ML20151V040

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Annual Environ Operating Rept Part B:Radiological for 1987
ML20151V040
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/31/1987
From: Mcdonald R
ALABAMA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NT-88-0199, NT-88-199, NUDOCS 8805020255
Download: ML20151V040 (42)
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!. AIABAMA POWER COMPANY NMRL DNIRONMENTAL OPERATING REPORT PART B RADIOLOGICAL JOSEPH M. FARIJ!"I NUCLEAR PLANT ..,

UNIT NO. 1 LIC1!NSE NO. NFF-2 AND UNIT No. 2-LICENSE NO. NPF-8 PERIOD ENDING DECEMBER 31, 1987 1-Annual DN Report /2

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< PART B: RADIOIDGICAL i

TABLE OF CONTENIS Section Title Page I Introduction 1 II Radiological Sangling and Analysis 2 III Results and Discussion 5 IV Land Use Census and Interlaturatory Comparison 8 Program V Data Trends and Conclusions 8 I

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RADIOLOGICAL DNIROtMENTAL OPERATING REPORT LIST OF FIGURES Figure Title Page 3.1h-1 Indicator Sampling Locations for Airborne 9 Environmental Radioactivity at the Farlesy Nuclear Plant.

3.12-2 Community (Indicator II) Sampling Locations for 10 Airborne Radioactivity in the Farley Nuclear Plant Area.

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Conttel Sampling Locations for Airborne 3.12-3 11 Environmental Radioactivity in the Farley Nuclear Plant Area.

3.12-4 Indicator and Control Sampling Locations for 12 Waterborne Environmental Radioactivity in the Farley Nuclear Plant Area.

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e RADICIDGICAL DNIRONMDEAL OPERATING REPORT 1

LIST OF TABLES j i

Table Title Page 1 Scope of Operational Radiological Environmental 13 Monitoring Program at the Farley Nuclear Plant During 1987 2 Outline of Operational Radiological Environmental 14 M Titoring Program for Farley Nuclear Plant During 1987 l 3 Detection Capabilities for Environmental Sanple 19 Analysis for Farley Nuclear Plant 4 Reporting Levels for Radioactivity Concentrations 21 in Environnxntal Samples 5 3ampling and Analysis Deviations During 1987 22 1987-01 Airborne: .? articulates - Operational Radioactivity 26 Summary 1987-02 Airborne: Iodine - Operational Radioactivity 27 Summary 1987-03 External Radiation - Operational Radioactivity 28 Sunnary 1987-04 Milk - Operational Radioactivity Sunmary 29 1987-05 Vegetation: Forage - Operational Radioactivity 30 Summary 1987 06 Soil - Operational Radioactivity Sunmary 31 1987-07 Waterborne Surface Water - Operational 32 Radioactivity Sunmary 1987-08 Waterborne: Ground Water - Operational 34 Radioactivity Sunurary lii

4 RADIOLOGICAL DNIRONMENTAL OPERATING REPORT LIST OF TABLES CONTINUED, Table Title Page 1987-09 Sediment: River - Operational Radioactivity 36 Summary 1987-10 rish: River (Game) - Operational Radioactivity 37 Summary 1987-11 Fish: River (Bottom Feeding) - Operational 38 Radioactivity Sumary t

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RADIOI4GICAL DNIRCl@ ENTAL OPERATING REPORT LIST OF ATTACHMENTS Attachment Title Page 1 Land Use Survey for Radiological Environmental 39 Monitoring Program, Joseph M. Farley Nuclear Plant, July 1-7, 1987 a

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OPERATIONAL RADIOIOGICAL DWIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 I. Introduction he Joreph M. Farley Nuclear Plant, c'.wi and operated by Alabama Power Company (APCo), 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 ( me) achieved initial criticality on Augast 9, 1977. We unit was decisted "comercial" on tweember 1, 1977. Unit No. 2, also a 860 W e Westinghouse PWR, achievd initial criticality on May 8,1981 and was declared "comercial" on July 30, 1981.

During 1987, Unit No. I was off-line from April 6-15 and December 7-17 for maintenance. Unit No. 2 was off-line January 10-24 for maintenance activities and October 3 through December 5 for the fifth refueling outage. Unit No. 2 was also off-linc December 9-31 for additional maintenance activities.

We sample collection and analysia 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 1987 for both Units No. 1 and 2.

W e program was further modified effective April 1982 to reflect Amendment No. 26 to the Unit 1 Technical Specifications issued March 1, 1982. W is program was designed to monitor any radioactivity contribution to the environs from the plant through either the airborne or waterborne pathways. he type of samples monitored, and number and type of sampling stations are shown in Table 1. 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 radiological levels might be made with meacured levels. We 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). Wese 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.

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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 specificaticus for both Units No. 1 and 2.

h e sapples were collected by APCo's technical staff except for the in situ high purity germanium (HP(Ge)) gansna-ray spectroscopy measurements of soil. % e latter were made by staff members of the University of Georgia (UGA), Center for Applied Isotope Studies. All sanple analyses were contracted to UGA. he minimum detectable concentration (MDC), specified for the various canples and their respective analyses are given in Table 3. %e reporting levels for radioactivity concentrations in environmental sangles are provided in Table 4. Sanpling and analysis deviations during 1987 are listed in Table 5.

A. Airborne Particulates and Iodine >

All airborne particulate and iodine nonitoring stations shown in Figures 3.12-1 through 3.12-3 were equipped with Roots vacuum pumps 0.04 m y/ min (1.5 ft / min).hich We operatep particulatescontinucaisly at a flowonrate of approxim were collected Gelman Metricel 47am (or equivalent) filters. In series with, but downstream of the particulate filters, r&J 50 nun (or equivalent) activated charcoal cartridges were used for collection of iodine.

%e Roots system has the sanple collector mounted outside of the cabinet horizontally to the ground with a Singer gas meter measuring the cumulative air flow. We gas a ters 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 Tennelee low background alpha-beta counting system. The filters from each station, composited at the end of each quarter, were analyzed for gamma emitters using a fifteen percent relative efficiency low background germanium lithium (Ge(Li)) detector and a Canberra 4096 channel computer-based multichannel analyzer (MCA). ,

All air monitoring station locations shown in rigures 3.12-1 through 3.12-3 have the capability of monitoring airborne iodine. Weekly routine r,amples were analyzed for I-131 by UGA using a Canberra 1024 channel MCA and two 1" x 3" NaI detectors and matched photomultiplier tubes.

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'4 B. External Radiation .

For the continuous measurement of environmental gasuna radiation, natural Lithium Fluoride (Lir) (TLD-700) chips, manufactured by Harshaw-riltrol Chemical Company, were used.

TLD packets each containing four annealed Lir chips were sealed in opaque mylar to produce a packet that was light-tight, weather-proof, and which radiation (approximately had a 1 p). On 50mg/cm mass theattenuation forTLD plant site, all 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 l We milk sanple locations are as indicated on rigure 3.12-3.

All milk sa.1ples, collected bi-weekly, were analyzed by UGA for I-131 and gamma emitters. As a preservative for shipment,1 al of 25 weight percent merthiolate ( himerasol) solution was added to each one gallon sample. %e I-131 concentration in each sample was determined by collection on anion exchange resin, elution with sodium hypochlorite, follrued by organic extraction and counting, by beta-gamma coincidence, the resultant toluene-iodine solution in a low level liquid scintillation counter. Stable iodine carrier was added to each sample for determination of the radiochemical yield.

A one liter quantity of each sample was placed in a marinelli beaker and then analyzed for gansna 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 sanples were analyzed by UGA for gamma emitters using a 15 percent relative efficiency low background Ge(Li) detector and i a Canberra 4096 channel computer-based MCA.

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E. Soil Annual in situ gama-ray spectroscopy measurements were made by UGA vzing 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 comunity 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 Rivor, 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. Two liter aliquots from each monthly composite were placed in trays lined with plastic film and evaporated to dryness at 100*C. he residue and plastic film was folded to fit a petri-dish and analyzed for gama emitters using a 15 percent relative efficiency Ge(Li) low background detector and n 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 ml from each quarterly composite sample was distilled and a 25 ml aliquot taken for tritium analysis using a large volume (100 ml)

Hewlett-Packard 200 low background liquid scintillation counter.

G. Groundwater: Well Water:

In the Farley Plant area there are no trut 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 rcsidence 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 m1 samples were analyzed using a large volume (100 ml) low background liquid scintillation counter. From the remainder of each samp12, a two liter aliquot was taken and evaporated to dryness at 100'C in a tray lined with plastic film. We residue and film was folded to fit a petri dish and analyzed for gama emitters using a 15 percent relative efficiency Ge(Li) detector and a Canberra 4096 channel co:rputer-based MCA.

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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 gama-ray spectroscopy analysis. Both semi-annual fish samples sent to UGA consisted of fish fillets that had been split with Alabama e

Bureau of Radiological Health. These fish samples were coarsely chopped at UGA and were analyzed for gamma emitters using a 15 percent relative efficiency low backgrot d 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. One semi-annual sediment sample was split with Alabama Bureau of Radiological Health.

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 1987. No radiological effects l

from the Chernobyl Nuclear Power Plant accident in the U.S.S.R. in April of 1986 were evidenced in 1987.

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. The 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 without respect to the size of sample and/or radiochemical yield and to measurements which by their nature do not involve concen-trations, e.g. radiation dose rates (mrad /hr., mrad /qtr., etc.)

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+ A. Airborne Particulates h results of the radioactivity analyses of airborne particulate filters are shown in Table 1987-01. h mean gross beta activity value for the air particulate indicator sampling locations was lower than the commanity and control-4 sampling locations. %e indictor and control gross beta activity means were slightly lower than the 1986 values; ,

however, the gross beta. activity mean for the community location was higher than in 1986._ All air particulate activity was lower than the preoperational values. ,

he gross beta and gansna-ray spectroscopy data for the air particulate filter composites showed a decrease of beta gassas, Cs-134, Cs-137, and I-131 in indicator, control and community samples as compared to 1986. All values for Cs-134, Cs-137, and I-131 were below the measured MDC.

B. Airborne Iodine he results of the radioactivity analyses of iodino. charcoal I

, . cartridges are shown in Table 1987-02. %e iodine activity

. for 1987 samples at all locations was less than the minimum detectable concentration values. %ese activity levels were i lower than the iodine levels of 1986 and the precperational period.

C. External Radiation

%e results of the external radiation measurements using TLD packets, each containing four Lir chips, are shown in Table

. 1987-03. As round during the preoperational measurement l period and duritig 1986, the data reflect the differences in

, site specific soil radioactivity. Exposures recorded by l

quarterly TLDs in 1987 were greater than those recorded in 1986 for all sampling locations. %e exposures recorded by annual TLDs in 1987 were also greater than that observed in l , 1986 and during the preoperational period. However, no i deviate trends can be concluded since the data for 1987 is j comparable to that recorded in 1985 and 1983. Also evident in 1987 as in previous years, the exposure recorded by annual TLDs were less than the sum of the exposure from the four [

quarterly TLDs. i

, C. Milk 1he results from the radioactivity analyses of milk are shown l in Table 1987-04. Milk from the Silcox Dairy was sanpled from  !

January through August and from the Lewis Dairy from September

, through December as the control. An indicator milk location I provided a sample during August. Only naturally occurring .

radioactive isotopes were detected in both the indicator and control sanples.

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E. Vegetation Forage was the only vegetation sampled during this operational period. %e radioactivity, analysis results are shown in Table 1987-05. Forage, as during the preoperational period, continued to be a very effective and sensitive indicator of airborne radioactivity. %e specific activity values for the various gasuna emitting radionuclides at indicator locations were slightly higher than the control locations. Traces of Cs-137 were found in some indicator samples; howtaer, the values were lower than 1986. We data for 1987 indicated fewer fission product radionuclides than the preoperational data.

F. Soil he results of the in situ HP(Ge) gansna-ray spectroscopy analysis of soil duH ng this operational period are shown in Table 1987-06. We 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. We 1987 levels of Cs-137 found at indicator locations were not significantly different from control locations. %ese levels were approximately the same as the 1986 period and lower than the preoperational period.

G. Waterborne: Surface Water h e results of radioactivity analysis of surface water are shown in Table 1987-07. Cs-134 and Cs-137 activity levels were below the measured MDC values. %ese values nrrs also less than the 1986 and preoperational data.

We average su: face water indicator tritium level was higher ,

than the control, less than that observed in 1986 and as in '

previous years higher than that observed during the preoperational period.

H. Waterborne: Ground Water The results of the radioactivity analysis of ground water are shown in Table 1987-08. he Cs-134, Cs-137, and I-131 activity values were less than MDC which was conparable to 1986 values.

I. Sediment: River he results of radioactivity analysis of sediment samples from the Chattahoochee River are sh Wn in Table 1987-09. %ere were no manmade isotopes detected in any sediment sample.

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J. Fish: River (Game) he results of gama-ray spectroscopy analysis of the edible portions of game fish taken from the Chattahoochee River are shown in Table 1987-10. Cs-137 was found at low levels in both the indicator and control samples of game fish with the indicator Cs-137 level higher than the control value. %e 1987 average indicator and control Cs-137 values were found to be higher than 1986 data but lower than the preoperational data.

K. Fish: River (Bottom Feeding) he results of gama-ray spectroscopy analysis of the edible portions of bottom feeding fish taken from the Chattahoochee River are shown in Table 1987-11. Cs-137 was found at low levels in both indicator and control samples of bottom-feeding fish. %e indicator Cs-137 level was slightly higher than the control value. We 1987 Cs-137 levels for both sampling locations were higher than 1986 but lower than the preoperational period.

IV. Land Use Census and Interlaboratory Comparison Program A. Land Use Census h e results of the July, 1987, Land Use census are given in Attachment 1 to this report.

B. Interlaboratory Comparison Program During 1987, the University of Georgia Center for Applied Isotope Studies (UGA) was a participant in the EPA crosscheck Program. We UGA EPA Program code designation is EA. Although Farley Nuclear Plant (FNP) also participates in the EPA crosscheck trogram under code designation FU. none of the environmental analyses reported herein were performed by FNP.

V. Data Trends and Conclusion A review of the 1987 environmental data indicated some changes in the parameters monitored when compared to previous years' data.

Slight increases of Cs-137 in fish were observed as well as external gama radiation as measured by TLD. Wess Cs-137 levels, though slightly higher than 1986, were lower than the preoperational values. We external gama radiation values were conparable to the 1985 and 1983 TLD measurements. %e review also indicated either no change or decreases in numerous parameters including air particulates, milk, vegetation, soil, water, and sediment. Werefore, data obtained during the 1987 sampling yeat demonstrated that there was no significant adverse impact on the surrounding environs of Farley Nuclear Plant as a result of its operation.

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TABLE 1 SCOPE OF OFERATIONAL RADIOLOGICAL 21VIR0hMENTAL PKNITORING PROGRAM AT 1EE FARLEY NUCIM_I FLANtJe.Ilr,1987 Principal Type of Rzober of Stapling Stations Pathway samples IndWiig Community control Airborne Particulates 3 3 3 Airborne Iodine 3 1 3 External Radiation 16 18 4 Airborne Milk - - 1 Forage

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1 Soil" 7 3 2 River Water 1 -

1 Groundwater 1 -

1 Waterborne River Fish 1 -

1 River Sediment 1 -

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  • Forage sanpling in lieu of vegetable and fruit. Vegetable and fruit sampling discontinued witFimplementation of Unit 1 Technical Specification Upgrade (Amendment No. 26, issued March 1, 1982).

"Annual y Situ Gamma Measurements continued by choice of licensee during 1987.

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i 13 Annual DN Report /3 l

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'mBLE 2 OLTII.INE Or OPERATICNAL RADIOf4GICAL DWIlOSENFAL MONI'IORING PROGRAM EUR FARLEY NUCLEAR PUNr DURING 1987 Types of Samples and Sampling Type and Frequency Sampling Iocations and of (Distances Given in Miles) Collection Frequency Analysis AIRBORC Particulates Continuous operation cf sampler with Particulate sampler sample collection Snng 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 changa.

Perform gamuna 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 isctopic analysis on composite Community 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 Radioiodine 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 - (WSH)-0.9 River Intake Structure (ESE-0.8)

Annual DN Report /4 Page 1 of 5

l TABLE 2 (cono d)

Types of Samples and Sampling Type and Frequency Sampling Locations and of j (Distances Given in Miles) Collection Frequency Analysis l

l Cnemmiriity Stations:

1 Great Southern Paper Co. (SSE-3) l l Control Stations:

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Blakely, GA. (NE-15) l Dothan, AL. (W-18) l Neals Landing, FL. (SSE-18)

Soil Annual in situ Ge(L1) gas ===-ray c.==== Isotopic spectroscopy measurements. Annually- '

Indicator Stations:

Seven Stations along the plant perimeter (N-0.8, NE-1.0, E-0.8, lG SSE-1.0, SSN-1.0, WSW-0.9, and

NNN-0.8)

Community Stations:

Columbit t. (N-5)

Great Sot N "it Paper Co.(SSE-3)

Ashford, *SN-8)

Control Scat. ions:

Blakely, Ga. (NE-15)

Dothan, Al. (W-18)

DIRECT RADIATION At least once per 92 days c.amma dose Readout at least once per 92 days Annual ENV Report /4 Page 2 of 5

TABLE 2 (con'd) l Types of samples I and Sampling Type and Frequency l Sampling Locations and of (Distancen Given in Miles) Collaction Frequency Analysis 1

Indicator I Stations:

Sixteen stations, one in each neteorological sector along the plant perimeter (N-0.8, FNE-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, 54-0.9, WF4-0.9, W-0.8, hwd-0.8, IM-1.1, and tcM-0.9) .

Indicator II (Ccamunity) Stations:

Eighteest stations, one in each meteorological sector at a distance of 4-5 miles (?@iE-4, NE-4, ENE-4, E-5, ESE-5, SE-5, SSE-3, S-5, SSW-4, SW-5, WSW-4, W-4, WITd-4, IM-4, PCM-4, and N-5). Additional stations located at WSW-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 ganna isotopic tional semi-continuous sampler, analysis of each composite Indicator Station: having a mininnnn sampling fre- sample. Tritium analysis quency not exceeding two hours of each composite sample collected over a period f 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

3 ThBLE 2 (con'd) ,

Types of Samples and Sampling Type and Frequency Sampling Iocations and of (Distances Given in Miles) Collection Frequency Analysis Control Station:

Upstreart of Andrews Lock and Dam

(-3 miles above plant intake, n River Mile 47)

Ground Water Grab sample taken at least Camma isotopic and tritium ~ 2 once per 92 days. analyses of each' sample Indicator Stat. ion: once per quarter.

Great Souther Paper Co., Well (SSE-4)

Control Station:

C Whatley Residence, Well (SN-1.2)

River Sediz:ient Grab sample taken at least Gamma isotopic analysis "

once per 184 days. of each sample twice per year.

Indicator Station:

Downstream of plant discharge at Smith's Pend (River P.ile - 41)

Control Station: -

l Upstream of plant discharge l at Andrews Lock & Dam Reservoir .

l (River Mile - 47)

Annual E2N Report /4 Page 4 of 5 l

1NEz 2 (conod)

Types of Samples and Sampling Type and Frequency sampling Iocations and of (Distances Given in Miles) Collection Frequency Analysis INGESTICN Milk l Indicator Station: At least once per 16 days c - isotopic and I-131 Mr. Bobby Searcy (NDIE: Indicator sample analysis of each bi W ly Ashford, AL (WSW-01) collected only once during sample when animals are on 1987) pasture.

Control Station:

Silcox Dairy, Ashford, AL. (WSW-10)

Iewis Dairy Avon, AL (WSW-14) i Fish One sample of the following Gamsa isotopic analysis g species at least once per 184 on edible portions once l Indicator Station: days: 1. Game Fish per 184 days.

l 2. Botton Feeding Fish

l. Downstream of plant discharge j in vicinity of Smith's Bend (River Mile - 41) i t Control Statica:

Upstream of plant discharge in Andrews Lock & Dan Reservoir (River Mile - 47)

I Forage Grab sample cut from green r - 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 DW Report /4 Page 5 of 5

TABLE 3 DETECTIN CAPABILITIES FOR DNIlOSENIAL SAMPLE ANALYSIS FOR FARLEY FUCLEAR FIRrr VAIDES FOR *IHE MINIPEM DETECD4BLE CINCENIRATIN(TOC)* **

Airborne Particulate Water or Gap Fish Milk Food Products Sediment Analysis (pCi/1) (pCi/m ) (pCi/kg. wet) (pCi/l) (pCi/kg. wet) (pCi/kg. d g Gross beta 4 1 x 10'* NA la PR tm H-3 2000 ta fa la . la la Mn-54 15 la 130 . la ta la Fe-59 30 ta 260 ta ta la G

Co-58, 60 15 ta 130 NA ta la 2n-65 30 ta 260 Ia ta la Ir-95 30 ta ta NA NA la Nb-95 15 NA NA ta la fa l

l I-131 l' 7 x 10-* NA la NA la l

Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 60 180 Ba-140 60 ta la 60 la PR La-140 15 ta NA 15 NA la Page 1 of 2

_ _ . . _ _ , . . . . _ . . , , _ _ _ _ _ _ . . . _ . . _ _ , , . ~ . - . _ _ . . . .-._. . . . , . ..- _ - . . _ . . _ .__ . _ . _ - - . . ._

TABLE 3 (con'd)

  • h e MDC is the smallest concentration of radioactive material in a sanple that will be detected with 951 probability with 51 probability of falsely concluding that a blank observation represents a "real" 7 signal.- - '

For a particular measurement system (wMch may include radiochemical j separation):

MDC = _ 4.66 S, E V 2.22 Y exp (-Aot)

Where:

MDC is the "a priori" lower limit of detection as defined above (as picoeurie per unit macs oc 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 sample size (in units of mass or volt.me).

2.22 is the number of transformations per minute per picoeurie.

Y is the fractional radiochemical y!. eld (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.

I *We MDC's for Trititnn, Gross beta, and Radiciodine were e,btained using

! hiank background (A Priori), whereas, for gamno-ray spectroscopy actual sanple backgrounds were used (A Posteriori),

1

  • MDC for drinking water.

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1RBLE 4 REPORTING LEVELS EUR RADIOPCTIVITY CCNCDmtATIG4S IN ENVIlOWEENIRL SARPES s Reporting Levels ,

Airborne Particulate Water or Gay Fish Milk Food Products Analysis (pCi/1) (pCi/m ) (pCi/kg. wet) (pCi/1) (pCi/kg. wet)

H-3 2 x 10** NA IR NA IR 1

l Mn-54 1 x 10' NA 3 x 10' Im IR-Fe-59 4 x 10' NA 1 x 10' ra IR

, co-58 1 x 10' NA 3 x 10' NA PR l

2 Co-60 3 x 10 NA 1 x 10' NA  !%

2 lu Zn-65 3 x 10 tm 2 x 10' In NA i~

( Zr/Nb-95 4-x 10' NA NA !R NA t

l I-131 2 0.9 NA 3 1 x 10'

( Cs-134 30 10 1 x 10' 60 1 x 10' 1

Cs-137 50 20 2 x 10' 70 2 x 10' .

l Ba/La-140 2 x 10* NA la 3 x 10 2 la -

.8

  • For drinking water samples.

Annual ENV Report /4(7)

.-___ _,- --_- - -.,-.- ..,,, ,._. . ~ . . . , - . , , . . . . . . . , , - - - , _ ~ - - - - - - , _ , . . . - - - - - - , , . ~ .--- - - . . - - . - . - -

TABLE 5 SAMPLING AND ANALYSIS DEVIATIONS DURING 1987 Component Time Period

  • Reason for DeviatioVCosaments Air Monitoring Station 1601 1-29-87 to 2-5-87 Low flow rate due to ig roper setting.

Adjusted flow rate to proper setting.

Forage at 1601 2-3-87 Substituted 1501 forage plot due to unavailability of forage.

Air Monitoring Station 1601 2-5-87 to 2-12-87 Low flow rate due to loose fan belt.

Belt tightened.

Air MonitorAng Station 1108 2-12-87 to 2-19-87 Sample missing due to failed motor.

2-26-87 to 3-5-87 Motor replaced 3-11-87.

3-5-87 to 3-12-87 Air Monitoring Station 1605 2-19-87 to 2-26-87 Low flow rate due to loose fan belt.

ran belt tightened.

Forage at 1601 3-5-87 Substituted 1501 forage plot due to unavailability of forage.

Air Monitoring Station 0718 3-12-87 to 3-19-87 tow flow rate due to faulty pump. New pump inst 311ed 5-1-87.

Air Monitoring Station 1218 3-12-87 to 3-19-87 Low flow rate due to manual unloading 3-19-87 to 3-26-87 valve being closed, Valve opened 3-27-87.

TLD RC-1104 ist Quarter, 1987 Destroyed by vandals.

Forage at 1601 4-6-87 Substituted 1501 due to lack of adequate forage.

Air Monitoring Station 1101 4-2-87 to 4-9-87 Low air volume due to blown fuse, ruse replaced.

Air Monitoring Station 1108 4-16-87 to 4-30-87 Low air flow due to pump failure. New -

pump installed 4-25-87.

Air Monitoring Station 0718 4-23-87 to 4-30-87 Low air flow due to failed pump. Pug replaced 5-1-87.

Air Monitoring Station 0718 4-30-87 to 5-7-87 Low air flow due to manual unloading valve being closed. Valve opened.

Air charcoal I-131 4-30-87 to 5-7-87 MDC not acnieved due to low air flow.

Flow increased by opening manual unloading valve.

Annual DN Report /10 22 ,

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nM lTablo5(cont.) g i Cogonent , Time Period Reason for' DeviatiorvComments ,

~ 6,A Air Monitoring station 0215 5-14-d7 to 5-21-87 Low flow rate due to failed actor. New I motor installed 5-26-87. i

-Air charcoal I-131 5-14-87 to 5-21-87 railure to achieve lec due to low air [

1 flow. Flow restored by new motor l 1 5-26-87. t

- i Air Monitoring station 0215 5-21-87 to 5-28-87 sasple missing due to failed motor.  :

Motor rewired.

Air Monitoring station 0501 5-21-87 to 5-23 47 sagle missing due to blown fuse, ruse f

. replaced.  ;

>4  ;

Air Monitoring station 0703 5-21-87 to 5-28-67 tow flow rate due to blown fuse. Fuse l replaced.  !

, Forage at 1501 6-2-87 substituted for 1601 due to inadequate .

1 forage. ]

e

! Air Monitoring station 0215 5-28-87 to 6-4-87 sample missing due to failed motor. -

Motor rewired 6-5-87.

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! Air Monitoring station 0215 6-4-87 to 4-11-87 Low flow rate. Flow rate adjusted.  !

1 Tim RC-1104 2nd Quarter 1987 Destroyed by vandals. Relocated TLD stake to nearby area. ,

i TLD RC-1504 2nd Quarter 1987 Destroyed by vandals.  !

tim RC-1215 2nd Quarter 1987 Destroyed by lawn sowing equipment.  !

Air Monitoring station 0215 6-25-87 to 7-2-87 Low flow rate. Rate adjusted to proper  !

, setting, j Air Monitoring station 1108 6-25-87 to 7-2-87 tow flow rate due to blown fuse. Fuse  !

! replaced. l Air Monitoring station 1108 7-9-87 to 7-16-87 Low flow rate due to loose fan belt.

2 Fan belt tightened and suffler t i replaced. [

) Forage at 1601 8-4-87 Subetituted 0201 due to inadequate [

forage.

Air Monitoring station 1108 7-30-87 to 8-6-87 tow flow rate due to loose motor. .

8-13-87 to 8-20-87 Motor base plate tightened and insect

  • nest removed from motor 8-22-87. .

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Annual DN Report /10 23 i

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. , - - - . - , , - - , . . . . _ , _ _ , . _ _--., ..,,_ ,_,,-. .__. _ -. - - ,._ ..._...,_ ----r,.---

Table 5 (cont.)

Component Time Period Reason for Deviatiorytcaunents

, Air Monitoring Station 1601 8-13-87 to 8-20-87 Low flow rate due to damsged power source. Power source and cables repaired.

Charcoal sample missing due to defective cartridge, charcoal spilled as cartridge was removed from monitor.

Air Monitoring Station 1101 8-20-87 to 8-27-87 Low flow rate due to blown fuse. ruse replaced.

Air Monitoring Station 1108 8-20-87 to 8-27-87 Low flow rate due to motor failure.

Motor shaft replaced and motor cleaned.

Air Monitoring Station 1601 8-20-87 to 8-27-87 Low flow due to failed motor. Motor replaced.

Milk at 1101 8-27-87 railure to achieve MDC due to aged sample from shipping delay by United Postal Service.

Air Monitoring Station 1601 8-27-87 to 9-3-87 Low flow due to power source to station damaged by lightning. Power source repaired.

Parage et 1601 9-3-87 Substituted 0201 forage plot due to inadequate forage.

Air Monitoring Station 1101 9-10-87 to 9-17-87 Low flow due to electrical short in breaker. Breaker repaired.

Air Monitoring Station 1218 9-24-87 to 10-1-87 Low flow rate due to blown fuse, ruse replaced.

TLD RI-0401 3rd Quarter 1987 Destroyed by tractor while catting grass.

Air Monitoring Station 1605 10-1-87 to 10-8-87 Low flow rate due to loose fan belt.

Belt replaced.

Air Monitoring Station 1108 10-1-87 to 10-8-87 Low flow due to loose fan belt. ran belt replaced.

Air Monitoring Station 0701 10-15-87 to 10-22-87 Low flow due to blown fuse. ruse replaced.

Annual DN Report /10 24

... Tablo 5;(cont.)

comement Time Period Reason for DeviatiorVConsents Air Monitoring Station 0703 10-29-87 to 11-12-87 Failure to achieve m)c due to low flow 11-12-87 to 12-17-87 rate. Sample missing due to no air flow. Gas totaliser changed out for calibration 12-14-87. Flow restored.

Air Monitoring Station 1108 11-5-87 to 11-12-87 Low flow due'to broken fan belt. Fan belt ~ replaced.

Forage at 1601 11-2-87 substituted 0201 due to lack of forage.

Air Monitoring Station 1108 11-12-87 to 12-31-87 sample missing due to broken motor pulley. New pulley ordered.

Air Monitoring Station 1601 11-19-87 to 12-31-87 sample missing duo to loss of power to t station - power cables damaged. ,

Forage at 1601 12-2-87 substituted 0201 forage plot due to lack of adequate forage.

4 8 Day sample Period 12-23-87 to 12-31-87 Work Sebedule, e 11b RC-1108 4th Quarter 1987 Destroyed by vandals. Placed tim stake  :

inside locked fence at same location. ,

TIE RI-0401 Annual 1987 Destroyed by tractor, ,

TLD RI-0801 Annual 1987 Destroyed by farm machinery.

TLD RB-1215 Annual 1987 Destroyed by vandals.

T!m RC-1104 Anuual 1987 Destroyed by vandals. Relocated 7tb ,

stake to nearby area.  ;

! TLD RC-1108 Annual 1987 Destroyed by vandals. Placed TLD stake inside locked fence at same location.

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Annual E2N Report /10 25 [

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@ p m e Oa w a w a w w w 2**O eM N4 JO MM O w v'J w O" O a> ma . O. **O. U tg

>426 O O O O 2042 3 3 OOW4 U J X f* V V V w w am u m -

e n ae eO a a a e

, he *= g e sa ** e-

+- e *=

4 M. e- M.

%0 %O N A N  %

e *- O O O *=

4 e m e

>HQm wa ws w w w w

>= 2 % O hN P= N O

    • O O w *O NM e Mw * ,

{i p W O. O. e-. O. U U U . j O

420 O O O O u42 3 3 3 OW4

> 4 UJ35 w w W V V E 3 -

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    • >2 Wa O +- Q F 23h 3 i W -O *- 4 U 4O@ Z t 20 00 e 4 _J U - O .J s42 ". O. m .

meIW4 O O A O & M da M 2N >= 3 1 3U e C O aOe 42 i 20 4 (> U2 e >

m WM O4 I w w e~~- - . h J3O J - - - -

V&*

J U O t- >* 5 4 31 M e F 0Oe 2 2 W t O e 3 eO e P- 21 4 m a3 3= LMe On >ae OOe e aA =2 e

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  • a a

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-- - .- - ~ - - - - - - - - . Oew3 M @ G e e *= C ** O E N N M M M 4 e &

OO 9 OeO O MW e O 2 M ** 3 CCCL 4 EMW 9 P- e 34e

.J W > 0 M M M *- +* E a o W 4 82 .A ek A4 P* e e M O 3- E he34E Op 4 I e 4 0CD3

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2 u a OeeO E W e M 2 3 3 >=

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  • E wwww 3 3 .J >= 3 4 e%

M I ik n e ee O >= 3 2 4 L ** u W44DW e eO 34Hw3 4-w 26

  • - ry TOBLE 1987-02 AIRBORNE: IODINE - OPERATIONAL RADIDACTIVITV $UMMARv JOSEPH M. FARLEV NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8 HOUSTON COUi4TV ALABAMA

SUMMARY

9EPORT FROM 010187 TO 123187 (A)

MEDIUM OR (TVPE AND lAL, INDICATOR INDICATOR LOCATION l COMMUNITV CONTAOL PATHaAV l TOTAL l LOCATIONS WITH HIGHEST ANNUAL MEAN l LOCATIONS LOCATION 2 SAMPLED INUM3ERS OF NOMINAL MEAN (C/D) ~~~-------~~~~~*---*------------- MEAN (C/D) MEAN (C/D)

(UNIT OF l ANALYSIS MDC(B) RANGE (C) NAME MEAN (C/D) RANGE (C) RANGE (C)

MEA 50eEMENT){ PERFORMED DISTANCE RANGE (C) i AND DIRECTION Air Iocine IIODINE 3721 196 i < MDC ( 0/166) I < MDC ( O/ 49) I < MDC ( O/157)

' (pci/m**3)

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i (A) No Nonreuttne Anomalous Measurements Reported During This Perico.

.l (B) Mean Minimum Detectable Concentration Calculateo Per Table 3 Of This Report.

'i (C) Mean and Range Of Numoer Of Measurement s wi t h Detectable Activity Only.

(D) Total Number Of Measurements Taken.

4 t

TAILE 1987-03 EXTE"'" AL RADI ATION - CPSRATIOEAL RADIOACTIVITY SUMMJCT JOSEPN M. FARLET NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8 NOUSTON COUNTY ALABAMA

SUMMARY

REPORT FROM 010187 TO 123187 (A)

MEDIUM OR lTTPE AND l lALL INDICATOR l INDICATOR LOCATION l COMh0NITY l CONTROL PATNWAT l TOTAL l l LOCATIONS l WITN NIGNEST ANNUAL MEAR { LOCATIONS l LOCATION SAMPLED l NUMBERS OF l WOMINAL lMEAN (C/D) l l MEAN (C/D) l MEAN (C/D)

(UNIT OF l ANALYSIS l MDC(B) l RANGE (C) l NAME l MEAN (C/D) l RANGE (C) l RANGE (C)

MEASUREMENT)l PERFORMED l l ] DISTANCE l RANGE (C) l l l l l lAND DIRECTION l l l TLD-Quarter l GROSS 145l 10.000 l 20.807( 63/ 63) l EAST SERIM. l 28.512( 4/ 4)l 18.058( 67/ 67) l 20.048( 15/ 15) l GAMMA l l( 9.97- 39.71) l1.0 MI. NE, l( 18.53- 39.71l( 9.63- 29.31)l( 12.19- 30.31)

(MRAD) l l l l l l l l 1 l I I I I TLD-Annual l GROSS 33l 10.000 l 67.797( 14/ 14) l EAST PERIM. l 101.110( 1/ 1)l 55.469( 16/ 16) l 67.446( 3/ 3) l GAMMA l l( 52.96- 101.11) l1.0 MI. NE l l( 47.84- 62.82)l( 60.26- 76.70)

I 1 l 1 I I I TLD-Annual-El GROSS 38l 10.000 l 81,9294 16/ 16) l EAST PERIM. l 114.050( 1/ 1)l 66.199( 18/ 18) l 15.202( 4/ 4) l GAMMA l l( 67.51- 114.05) l1.0 MI. NE l l( 25.61- 80.55)l( 66.26- 84.43) i I l l 1 I I fu (D

(A) No Nontoutine Anomalous Measurements Reported During This Period.

(B) Lower limit of Detection as defined in NASL-300, for Lir TLDs as achievable in practice.

(C) Mean and Range of Number Of Measurements with Detectable Activity Only.

(D) Total Number Of Measurements Taken.

(E) Sun Of Four Quarters For Comparative Purposes

t TABLE 1987-04 w!La - CPERATIONAL RADIOACTIVITY Sutc A R

  • JOSEPH w. FARLEW NUCLEAR 8'LANT LICENSE NOS. NPF-2 AND NPF-8 HOUSTON COUNTV ALABAwa SuwwARv REPORT FROu 010187 TO 123187 (A) wEDIUw OR l TYPE A4D l lALL INDICATOR l INDICATOR LOC
  • TION l CowwuMITY CONTROL PATHmAv l TOTAL i 1 LOCATIONS I w2TH HIGHEST ANNUAL MEAN I LOCATIONS LOCATION SAMPLED lNUMBENS OF NOMINAL lMEAN (C/D) l-----~~--------~~~~-~~----------- WEAN (C/D) WEAN (C/D)

(UNIT OF l ANALYSIS WDC(B) l RANGE (C) l NAME l MEAN (C/D) RANGE (C) RANGE (C)

WEASUREMENT) PERFORMED l DISTANCE RANGE (C)

AND DIRECTION wilm IBA-140 281 54.142 i < MOC ( O/ 1) I i i l < wDC ( O/ 27)

(pci/1)

IC5-134 281 14.107 < MDC .( O/ 1) l l l l < WDC ( O/ 27) l l l l t i i l l l l 1 lCS-137 28 .

13.714 l < wDC ( O/ 1) . I I l < MDC ( O/ 27)

I l 8 i l l I I i 1 i i 271 .259 l l l  ! i < MDC ( O/ 27)11-131 l I l i l I

, M-40 28 143.392 1460.000( 1/ 1) l PLANf ENTR. I 1460.000( 1/ 1) 1350.370( 27/ 27) i i

l l l 1 0.9 w3. wSw l $( 1200.00- 1630.00)

I I I I i LA-140 28 10.821 < MDC ( O/ 1) < wDC ( O/ 27) l

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l (A) No Noorout ine Anomalous wedsurements Reported During This Period.

(B) wenn winimum Detectable Concentration Calculated Per Table 3 Of This Report.

(C) wenn and Range Of Number Of weasurements with Detectante Activity Only.

(D) Total Nv=ber Of Measuremente Tamen.

1

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TASLE 1987-05 VEGETATION: FORAGE - ODERATIONAL RADI0 ACTIS!'s SUMMARv JOSEPH 9. FARLEY NUCLEAR PLANT sICENSE N05. NPF-2 AND hPF-8 HOUSTON COUNTv ALA8AMA

SUMMARY

REPORT FROM 010187 TO 123187 (A)

MEDIUM OR lTvPE AND lALL INDICATOR INDICATOR LOCATION l COMMUNITY ,

CONTROL PATHwAv l TOTAL l LOCATIONS WITH HIGHEST ANNUAL MEAN 1 LOCATIONS i LOCATION SAMPLED lNUM8ERS OF NOMINAL lMEAN (C/0) ---------------------------------j MEAN (C/D) i MEAN (C/D)

(UNIT OF lANALv515 MDC(B) l RANGE (C) NAME i MEAN (C/0)  ! RANGE (C) l RANGE (C)

  • MEASUREMENT)lPERFORMED l l l DISTANCE l RANGE (C) l i l l l IAND DIRECTION l l ,1 Forage (E) LAC-228 41 284.250 1 561.666( 3/ 3) 150VTH PERIM. i 83?.000( 1/ 1) l 278.000( 1/ 1) ,

(pct /mg-dry) -

( 166.00- 837.00) 1.0 MI. SSE

$8E-7 36 564.888 6262.000( 25/ 25) 1500TH PERIM. l 6226.666( 12/ 12) I 8069.4G4( it/ 1')

l ( 1500.00-17900.00) 1.0 MI. SSE l( 2070.00-17900.00 L ( 1920.00-45404.00) l I l 1 181-212 1 '1170.000 1520.000( 1/ 1) SOUTH PERIN. i 1520.000( 1/ 1)$

l l 11.0 MI. SSE l l 1 I i i i l l81-214 3 158.000 615.500( 2/ 21 l$OUTH PERIN. l 816.000( 1/ 1) i 183.000( 1/ 1) "

l 1 ( 415.00- 816.00) 11.0 MI. SSE I I I l I l 1C5-134 361 81.416 < MDC ( 0/ 25) l l < MDC ( 0/ 11) l l l I I i i

lC5-137 36 69.305 l 137.200( 5/ 25) l NORTH PERIM. l 167.333( 3/ 3)! < MDC ( 0/ 11) l .

I 1( 57.00- 339.00) 10.9 MI.NNw (F)l( 57.00- 339.00J 2$ I I l IK-40 36 605.257 13753.600( 25/ 25) NORTH PERIM. l19975.000( 4/ 4)l .

17560.000( 11/ 11)

( 1900.00-40500.00) 0.8 MI. N

( 6500.00-40500.00 ( 8290.00-30000.00) lPB-214 2 142.000 611.000( 2/ 2) SOUTH PERIM. 871.000( 1/ 1)!

! ( 351.00- 871.00) 1.0 MI. SSE i i

PB-212 5l 99.400 393.500( 4/ 4) SOUfM PERIN. 496.500( 2/ 2) 134.000( 1/ 1)

( 75.00- 886.00) 1.0 MI. SSE l( 107.00- 886.00 l

l lEA-226 1 1370.000 1 1770.000( 1/ 1) SOUTH PERIM. I 1770.000t ./ 1) l l l l 't.0 MI. SSE l I l i ITL-208 5 77.800 l 240.333( 3/ 3) -

SOUTH PERIM. 370.000( 1/ 1)' 89.000( 2/ 2)

I j ( 80.00- 370.00) 11.0 MI. SSE I l [ 85.00- 93.00) i i i i i (A) No honroutine Ano,atous Measurements Reported During Th9s Period.

(8) Mean Minimum Detectable Concentration Calculated Per Table 3 Of This Report.

(C) Mean and Range 0* Number O* Measurements with Detectable Activity Only.

(D) Total Nueber Of Measurements Taken.

(E) Mean het/ Dry Ratto for 1987 =as 2.933 (F) Subs 9tute Location Due to Unava911bity of Forage During some Sample Perlods.

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ATTACittINF i i

!.AND USE SURVEY FOR RADIOT.OGICAL ENVIRCl@GNIAL MCHI'IORING PROGWM JOSEPH M. FARLEY NUCLEAR P!JMP .

JULY 6-10, 1987 (

W is Land Use survey was performed to meet the requirements of the Farley Units 1 and 2 'I4chnical specifications, Section 3.12.2 and 4.12.2.

A. Houston County, Alabama Lamar Nichols, Houston County Livestock Agent, was contacted for the purpose of reviewing known locations of milk animals in the county.

He knew of no individual milk cows in the county. He did give information concerning a dairy owned by Mr. Ray Lewis of Avon, Alahnma.

A house-to-house canvas of Alabama residents in a five-mile radius of the plant was conducted along Highways 95 and 52, Houston County Roads 42, 33, 75 and the interconnecting light-duty roads. Milk animals were located across Highway 95 on the Calhoun property in sector 11, WSW of Farley Nuclear Plant. %ese cows had been milked in the past to provide milk for human consumption, but were not being milked at the time the census was performed. Individuals interviewed were Mr. Walter Whatley, Mr. Bobby Searcy, Mrs. Marvin T. Homes, and Mrs. Billy Ryals.

Simultaneous with the milk animal survey, the nearest resident in each meteorological sector was identified. A new residence was  :

found in Sector 14, NW of Farley Nuclear Plant, which was occupied by Billy and Lyteasa Ryals.

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 knew of no individual milk animals nor dairies in Early County.

A house-to-house canvas of residents in the area across the  :

Chattahoochee River east of Farley Nulcear Plant revealed neveral goats in sector 5, ESE. We goats were not not being milked. No milk cows were located. %e census of Georgia residents was ',

conducted along Highways 62 and 370, Early contry Roads 219, 239, 140 and the interconnecting light-duty roads. Individuals interviewed were Mr. Tony Knighton, Mr. Richardson, and Mr. Cecil Garrett.

Simultaneous with the milk animal survey, the nearest resident in f each meteorological sector was identified.

C. Results and Conclusions

) We results of the Land Use Survey are shown in Table I. Based on the survey results, milk samples will be obtained when available from the cows located across Highway 95 from Farley Nuclear Plant.

Annual ENV Report /6 39 j

TABLE I Or ATTACHMENT 1 JOSEPH M. FARLEY NUCIAAR FIANT IR C USE SURVEY JULY 1-7, 1987 (DISTANCE MILES TO NEAREST)

. RADIAL SEC1cm3 (22.5 DEGREES) RESIDENT MILA ANIMAL North Northeast (01) 2.5 >5

< Northeast (02) 2.4 >5 East Northeast (03) 2.4 >5 East (04) 2.8 >5 ,

East Southeast (05) 2.0 >5 Southeast (06) 3.4 >5 South Southeast (07) >5 >5 t

SrAith (03) 4.3 >5 South Southwest (09) 2.9 >5 southwest (10) 1.2 >5 West Southwest (11) 2.4 1.0 West (12) 1.3 >5 West Northwest (13) 2.1 >5 Northwest (14) 1.5 >5 ,

North Northwest (15) 2.0 >5 .

North (16) 2.6 >5 I

I f

I f

i Annual DN Report /6 40

. Alabama Power Company 1 NT 88-0199 c

6 600 North 18th Strxt Post Office Box 2641 Birmingham, Alabama 35291-0400 3 Telephone 205 250-1835 R. P. Mcdonald Senior Vice President Alabama Power tre southern ekctrc system April 26, 1988 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C. 20555 RE: Joseph M. Farley Nuclear Plant Annual Environmental Operating Report Gentlemen:

'Ihe atte..hed "Annual Environmental Operating Report, Part B:

Radiological" ?or the period January 1, 1987 through December 31, 1987, is transmitte.,in accordance with the Joseph M. Earley 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 truly, l .

R. P. Mcdonald RPM /NAT:emb Attachment cc: Dr. J. N. Grace U. S. Nuclear Regulatory Comission Mr. W. H. Bradford Mr. E. A. Reeves U. S. Nuclear Regulatory Comission Director, Bureau of Radiological Health State of Alabama Director, Environmental Protection Division State of Georgia

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