ML20107M109

Jm Farley Nuclear Plant,Radiological Environ Operating Rept for 1995

ML20107M109
Person / Time
Site:	Farley
Issue date:	12/31/1995
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604300199
Download: ML20107M109 (38)

Text

1 Southern Nucitar Op ratin0 Company Post Offics Box 1295 Birmingham, Alabama 35201

, Tiliphons (205) 868 5131 o ,,, ,,,,, Southern Nudear Operating Company YarIeINNec"t April 22, 1996 the southem electnc system Docket Nos. 50-348  !

50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant <

Radioloaical Environmental Ooeratina Report for 1995 l Gentlemen:

The enclosed " Radiological Environmental Operating Report for 1995",

is transmitted in accordance with the Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 Technical Specifications Section 6.9.1.6 and 6.9.1.7.

If you have any questions, please advise.

Respectfully submitted, f U Dave Morey DM/WHO ENV-96-083

Enclosures:

Subject Report cc: U. S. Nuclear Reaulatory Commission. Washinoton. D. C.

S. D. Ebneter, Regional Manager G. F. Maxwell, Senior Resident Inspector State of Alabama Director, Division of Radiation Control 3000M

. s ,

9604300199 951231  ;

PDR ADOCK 05000340 g PDR

ALABAMA POWER COMPANY RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 1995 JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO.1 LICENSE NO. NPF-2 AND UNIT NO. 2 LICENSE NO. NPF-8 l

I 1

l

• I 1

TABLE OF CONTENTS SECTION TITLE EAOL I INTRODUCTION 1 11 PROGRAM DESCRIPTION 1 Ill LABORATORY ANALYSIS RESULTS 5 IV OTHER ACTIVITIES 10 V CONCLUSIONS 10 i

1 4

LIST OF FIGURES Figure Iitle 1 Indicator Stations for Monitoring Gaseous Releases

] 2 Community (Indicator II) Stations for Monitoring Gaseous Releases

.i

, 3 Control Stations for Monitoring Gaseous Releases

4 Indicator and Control Stations for Monitoring Liquid Releases i

l .

)

i e t i

i 4

1

{

l d

J 4

j ii

l LIST OF TABLES Table Iille i Outline of Operational Radiological Environmental Monitoring Program for Farley Nuclear Plant During 1995 l

2 Environmental Monitoring Program Deviaaons 1995 l 3 Radiological Environmental Monitoring Program Summary for 1995 l

l l

l 1

1 l

l l

iii

LISTOF ATTACllMENTS f

Attachment Sub,iect I Joseph M. Farley Nuclear Plant, Land Use Census and Milk Animal Survey 4

4 1

i I

l 4

iv

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

l l ACRONYMS A2LA American Association of Laboratory Accreditation APC0 Alabama Power Company ASTM American Society for Testing and Materials CL Confidence Level

EL Environmental Laboratory 1

I

[ EPA Environmental Protection Agency i

I

FNP Joseph M. Farley Nuclear Plant

! ISCO Instrument Specialties Company l

MDC Minimum Detectable Concentration j j

MDD Minimum Detectable Difference MWe Megawatt electric NA Not Applicable NDM No Detectable Measurement (s)

NRC 'tJuclear Regulatory Commission ODCM Offsite Dose Calculation Manual PWR Pressurized Water Reactor REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SAIC Science Applications International Corporation TLD Thermoluminescent Dosimeter TS Technical Specifications y

1. INTRODUCTION The Radiological Environmental Monitoring Program (REMP) for the Joscph M. Farley Nuclear Plant (FNP) is conducted in accordance with Technical Specifications (TS) 6.8.3.f and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). He REMP activities for 1995 are reported herein in accordance w:th TS 6.9.1.6 and 6.9.1.7, and ODCM 7.1. All dates in this report are for 1995 unless otherwise indicated.

FNP is owned by Alabama Power Company (APCo) and operated by Southern Nuclear Operating Company. It is located in Houston County, Alabama 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 1 megawatts electric (MWe) achieved initial criticality on August 9,1977 and was declared  !

" commercial" on December 1,1977. Unit 2, also a 860 MWe Westinghouse PWR, achieved initial criticality on May 8,1981 and was declared " commercial" on July 30,1981. ,

Unit 2 was shutdown for its tenth refueling outage from Mr.rch 11 through April 27. Unit I was shutdown for its thirteenth refueJng outage from September 16 through November 4.

A description of the REMP - the locations for sampling, the samples to be analyzed, the sampling equipment and how the analyses are performed - is provided in Section II. The laboratory analysis results are discussed in Section III. Other REMP activities are presented in Section IV. Conclusions are provided in Section V.

II. PROGRAM DESCRIPTION i The objectives of the REMP are to ascertain the levels of radiation and concentrations of radioactivity in the environs of FNP and to assess any radiological impact upon the environment due to plant operation.

l The bases for such an assessment include appropriate comparisons between the results of the j i radiological analysis of envire .mtal samples obtained at control stations (locations where

radiological levels are not expected to be significantly affected by plant operation, i.e. at  ;

background levels) with those at indicator stations (locations where it is anticipated that )

l radiological levels are more likely to be affected by plant operation, such as, the plant perimeter),

i and comparisons between results obtained during preoperation with those obtained during operation. Samples are also collected at several community stations (locations of population centers between the indicator and the control stations or at locations of special interest).

i A summary description of the REMP is provided in Table 1. This table portrays the program in i the manner by which it is being regularly carried out. Table I summarizes the programs 4

requirements as outlined in ODCM Table 4-1 by detailing the sample types for n-nitoring the airborne, direct radiation, waterborne and ingestion pathways and delineating the collection and

analysis frequencies. Table 1 also describes the locations of the indicator, community and control stations as spelled out in ODCM Table 4-4. The sampling locations are also depicted on

! maps in Figures 1 through 4.

i To identify the locations of environmental monitoring stations which monitor gaseous releases, the area surrounding FNP is divided into 16 radial sectors which are centered on the major compass points and whose origin is the point midway between the Unit I and Unit 11 plant vent stacks. Each sector is numbered sequentially clockwise and oriented so that the centerline of d

1 r y .- . - - - - - - -_

w . - _ -

sector 16 is due north. Each sampling point is identified by a four digit number. The first two digits indicate the sector number, and the last two digits indicate the distance to the nearest mile from the origin. For example, TLD station 0304 is located 4 miles east northeast of the origin.

The locations for the sampling stations along the river are identified by the nearest River Mile (RM) which is the distance along the navigable portion of the river upstream of the Jim Woodruff Dam near Chattahoochee, Florida. The approximate location of the plant intake structure is RM 44.

In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule as set forth in Table 1 are permitted if samples are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or otherjust reasons. All program deviations are listed in Table 2.

The samples are collected by the plant's technical staff except for fish and river sediment samples which are collected by APCo Environmental Field Services personnel. All sample analyses are contracted to the Georgia Power Company's Environmental Laboratory (EL) in Smyrna, Georgia; in 1994, the EL replaced the University of Georgia for this task. Since 1987, the EL has been accredited by the American Association of Laboratory Accreditation (A2LA) for radiochemistry. The A2LA is a nonprofit, nongovernmental, public service, membership society dedicated to the fonnal recognition of competent laboratories and related activities.

Accreditation is based upon internationally accepted criteria for laboratory competence.

(ISO /IEC Guide 25,1990, " General Requirements for the Competence of Calibration and Testing Laboratories")

A. Airborne Particulates and Iodine The airborne particulate and iodine monitoring stations are equipped with FN-210B air samplers manufactured by Science Applications International Corporation (SAIC). Each air sampler is a modular unit consisting of a sample pump, regulator valve assembly, a i microprocessor based air volume totalizer, an open faced combination filter holder and a thermostatically controlled exhaust fan, all mounted in a ventilated aluminum weather house.

In March 1993, electrical surge protectors were installed on all air monitoring stations. A 47 millimeter particulate filter and a 50 millimeter F&J activated charcoal cartridge are installed in separate compartments of the combination filter holder, which is mounted vertically on the pump suction. In September 1993, the Gelman VM 1 Metricel membrane particulate filters l which had been used since 1977 were replaced with Gelman A/E glass fiber filters.

Sampled air flows vertically from top to bottom, first through the particulate filter, then through the charcoal cartridge. To compensate for dust buildup on the sample filters, the regulator valve assembly, located downstream of the combination filter holder, maintains a constant sample flowrate over a wide range of pressure differentials across the filters. The design of the filter holder allows uniform distribution of sampled airborne particulates over the entire filter disk. The totalizers are calibrated using the SAIC Model C-812 calibrator.

Charcoal cartridges and/or particulate filters are collected weekly at 4 indicator,3 community and 3 control stations as shown in Figures 1,2 and 3, respectively. Gross beta radioactivity measurements are performed on each air particulate filter using a low background gas flow proportional counting system. A gamma isotopic analysis is performed quarterly on a composite of the particulate filters for each station using either a twenty percent or forty percent relative efficiency EG & G Ortec intrinsic germanium detector system. The charcoal filters are analyzed for 1-131 using the same germanium detector system.

2

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

b

, B. Direct Radiation

. Direct (external) radiation is measured utilizing Panasonic UD-814 thermoluminescent dosimeters (TLDs) and a Panasonic UD-710A reader. Each TLD badge contains 3 phosphors

which are composed of calcium sulfate (with thulium impurity) crystals and are encased in 860 2 2 mg/cm of plastic and lead. Each badge is sealed in a 10 mg/cm plastic bag to protect it from j moisture while in the field. On the plant site, all TLD packets which are not in the field are 3 kept in a lead safe with 2-inch walls.

j The 16 TLD stations shown in Figure 1, located near the plant perimeter in each of the radial sectors are designated as the indicator stations. The community stations shown in Figure 2 consist of the 16 TLD locations in each sector at approximate distances between 3 and 5 miles, I plus 2 special interest areas (the nearest occupied residence and the City of Ashford). Each of the 6 control stations shown in Figure 3 are more than 10 miles from the plant.

, At each TLD station, two TLD badges are exposed side-by side on metal stakes at a height of j one meter above the ground. For the computation of the net field doses, a log of all exposure -;

periods is maintained for each TLD packet. l

C. Milk A milk sample is collected biweekly from one control station, the Ivey Dairy (Green Valley j Farms) in Webb, Alabama which is located about 12 miles west of the plant as shown in Figure i

3. This station replaced the Lewis Dairy in February 1994. As borne out by the results of the i land use census, no indicator stations for milk are available. The samples are kept at a low temperature and shipped to the EL via overnight express. Chemical preservatives stopped being added to the samples in November 1994. Gamma isotopic and I-131 analyses are performed on each sample.

The I-131 concentration in each sample is determined by collection on anion exchange resin, elution with sodium perchlorate, followed by precipitation as silver iodide and counting on a beta-gamma coincidence counter or the low background gas flow proportional counter. Stable iodide carrier is added to each sample for determination of the radiochemical yield. The concentration of stable iodine present in the sample before carrier addition is also determined and accounted for in the chemical yield determination. One liter of each sample is placed in a marinelli beaker and analyzed for gamma emitters using the germanium detector system. ,

l D. Forage -

Forage samples are collected monthly from 3 grass plots, each of which is located adjacent to an air sampling station. The 2 indicator locations are on the plant perimeter as shown in Figure I and the control location is in Dothan about 18 miles west of the plant as shown in Figure 3.

After the samples are chopped to a smaller size and mixed well,200g aliquots are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system. j i

E. Ground Water i

In the FNP environs, there are no true indicator sources of ground water. A well which serves Georgia Pacific Paper Company as a source of potable water, located on the east bank of the 3

i '

j Chattahoochee River about four miles south-southeast of the plant, is designated as the indicator station. A deep well which supplies water to the Whatley residence located about 1.2 miles southwest of the plant is designated as the control station. Samples are collected quarterly from each of these stations.

Tritium, gamma isotopic and 1-131 analyses are performed on each sample. The tritium and gamma isotopic analyses are done in the same manner as described below for surface water.

The low level 1-131 analysis is performed by precipitating one liter of sample as palladium iodide and counting the final palladium iodide precipitate on a beta-gamma coincidence counter or the low background gas flow proportional counter, i

F. Surface Water l

[ Samples of water are collected from the Chattahoochee River at locations about 3 miles

upstream and 3 miles downstream of the plant as shown in Figure 4. The collections are made j on a semi-continuous basis with ISCO (Instrumentation Specialties Company) samplers. For

] each 28-day surveillance interval, one liter of each week's indicator and control samples are i'

combined to make 4-liter composite samples. One liter of each sample is placed in a marinelli beaker and analyzed for gamma emitters using the germanium detector system.

For each calendar quarter,75 ml of each week's indicator and control samples are combined separately to make a 975 ml composite sample for each of these stations. An aliquot of each of these samples is distilled after mixing with sodium hydroxide and potassium permanganate, a liquid scintillation cocktail is then added and the analysis for tritium is conducted on a Beckman LS7800 Liquid Scintillation Counter employing the appropriate window setting and optimized sample size.

G. Fish Two types of fish, bottom feeding and game, are collected semiannually from the Chattahoochee River at a control location which is several miles upstream of the plant and at an indicator location which is a few miles downstream of the plant. These locations are shown in Figure 4. A gamma isotopic analysis is performed on the edible portions of each sample. Af ter the fillets from each sample are chopped to a smaller size and mixed well,450 gram aliquots are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system.

11. River Sediment Sediment samples are collected semiannually from the shoreline of the Chattahoochee River at the same approximate locations as described above for the fish samples. A gamma isotopic analysis is performed on each sample. After approximately one kilogram of each sample is dried, ground and well mixed,450 gram aliquots are placed in 0.45 liter marinelli beakers and analyzed for gamma emitters using the germanium detector system.

I 4

1 j -

I 1

l

! l l 111. LABORATORY ANALYSIS RESULTS  ;

In accordance with ODCM 7.1.2.1, summarized and tabulated results of the laboratory analyses

for all of the regular samples collected for the year at the designated indicator, community and j control stations are presented in Table 3 in a format similar to that found in Table 3 of the Nuclear Regulatory Commission (NRC) Radiological Assessment Branch Technical Position, Revision 1, November 1979. Since no reportable occurrences were called for during the year,

the column entitled " Number of Reportable Occurrences" has been excluded from Table 3.

u j In accordance with ODCM 4.1.1.2.2, only the naturally occurring radionuclides which are found in the plant's effluent releases need be reported. The radionuclide, Be-7, which occurs abundantly in nature is also produced in the FNP reactors. Minuscule quantities are found in the

liquid releases. No other naturally occurring radionuclides are found in the plant's effluent releases. Hence, the radionuclides ofinterest for the samples monitoring liquid releases (surface water, fish and river sedi;nent) are man-made radionuclides plus Be-7, while only man-made

,l radionuclides are ofinterest for the other REMP samples. During 1995, Be-7 was not detected in

any of the samples monitoring liquid releases.

i j An interpretation and evaluation, as appropriate, of the laboratory results for each type sample

are included in this section. Relevant comparisons are made between the difference in average values for different station groups (such as the indicator and control stations or the indicator and l community stations) and the calculated Minimum Detectable Difference (MDD) between these j two groups at the 99 percent Confidence Level (CL). The MDD is determined using the standard Student's t-test. A difference in the average values which is less than the MDD is considered to be statistically indiscernible.

i '

Pertinent results are also compared with past results including those obtained during i preoperation. The results are examined to perceive any trends. To provide perspective, a result might also be compared with its Reporting Level (RL) or Minimum Detectable Concentration

. (MDC) whose nominal values are found in ODCM Tables 4-2 and 4-3, respectively. During the 1

year there were no failures in the laboratory analyses for any of the sr.mples in attaining the MDCs required by ODCM Table 4-3.

j All results are tested for conformance to Chauvenet's Criterion (G. D. Chase and J. L.

Rabinowetz, Princioles of Radioisotope Methodology, Burgess Publishing Company,1962 pages 87-90) to flag any values which might differ from the others in its set by a relatively large amount. Identified outliers are investigated to determine reason (s) for deviation from the norm, If the deviation is due to an equipment malfunction or other valid physical reason, the anomalous

. result is deemed non-representative and excluded from the data set. No datum is excluded for failing Chauvenet's Criterion only. Any exclusions are discussed in this section under the appropriate sample type.

The series of detonations of nuclear devices in weapons tests conducted on the mainland of China prior to and during preoperation, and the early years of operation had a significant impact upon the radiological levels in some of samples for several years afterwards. These atmospheric tests occurred on:

September 26,1976; November 17,1976; September 17,1977; March 14,1978; December 14,1978; and October 15,1980.

5

. 1 i

i Significant uptrends in the results also followed the Chernobyl incident in the Ukraine which began i

on April 26,1986.

A. Airborne Particulates and lodines As seen in Table 3, the annual average weekly gross beta activity of 21.7 fCi/m3 for the 3

indicator stations was 0.1 fCi/m greater than that for the community stations and 1.2 3

fCi/m less than thnt for the control stations. For each of these cases, the MDD was 3

calculated as 1.' .Ci/m Since each of these differences is less than its MDD, there is no j

discernible dif erence between the average levels at the indicator stations and those for the I other two str ,on groups.

During pre aperation and the early years of operation the average gross beta readings were 5 to 10 times greater than those currently being obtained. By the mid 1980s, the readings

" had dimbiished to about half the current levels. These annual averages about doubled with the Cheaobyl incident in 1986; this impact faded away after a year or two. The

, instal!?.tian of new air monitoring equipment in 1992 brought a step increase in the readmg ,, roughly by a factor of two. Subsequently, the levels have been essentially flat ti.mgh 1995.

During 1995, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly wmposites of the air particulate filters for each station. This has generally been the case after the impact of the weapons tests had gone away. During preoperation and the early years of operation, a number of fission and activation products were detected 3 at low levels. For example, during preoperation, the average positive levels for Cs-134 3

and Cs-137 were 22 and 9 fCi/m , respectively. For 1986 as a consequence of the f

Chernobyl incident, cesium levels of around 3 or 4 fCi/m were found. It might be noted 3

l that the MDC for Cs-134 and Cs-137 are 50 and 60 fCi/m .

8 i Airborne I-131 is not normally detected in the charcoal canisters and 1995 was no exception. In an early year of operation (1978), levels between 40 and 50 tCi/m3 were found in a few samples; then after the Chernobyl incident, levels up to a few hundred 3

fCi/m were found in a number of samples. At no other times has airborne I-131 been

detected in the environmental samples.

l Listed in Table 2 are a number of deviations which occurred during the year. In each case, 1

the affected samples were tested for conformance with Chauvenet's Criterion; in six cases,

the criterion was not satisfied, the results for these samples were thus deemed

nonrepresentative and excluded from the data set. Listed below are the collection dates

and stations which were excluded.

] Collection Date Station Number j

July 25 1601

. October 10 1605

October 17 1108 i November 7 1108 i December 5 0701 December 12 1218 f

i 1

6 i

i l

1

+ j l B. External Radiation

! As shown in Table 3, the average quarterly exposure of 14.0 mR acquired at the indicator

stations was 2.2 and 1.5 mR greater than that for the community and centrol stations, respectively. Each of these differences are discernible as each is greater than the MDDs calculated as 0.9 mR between the indicator and community stations, and 1.4 mR between the indicator and control stations.

I These differences between the station groups for 1995 are typical of those found in recent years. For example, during the previous 5 years (1990 through 1994), the average j quarterly exposure at the indicator stations was 2.9 and 2.2 mR greater than that at the i community and control stations, respectively, i .

i The results for Station 0104 in the first quarter were excluded from the data base after failing to conform with Chauvenet's Criterion. The details of the deviation which l

, prompted this test are provided in Table 2.

The results for TLD badges 0701 A and 0104A exposed during the first quarter and 0703B exposed during the third quarter were also excluded from the data base because the standard deviation was greater than 1.4. In each of these cases, the readings for the

. companion TLD only were used to determine the quarterly doses at those stations.

The standard deviation limit of 1.4 was calculated using a method developed by the American Society for Testing and Materials (ASTM). (ASTM Special Technical Publication ISD, ASTM Manual on Presentation of Data and Control Chart Analysis. j Fourth Revision, Philadelphia, PA, October 1976) The calculation was based upon the standard deviations obtained by the EL with the Panasonic UD-814 badges during 1992.

This limit serves as a flag to evoke an investigation. To be conservative, readings with a standard deviation greater than 1.4 are deleted since the high standard deviation is mterpreted as an indication of a suspect TLD.

No reason was found for the high deviations obtained with the results for any of these badges. Each was visually inspected under a microscope; the glow curve and test results for the anneal data and the element correction factors were reviewed.

C. Milk No radionuclides were detected by gamma isotopic analysis of the control station milk samples. No milk animals were identified within 5 miles of the plant as an indicator station.

Not since the early years of operation have any positive results been found from either the gamma isotopic or the I-131 analyses. During preoperation, some results for I-131 were over a hundred pCi/1, while the average positive results for Cs-137 were around 30 pCi/1.

In the second year of operation (1978), the average positive results were 21 and 16 pCi/l for I-131 and Cs-137, respectively. During these periods, positive results were found in only about a fifth of the samples. The MDC and RL for I 131 are 1 and 3 pCi/l, respectively; for Cs-137,18 and 70 pCill.

7

1 l

D. Vegetation )

No man-made radionuclides were detected from the gamma isotopic analysis of the forage l samples during 1995. In 1994 Cs-137 was found in two samples at the control station; the  !

average level was 24 pCi/kg wet. Since 1986, only Cs-137 has been found; since 1988, it has been found in only one or two samples out of the 35 to 40 samples collected. During '

preoperation, the early years of operation and in 1986 (the year of the Chernobyl incident),

Cs-137 was found in about a third of the samples and the levels were about 10 times )

greater than those found in recent years. The MDC and RL for Cs-137 in forage are 80 and '

2000 pCi/kg wet.

In these earlier periods,1-131 was found at very high levels which ranged from around 100 l to 1500 pCi/kg dry. The MDC and RL for 1-131 are 60 and 100 pCi/kg wet. In 1978,1980 and 1981, a number of fission and activation products were also found in the forage samples.

There has been a steady decline in the number of radionuclides detected, their level and the frequency at which they are found.

E. Ground Water As usual, no radionuclides were detected from any of the analyses (gamma isotopic,1-131 and tritium) of the samples. During preoperation and through 1983, tritium was found at levels of a few hundred pCi/l in a few of the samples each year. The MDC and RL of tritium is 2000 ar.d 20,000 pCi/1, respectively.

F. Surface Water No positive results were found this year from the monthly gamma isotopic analysis of the samples. Prior to 1987 low levels of Cs 134 and Cs-137 were detected in some of the samples.

On 5-18-89, the river water samplers sampling frequency was changed from a 120 minute interval between aliquot samples to a more conservative time interval of 90 minutes to ensure the interval did not exceed the procedure requirement of 120 minutes. When the interval was changed to 90 minutes, the total number of samples collected per week was not changed from 84 to 112 in the samplers' processor settings. This change in processor settings is necessary to ensure aliquots of sample are collected over a full 7 day period.

As a result, during the time period from 5-18-89 through 8-1-95, the samplers would obtain samples every 90 minutes for a total number of 84 samples and then sit idle for the remaining 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> of the week and thereby miss 28 aliquots. In August 1995, the sampler processors were reprogrammed to collect sample aliquots at 90 minute intervals across the full 7 day period. To ensure no dose limits had been approached or exceeded, the effluent release data during this time period (5-18 89 through 8-1-95) were evaluated.

There were no abnormally high radioactive releases identified from this review, No adverse environmental impact resulted from the time period of reduced river water sampling.

As may be seen from Table 3, only one out of the eight surface water samples had tritium activity. The analysis showed a level of 257 pCi/1, which is far below the MDC of 3000 pCi/1. Generally speaking the annual average levels at the indicator station have been a 8

little greater (by one to two hundred pCi/l) than those at the control station. The highest annual level in the past was around 500 pCi/l. In general, there appears to be a slight downward trend in the levels as well as the frequency at which positive results are found.

Listed in Table 2 are the deviations that occurred during the year.

G. Fish As may be seen from Table 3, Cs-137 was the only radionuclide ofinterest which was found from the gamma isotopic analysis. For the bottom feeding fish, it was found in only one of the samples; at the control station, the level was 14.2 pCi/kg wet. For the game fish, it was found in the two samples collected at both the indicator station and the control station. The average level at the indicator station of 17.9 pCi/kg wet was 0.3 pCi/kg wet less than that found at the control stations; this difference is not discernible since it is less than the MDD of 13.3 pCi/kg wet.

Over the years, Cs-137 has been found in about 85% of the game fish samples but in only around 30% of the bottom feeding fish samples. Every year (except one) the average levels for the game fish have been greater than those for the bottom feeding fish, typically about 50% greater. During preoperation, the levels were about 5 times greater than the current levels; during 1980 and 1981, they were an order of magnitude greater.

On only a few occasions in the past have radionuclides ofinterest other than Cs-137 been found. In 1986 (the year of the Chemobyl incident), Co-60 was found at a level of 25 pCi/kg wet in one of the two game fish samples collected at the indicator station. In 1982, Nb-95 was found at a level of 31 pCi/kg wet in one of the three game fish samples from the indicator station. In 1981, Nb-95 was found at a level of 38 pCi/kg wet in one of the two bottom feeding samples from the indicator station. The impact of weapons testing was evident during the early eighties.

t IL Sediment

No positive results for the radionuclides ofinterest were found during 1995 from the 1 gamma isotopic analysis of the samples. Over the years only a few positive results were i found, which were for Be-7, Nb-95, Cs-134 and Cs-137; all of these positive results were i from samples collected at the control station except for two each of the cesium isotopes.

{ Be-7 was detected only once, in 1985 at a level of 945 pCi/kg dry; its MDC is 655 pCi/kg i'

dry. Nb-95 was also detected only once, in 1981 at a level of 113 pCi/kg dry; its MDC is 50 pCi/kg dry. Cs-134 has been detected six times at levels ranging from 45 to 138 pCi/kg i dry; its MDC is 150 pCi/kg dry. Cs-137 has been detected seven times at levels ranging

, from 11 to 185 pCi/kg dry; its MDC is 180 pCi/kg dry. No trend is recognized from these

data, t

I 9 l l

IV. OTHER ACTIVITIES A Land Use Census An annual land use census as required by TS 6.8.3.f(2) and ODCM 4.1.2 was completed on June 16. The results are provided in Attachment L A new residence which is closer to the plant than the current controlling receptor was found in the West Sector at 0.9 miles. The current controlling receptor as described in ODCM Table 3-7 is a child in the SW Sector at 1.2 miles receiving dose via the inhalation, ground plane, vegetable garden and cow meat pathways. Since there was no vegetable garden, meat animal or milk animal at the new closer residence, the dose pathways would consist of only inhalation and the ground plane. A calculation was made which showed that the dose received by the current controlling receptor is greater than that which would be received by the new resident. Thus, the present controlling receptor was retained.

B. Interlaboratory Comparison Program As required by ODCM 4.1.3, the EL participates in an interlaboratory comparison program, namely the Environmental Protection Agency's (EPA) Crosscheck Program. The EL's EPA program code designation is MQ.

V. CONCLUSIONS This report confirms the licensee's conformance with the requirements of TS 6.8.3.f and Chapter 4 of the ODCM during 1995. It shows that all data were carefully examined. A summary and discussion of the results of the laboratory analyses for each type sample were presented.

It was shown that all of the radiological levels were low and generally trending downward. No radiological impact upon the environment or to the public as a consequence of plant discharges to the atmosphere and to the river was established.

I 1

10

. . L II l

- ~ ~ ?'? _ ~ ~ . -~ / $.

] g e

7175 WARE

$PUT-MORMAL g\

t

""" ""( -

X/Q = 1.0.10 4

l 4

% ,.,,,j $EC/M 8

14 ,

• • g * ,* 2 l NW Nt c

.- ('. ,

i-

,,, % v s

/ g

.N.

macas I

tr w

/,s,.m i

$ . g 4

I < f*

• kl.

nEn s f ,

g g. . ..

• l [l 4

l. , S \

N 3 10 .g**.., . 1 i

• 0 4

\ SW semc n,e. I ,,,* I

/ k '"*" $*

• 'd' , " . . . .*

l '

l 't')

& . $$w

' $5E ,

I i

I

\ f 1.)

'l ,

i u ,

? gi s ,,, ~ A _ <

_7_

\ . _ _,_

A TLD SAMPLING

, @ TLD, PARTICULATES & 100tNE SAMPLING 1

4 INDICATOR STATIONS FOR MONITORING GASEOUS RELEASES Figure 1

1 i

15 sunne

/

i is

/ i /

'""" NN(

14 1

Rn (  !

u at i

C0tuullA l M / muon.

l 13 j u 3

nNw ric l

u n a

]j tru]

i i 12 W " ,h mUli"u. raarv 4 4 l

g- * * ' ' ' * '

i n \

i

- s.

1 , crou l m a '. 3 SPtinGS

! m 33 "I 3

, ist l

\_ g 03

, sonooN.

a

! 10

. $1 IARIN f

l s i 1

! sm sst

i

',8 j j 8, j j j

@ TLD, PARTICULAIES & 100lME SAMPUNG

on..e i

i i

A i

4

}

i COMMUNITY (INDICATOR II) STATIONS FOR MONITORING GASEOUS RELEASES 1

Figure 2

l

. / . '

3

--~ I y e,

\

$5 5. l,

• " '**". . 3

. . . . . . . . e. .g-

~ a i 5,,8 u

~g

.- *< e. </

~~-

sl!

• l l

} ,y

.......~."..

w=

i

)-

d

,, a 4

u m pg a

~n

~

.^ . ,+. _

~

N

]!( ~ ..

I g .

i

,' .Mt-(

,~ .  :

l e

x

!g j

_s

= .,

N

-a..

.* =, .,

g,l I

....- jj

. a ... <

a.

.. * ..~~ ' .........

. ~ . . . . .

= =g

= ,9 j  :

yl j 3 i

~

i Qk\INI

, g

~~

> %M. . . , , * . . w.. . . . ' , --

• =

• • e tungp'

• ens i'., j g!ll1

/

1

. um I

n.-

• 4 em as ,

5 CONTROL STATIONS NITORING GASEoug RELEASES Figure 3

D 11 ANDREWS Locs a oAu j FAttiy

to uitt! j NUCLEAR PLANT 1 / unty coum A$arono j s*# " "**

I _____ '

12 1

i "I u _

l conooM :

\ k HOUSTON COUNTY ALABAMA 4

I INDICATOR STATIONS CONTROL STATIONS q W $uRrAct AND cro0ND WAftA h $URfAct WATER, fl$H AND $lDlWINT

@ FISH AND $[0lWENT h GROUND WATER INDICATOR AND CONTROL STATIONS FOR

. MONITORING LIQUID RELEASES Figure 4

TABLE 1 OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1995 Types of Samples and Sampling Locations Sampling and Collection Frequency Type and Frequency of Analysis (Distances Given in Miles)

AIRBORNE Particulates Continuous sampler operation with filter Particulate filter- Analyze for gross beta collection performed once per 7 days. r;.Jioactivity 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter Indicator Stations: change. Perform gamma isotopic analysis on North Perimeter (N-0.8) each sample when gross beta activity is >10 South Perimeter (SSE-1.0) times the yearly mean of control samples.

Plant Entrance (WSW-0.9) Perform gamma isotopic analysis on River Intake Structure (ESE-0.8) composite (by location) sample at least once per 92 days.

Community Stations:

Blakely, GA. (NE-15)

Dothan, AL. (W-18)

Neals Landing, FL. (SSE-18)

Iodine Continuous sampler operation with charcoal Radioiodine canister- Analyze at least once canister collection performed once per 7 days. per 7 days for I-131.

Indicator Stations:

North Perimeter (N-0.8)

South Perimeter (SSE-1.0)

Plant Entrance (WSW-0.9)

River Intake Structure (ESE-0.8)

Community Stations:

Georgia Pacific Paper Co. (SSE-3)

Control Stations:

Blakely, GA. (NE-15)

Dothan, AL. (W-18)

Neals Landing, FL. (SSE-18)

Table 1 PageI of4

TABLE 1 (continued) .

OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1995 .

Types of Samples and Sampling Locations Sampling and Collection Frequency Type and Frequency of Analysis ,

(Distances Gives in Miles) j DIRECT RADIATION At least once per 92 days. Gamma dose - Readout at least once per 92  !

days Indicator I Stations: -

Sixteen stations, one in each meteorological sector along the plant perimeter (N-0.8, NNE-0.9, NE-1.0, .

ENE-0.9, E-0.8, ESE-0.8, SE-1.1, SSE-1.0, S-1.0, SSW-1.0, SW-0.9, WSW-0.9, W-0.8, WNW-0.8, t NW-1.1, and NNW-0.9). [

Indicator II(Community) Stations:

Sixteen stations: At least one in each i meteorological sector at a distance of ,

3-5 miles (NNE-4, NE-4, ENE-4, E-5, i ESE-5, SE-5, SSE-3, S-5, SSW-4, 4

SW-5, WSW-4, W-4, WNW-4, NW-4, l NNW-4, and N-5).

SpecialInterest Stations:  !

Occupied residence nearest the plant site ,

(SW-1.2)

CityofAshford, AL (WSW-8.0) ,

f i

i Control Stations Blakely, GA. (NE-15) l Neals Landing, FL. (SSE-18) [

Dothan, AL.(W-18)  !

Dothan, AL.(W-15) ,

Webb, AL.(WNW-11) l Haleburg, AL (N-12)  !

P i

Table 1 i Page 2 of4

i TABLE 1 (continued)

OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1995  ;

Types of Samples and Saaspling Locations Sampling and Collection Frequency Type and Frequency of Analys (Distances Given in Miles)

WATERBORNE r

Surface Water Composite taken with proportional Analyze gamma isotopic analysis of each semicontinuous sampler having a minimum - composite sample monthly. Analyze tritium [

Indicator Station: sampling frequency not exceeding two hours in each composite sample at least once per 92 Paper Mill at Cedar Springs,GA collected over a period 5 31 days. days.

(3 miles downstream of plant  !

discharge, River Mile-40) j Control Station:

Upstream of Andrews Lock and Dam j

(~ 3 miles upstream of plant intake,  !

River Mile-47)

) Ground Water Grab sample taken at least once per 92 days. Gamma isotopic and tritium analyses of each sample once per quarter.

Indicator Station:

Paper Mill at Cedar Springs, GA, Well

(SSE-4)

Control Station:

Whatley Residence, Well(SW-1.2)

River Sediment Grab sample taken at least once per 184 days. Gamma isotopic analysis of each sample twice per year.

Indicator Station:

2 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)

Table 1 Page 3 of 4

l TABLE I (continued) .

OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL '

MONITORING PROGRAM FOR FARLEY NUCLEAR PLANT DURING 1995 Types of Samples and Sampling Locations Sampling and Collection Frequency Type and Frequency of Analysis (Distances Given in Miles) j INGESTION Milk At least once per 16 days. Gamma isotopic and I-131 analysis of each biweekly sample when animals are on pasture.

Control Staton:

Ivey Dairy (Green Valley Farms) Webb, AL. (W-12)

Fish One sample each of the following species at Gamma isotopic analysis on edible portions least once per each season (March 15 - May 15 once per season.

Indicator Station: and September 15 - November 15)

Downstream of plant discharge in 1. Game Fish vicinity of Smith's Bend 2. Bottom Feeding Fish (River Mile - 41)

Control Station:

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

Forage Grab sample cut from green forage at least Gamma isotopic analysis (which includes once per 31 days. 1-131) of each monthly sample.

Indicator Station:

North Perimeter (N-0.8)

South Perimeter (SSE-1.0)

Control Station:

Dothan, AL.(W-18)

Table 1 Page 4 of 4

TABLE 2 'l ENVIRONMENTAL MONITORING PROGRAM DEVIATIONS 1995 DATE/ITME COMPONENT CAUSE OF DEVIATION RESOLUTION REMARKS 2-7-95/1300 Community TLD TLD found missing Area searched, TLD replaced with 35 days of data lost 0104 a spare 2-21-95/0719 Control air monitor Power secured for substation work Power was restored - Sampler was ofr7:08 hours station 1218 2-21-95/1044 Community air Power lost during thunderstorm, Power was restored Sampler was off 3:51 hours monitor station 1605 probably on 2-18 2-28-95/1030 Community TLD TLD missing a second time Area was searched, then TLD was 21 more days lost for a total of 56.

0104 replaced on 3-1-95/1150 and Results were excluded.

labeled"Farley Nuclear Plant Do l not Remove" 6-1-95/1120 Community air Pump would not restart after Pump repaired 6-2-95 Sampler was off 21:27 hours 1

monitorstation 0703 calibration and service 6-13-95/0835 Control air monitor Pump tripped after 102:19 hours Isreaker was reset Sampler was oft 65:26 hours station 0718 7-18-95/0932 Control air monitor Pump and totalizer tripped after Totalizer breaker was reset Sampler lost 41:49 hours station 0718 127:16 hours 7-18-95/1236 Community air Pump tripped after 28:43 hours, Pump was reset Due to low sample volume, entire  ;

monitor station 1605 likely due to thunderstorm sample was not reported,169:50 j hours lost l

7-19-95/1500 Community air Samplerchecked after suspected Power restored and pump restarted Sampler was ofr22:09 hours monitor station 1605 power loss. Pump had tripped after 2:10 hours 7-25-95/0710 Indicator air monitor Sampler tripped after 3:49 hours Pump was restarted Sampler lost 161:40 hours, analysis station 1601 results failed review and were I discarded I July 1995 River Auto Samplers Samplers found configured Samplers were configured See discussion in body of the report incorrectly such that insufficient correctly, procedures were (Section III. F.)

samples were collected in 7 days corrected f,-29-95/1335 Air monitor stations Power secured for substation work Power restored 45 minutes lost 1601 and 1605 10-4 to 10-7-95 River water auto Samplers were removed in Samplers replaced Background sampler 005 - 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> samplers preparation for Hurricane Opal Indicator Sampler 005 - 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Table 2 PageI of2

t TABLE 2 (continued) ,

ENVIRONMENTAL MONITORING PROGRAM DEVIATIONS 1995 DATE/ TIME COMPONENT CAUSE OF DEVIATION RESOLUTION REMARKS Time Lost: 1601 - 18:35 hours, l 10-10-95/1440 Air monitors Samplers lost power during Power was restored 1601,0703,1108, hurricane Opal 0703 - 5:49 hours,1108 - 14:20 hours j 0718,1605 0718 - 39:00 hours,1605 - 6:16 hours 10-17-95/1342 Community air Pump fuse blown after 272.6 m' Fuse replaced and pump restarted Sample run time was unknown monitor station 1108 collected, time unknown volume thought to be accurate,  !

Results failed review and were ,

discarded.  !

11-7-95/0730 Community air Pump fuse blown again after 311.7 Pump was replaced Sample run time was unknown j i- monitor station 1108 m' collected volume thought to be accurate,  :

Results failed review and were [

discarded.  :

12-5-95/1220- Indic.ator air monitor Sampler found with low flow. Flow was set and monitored for Sample ran continuously but analysis i I

station 0701 Average for the week was 23.9 Ipm reoccurrence results failed review and were j over 173.29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> discarded i 12-12-95/1015 Control air monitor Breaker tripped after 6:02 hours, Breaker was reset and pump Volume collected was low, results station 1218 probably during thunderstorm restarted were discarded.  ;

f I

t i

1 I

i i

P Table 2 Page 2 of 2

TABLE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Indicator Indicator Location With Community Control Type and Minimum Locations Highest Annual Mean Locations Locations Total Number Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range. Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction)

AIRBORNE PARTICULATES (fCi/m3)

Gross Beta 10 21.7 Plt. Perim. 24.7 21.6 22.9 514 9-41 0.8 miles 12-37 10-39 9-50 l (206/206) N (51/51) (153/153) (155/155)  !

Gamma Isotopic 40 l I-131 70 NDM(c) NA (d) NDM NDM (0/16) (0/12) (0/12)

Cs-134 50 NDM NA NDM NDM (0/16) (0/12) (0/12)

Cs-137 60 NDM NA NDM NDM (0/16) (0/12) (0/12)

AIRBORNE RADIOIODINE (fCi/m3)

I-131 70 NDM NA NDM NDM 413 (0/206) (0/52) (0/155)

Table 3 Page1 of10

T

-TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 11ouston County, Alabama Indicator Indicator Location With Community Control

. Type and Minimum Locations liighest Annual Mean Locations Locations

! TotalNumber Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction)

DIRECT RADIATION (mR/91 days)

, Gamma Dose NA 14.0 Pit. Perim. 21.5 11.8 12.5 159 10-23 0.8 miles 20-23 9-14 10-15

, (64/64) E (4/4) (71/71) (24/24)

MILK (oCi/1)

Gamma Isotopic 26 Cs-134 15 NA NA NA '

NDM (0/26)

Cs-137 18 NA NA NA NDM (0/26)

Ba-140 60 NA NA NA NDM (0/26)

La-140 15 NA NA NA NDM (0/26)

I-131 1 NA NA NA NDM 26 (0/26)

Table 3 Page 2 of10

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Indicator Indicator Location With Community Control Type and Minimum Locations Highest Annual Mean Locations Locations TotalNumber Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction) .

FORAGE (oCi/kg wet)

Gamma Isotopic 39 l-131 60 NDM NA NA NDM (0/26) (0/13)

Cs-134 60 NDM NA NA NDM (0/26) (0/13)

Cs-137 80 NDM NA NA NDM (0/26) .(0/13)

GROUND WATER (oCi/l)

H-3 2000 NDM NA NA NDM 8 (0/4) (0/4)

I-131 1 NDM NA NA NDM 8 (0/4) (0/4) i

' Table 3 Page 3 of10

l TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 i Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 '

Houston County, Alabama

, Indicator Indicator Location With Community Control l Type and Minimum Locations Highest Annual Mean Locations Locations Total Number . Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction)

Gamma Isotopic l 8

Mn-54 15 NDM NA NA NDM (0/4) (0/4)

Fe-59 30 NDM NA NA NDM (0/4) (0/4) j Co-58 15 NDM NA NA NDM (0/4) (0/4)

Co-60 15 NDM NA NA NDM l (0/4) (0/4) 1 Zn-65 30 NDM NA NA NDM (0/4) (0/4)

Zr-95 30 NDM NA NA NDM (0/4) (0/4)

Nb-95 15 NDM NA NA NDM (0/4) (0/4)

Cs-134 15 NDM NA NA NDM (0/4) (0/4)

Table 3 Page 4 of 10

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Indicator Indicator Location With Community Control Type and Minimum Locations Highest Annual Mean Locations imtions Total Number Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction)

Cs-137 18 NDM NA NA NDM (0/4) (0/4)

Ba-140 60 NDM NA NA NDM (0/4) (0/4)

La-140 15 NDM NA NA NDM (0/4) (0/4)

SURFACE WATER (oCill)

H-3 3000 257 Paper Co. 257 NA NDM 8 257-257 3 miles 257-257 (0/4)

(1/4) Downstream (1/4)

Gamma Isoto,aic 26 Be-7 124 (e) NDM NA NA NDM (0/13) (0/13)

Mn-54 15 NDM NA NA NDM (0/13) -(0/13)

Fe-59 30 NDM NA NA NDM (0/13) (0/13)

Table 3 Page 5 of10

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING %OGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Indicator Indicate ,ocation With Community Control Type and Minimum Locations liighc .nnual Mean Locations Locations Total Number Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction)

Co-58 15 NDM NA NA NDM (0/13) (0/13)

Co-60 15 NDM NA NA NDM (0/13) (0/13)

Zn-65 30 NDM NA NA NDM (0/13) (0/13)

Zr-95 30 NDM NA NA NDM (0/13) (0/13)

Nb-95 15 NDM NA NA NDM (0/13) (0/13) 1-131 15 NDM NA NA NDM (0!!3) (0/13)

Cs-134 15 NDAT NA NA NDM (0/13) (0/13)

Cs-137 18 NDM NA NA NDM (0/13) (0/13)

Ba-140 60 NDM NA NA NDM (0/13) (0/13)

Table 3 Page 6 of10

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

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama  ;

Indicator Indicator Location With Community Control Type and Minimum Locations Highest Annual Mean Locations Locations Total Number Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range.. Range Performed (MDC)(a) (I'titetion) Direction (Fraction) (Fraction) (Fraction) 5 La-140 15 N D.'.' NA NA NDM (0/13) (0/13)

BOTTOM FEEDING FISil(cCi/kg wet)

Gamma Isotopic l 4

Be-7 655 (e) NDM NA NA NDM (0/2) 9/2)

Mn-54 130 NDM NA NA NDM .I (0/2) (0/2)

Fe-59 260 NDM NA NA NDM  ;

(0/2) (0/2)

Co-58 130 NDM NA NA NDM (0/2) (0/2)

Co-60 130 NDM NA NA NDM (0/2) (0/2)

Zn-65 260 NDM NA NA NDM (0/2) (0/2)

Table 3 Page 7 of 10 i

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995 Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 Houston County, Alabama Indicator Indicator Location With Community Control Type and Minimum Locations Highest Annual Mean Locations Locations ,

Total Number Detectable Mean (b) Name Mean (b) Mean (b) - Mean (b) '

ofAnalyses Concentration Range Distance & Range Range Range Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction) i Cs-134 - 130 NDM NA NA NDM l' (0/2) (0/2)

Cs-137 150 NDM NA NA 14.2 (0/2) 14-14 (1/2) ,

GAME FISil(oCi/kg wet) ,

Gamma Isotopic 4

Be-7 655 (e) NDM NA NA NDM (0/2) (0/2)

Mn-54 130 NDM NA NA NDM

-(0/2) (0/2)

Fe-59 260 NDM NA NA NDM (0/2) (0/2)

Co-58 130 NDM NA NA NDM '

(0/2) (0/2)

Co-60 130 NDM NA NA NDM (0/2) (0/2)

Table 3 Page 8 of 10

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

=

L I

TABLE 3 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995  ;

Farley Nuclear Plant, Docket Nos. 50-348 and 50-364 ,

llouston County, Alabama f

Indicator Indicator Location With Community Control  ;

Type and Minimum Locations flighest Annual Mean Locations Locations 6 Total Number Detectable Mean (b) Name Mean (b) Mean (b) Mean (b) ofAnalyses Concentration Range Distance & Range Range Range I Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) (Fraction) +

i Zn-65 260 NDM NA NA NDM (0/2) (0/2) ,

Cs-134 130 NDM NA NA NDM  !

(0/2) (0/2)

Cs-137 150 17.9 Smith's Bend 17.9 NA 18.2 16-19 2 miles 16-19 17-19 (2/2) Downstream (2/2) (2/2) l i

RIVER SilORELINE SEDIMENT (oCi/kg drv)

Gamma Isotopic 4

Be-7 655 (e) NDM NA NA NDM j (0/2) (0/2)  ;

Cs-134 150 NDM NA NA NDM (0/2) (0/2) .

Cs-137 180 NDM NA NA NDM i (0/2) (0/2) j Table 3 Page 9 of 10

1 TABLE 3 (continued) ,

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

FOR 1995  !

Farley Plant, Docket Nos. 50-348 and 50-364

)

Houston County, Alabama

]

NOTAT' OMS i

a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed m  ;

this column are the detection capabilities required by ODCM Table 4-3. The values  !

listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori l (after the fact) MDCs are generally lower than the values listed. There were no l MDC values during the year which were greater than the values listed in this column.

b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location which is detectable is placed in parenthesis.

l

c. No Detectable Measurement (s).

d. Not Applicable.

4

e. The EL has determined that this value may be routinely attained under normal i

, conditions. No value is provided in ODCM Table 4-3. I i

4 l

l i

4 1

i 4

i i

j i

J Table 3 Page 10 of 10

1 l

4 ATTACllMENT 1 I JOSEPH M. FARLEY NUCLEAR PLANT LAND USE CENSUS AND MILK ANIMAL SURVEY JUNE 16,1995 Distance in Miles To Nearest Resident Milk Animal Radial Sectors 22.5 Degrees Each 1994 1995 1994 1995 Reason For Change Individuals Interviewed North Northeast (01) 2.5 2.5 >5 >5 N/A Mr. Art Freeman Note 3 Northeast (02) 2.4 2.4 >5 >5 N/A *Mr. Judson Freeman Ms. Barbara Kilpatrick East Northeast (03) 2.4 2.4 >5 >5 N/A *Mrs. Jim Donaldson i East (04) 2.8 2.8 >5 >5 N/A *Mrs. Booker T. Spivey i l

East Southeast (05) 3.0 3.0 >5 >5 N/A *Mrs. Mary Esther Allums Southeast (06) 3.4 3.4 >5 >5 N/A 'Ms. Katherine Smith i Mr. David Barber  !

South Southeast (07) >5 >5 >5 >5 N/A Note 2 South (08) 4.3 4.3 >5 >5 N/A Ms. Dorris Wade Mrs. Thomas Dean Note 3 South Southwest (09) 2.9 2.9 >5 >5 N/A *Mr. Roderick Marshall Ms. Delores McGriff I Southwest (10) 1.2 1.2 >5 >5 N/A *Mr. Walter Whatley West Southwest (11) 2.4 2.4 >5 >5 Note 1 Mr. George Grimsely Note 3 West (12) 1.3 0.9 >5 >5 Note 4 *Ms. Cheryl Shaw West Northwest (13) 2.1 2.1 >5 >5 N/A *M- Robert Sauls Northwest (14) 1.5 1.5 >5 >5 N/A h5.'Lytesia Ryalls Note 3 North Northwest (15) 3.3 3.3 >5 >5 N/A *Mrs. Thomas Steely North (16) 2.6 2.6 >5 >5 N/A *Mr. Tony Knighton

• Nearest Resident in Sector Note 1: The closest residence was listed as unoccupied in 1994 but is now occupied. I Note 2: No resident within 5 miles in sector 7. Georgia Pacific Paper Co. (GPPC) located in sector 7,3.9 I miles from plant site. Air sampler, surface water sampler, TLD located on GPPC plant site. I Note 3: Unable to contact nearest resident in this sector. Personal chervation of residence location and l interviews with neighbors or other residents indicate no mil < animals present.  ;

Note 4: A new trailer was placed at the intersection of Alabama liighway 95 and Nuclear Plant Road approxiamtely 0.9 miles from the plant vent stacks.

Attachment I