ML20245F530

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Annual Environ Operating Rept,Part B: Radiological,1988
ML20245F530
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/31/1988
From: Woodard J
ALABAMA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905020414
Download: ML20245F530 (45)


Text

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ALABAMA POWER CCMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO. 1 LICENSE NO. NPF-2 AND UNIT NO. 2 .

LICENSE NO. NPF-8 PERIOD ENDING DECEMBER 31, 1988 8905020414 881231  ?

PDR ADOCK 0500034sy R PNU; ENV Annual Report /2 es

i ANNUAL ENVIRONMENTAL OPERATING REPORT l PART B: RADIOLOGICAL 1'

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

ENV Annual Report /2

RADIOLOGICAL ENVIROf@iENTAL OPERATING REPORT LIST OF FIGURES Figure Title Page 3.12-1 Indicator Sampling Locations for Airborne 9 Environmental Radioactivity at the Farley Nuclear Plant.

3.12-2 Community (Indicator II) Sampling Locations for- 10 Direct Radiation b the Parley Nuclear Plant Area.

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

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

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l RADIOLOGICAL ENVIRONMENTAL OPERATItK3 REPORT LIST OF TABLES Table Title Page 1 Scope of Operational Radiological Environmental 13 Monitoring Program at the Farley Nuclear Plant During 1988 2 Outline of Operational Radiological Environmental 14 Monitoring Program for Farley Nuclear Plant During 1988 3 Detection Capabilities for En"ironmental Sample 19 Analysis for Farley Nuclear Plant 4 Reporting Levels for Radioactivity Concentrations 21 in Environmental Samples 5 Sampling and Analysis Deviations During 1988 22 1988-01 Airborne: Particulate - Operational Radioactivity 25 Summary 1988-02 Airborne: Iodine - Operational Radioactivity 26 Summary 1988-03 External Radiation - Operational Radioactivity 27 Summary 1988-04 Milk - Operational Radioactivity Summary 28 1988-05 Vegetation: Forage - Operational Radioactivity 29 Surr..ary 1988-06 Soil - Operational Radioactivity Summary 30 1988-07 Waterborne: Surface Water - Operational 31 Radioactivity Summary 1988-08 Waterborne: Ground Water - Operational 32 Radioactivity Summary iii ENV Annual Report /2

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES CONTINUED Table- Title Page 1988-09 Sediment: River - Operational Radioactivity 34 Summary 1988-10 Fish: River (Game) - Operational Radioactivity 35 Summary 1988-11 Fish: River (Bottom Feeding) - Operational 36 Radioactivity Sunnary 4

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RADIOLOGICAL DNIRONMENTAL OPERATING REPORT LIST OF ATTACHMENTS Attachment Title Page 1 Land Use Survey for Radiological Environmental 37 Monitoring Program, Joseph M. Farley Nuclear Plant, July 11-15, 1988 4

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1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 I. Introduction The Joseph M. Farley 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 bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a rated power output of 860 megawatts electrical (MWe) achieved initial criticality on August 9, 1977. The unit was declared "comercial" on December 1, 1977. Unit No. 2, al a a 860 MWe Westinghouse PWR, achieved initial criticality on May 8, 1981 and was declared

" commercial" on July 30, 1981.

During 1988, Unit I was off-line from March 26, 1988 to May 21, 1988 for the eighth refueling outage. Unit II remained in service the entire year of 1988.

The 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 1988 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. This program was designed to monitor any radioactivity contribution to the environment from the plant through either the airborne or waterberne pathways. The type of samples monitored, and number and type of sampling stations are shown in Table 1. Indicater 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 j' sanples collected should provide a significant indication of potential doce to man, and where an adequate comparison of predicted radiological levels might be made with measured levels.

The 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 i radioactivity samples, community stations are located at the principal population centers between the indicator and the control stations (3-8 miles). Community stations could be used, if desired, as additional control stations, and alternatively, as indicator stations for the nearest population centers in the event of a major airborne release from the plant.

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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.

The samples were collected by APCo's technical staff except for the in situ high purity germanium (HP(Ge)) gamma-ray spectroscopy EUasurements of soil. The latter were made by staff members of the University of Georgia (UGA), Center for Applied Isotope Studies. All sample analyses were contracted to UGA. The minimum detectable concentration (MDC), specified for the various samples and their respective analyses are given in Table 3. The reporting levels for radioactivity concentrations in environmental samples are provided in Table 4. Sampling and analysis deviations during 1988 are listed in Table 5.

A. Airborne Particulate and Iodine All airborne particulate and iodine monitoring stations shown in Figures 3.12-1 througn 3.12-3 were equipped with Roots vacuum pumps 0.04 m p/ min (1.5 ft / min).ichoperatepcontinuouslyataflowrateofapproximately The particulate were collected on Gelman Metricel Sum filters. In series with, but downstream of the particulate filters, F&J 50 mm (or equivalent) activated charcoal cartridges were used for collection of iodine. The Roots system has the sample collector mounted outside of the cabinet horizontally to the ground with a Singer gas meter neasuring 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 OGA for radioactivity analysis.

Gross beta radioactivity measurements vere performed on each i air particulate filter using a Tennelec low backgrcund l alpha-beta counting system. The filters from each station, composited bt the end of each quarter, were analyzed for gamma q emitters using a fifteen pe cent relative efficiency low J background yermanium lithium (Ge(Li)) detector and a Canberra )

4096 channel computer-based multichannel analyzer (MCA). J 1

All air monitoring station locations shown in Figures 3.12-1 j through 3.12-3 have the capability of monitoring airborne j 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. l 1

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B. External Radiation For the continuous measurement of environmental gama radiation, natural Lithium Fluoride (LiF) (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, and which had a low p ss attenuation for 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 packecs, one changed and read quarterly and one changed and read annually, were exposed side-by-side on metal stakes at a height of one meter above the ground. For the computation of the net field doses, a log of all exposure periods was maintained for each TLD packet.

C. Milk The milk sample location is as indicated on Figure 3.12-3. 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 (Thimerasol) solution was added to each one gallon sample. The I-131 concentration in each sample was determined by collection on anion exchange resin, elution with sodium hypochlorite, followed by organic extraction and counting, by beta-gamma coincidence, the resultant toluene-iodine solution in a low level liquid scintillation counter. Stable iodine carrier was added to each sample for determination of the radiochemical yield.

A one liter quantity of each sample was placed in a marinelli beaker and then analyzed for gamma emitters using a 15 percent telative 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, Alabama. After drying and ,

pulverizing, the samples were analyzed by UGA for gamma l emitters using a 15 percent relative efficiency low background i Ge(Li) detector and a Canberra 4096 channel computer-based MCA.

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E. Soil Annual in situ gamma-ray spectroscopy measurements were made by UGA usiF 3 a ID percent relative efficiency high purity germanium detector and gamma-ray spectroscopy system specially designed for field use. Measurements were taken at the seven indicator locations and at the 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 (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. Two liter aliquots from each monthly composite were placed in trays lined with plastic film and evaporated to dryness at 100'C. The residue (on plastic film) was folded to fit a petri-dish and analyzed for gamma emitters using a 15 percent relative efficiency Ge(Li) 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 ml from each quarterly composite sample was distilled and a 25 ml aliquot taken for tritium analysis using a large volune (100 ml)

Hewlett-Packard 200 low background liquid scintillation counter.

G. Ground (Well) Water In the Parley Plant area there are no true indicator sources of groundwater. A well which serves Great Southern Paper Company as a source of potable water, lecated 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 (on plastic 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 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 gamma-ray spectroscopy analysis. Both semi-annual fish samples sent to UCA consisted of fish fillets that had been split with Alabama Bureau of Radiological Health. These fish samples were coarsely chopped at UGA and were analyzed for gama emitters using a 15 pe:'cer.t 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 kilogram 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 D_iscussion No known atmospheric nuclear tests were conducted during 1988.

Identifiable radioactivity effects from the last test conducted by the Peoples Republfc of China on October 16, 1980, were minimally existent during 1988. No radiological effects from the Chernobyl Nuclear Power Plant accident in the U.S.S.R. on April 26, 1986, were evidenced in 1988.

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 j measurement systems which denote a limiting detection capability I 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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J A. Airborne Particulate The results of the radioactivity analyses of airborne 1 particulate filters are shown in Table 1988-01. The mean l gross bet'a activity values for the air particulate indicator j and cont =41 sampling locations were lower than the community sampling locations. The gross beta activity nean for all locations was lower than in 1987 and the preoperational l period.

The gross beta and gamma spectroscopy data for the air particulate filter composites showed Cs-134 and I-131 below MDC at all sampling locations. Cs-137 was detected at community sampling locations but at levels less than in 1987.

B. Airborne Iodine The results of the radioactivity analyses of iodine charcoal cartridges are shown in Table 1988-02. The iodine activity for 1988 samples at all locations was less than the minimum '.

detectable concentration values.

C. External Radiation The results of the external radiation measurements using TLD packets are shown in Table 1988-03. As found during the preoperational period and during 1987, the data reflect the differences in site specific soil radioactivity. Exposures recordea by quarterly TLDs in 1988 were comparable to those recorded in 1987 for indicator, community and control sampling locatioas. The exposures recorded by annual TLDs in 1988 were lower than that observed in 1987 but greater than during the preoperational period. Also evident in 1988 as in previous years, the exposures recorded by annual TLDs were less than the sum of the exposures from the associated quarterly TLDs.

D. Milk The results from the radioactivity analyses of milk are shown in Table 1988-04. Milk from the Lewis Dairy was sampled as j the control location. There were no indicator samples during 1988. Only naturally occurring radioactive isotopes were detected in control samples.

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1 E. Vegetation Forage was the only vegetation sampled during 1988. The radioactivity analysis results are shown in Table 1988-05.

Forage, as during the preoperational period, continued to be a very effective and sensitive indicator of airborne radioactivity. Traces of Cs-137 were found in some indicator and control samples; however, the indicator values were lower than in 1987. The data for 1988 indicated fewer fission product radionuclides than the preoperational data.

F. Soil The results of the in situ HP(Ge) gamma-ray spectroscopy analysis of soil duH ng this operational period are shown in Table 1988-06. The 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 1988 levels of Cs-137 found at indicator locations were not significantly different from control locations and were lower than the 1987 levels and the prennerational levels.

G. Waterborne Activity (Surface Water) l The results of radioactivity analysis of surface water are shown in Table 1968-07. Cs-134 activity levels were below the measured MDC values. Cs-137 was detected in one indicator sample in 1988; however, this value was also less than the 1987 and preoperational data.

The average surface water indicator tritium level was higher than the control but approximately the same as in 1987. As in i previous years, surface water tritium was again higher than that observed during the preoperational period. ,

H. Wahrborne Activity (Ground Water)

The results of the radioactivity analysis of ground water are shown in Table 1988-08. The Cs-134, Cs-137, and I-131 activity values were less than MDC aC observed in 1987 and lower than the preoperational data.

I. River Sediment The results of radioactivity analysis of sediment samples from the Chattahoochee River are shown in Table 1988-09. There were no manmade isotopes detected in any sediment sample.

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The results of gamma-ray spectroscopy analysis of the edible portions of game fish taken from the Chattahoochee River are shown in Table 1988-10. 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. 'Ihe 1988 average indicator and control Cs-137 values were found to be lower than 1987 data and lower than the preoperational data.

h. Bottom Feeding Fish (River)

The results of gamma-ray spectroscopy analysis of the edible portions of bottom feeding fish taken from the Chattahoochee River are shown in Table 1988-11. Cs-137 was found at low levels in both indicator and control samples of bottom-feeding fish. The indicator Cs-137 level was slightly higher than the control value. The 1988 Cs-137 levels for both sampling locations were higher than 1987 but lower than the preoperational period.

IV. Land Use Census and Interlaboratory Comparison Program A. Land Use Census The results of the July, 1988, Land Use Census are given in Attachment 1 to this report. ,

1 B. Interlaboratory Comparison Program During 1988, the University of Georgia Center for Applied Isotop Studies (UGA) was a participant in the EPA Crosscheck Program. The UGA EPA Program code designation is EA. Although Farley Nuclear Plant (FNP) also participates in the EPA Crosschack Program mder code designation FU, only TLD analyses were performed by FNP.

V. Data Trends and Conclusion A review of the 1988 environmental data indicate some changes in <

the parameters monitored when compared to 1987 data. Slight increases of Cs-137 in fish were indicated. Cs-137 levels, though slightly higher than in 1987, were lower than the preoperational I values. The external gamma radiation values were comparable to j 1987 TLD measurements. Either no change or decreases were 1 indicated in air particulate, milk, vegetation, soil, water, and  !

sediment. Therefore, data obtained during the 1988 sampling year demonstrate that there was no significant adverse impact on the surrounding environs of Farley Nuclear Plant as a result of its i '

operation.

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TABLE 1 EMPE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL I MONITORING PROGRAM AT THE FARLEY NUCLEAR PLANT DURING 1988 Principal Type of Number of Sampling Stations Pathway Samples Indicator Community Control Airborne Particulate 3 -3 3 Airborne Iodine 3 1- 3 External Radiation 16 18 4 Airborne Milk - -

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

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  • ' 'd TABLE 3 (con'd)

Ihe 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 (-Aot)

Where:

MDC is the "a priori" lower limit of detection as defined above (as picoeurie per unit mass or volume).

S is the standard deviation of the background counting rate or oIthecountingrate_ofablanksampleasappropriate(ascounts per minute).

E is the counting efficiency (as counts per transformation).

V is the sample size (in units of mass or volume).

2.22 is the number of transformations per minute per picoeurie.

Y is the fractional radiochemical yield (when applicable).

A is the. radioactive decay constant for the particular radionuclides.

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 radionuclides 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 gamma-ray spectroscopy actual sample backgrounds were used (A Posteriori).

"MDC for drinking water.

l.

20 Page 2 of 2

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TABLE 5 SAMPLING AND ANALYSIS DEVIATIONS DURING 1988 Component Time Period Reason for Deviation / Comments Forage at.1601 1/6/88 Obtained forage from sector 0201 due to unavailability of forage at 1601.

Air Monitoring Station 12/31/87-1/21/88 Low air flow due to station's 1601 power cables being severed during road construction. Power restored 1/24/88.

Air Monitoring Station 12/31/87-3/10/88 Air sample missing due to a broken 1108 motor pulley and bushing. Pulley

, and bushing replaced 3/7/88.

Forage at 1601 2/.8/88 Forage obtained from 0201 forage plot due to unavailability of forage at 1601.

TLD RC-0504 1st Quarter 1988 TLD missing due to vandalism.

Air Monitoring Station 4/14/88-4/21/88 Low air volume due to failed pump.

1218 Pump pulley and new fan belt replaced 4/29/88.

4/21/88-4/28/88 Sample missing due to failed pump.

Pump pulley and fan belt replaced 4/29/88.

A'r Monitoring Station 4/28,'88-6/9/88 Low air volume and failure to 0601 achieve iodine MDC due to failed pump and fan belt. Pump replaced 5/25/88. Fan belt replaced 6/3/88.

Air Monitoring Station 6/9/88-6/16/88 Sample missing due to tripped 0501 electrical breaker. Breaker reset.

TLD RC-1104 2nd Quarter 1988 TLD missing due to vandalism.

22 Annual LNV Report /11

4 i

Air Monitoring Station 6/16/88-8/11/88 . Sample missing due to faulty 0501 flow meter. Flow meter replaced 8/12/88.

Air Monitoring Station 7/7/88-7/14/88 Low air volume due to low air flow.  !

- 1605 Leaf was adhered to filter and obstructed air flow.

Air Monitoring Station 7/21/88-7/28/88 Low air volume due to decreased air

1605 flow. Flow adjusted to 90 cfh.

Air Monitoring Station 7/21/88-7/28/88 Sample missing due to filter being 1108 swept away by wind.

Air Monitoring Station 7/28/88-8/4/88 Low air flow due to failed motor.

- 0718 Motor replaced 7/30/88.

Air Monitoring Station 8/18/88-8/25/88 Low air volume due to failed motor 1108 and fan belt. Motor and belt replaced 8/19/88.

Air Monitoring Station 8/18/88-8/25/88 Low air flow due to oil leakage from 0501 pump. Pump replaced 8/21/88.

- Air Monitoring Station 8/25/88-9/29/88 Low air volume due to failed pump.

1605 Pump replaced 9/23/88.

Air' Monitoring Station 10/20/88-10/27/88 Sample missing due to failed pump, 1218 fan belt, and air totalizer. Totalizer replaced 10/17/88. Pump and belt replaced 10/25/88.

Air Monitoring Station 10/20/88-10/27/88 Low air volume due to heavily 0703 clogged filter.

Air Monitoring Station 11/23/88-12/8/88 Low air volume due to failed 0215 motor. Motor, fan belt, and fuse replaced 12/5/88.

Air Charcoal I-131 11/23/88-12/8/88 MDC not achieved due to low air 0215 volume as a result of failed motor.

Motor, fan belt, and fuse replaced 12/5/88.

i Annual ENV Report /11 23

.______s__w ______.___._u__--_,._ _ ___,__ __ _ _ _ _ _ u_ .__ . _ . _ __ _.___, _ _ . _ _ _ _-_ _. _ _ _ _ _ _ _ , _ _ _ _ _ _

l-l:

Air ~ Monitoring Station Sample missing due to electrical 12/15/88-12/29/88 0701- power cable being cut.during road construction.

TLD RC-0504 1/1/88-12/31/88 Annual TLDs missing due to TLD RC-1104 vandalism.-

TLD RB-1215 Annual ENV Report /11 24

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A'ITACHMENT 1 LAND USE SURVEY FOR RADIOLOGICAL ENVIRONMENTAL MONI'IORING PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT JULY 11-15, 1908 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 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 milk goats owned by Mr. Thomas Dean of Gordon, AL. The residence is located in sector 08, 6 miles from l FNP.

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. No milk animals were located. Individuals interviewed were: Mr. Walter Whatley, Mr. Bobby Se3rcy, Mrs. Marvin T. Homes, Mrs. Jerry Carpenter, and Mrs. Ezzie Respress.

Simultaneous with the milk animal survey, the nearest resident in each meteorological sector was identified. No new residences were found.

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 Nuclear Plant revealed several goats in Sectors 5, ESE & 6, SE. The goats were not being milked.

There were no milk cows located. The census of Georgia residents  !

was conducted along Highways 62 and 370, Early County Roads 219, j 239, 140 and the interconnecting light-duty roads. Individuals j interviewed were Mr. Tony Knighton and Mr. Cecil Richardson. i I

Simultaneous with the milk animal survey, the nearest resident in i each meteorological sector was identified. No new residences were found.

C. Results and Conclusior.s l l

The results of the Land Use Survey are shown in Table 1. The survey located milk goats 6 miles from FNP; however, no action is required for animals located outside a 5 mile radius. Therefore, based on the survey results, no change in the present milk sampling program is required.

Annual a:W Report /6 37

A % 1, ,.

TABLE 1 or ATTACHMENT 1 l

JOSEPH M. FARLEY NUCLEAR PLANT LAND USE SURVEY JULY 11-15, 1988 (DISTANCE MILES 'IO NEAREST)

RADIAL SEC'IORS (22.5 DEGREES) RESIDENT MILK 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) 2.8 >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) 2.4 >5 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

Annual DN Report /6 38

-_ - - _ - - - - . - - _ - - - - - - - - - - - - - _ - - - - - . - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

i

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i.edY Post f ox 95 Birrrungham, Alabama 35201

, Telephone 205 668 5086 m

~ J. D. Woodard AlD[)Dllla Power Vice Presdent-Noclear Farley Proect n tre southern okctnc system April 28,1989 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 JOSEPH M. FARLEY NUCLEAR PLANT - UNITS 1 AND 2 ANNUAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL Gentlemen:

ine attached " Annual Environmental Operating Report, Part B: Radiological" for the period January 1, 1988 through December 31, 1988, 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 contact our office.

Sincerely, i

jf

'ddar av&

JDW:DMH/db Attachment cc: U. S. Nuclear Reaulatory Commission Mr. S. D. Ebneter Mr. G. F. Maxwell Mr. E. A. Reeves State of Alabama Director, Bureau of Radiological Health State of Georoia Director, Environmental Protection Division [} I

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