SSN-4, SW-5, WSW-4, W-4, WtM-4, IM-4, NNW-4, and N-5).
Additional stations located at WSN-8 and SW-1.2.
E Control Stations:
Blakely, Ga. (NE-15)
Neals Landing, Fl. (SSE-18)
Dothan, AL. (W-18)
Dothan, AL. (W-15)
WATERBORNE Surface Water Composite taken with propor-Monthly gansna 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 5 31 days, at least once per 92 days.
Great Southern Paper Co.,
(3 miles below plant discharge, River Mile-40)
Annual ENV Report /4 Page 3 of 5
TABLE 2 (con'd)
Types of Samples and Sampling Type and Frequency Sampling Incations and of (Distances Given in Miles)
Collection Frequency Analysis Control Station:
Upstream of Andrews Lock and Dam
(~3 miles above plant intake, River Mile 47)
Ground Water Grab sample taken at least Ganna isotopic and tritium once per 92 days, analyses of each sample Indicator Station:
once per quarter.
Great Souther Paper Co., Well (SSE-4)
Control Station:
Whatley Residence, Well (SW-1.2)
River Sediment Grab sample taken at least Ganna 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)
Annual ENV Report /4 Page 4 of 5
TRBLE 2 (con'd)
Types of samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis INGESTION Milk control Station:
At least once per 16 days nannna isotopic and I-131 Silcox Dairy, analysis of each bi-weekly Ashford, AL. (WSW-10) sample when animals are on pasture.
Fish One sample of the following nannna isotopic analysis species at least once per 184 on edible portions once Indicator Station:
days: 1.
Game Fish per 184 days.
2.
Bottom Feeding Fish Dcwnstream 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)
Forage Grab sample cut from green nannna isotopic analysis forage at least once per 31 which includes I-131
- days, analyses of each monthly Indicator Station:
sample.
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Control Station:
Dothan, AL. (W-18)
Annual EIN Report /4 Page 5 of 5
TABLE 3 DETECTICN CAPABILITIES FOR EINIRCNtENTAL SAMPLE ANALYSIS EDR FARLEY NUCLEAR PIAYr VALUES FOR 'IEE MINIMUM DETECTABLE CCNCENIRATICN(MDC)*
- D Airborne Particulate Water or Gas Fish Milk Food Products Sediment Analysis (pCi/1)
(pCi/m,)
(pCi/kg. wet)
{pCi/1)
(pCi/kg. wet)
(pCi/kg. dry)
Gross beta 4
1 x 10'*
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 g
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 ic>-95 15 NA NA NA NA NA I-131 1*
7 x 10~*
NA NA NA NA Cs-134 15 5 x 10~*
130 15 60 150 Cs-137 18 6 x 10~*
150 18 60 180 Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA Page 1 of 2
TABLE 3 (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):
-MDC =
4.66 S, E
V 2.22 Y
exp (-Mt)
Where:
MDC is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume).
S is the standard deviation of the background counting rate or oI 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 sanple size (in units of mass or volume).
2.22 is the number of transformations per minute per picocurie.
Y is the fractional radiochemical yield (when applicable).
A 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).
The value of S, used in the calculation of the MDC for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the MDC for a radionuclide determined by gama-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 Radiciodine were obtained using blank background (A Priori), whereas, for gama-ray spectroscopy actual sample backgrounds were used (A Posteriori).
'MDC for drinking water.
22 Page 2 of 2
TABLE 4' REPORTING LEVELS FOR RADIOACTIVITY CONCEffIRATINS IN DNIlO@ ENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gap Fish Milk Food Products Analysis (pCi/1)
(pCi/m )
(pCi/kg. wet)
(pCi/1)
(pCi/kg. wet)
H-3 2 x 10
NA NA NA NA Mn-54 1 x 10 NA 3 x 10' NA NA 3
Fe-59 4 x 10 NA 1 x 10' NA NA 2
Co-58 1 x 10' NA 3 x 10' NA NA Co-60 3 x 10 NA 1 x 10' NA NA 2
2n-65 3 x 10 NA 2 x 10' NA NA 2
g 2
Zr/Nb-95 4 x 10 NA NA NA NA I-131 2
0.9 NA 3
1 x 10' Cs-134 30 10 1 x 10' 60 1 x 10' 3
Cs-137 50 20 2 x 10' 70 2'x 10 Ba/La-140 2 x 10 NA NA 3 x 10*
NA 2
- For drinking water samples.
Annual ENV Report /4(7)
TABLE 5 SAMPLING AND ANALYSIS DEVIATIONS DURING 1986 Component Time Period Reason for Deviation /Comuments i
Air Monitoring Station 0701 1-1-86 to 12-31-86 Station down due to no power source.
Lightining destroyed underground cable.
PCR submitted.
Indicator water sampler 12-2-86 Malfunction in water sampler control box resulted in lost sample. Control box replaced.
8-Day Sample Period for air 1-16-86 Work schedule.
particulate and iodine samples 1
Air Monitoring Station 1601 1-22-86 Station turned off 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to replace i
fan belt.
Air; monitoring station 1218 1-24-86 to 2-6-86 No sample and low flow due to problems with sample motor. Motor replaced 2-4-86.
6-Day Sample Period for air 1-24-86 to 1-30-86 Work schedule.
particulate and iodine samples Air monitoring station 1108 2-6-86 to 2-13-86 Low flow rate due to faulty pump.
Flow j
rate increased. Maintenance performed on punp.
~
Air monitoring station 0718 2-13-86 to 2-20-86 Low flow due to blown fuse.. Fuse replaced.
Air monitoring station 1218 2-20-86 to 2-26-86 Low flow rate due to loose fan belt.
Fan belt replaced.
6-Day sample period for air 2-20-86 to 2-26-86 Work schedule particulate and iodine
]
Oamples 8-Day sample period for air 2-26-86 to 3-6-86 Work schedule particulate and iodine samples Air monitoring station 1101 3-20-86 to 3-27-86 Low flow rate due to faulty filter 1
paper. Filter paper replaced.
Air monitoring station 1601 3-27-86 to 4-3-86 Low flow rate due to clogged filter.
and 0215 Filter changed.
Air monitoring station 0703 4-3-86 to 4-10-86 Power turned off for few hours during sample period for maintenance. Power restored.
Annual ENV Report /8 24
Component Time Period Reason for Deviation / Comments i
Air monitoring station 0501 4-10-86 to 5-1-86 No samples due to broken fan belt. Fan belt replaced.
Air monitoring station 1218 4-10-86 to 5-8-86 Station down due to broken fan belt.
Fan belt replaced.
Air monitoring stations 4-24-86 to 5-1-86 Low flow due to mechanical stress.
1605 and 1108 Flow rate increased.
Air monitoring station 1218 May 1986 Station removed from routine program in order to monitor Chernobyl release.
Forage, rain water, soil May 1986 Special samples collected to monitor Chernobyl release.
Air monitoring stations 5-8-86 to 5-15-86 Low flow rates due'to mechanical 0501 and 1605 stress. Increased flow.
Air monitoring station 1108 5-22-86 to 5-29-86 Low flow rate due to mechanical stress. Increased flow.
Air monitoring stations 6-5-86 to 6-12-86 Charcoal fell out of charcoal 0215 and 1218 cartridge due to damaged retaining paper breaking. Vendor notified.
Air monitoring station 1101 6-21-86 to 6-24-86 Station was down due to blown fuse,.
Fuse replaced.
Air monitoring station 1601 5-23-86 to 5-24-86 Station down due to construction turning power off for maintenance.
Power restored.
Air monitoring station 1101 7-3-86 to 7-10-86 Low flow due to blown fuse.
Fuse replaced. Work request written to check voltage.
Air monitoring station 1101 7-10-66 to 7-17-86 Low flow due to blown fuse.
Fuse replaced.
Air monitoring station 0718 7-17-86 to 7-24-86 Low flow due to broken fan belt.
Fan belt replaced.
Air monitoring station 0703 7-10-86 to 7-24-86 No sample due to damaged pump.
Pump replaced.
Air monitoring station 0215 7-10-86 to 7-24-86 No samples due to no power. Breaker box replaced.
I Annual ENV Report /8 25
Component Time Period Reason for Deviation /C m nts Air monitoring station 0215 9-25-86 to 12-11-86 Station down due to no power. Breaker box replaced.
Air monitoring station 0501 10-23-86 to 11-13-86 No sample and low flow due to broken
]
fan belt. Fan belt replaced.
J Air monitoring station 1101 11-6-86 to 11-13-86 Low flow due to breaker being opened.
Breaker closed.
Forage at 0501 January 1986 Substituted for 1601 forage plot.
Forage at 0501 February 1986 Substituted for 1601 forage plot.
Forage at 1601, 1218, 0701 May 1986 Low weight due to no rainfall.
Forage at 1601 August 1986 Low weight due to no rainfall.
Forage at 1601 October 1986 Low weight due to no rainfall.
Forage at 1601 December 1986 Low weight.
TLD RC-0204 2nd Qtr 1986 Destroyed by vandals.
TLD RC-1304 2nd Qtr 1986 Destroyed by vandals.
TLD RC-0204 4th Qtr 1986 Destroyed by vandals.
TLD RC-0204 Annual 1986 Destroyed by vandals.
TLD RC-1304 Annual 1986 Destroyed by vandals.
Totalizer at station 1605 6-19-86 to 12-13-86 As found % error was 11.3% where 10% is max tolerance. Totalizer replaced, nilk Cs-134 and Ba-140 9-8-86 MDC not achieved. Corrective action completed.
Ground water background 3rd Qtr 1986 I-131 MDC not achieved. Revision to
+
and indicator I-131 blanket purchase order with UGa-CAIS submitted to correct deficiency.
Milk Cs-134 and Ba-140 10-6-86 MDC not achieved. Old counting schedule inadvertently used by UGa-CAIS. CAIS procedure updated.
i 1
l l
1
/
l Annual ENV Report /8 26 i
i
Component Time Period Reason for Deviation /Comunents Ground Water background 4th Qtr 1986 I-131 MDC not achieved. Revision to and indicator I-131 blanket purchase order not received by CAIS in time for fourth quarter analysis. CAIS to implement corrected methodology first quarter 1987.
Back-up Met Tower 6-30 2 hrs.
Loss of data due to loss of ambient temperature electrical power. Power restored.
Primary Met Tower 9-23-86 at 0825 to Loss of data for wind speed and 9-29-86 at 1200 direction at 150 ft, AT 35ft - 200ft (primary and secondary), solar, rain, bivane verticle and horizontal, and dew point sensors due to replacement of primary met tower sensors.
Back-up Met Tower 9-21-86 at 1345 Loss of data for ambient temperature to 9-21-86 at 1904 due to tripped breaker. Breaker reset.
Back-up Met Tower 9-23-86 to 9-29-86 Loss of data for bivane vertical due to a bad IC chip. IC chip replaced.
Annual DN Repott/8 27
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TAPtf f040-2 EITIkNAL RADI ATION. OPERAfl0NAL R ADIO?.CT!vlTV
SUMMARY
JOSEPH M. F ARLEY NUCLEAR PLANT LICE 45E N05. hPF.2 Am hrF 8. HOUSTON COUNTY, ALABAMA January. December,1986 (a) l ALL INDICATOR IPOICATOR LOCATION WITH HIGHEST ANMJAL MEAN COMM1N IT Y CONTROL MQluM CR TYPE AND LOC AT IONS LOCATIONS LOCATIONS PATHWAT SAMPt[D TOTAL NUPEER OF h0M!NAL ME AN (f)(c)
MAME l MEAN (f)(c)
ME AN (f)(c)
MEAN (f)
(UNIT OF ME ASUREMENT)
ANAlf5ES PERFORMED MDC(b)
RANCE(c)
DISTANCE AND DIRECTION l RANCE(C)
RANGE (c)
RANGI(C)(c)
=..........
TLD Duarterly Gross Garuma 149 10.0 17.8 (64/64)
East Perimeter 24.1 (4/4) 15.1 (69/69) 17.7 (16/16)
(NAD)
(13.1 - 26.6) 0.8 Miles - E (23.7 - 26.6)
(6.32 19.0)
(12.8 - 22.9)
TLD Annual Gross Capuna 35 10.0 55.7 (16/16)
East Perimeter E5.1 (1/1) 45.1 (15/15) 53.9 (4/4)
(MRAD)
(40.8 - 85.1) 1.0 Miles hE (38.0 51.8)
(45.6 - 61.8)
TLD. Annuayd Gross Ganna 36 10.0 71.2 (16/16)
East Perineter 98.7(1/l) 60.4 (16/16) 70.8 (4/4)
(PW AD)
(60.5 98.7) 0.H Miles. E (50.4 71.1)
(61.4 74.1) 3 (a) No nonroutine anomalous measurements reported during the period.
(b) Laeer Limit of Detection as defined in HA5L.300, for LIF TLDs as achievable in practice.
(c) Mean and Range based on detectable measurements only. Fraction of detectable measurements at specified locations in parenthesis (f)
(d) Sum of four quarters for comparative purposes.
TABLE F010-3 MILE - OPERATIONAL RADIDACitvITY SunftARY J05fPH M. FANLEY NUCLEAR PLANT LICENSE N05. NPF-2 Ale NPF.8, HOUSTON COUNTY, ALA8AMA January - December, 1986(a) l l
ll ALL 110lCATOR IICICATOR LOCATION WITH HIGHEST ANNUAL Nf AN COMMJNITY CONTROL MtDluM OR TVPE AND LOCAi!ONS LOCATIONS LOCATIONS
=.- ---------
PAf thAf SAMPi f 0 TOTAL IGJMCf W Of NOMINAL ME AN (f)(c) hAMF NEAN (f)(c)
MfAN(f)(c)
EAN (f)(c)
(UNIT M MLA5uk! Min!)
ANALY5ES PENf0RMtD
- 0C(b)
RANGI(c)
DI51ANCE AND DIRECil0N RANGE (c)
R AIIGE(c)
RAIIGl(c)
__ _=......__
. - - = -
Malt Ca-e a Wc 26 (pct /I)
K-40 129.
1400. (26/26)
(1190. - 1710.).
1-131 21.0 30.0 (1/26) u CS-134 14.7
< M)C o
Cs-137 14.1 16.5 (2/26)
(15.0-18.0)84-140 54.7
< 10C La-140 8.60 H.50 (2/26)
(7.00 - 10.0)
Radioiodine 26 l-131 0.260 5.02 (3/26)
(0.530 - 12.4)
(4) W Enaruutine Anumalous Namuremente Reported During this Period.
(b) N an Mananna. Detestable Concentratios.m Calculated Per Table 3 of This Report.
(c) Nan and R4.ge 84=ed on Detec table Namurements only. Fraction of twtsctable N asurements at Specifled Location in Parenthesis (f).
TA8tt F010-4 WEGETATIUM: FORAGE, WEGETABLES AND FRUITS - OPERAil0NAL RAD 10Acilvliv SUMMaar JOSEPH M. FARLEY NUCLEAR PLANT LICENSE N05. NPF-2 AND NPF-8, HOUSTON COUNiv. ALABAMA January - December,1986 (a)
I ALL IN0!CATOR IN0lCATOR 10 Call 0N WiiH HIGHEST ANMJAL MEAN COMNINITY CONTROL MfoluM OR TYPE AIO LOCATIONS LOCAil0NS LOCATIONS
= -
PAIHWAT $AMPtfD TOTAL MneER OF NOMINAL MEAN (f)(c)
NAME NE AN (f](c)
M AN (f)(c)
MEAN ff)(c)
_- =---
(UNIT Of MEA 5UREMENT)
ANALY5ES PfRF0kMED feC(b)
RANGE (c)
Dl5fANCE A80 DIRECTION NANGE(c)
RANGE (c)
RANGElc3
_ __ __--=
_ __--------= =--__ _ _____ -----------
forage (d)
Ganna Spec 39 (Pct /k9 - Der)
Be-7 622.
5150. (26/27)
River Intake Structure 6490. (3/3) 3280. (11/12)
(1620. - 11800.)
0.8 Miles - E5E (e)
(5020. - 8360.)
(809. - 6920.)
K-40 645 15500. (27/27)
Ibrth Perimeter 30900. (1/l) 19200. (12/12)
(4760. - 30900.)
0.9 M1les - NNE (H230. - 39400.)
1-131 123.
657. (4/27)
East Pertneter(e) 1000. (1/1)
(240. - 1000.)
1.0 Miles - NE s)
Cs-134 69.6 115. (3/27)
North Perimeter 144. (1/9) 184.(1/12)
(82.0 - 144.)
0.8 Miles - N Cs-137 13.1 141. (12/27)
East Perimeter (e) 224. (1/3) 129. (2/12)
(56.0 - 282.)
I.0 Miles - NE (107. - 150.)
84 140 192.
1%. (1/12)
La-140 0.0 28.0 (1/12)
TI-208 72.4 95.7(11/27)
River intake Structure 134.(1/3)
(49.0 - 134.)
0.8 Miles - ESE (e) 89.5 (2/12)
(51.0 - 128.)84-212 959 1230. (1/27)
South Perimeter 1230. (1/11) 1.0 Miles - SSE Pb-242 103.
163. (R/27)
River Intake Structure 197. (1/3)
(109. - 366.)
0.8 Miles - ESE (e)
(a) No Noncoutine Measurements Reported During This Period.
(b) Nan Minimum Detectable Concentrations Calculated Per Table 3 of This Report.
(c) Mean and kange Based on Detectable Measurements only. Fraction of Detettable Measurements at Specified locations in Parenthesis (f).
(J) Mean Wet / Dry Ratio for 1956 was 1.%7.
tr) Nubt itute 14=.et ion Due to Unavali.abilit y of lorage at For. age Plot on South Perimeter and North Perimeter During Some Sample Periods.
Page 1 of 2
TABLE F01D-4 (Cont *d)
VICETATION: FORAGE. VIGETARLES AND FRUI 15 - OPERATIONAL RADIDACTIVITY
SUMMARY
JOSEPH M. FARLEV MJCLEAR PLANT L ICENSE N05. NPF.2 AND NPF.B. H00510N COUNTY ALA8AMA January. December,1986(a) l l
ALL INDICAf 0R INDICATOR LOCAi!0N WITH HIGHEST ANNUAL MEAN COMMINIIY CONTROL MtDIUM OR TYPE AND LOCAI!ONS LOCATIONS LOC All0NS PAINWAf SAMPLTD TOTAL NJMBER OF NOMINAL MEAN (f) (c)
NAME l ME AN ( f) (c)
MEAN (f](c) f( AN (f)(c)
(UNii Of MEASUREMENT)
ANALYSES PERF0bMED NUC (b)
R ANGE (c)
DISTANCf AND DIRECTION RANGE (d R ANGE (c)
.....................................................................................................l....................
RANGE (c) 86 214
- 152, 214. (4/27)
South Perimeter 214. (4/11)
(182.
213.)
1.0 Miles SSE (182.
273.)
Pb 214 130 170. (4/27)
South Perimeter 1R1. (3/11)
(136.
224.)
1.0 Miles - 55E (154.
224.)
Ac.228 287 442. (6/27)
North Perimeter 781. (1/1) 373. (2/12)
(186.
781.)
0.9 Miles. NNE (309.
437.)
u N
(a) No Nonroutine An. m lous Measurements Reported During This Period.
(b) Mean Minimum Deten t.sble Concentration (~alculated Per Table 3 of This Report.
h)
N-an and k.ange B.aeJ on Detec table Measurement s only.
Fr.sc t ion of Detectable Me.asurements at Specified locations in Parenthesis (f).
Page 2 of 2
]
1 TABLE FC10-5 SOIL. OPERATIONAL RAD 10ACTIVIIV
SUMMARY
J0$f PH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF.8. HOUSION COUNTY, ALA8AMA January - December,1986 (a) l ALL IN0!CATOR 1801CATOR LOCATION WITH HIGHf 51 ANNUAL MEAN COMetJNITY CONTROL MfDluM UR IfPE AND LOCAil0NS
-.= =-- - ----
}j LOCATIONS LOCATIONS PAfhuAt SAMPLip TUTAL NUMBik 0F-kUMINAL MEAN (f)(c)
NAME l MI AN ( f )(c)
ME AN (f)(c)
M AN (f)(c (uMIT OF MEAsuk!MEhr)
ANAL YSIS PENFukMID MDC (b)
RANGE (c)
DISTANCE Afc DIRECTION l RANGE (c)
RANGE (c)
RANGE (c) )
-..................=
1 1
$ual (in $ttu)
Comma Spec 12 (pCi/6a. Dry) 1
]
K-40 525.
6100. (7/7)
East Perimeter 17800. (1/l) 1510. (3/3) 2640. (2/2)
(1110.
17800.)
0.8 Miles. [
(1120.
2230.)
(1150. - 4130.)
Cs.137 44.6 261. (7/7) best Perimeter 426. (1/1) 198. (3/3) 245. (2/2)
(145. - 426.)
0.8 Miles - WNW (139.
299 )
(170. - 320.)
l g
TI-208 127.
156. (7/7) fast Perimeter 1450. (1/I) 4 34. (3/3) 632. (2/2) j u
1 (412.
1450.)
1.0 Miles - NE (346.
537.)
(559.
705.)
I 86-212
- 890, 1620. (6/7)
East Perimeter 2810. (1/1) 832. (3/3) 1040.(2/2) j (975. - 2810.)
1.0 Miles - NE (572.
1050.)
(897. - 1180.)
l Pb 212 288.
1500. (7/7)
East Perinerer 3140. (1/l) 984. (3/3) 1040. (2/2)
(758.
3140.)
1.0 Miles. M (812.
1200.)
(H21.
1360.)
8i.214 185.
1490. (7/7)
East Perimeter 2330. (1/I) 1060. (3/3) 2730.(2/2) d (1040. - 2330.)
1.0 Miles. NE (932.
1150.)
(1720.
3750.)
1 Ph.214 299 161D. (7/7)
East Perimeter 2670. (1/l) 1190. (3/3) 2040. (2/2) 4 i
(1050.
201u.)
1.0 Miles. NE (1040. - 1360.)
(1630. - 2450.)
i ka-226 1250.
< MDC e
Ac.228 330 2120. (7/7) fast Perimeter 4010. (1/I) 1300. (3/3) 1980. (2/2)
(1190.
4070.)
1.0 Miles. NE (10H0.
1580.)
(1410. - 2560.)
i i
l
(.4 ) No honrowt tne Anomatom Measurements keported 1Aaring This Period.
}
(b) Heaa Mlaimum twees table Concent r.stion Calculated Per Table 3 of This keport.
j te) Me a and iLsuge B..=ed ou th:Lectat.te Measuremeut h Outy. Frac t ion et Iktec table Measurements at Specified 1.ocat tor.3 in Parenthesis (f).
J f
_m
__-____m._._.~
,_- ~__. _ _ __
.-,m..
}
l i
e i
TA8tf F010-6 WATER 80kNE: SURF ACE AND GROUND WATER - OPERAll0NAL RADI0ACTIVliv SUMMART 4
1-JOSEPH M. FARLEY NUCLEAR PL ANT LICENSE N05. NPF-2 Af0 NPF-8, HOUSTON COUNIV, ALABAMA January - December,1986(a) i e
a l
ALL IWICATOR INDICATOR LOC ATION WiiH HIGHEST AhmlAL MEAN COMpemlif CONTROL MEDIUM OR I1PE AND LOCAT1095 I
LOCAi!ONS LOCATIONS i
PATHWAf SAMPtED TOTAL NUMBTR OF NOMINAL MAN (f) (c)
NAME l MEAM (f)(c) f( AM (f)(c)
MAN (f)(c)
(upIT OF MEASUPEMENT)
ANALT5ES PERf 0RMED MC (b)
RANGE (c)
DISTANCE AW DIRECTION l RANGE (c)
RANr.E (c)
RANGKc)
- - - - - - - - - - - - - - - = - - _ _ _ _ _
t Surface Water (Rtver)
Camune Spec 19
}
(pCi/l)
Be-F 33.0 34.0 (1/9) 1 1
i K-40 0.0 59.0 (1/10)
Great Southern Paper 59.0 (1/10)
}
River Mile, 40
[
pb-54 3.10
< NC
< IOC v
4-Co-58 3.60
< B0C
< PCC L
Te-59 6.80
< #0C
< DOC 3
Co-60 2.60 1.00 (1/10)
Great Southern Paper 1.00 (1/10) 2.00 (t/9)
}
River Mile. 40 2n-65 6.40
< P0C
< 89C Mb-%
3.80
< #0C 3.00 (1/9) fr-%
6.10
< IOC
< fec
!.1 31 6.50
< 70C
< #0C Cs.134 3.55 2.00 (1/10)
Great Southern Paper 2.00 (1/10) 4.00 (1/9)
River Mile, 40 I
Cs-137 3.47 3.75 (4/10)
Great Southern Paper 3.75 (4/10) 4.50 (2/9) l l
l (3.00 - 4.00)
River Mile, 40 (3.00 - 4.00)
(4.00 - 5.00) i (a) iso w arm. time Am.malous h e urements Neported During This Period.
(b)
N.am Minimus Detectable Concentrations Calculated Per Table 3 of This Report, u3 w...a nou n d i:co. D tecta 6:e woore.e Em o ir.
rr.< tion or Detect.6:e neasore.e=t. at sPecifsed location in Parenthesis (f).
j Page i et 1 i
a
TABLE F010-6 (Cont'd)
WATEPBORNE: SJRF ACE AND GROUND idATER - OPERATIOhAt RADICACTIVITY
SUMMARY
JOSEPH M. FARLEY MUCLEAR PLANT LICENSE N05. NPF-2 AND NPF-8, HOUSTON COUNTY, ALA8AMA January - December,1986 (a) l
[
ALL IW!CATOR IPO!CATOR LOCATION WITH HIGHEST ANNUAL MEAN ' COMmMITY CONTROL MEDIUM OR TVPE AND LOCATIONS LOCATIONS LOCATIONS PAT WAV SAMPLED TOTAL fifMPER OF NOMINAL MEAN (f)(c) hAME l ME AN (f)(c)
MEAN (f)(c)
MEAN (f)(c)
(UN!T OF MEASUREMENT)
ANALYSE 5 PERFORMED P0C (b)
RANGE (c)
DISTANCE AND OIRECTION l RANGE (c)
RANGE (c)
RANGE (c)
Ba-140 16.1
< P0C
< POC La-l*O 0.700
< POC a
( POC TI-208 3.50 4.50 (2/10)
Great Southern Paper
- a. " (2/10)
(4,00 - 5.00)
River Mile, 40 (4.00 5.00)81-212 38.0 52.0 (2/10)
Creat Southern Paper 52.0 (2/10) j (34.0 70.0)
River Mile, 40 (34.0 70.0) 44.0 (1/9)
I B1-214 5.00 10.0 (1/10)
Great Southern Paper 10.0 (1/10) j River Mile, 40 u
Ac-228 0.0 9.00 (1/10)
Creat Southern Paper 9.00 (1/10) 9.50 (2/9)
River Mile, 40 (8.00 11.0)
Tritium 8
H-3 122.
478. (3/4)
Great Southern Paper 478 (3/4) 272. (2/4)
(359. - 540.)
River Mile, 40 (359. - 540.)
(101.
442.)
Ground Idater (nsell)
Gamna Spec 6
l (PC8/I) i Be-7 27.0 30.0 (t/3)
Great Southern Paper 30.0 (1/3) ideI1 4 Mties. 55E Mn-54 3.25
< MOC
< MDC Co-53 3.75
< MDC
< POC (a) No Nooroutine Anomalous h asurements Reported During This Period.
(b) Mean Mlainum Detectable Concentrations calculated Per Table 3 of This Report.
(c) k an and Range Based t?pon Detectable Measurements only. Fractica of Detectable Measurements at Specified location in Parenthesis (f).
Page 2 of 3 i
TAatt 5010-6 (Comt 'd) kAffkBOwNf: SURF ACE AM) CatAJM) HATER - OPER Ai!ONAL R4010ACTIVITV $UMMARY J05f PH M. FARL EY NUCt f AR PL A4T L ICimSE N05 hPF-2 AW hPF-8. HOU5 TON COUNTV, ALABAMA January - December,1986 (a) ll ALL IW!CATOR IM)!CATOR LOCATION WITN HIGHEST AhMUAL MfAN COMMINITY C0h!ROL MIDit,M Da TVPE Am 10CAi!025 LOCATIONS LOCATIONS PAlpr.AT SAMPtID IOTAL NU W fR OF huMIRAL pt AM (f) (c)
MAME ME AM (f)(e)
MI AN {(f))(c)
RANGECCI(c)
(t:all 0F Pt a saat!Mt ni)
ANAL V 5E 5 PE RFORMt D MDC (b)
RANCE (c)
DISTANCE Am DIRICTIOm RANGE (()
RANGE c ME AM if1 00-60 3.00
< P0C
< MT Zn-65 4.50
< P0C
< M)C Be-%
3.75
< ME
< M)C Zr-%
6.25
< P0C
< K)C I-131 6.00
< P0C
< Mic C5-134 3.00
< P0C w
3.00 (1/3)
Cs-137 3.75
< P0C
< M)C Ba-140 16.8
< POC
< MDC 14-140 1.50
< MDC
( Mt Ac-??8 0.0 8.00 (1/3)
Creat Southern Paper 8.00 (1/3) heII 4 Miles - 551 Tr s t t e 8
M.3 m.5
< P0C
< MC (4) h wareut an, n==
- 1. mas Nasurements Reported thring This Period.
(b) man Minimum Detectable Concentrations Calculated Per Table 3 of This Report.
- t. ) Nam emJ We hm=J L'pon Detec table Nasurements only.
Fractica of Detectable Measurements at Specified location in Farenthesis (f).
rue sf 3
TA8tf F010-F SfD!MmT: RivfR - OPfRAll0eAL Re l0ACTIVITT Sumpanat J05fPN M. FAmtfy muCL[AR PtApi LICf tsf N05. WF-2 As NPF.8. Houston CoveTV. ALAsann Jeauery - Decaneer.1986(4)
Att IWICATOR IW!CATOR LOCAllom WITH MIGHf 57 JuuaAAL MEAm (0*=t::1!TV Cont 80L MDIUM 09 ITP1 Age LUCAil045 LOCATIoms LOCAllons PATMinAv SAptID TOTAL sessGER N hominAt MAa (f)(c)
HAM l M AN (f)c)
MAN (f)c)
Me (t)(c)
(umIT W M A5ualMnT)
AhALv515 Pf pFOAMD set (b)
SamG1 (c)
DISTANCf Ase DIRECTION l ammGE (c)
R ANGl (c)
RANGE (c) 5edament (R1ver)
Camune Spec 4
(pCi/kg - Dry)
E-40 230.
1890. (2/2)
Smith's tend 1890. (2/2) 5350. (2/2)
(1790. - 1990.)
Rtver Mile. 41-42 (1790. - 1990.)
(4380. - 6320.)
Cs.134 39.0
< feC
< 8ec Cs.13F 38.5
< sec
< pec II.208 46.0 59.0 (1/2) 9tth's Bend
$9.0 (1/2) 564. (3/2)
U River Male. 41-42 (142. - 1040.)
86 212 886.
3720. (1/2)
Pb 212 81.8 234. (2/2) hith's Bend 734. (2/2) 1690. (2/2)
(!$7. - 311.)
River Mile. 41-42 (157. - 311.)
(964.
2420.)
8.214 80.8 178. (2/2)
Smith's Send 178. (2/2) 1200. (2/2)
(150. - 205.)
River #tle. 4142 (150. - 205.)
(190. - 1600.)
l Pts 214 87 3 199. (2/2)
Smith's Dead 199. (2/2) 1230. (2/2)
(192. - 7tJa.)
River #tle. 4142 (192. - 206.)
(852.
1610.)
l ta-??6 l 841.
l 1720. (2/2)
.~.
(10u0. - 2350.)
Ac.225 l138.
' 292. (2/2)
Smith's Bend 292. (2/2) l 2040. (2/2) l (214. - 36N.)
l River Male. 41 42 (216 368.)
l l (!!60.
2910.)
l I
l (a) abe Muarewatae Ammulems Nasarements Wre Reported thar tag This Perted.
sbn km na.- Ntatate wesar.t s.es calculated Per T.ba. 3
.t This aeport.
se p Nm.ma age 243 4 t:Fue Detectable N.smurreests Umly. Fraction et Detectable N asurements at Specified Locattues la Patenthemis (f).
l i
TABLE F 010.-e Fl54: Stuf f - OPTRAf tchAL RJOl0ACilutiv 9estav JOSEPH M. F AR117 huftf AR PLANT LICth5[ hei. hPF-2 As0 MPF-8. HOU5fCm COJmf f, AL AaAMA January - Decenter,1984 (a) l l
l ALL 1901CATOR ll IW!CATOR 10 CATION istiM ItIGHEST Ahm1At MEAM COMae:aliv CONTROL MEDitw CA TYPE A80 10CATICm3 LOCAll045 (UCATIONS PAimAt SAP @t (O IDTAL SEM[R OF m0M! hat N AM (f)c) hAMF Mi A2 (f je)
Mf AN (f)(c)
M Ah (f)(c)
(Lati 0F M Awalqhi)
A4ALY5(5 Piaf 0 emf D 800 (b)
RA8sGf c)
DIST ANCE APO DIRfCTION B ANGl (c)
R ANGlac)
R ANGit c) t
_=.-
Fesh (Gene)
Carma Spec 4
(;Ct/ag - wt isssue)
Be-F 156 159. (1/2) hith's Be=2 159. (1/2)
River Male, 41-42 E -43 59.3 3270. (2/2) hith's Bend 3270. (2/2) 3120. (2/2) *
(2730 - 3800.)
1 River m ie, 41-42 (2730. - 3800.)
(2120. - 3510.)
Pti-54 23.0
( PCC
< POC w
C2 Co-58 I T.0
< P0C
< P0C re-5,
47.5
< n>C
< P0C Co-60 19.0 25.0 (1/2) hith's Bend 25.0 (I/2)
( P0C l
River Mile, 41 42 2n-65 46.0
< 70C
< POC Cs-134 22.0
( 700
( P0C Cs-137 23.0 53 u (2/2) htth's pend 51.0 (2/2) 35.0 (2/2)
(41.0 - 61.0)
Baver Male, 41-42 (41.0 - 61.0)
(35.0 - 35.0)
Iash (Botton feediaq)
- Casvu Spec 4
(PCI/64 - het Issive)
E 40 217 2930. (2/2) vtth's Bend 2930. (2/2) 2940. (2/2)
(2650. - 3210.)
River Mile, 41-42 (2650. - 3210.)
(2700. - 3170.)
l l
Ms.54 20.5
< P0C 1
( MDC (43 E Eserout ame Amleos Measurements bere keported During Thas Period.
(b) Mean Maatauss IA-tn a ble C mcentrat toms calculated Per Table 3 of This Report.
- s. P M.- 4= 4.mt k.ngr E4>eJ Upen Detes table Measurenerat s Only. Fractiva of Detectable Measurements at Spectiled Im ations in rasentttests (f).
1 1
P a;e 8 of 2
T Akt E FO to-a (Coat'd)
FISH: alvtt. tete 4TIONAL RADIDACTIVITy swAug JOSEPM M. FADLif NUC1fAR PEARI L ICENSE N05, NPF-2 MD NPF-4, HOUSTON COUNTY, ALABAMA January. December,1986 (a)
ALL ISICATOR ISICATOR LOCAi!ON WITH HIGHE$i ANNIAL ME AN Comm'NITY CONT 80L pfDrum OR TYPE Ale 10CAi!045 LOCA!!aN5 LOCAil0N5
=.. -...
PATiesAt 5ApetfD TOTAL NUfGER OF NOMINAL MAN (f) (c)
NAME l M(M (f } (c)
MAN (f)(c)
ME AN (f)(c)
(UNil 0F MEA 5uafu(NT)
ANALYSE 5 PERF084ED feC (b)
RANGE (c)
DISTANCE Ase DIRECTION l RANr4 (c)
R ANr4 (c)
RANGE (c)
_.....==
Co-5N 22.0
<feC
< feC Fe-59 38.0
< feC
< PtC Co-60 17.0
< feC
< feC z 65 44.5
< pec
< eoC C5-134 25.0
< POC
< pec Cs-137 20.0 28.0 (1/2)
Snith's Bend 28.0 (1/2) 25.0 (1/2)
River Mile, 41-42 La c
(a) 90e Hoerouttee A-tous 90masuremente Were Reported During thte Period.
(b) plean Minimum Detectable Concentrations Calculated Per Table 3 of This Report.
(c) Mean and Range Based Upon Detectable 90easurements only. Fraction of Detectable pleasurements at Specified Incations in Parenthesis (f).
Page 2 of 2
ATIACHMENT 1 LAND USE SURVEY FOR RADIOIOGICAL DNIRONMENTAL MONI'IORING PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT JULY 23-30, 1986 This Land Use Survey was performed to meet the requirements of the Farley Units 1 and 2 Technical Specifications, Section 3.12.2 and 4.12.2.
A.
Houston County, Alabama Mr. A. M. Mathews, Houston County Extension Agent, was contacted for the purpose of reviewing known locations of milk animals in the county and discussion of any changes since the last milk animal survey (July, 1985).
l A house-to-house canvas of residents along Alabama 95 for a distance of about three miles from the plant entrance revealed no milk animals. Individuals at the following residences were questioned:
Walter Whatley, Maurice Gilbert, and Lula Mae McGriff.
Simultaneous with the house-to-house milk animal canvas, the nearest residence in each of the meteorological sectors was identified.
B.
Early County, Georgia Mr. Micky Fouracres, Early County Extension Agent, was contacted to determine if any milk animals were currently present in the county.
He stated that to his knowledge there were no milk cows or goats in Early County.
A house-to-house canvas of residents in the area across the Chattahoochee River east of the plant was negative with respect to the presence of milk animals. Individuals at the following residences were questioned: Tony Knighton and Jim Donaldson.
Simultaneous with the house-to-house milk animal canvas, the nearest residence in each meteorological sector was identified.
C.
Results and Conclusions The results of the Land Use Survey are shown in Table I.
Based on the survey results, no change in the present milk sampling program is required.
Annual DN Report /6 40
TABLE I OF ArrACHMENT 1 JOSEPH M. FARLEY NUCLEAR PLANT IAND USE SURVEY JULY 23-30, 1986 (DISTANCE MILES 'IO NEAREST)
RADIAL SECTORS (22.5 DEGREES)
RESIDENT MILK ANIMAL North Northeast (01) 2.4
>5 Northeast (02) 2.6
>5 East Northeast (03) 2.4
>5 East (04) 2.8
>5 East Southeast (05) 2.8
>5 Southeast (06) 3.4
>5 South Southeast (07)
>5
>5 South (08) 4.3
>5 South Southwest (09) 2.9
>5 Southwest (10) 1.2
>5 West Southwest (11) 0.9
>5 West (12) 1.3
>5 West Northwest (13) 2.1
>5 Northwest (14) 2.4
>5 North Northwest (15) 2.8
>5 North (16) 2.6
>5 Annual ENV Report /6 41
1 NT 87 0176 Afabims Power Company 600 North 18tn Street 1
Post Office Box 2641
)
Birmingham. Alabama 35291-0400 Telephone 205 250-1835 R. P. Mcdonald
- t Senior Vice President ObOMO bWOf the southem electnc system April 27, 1987
' Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Comission Attn: Document Control Desk washington, D. C. 20555 RE: Joseph M. Farley Nuclear Plant Annual Environmental Operating Report Gentlemen:
'Ihe attached " Annual Environmental Operating Report, Part B:
Radiological" for the period January 1, 1986 through December 31, 1986, is transmitted in accordance with the Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 Technical Specifications Sections 6.9.1.6 and 6.9.1.7.
If you have any questions, please advise.
Yours very ruly, f
R. P. Mcdonald RPM / MAT:emb Attachment cc:
Dr. J. N. Grace U. S. Nuclear Regulatory Comission Mr. W. H. Bradford Mr. E. A. Reeves U. S. Nuclear Regulatory Commission Director, Bureau of Radiological Health State of Alabama Director, Environmental Protection Division State of Georgia}