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ACCESSION NBR:9405040061 DOC.DATE: 9$)6~9+FACIL:50-220 Nine Mile Point Nuclear Station,

50-410 Nine Mile Point Nuclear Station,AUTH.NAME AUTHOR AFFILIATION

ABBOTT,R.B. Niagara Mohawk Power Corp.MUELLER,J.H. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION

NOTARIZED: NO DOCKETUnit 1, Niagara Powe 05000220Unit 2, Niagara Moha 05000410

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SUBJECT: "Annual Radiological Environ Operating Rept for NineMile Point Nuclear Station Units 1 6 2." W/ 4042 ltr.

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7 NIAGAR~U MOHAWK, .

NINE MILE POINT NUCLEAR STATION/P,O. BOX 63. LYCOMING.NEW YORK 13093/TELEPHONE (315) 343.21)0

April 28, 1994

United States Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555

RE: Nine Mile Point Nuclear Station Unit 1Docket No. 50-220Facility Operating License DPR-63

Nine Mile Point Nuclear Station Unit 2Docket No. 50-410Facility Operating License NPF-69

SUBJECT: Transmittal of 1993 Annual Radiological Environmental Operating Report

Gentlemen:

In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1and Unit 2, we are enclosing the Annual Radi lo ical Environmental 0 eratin Re ort forthe period January 1, 1993, through December 31, 1993.

Any questions concerning the enclosed report should be directed to Hugh J. Flanagan at NineMile Point (315) 349-2428.

Eui:w/ 98M~'Richard B. AbbottPlant Manager, Unit 1

J n H. MuellerPlant Manager, Unit 2

ipse(ANNUALRP.93)

Enclosure

pc: Mr. T. T. Martin, Regional Administrator, Region 1Mr. B. S. Norris, Senior Resident InspectorMr. R. A. Capra, Director, Project Directorate I-l, NRRMr. D. S. Brinkman, Senior Project Manager, NRRMr. J. E. Menning, Project Manager, NRRRecords Management

9405040061: 931231 ',PDR, ',ADQCK 05000220','R -' ':''"PDR

NIAGARA.MOHAWKPOWER CORPORATION

AI'PlUALRADIOLO I ALEIAMONMENTALOPERATING REPORT

January 1, 1993 - December 31, 1993

for

NINE MILEPOINT NUCLEAR STATION UNIT 1

Facility Operating License DPR-63

Docket Number 50-220

NIM':MILEPOINT NUCLEAR STATION UNIT 2

Facility Operating License NPF-69

Docket No. 50-410

9405040061

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TABLE OF CONTENTS

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LIST OF TABLES

LIST OF FIGURES

1.0 INTRODUCTION

2.0 AQUATIC SAMPLES

I Shoreline SedimentII FishIII Surface Water 12

3.0 DIRECT RADIATION

4.0 TERRESTRIAL SAMPLES

I Air Particulate/IodineII MilkIII Food Product

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IV Land Use Census 35

5.0 INTERLABORATORY COMPARISON PROGRAM

6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA

7.0 CHANGES AND EXCEPTIONS TO THE PROGRAM

8.0 CONCLUSION

9.0 GENERAL REFERENCE MATERIAL

10.0 DATA TABLES — 1993

11.0 FIGURES

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.LIST OF TABLES

I Table No.Table 1i

Content .

Sample Collection and Analysis, SiteRadiological Environmental MonitoringProgram — Aquatic Program and DirectRadiation

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Table 2

Table 3

Table 4

Table 5A

Table 5B

Sample Collection and Analysis, SiteRadiological Environmental MonitoringProgram — Terrestrial ProgramEnvironmental Sample Locations

Radiological Environmental MonitoringProgram Annual Summary

Concentration of Gamma Emittersin Shoreline Sediment Samples (pCi/g-dry)Concentration of Gamma Emitters inShoreline Sediment Samples (pCi/kg-dry)

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Table 6A

Table 6B

Table 8

Table 9A

Concentration of Gamma Emittersin Fish Samples (pCi/g-wet)Concentration of Gamma Emittersin Fish Samples (pCi/kg-wet)Concentration of Gamma Emitters inSurface Water Samples

Concentration of Tritiumin Surface Water SamplesDirect Radiation Measurement Results-mrem/Standard Month

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Table 9B

Table 10

Table 11

Table 12

Table 13

Direct Radiation Measurement Results-mrem/Quarterly Period

Environmental Airborne Particulate Samples-Offsite Stations, Gross Beta ActivityEnvironmental Airborne Particulate Samples-Onsite Stations, Gross Beta ActivityConcentration of Gamma Emitters in AirParticulate SamplesEnvironmental Charcoal Cartridge Samples-Offsite Stations, I-131 Activity

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LIST OF TABLES(Continued)

Table No.

t Table 14Table 15

Table 16

Table 17A

Tabl'e 17B

Table 18

Table 19

Table 20

Table 21

Table 23

Table 24

Table 25

Table 26

Table 27

Table 28

Content

Environmental Charcoal Cartridge Samples-Onsite Stations, I-131 ActivityConcentration of Gamma Emitters inMilkConcentration of Iodine-131 in MilkConcentration of Gamma Emitters inFood Products (pCi/g-wet)

Concentration of Gamma Emitters inFood Products (pCi/kg-wet)

Milk Animal Census

1993 Residence Census

Interlaboratory Comparison Program ResultsHistorical Environmental Sample DataShoreline Sediment (Control)

Historical Environmental Sample DataShoreline Sediment (Indicator)Historical Environmental Sample DataFish (Control)

Historical Environmental Sample DataFish (Indicator)Historical Environmental Sample DataSurface Water (Control)

Historical Environmental Sample DataSurface Water (Indicator)Historical Environmental Sample DataSurface Water Tritium (Control)Historical Environmental Sample DataSurface Water Tritium (Indicator)

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LIST OF TABLES(Continued)

Table No. Content Pacae

Table 29

Table 30(A- E)Table 31

Table 32

Table 33

Table 34

Table 35

Table 36

Table 37

Table 38

Table 39

Table 40

Historical Environmental Sample DataEnvironmental TLD (Control)

Historical Environmental Sample DataEnvironmental TLD (Indicator)Historical Environmental Sample DataAir Particulates Gross Beta (Control)Historical Environmental Sample DataAir Particulates Gross Beta (Indicator)Historical Environmental Sample DataAir Particulates (Control)Historical Environmental Sample DataAir Particulates (Indicator)Historical Environmental Sample DataAir Radioiodine (Control)Historical Environmental Sample DataAir Radioiodine (Indicator)Historical Environmental Sample DataMilk (Control)Historical Environmental Sample DataMilk (Indicator)Historical Environmental Sample DataFood Products (Control)

Historical Environmental Sample DataFood Products (Indicator)

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I. 4 LIST OF F GURES

le ContentFigure 1 - . Nearest Residence, Food Product, Fish and'Shoreline Sediment Sample LocationsPacae

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Figure 2

Figure 3

Milk Animal Census, Milk Sample andSurface Water Sample Locations

Off-site Environmental Stations and TLDLocations

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Figure 4 On-site Environmental Station and TLDLocations

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lFigure 5 New York State Map 148

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Le1.0 INTR D CTI N

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1 ~ 0 INTRODUCTION

This report is submitted in accordance with Appendix A (TechnicalSpecifications), Section 6.9.1.d to License DPR-63, Docket No. 50-220for the Nine Mile Point, Nuclear Station Unit 1 and Section 6.9.1.7 toLicense NPF-69, Docket No. 50-410 for the Nine Mile Point Nuclear-Station Unit 2 for the calendar year 1993.The Radiological Environmental Monitoring Program (REMP) is a jointprogram between the Nine Mile Point Nuclear Station (NMPNS) and theJames A. FitzPatrick Nuclear Power Plant (JAFNPP). The samplecollections for the radiological programs are performed in large part byEA Engineering Science and Technology (EA). EA also performs thesampling required for the Station's SPDES Permit. The same staff fromEA is utilized to perform the majority of terrestrial and aquaticsampling required for the REMP. In-plant canal water sampling, airsample collection, and environmental TLD collections are performed .-jointly by the NMPNS and JAFNPP staffs.The present sample collection and analysis schedule required by theTechnical Specifications for the Nine Mile Point Nuclear Station Unit 1and 2 is listed in Table 1 and 2.The REMP samples were analyzed by Teledyne Isotopes and by the SiteEnvironmental Laboratory during 1993. The following samples wereanalyzed by the Site Environmental Laboratory:

Shoreline sediment (gamma spectral analysis)Fish (gamma spectral analysis)Lake water (monthly gamma spectral analysis only)Air particulate filter (weekly gross beta analysis)Air particulate filter (monthly gamma spectral analysis)Airborne radioiodine cartridge (weekly gamma spectralanalysis)

Milk (gamma spectral and radioiodine analysis)Food products (gamma spectral analysis)

The remainder of the sample analyses, as outlined in Table 1 and 2, wereanalyzed by Teledyne Isotopes.

Data are evaluated only from locations required by the Technicali Specifications. Data from optional locations are not evaluated unlessindicated otherwise.I There were four separate groups of radionuclides that were detected inthe environment during 1993. Several radionuclides could possibly fal'linto two of the four groups. The first of these groups is naturally

occurring radionuclides. It must be realized that the environment

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I.'0 INTRODUCTION

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contains a broad inventory of naturally occurring radioactive elements.Background radiation, as a function of primordial radioactive elementsand cosmic radiation of solar origin, offers a constant exposure to theenvironment and man. These radionuclides, such as Ra-226, Be-7 andespecially K-40, account for a majority of the annual per capitabackground dose.

A second group of radionuclides that were detected are a result ofthe'etonationof thermonuclear devices in the earth's upper atmosphere.

The detonation frequency during the early 1950's produced a significantinventory of radionuclides found in the lower atmosphere as well as inecological systems. A ban was placed on atmospheric weapons testing in1963 which greatly reduced the inventory through the decay of shortlived radionuclides, deposition, and the removal (by natural processes)of radionuclides from the food chain. Since 1963, several

atmospheric'eaponstests have been conducted by the People's Republic of China. Ineach case, the usual radionuclides associated with nuclear detonationswere detected several months afterwards, and after a peak detectionperiod, diminished to a point where most could not be detected. Thelast such weapons test was conducted in October of 1980. The resultingfallout or deposition from this test had influenced the backgroundradiation in the vicinity of the site and was very evident in many ofthe sample media analyzed during 1981. Calculations from 1981 of theresulting doses to man from fallout related radionuclides in theenvironment show that the contribution from such nuclides (such as Sr-90or Cs-137) was significant and second in intensity only to naturalbackground radiation. Quantities of Nb-95, Zr-95, Ce-141, ,Ce-144,Ru-106, Ru-103, La-140, Cs-137, Mn-54 and, Co-60 were typical in airparticulate samples during 1981 and have a weapons test origin. During1993, Cs-137 and H-3 were the only radionuclides detected inenvironmental samples that had a weapons testing origin.-The third group of radionuclides includes those that were a result ofthe Chernobyl Nuclear Plant accident. These radionuclides were firstdetected in May of 1986 and were found in samples of air particulates,air radioiodine and milk. Applicable radionuclides include I-131,Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and La-140. Cs-137 was the onlyradionuclide in this category that could have contributed to the totalamount of Cs-137 detected during 1993.

The fourth group of radionuclides are those that could be related to.operations at the site. Many of these radionuclides are a by-productof both nuclear detonations and the operation of light water reactors.Therefore, making a distinction between the two sources can bedifficult, if not impossible. During 1993, no radionuclides weredetected at Technical Specification required locations that would fallinto this category.The evaluation and interpretation of environmental data must be made atseveral levels including trend analysis, dose to man, etc. An attempthas been made not only to report the data collected during 1993, butalso to assess the significance of the radionuclides detected in theenvironment as compared to natural radiation sources. It is importantto note that detected concentrations of radionuclides that are possibly

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1 ' INTRODUCTIONrelated to operations .at the site are very small and are not anindication of environmental significance. In regards to these verysmall quantities, it will be further noted that at such minuteconcentrations the assessment of the significance of detectedradionuclides is very difficult. Therefore, concentrations in onesample that are two times the concentration of another, for example, arenot significant overall. Moreover, concentrations at such low levelsmay show a particular radionuclide in one sample and yet not in anotherbecause of counting statistics at such low concentrations.The average annual dose equivalent to individuals in the United Stateshas been estimated to be 360 mrem (NCRP 93, 1987). The majority of thisdose (300 mrem) is attributed to natural background of which radon anddaughter products contributed 200 mrem. Of man-made sources, medicaldiagnosis was the highest, contributing approximately 50 mrem. Consumerproducts added the remaining 10 mrem. The annual dose from the nuclearfuel cycle (including the operation of nuclear power facilities) isconsidered essentially negligible.

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Background gamma radiation around the Nine Mile Point Site, as a resultof radionuclides in the atmosphere and the ground, accounted forapproximately 50 mrem during 1993. This dose is a result ofradionuclides of cosmic origin (for example, Be-7), of a primordialorigin (Ra-226, K-40, and Th-232) and, to a much smaller extent, of aman-made origin from weapons testing. A dose of 50 mrem, as abackground dose, is significantly greater than any possible dose as aresult of operations at the site during 1993.Environmental Sam le Locations — Table 3

Table 3 contains the locations of the environmental samples presentedin the data tables. The locations are given in degrees and distancefrom the Nine Mile Point Nuclear Station Unit 2 reactor centerline.Table 3 also gives the figure (map) number as well as the mapdesignation for each sample location by sample medium type. Therequirement for Table 3 is found in Section 6.9.1.d of the TechnicalSpecifications for the Nine Mile Point Nuclear Station Unit 1 andSection 6.9.1.7 of the Technical Specifications for the Nine Mile PointNuclear Station Unit 2.

Radiolo ical Environmental Monitorin Pro ram Annual Summar — Table 4Table 4 contains a summary of basic statistics for environmental samplemedia as required by the Technical Specifications. Table 4 is in theformat presented on Table 3 of the NRC Branch Technical Position(Revision 1 dated November 1979) to NRC Regulatory Guide 4;8"Environmental Technical Specifications for Nuclear Power Plants". Thetable is presented to meet the requirements of Section 6.9.1.d andSection 6.9.1.7 of the Technical Specifications for Nine Mile PointNuclear Station Unit 1 and Unit 2 respectively.

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A UATIC 'SAMPLES

Nf'II ~, SHORELINE SEDIMENT

A. 'am le Collection Methodolo and Anal sisShoreline sediment samples are collected twice per year fromone area of existing or potential recreational value and fromone area beyond the 'nfluence of the site. The area ofpotential recreational value is the only area from whichsamples are required by the Technical Specifications.Approximately one kilogram of shoreline sediment is obtainedfrom areas washed by the lakeshore surf at the two locations

'wiceper year. All samples are shipped and analyzed forgamma emitters at the Site Environmental Laboratory. Optionalsamples may be collected from .other shoreline locations at. or-near the site. 'la

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Shoreline sediment locations are shown on Figure 1 (refer toTable 3 for location designations and descriptions).Evaluation of Shoreline Sediment Data — Tables 5A and 5B

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Shoreline sediment samples were obtained in April and Octoberof 1993 at one off-site control location (near Oswego Harbor)and in May and October of 1993 at one indicator location(shoreline area with recreational value just east of thesite) .The results of the shoreline sediment samples collec'ted during1993 at the indicator and control locations are shown onTables 5A and 5B. Table 5A shows results in units of pCi/g(dry) for purposes of data evaluation. Table 5B shows resultsin units of pCi/kg (dry), as required by the TechnicalSpecifications. Only the Sunset Beach location was requiredby the Technical Specifications during 1993.Several radionuclides were detected in sediment samples usinggamma spectral analysis. K-40 was detected at both thecontrol location and indicator location for both collectionperiods during 1993. K-40 is a naturally occurring primordialradionuclide. In addition to K-40, Ra-226 and AcTh-228 werealso detected in control and indicator samples and are also.naturally occurring radionuclides.Cs-137 was detected once at the control location during 1993at a concentration of 0.03 pCi/g (dry). Cs-137 was detectedtwice at the indicator location at concentrations ranging from0.17 to 0.49 pCi/g (dry). Cs-137 has been detected each yearsince 1989 at the indicator location at concentrations rangingfrom 0.10 to 0.34. Cs-137 had not been detected prior to 1989(1985 — 1988). Although the control location did not containa detectable concentration of Cs-137 during 1992, it had beendetected intermittently in the past (1979, 1980, and 1982).Detectable control location quantities ranged from 0.05 to0.22 pCi/g (dry).

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2 ~ 0 - A UATIC SAMPLES.J

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RELINE SEDIMENT (Cont'd)a.

Evaluation of Shoreline Sediment Data-Tables 5A and 5B(Ctat'd)

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The source.; of Cs-137 in 1993 indicator shoreline sedimentsamples is difficult to determine. Possible sources arefallout from past weapons or from site operations; It ishighly probable that the Cs-137 is from fallout. Cs-137 hasbeen detected in the past at control locations beyond theinfluence of the site as well as from the control locationduring 1993. Due to the fact that few shoreline regions westof the site contain fine sediment and/or sand, it is difficultto obtain control samples which are comparable to the physicaland chemical characteristics of the indicator samples. Other

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factors, which include changing lake level and. shorelineerosion, further complicate any consistency in shorelinesediment sampling. Soil samples in areas which are likely tobe affected by plant operations, as well as soil beyond anyinfluence from the site, all contain levels of Cs-137 at orgreater than the concentration found in 1993 shorelinesediment. Cs-137 in soil samples has been attributed toweapons testing fallout. The indicator location, unlike thecontrol location, is very close to eroding ground areas and isbelieved to contain soil residues. Therefore, any

shoreline'edimentsample containing soil would reveal Cs-137. Thesefactors support the likelihood that the trace amounts ofCs-137 detected in the indicator shoreline sediment samples isdue to fallout from past weapons testing.

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Using Regulatory Guide 1.109 methodology, and conservativelyassuming that the maximum exposed individual (adult orteenager) would spend approximately 67 hours per year at thislocation, a conservative dose due to Cs-137 was calculated tobe 0.001 mrem to the whole body and 0.001 mrem to the skin.These doses are very small when compared to average annualwhole body doses due to natural background and may beconsidered insignificant. For the purpose of comparison, soilsampled at a location beyond any influence of the sitecontained Cs-137 at a concentration of 0.61 pCi/g. Using the.same methodology and assumptions for that of sediment, anannual whole body and skin doses of 0.002 mrem werecalculated. Thus, it is shown that a dose to an individual atthe shoreline is less than an individual would receive fromsoil.. Both doses may be considered insignificant.No other radionuclides were detected in shoreline sedimentsamples using gamma spectral analysis.Tables 21 and 22 show historical environmental data forshoreline sediment samples. Shoreline sediment samples at theindicator were not collected prior to 1985.

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2 ' A UATIC SAMPLESFISH

Sam le Collection Methodolo and Anal sis

Available fish species are obtained from collections duringthe spring and fall. Samples are collected from two of fourpossible on-site sample transects located in the vicinity ofthe site discharge points and one off-site sample transect.Available species are selected under the following guidelines:

1. Samples of 0.5 to 1 kilogram of edible fish portions fora minimum of two species per location.

2 ~ When two independent species are not available atall'amplelocations, a species may be divided into two

samples for each location. This procedure may beaccomplished provided that a sufficient sample size isavailable for the species in question at all threelocations.

Selected fish samples are segregated by species and locationand are processed immediately after collection. Samples areshipped frozen in insulated containers. Edible portions ofsamples are analyzed for gamma emitting radionuclides.Fish sample transects are shown on Figure 1 (refer to Table 3for location designations and descriptions).Evaluation of Fish Data — Tables 6A and 6B

A total of twenty-seven fish samples were analyzed as a resultof collections in the spring season (June 1993) and in thefall season (September 1993). Collections were made utilizinggill nets at one location greater than five miles from thesite (Oswego Harbor area), and at two locations in thevicinity of the lake discharges for the 'Nine Mile Point Unit¹1 (02), and the James A. FitzPatrick (03) generatingfacilities. The Oswego Harbor samples (00) served as controlsamples while the NMP (02) and JAF (03) samples served asindicator samples. Samples were analyzed for gamma emitters..Table 6A shows results in units of pCi/g (wet) for purposes ofdata evaluation. Table 6B shows results in units of pCi/kg(wet), as required by the Technical Specifications.Spring fish sample collections were comprised of five separatespecies and thirteen individual samples. Brown trout, whitesucker, lake trout, walleye, and smallmouth bass werecollected at the indicator locations (NMP and JAF). At thecontrol location (Oswego Harbor) white sucker, lake trout,brown trout, smallmouth bass, and walleye were collected.Cs-137 was detected in three of the eight indicator samplesand in one of the five control samples collected during the

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'2 0 A VATIC SAMPLES

FISH (Cont'd)

Evaluation of Fish Data - Tables 6A and 6B Cont'dspring. Cs-137 :concentrations in indicator and controlsamples were approximately equal, and are considered to berepresentative of background concentrations. The

detected's-137concentration in smallmouth bass was 0.026 pCi/g (wet)at one indicator sample, location. Cs-137 was not detected incontrol samples of smallmouth bass. Cs-137 in lake trout was0.029 pCi/g (wet) at one indicator location. Cs-137 was notdetected in the control sample of lake trout. Cs-137 wasdetected in- an indicator sample of walleye at a concentrationof 0.035 pCi/g (wet) and in the control walleye sample at a ."concentration of 0.041 pCi/g (wet). Cs-137 was not detectedin any of the other indicator or control location fishsamples.

K-40 was detected in all of the spring samples collected.K-40 is a naturally occurring radionuclide and is not relatedto power plant operations. Ra-226, also naturally occurring,was detected intermittently in both indicator and controlsamples. No other radionuclides were detected in the springfish samples.Fall fish sample collections were comprised of five separatespecies and fourteen individual samples. Brown trout,smallmouth bass, white sucker, walleye, and Chinook salmonsamples were collected at indicator sampling locations (NMPand JAF). At the control location (Oswego Harbor), whitesucker, brown trout, walleye, Chinook salmon, and smallmouthbass samples were collected.Cs-137 was detected in six of the fourteen samples whichincluded the control samples. Indicator samples showed anaverage Cs-137 concentration that was slightly greater thanthe control sample mean from the off-site location. Thedetected concentrations were not significantly different fromone another because of the extremely small quantitiesdetected. Cs-137 in samples at the indicator locations ranged.from 0.021 to 0.038 pCi/g (wet) and was 0.023 pCi/g (wet) ata control location.Cs-137 was detected in Chinook salmon sampled at NMP and JAFat concentrations of 0.021 and 0.038 pCi/g (wet) respectively.Cs-137 was detected in Chinook salmon collected at the controllocation (Oswego Harbor) at a concentration of 0.023 pCi/g(wet). The concentration of Cs-137 in walleye sampled at NMPand JAF was 0.029 pCi/g (wet) at both locations. Cs-137 wasnot detected in the control sample of walleye. Smallmouthbass sampled at the JAF location contained a concentration of0.032 pCi/g (wet). Cs-137 was not detected in the NMP or

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2 ' A UATIC SAMPLESFISH (Cont'd)

Evaluation of Fish Data — Tables 6A and 6B Cont'd

control samples of smallmouth bass. Brown trout samplescollected at indicator and control locations did not revealany detectable concentrations of Cs-137.

Naturally occurring K-40 was detected in all of the fallsamples collected. Ra-226, also naturally occurring, wasdetected intermittently in the control samples and in all ofthe indicator samples. -No other radionuclides were detectedin the fall fish samples.Review of past environmental data indicates that the meanannual Cs-137 concentration has decreased significantly fromthe 1976 through 1993 results for indicator samples. Averageconcentrations for these .samples decreased from a level of 1.4pCi/g (wet) in 1976 to a level of 0.026 pCi/g (wet) in 1992.The mean concentration of Cs-137 in indicator samples during1993 was 0.030 pCi/g (wet). Control sample results have alsodecreased from a level of 1.2 pCi/g (wet) in 1976 to a levelof 0.022 pCi/g (wet) in 1992. The mean concentration of Cs-137 in control samples during 1993 was 0.032 pCi/g (wet).Results from 1980 to 1986 have shown a fairly consistentdecreasing trend for control and indicator samples. During1987 through 1993, control and indicator mean resultsincreased slightly when compared to 1986.The general decreasing trend for Cs-137 is most probably aresult of ecological cycling. The concentrations of Cs-137detected since 1976 in fish are a result of weapons testingfallout, and the general downward trend in concentrations willcontinue as a function of ecological cycling and nucleardecay. There was no significant effect from the 1986Chernobyl Nuclear Plant accident during 1986 relative toCs-137 results in fish samples although an effect may havebeen detected during the period of 1987 through 1991 sinceboth indicator and control location mean results increasedslightly.Tables 23 and 24 show historical environmental sample data forfish.Lake Ontario fish are considered an important food source bymany. Therefore, fish are an integral part of the human foodchain. Based on the importance of fish in the local diet, areasonable conservative estimate of dose to man can becalculated. Assuming that an adult consumes 21.0 kg of fishper year (Regulatory Guide 1.109 maximum exposed age group)

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II — FISH (Cont'd)2 ' A VATIC SAMPLES

B. Evaluation of Fish Data — Tables 6A and 6B Cont'd

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and the fish consumed contains an average Cs-137 concentrationof 0.030 pCi/g (wet) (annual mean result of indicator samplesfor 1993), the adult whole body dose received would be 0.045mrem per year. The critical organ, in this case, is the teenliver which would receive a calculated dose of 0.072 mrem peryear. The Cs-137 whole body and critical organ doses areconservative calculated doses associated with consuming fishfrom the Nine Mile Point area (indicator samples). Noradiological decay is assumed for the calculation of doses.Conservative whole body and critical organ doses can becalculated for the consumption of fish from the controllocation as well. In this case the consumption rate isassumed to remain the same (16 kg per year for a teen and 21kg per year for an adult) but the average annual Cs-137concentration for the control samples is 0.032 pCi/g (wet).The calculated Cs-137 adult whole body dose is 0.076 mrem peryear and the associated dose to the teen liver is 0.048 mremper year. In this case, the fish from the control locationresulted in doses which were higher than that from theindicator location (near the nuclear facilities). The controllocation is located beyond any influence of the site. Thisstrongly suggests that any Cs-137 detected in fish samples isdue to weapons testing fallout and not due to plantoperations. iIn summary, the whole body and critical organ doses observedas a result of consumption of fish is small. Doses receivedfrom the consumption of indicator and control sample fish areapproximately the same. The doses from control sample fishare slightly greater, although well within naturalvariability. For example, the whole body and organ doses fromthe indicator samples were greater during 1990 and 1992.Doses from both sample groups are considered background dosesand negligible.

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2 ' "A VATIC 8AMPLE8III SURFACE WATER

A. Sam le Collection Methodolo and Anal sisSurface water samples are taken from the respective inletcanals of the J.A. FitzPatrick facility and Niagara Mohawk sOswego Steam Station'. The FitzPatrick facility removes waterfrom Lake Ontario on a continuous basis and generallyrepresents a "down-current" sampling point from the Nine MilePoint Unit 1 and Unit 2 facilities. The Oswego Steam Stationinlet canal removes water from Lake Ontario at a point

'pproximately7.6 miles west of the site. This "up-current"location is considered a control location because of thedistance from the site as well as the result of the lake,current patterns and current patterns from the Oswego

River..'ocatednearby (see Figure 2).

Samples from the FitzPatrick facility are composited fromautomatic sampling equipment which discharges into acompositing tank. Samples are obtained from the tank monthlyand analyzed for gamma emitters. Samples from the OswegoSteam Station are also composited from automatic samplingequipment which discharge to a compositing tank. Samples fromthis location are obtained weekly and are composited to formmonthly composite samples. Monthly samples are analyzed forgamma emitters.

A portion of the samples from each of the locations is savedand composited to form quarterly composite samples for eachcalendar quarter. Quarterly composite samples are analyzedfor tritium.In addition to the FitzPatrick and Oswego Steam Stationfacilities, data are presented for the Nine Mile Point Unit 1and Unit 2 facility inlet canals and city water from the Cityof Oswego. The latter three locations are not required by theTechnical Specifications, but are optional samples. Monthlycomposite samples from these three locations are analyzed forgamma emitters and quarterly composite samples are analyzedfor tritium.Sampling for ground water and drinking water, as found inSection 3.12.1 of the Nine Mile Point Unit 2 TechnicalSpecifications, was not required during 1993 because thesepathways were not applicable to the Site during the year.Applicable sampling requirements and conditions are presentedin the Unit 2 Off-Site Dose Calculation Manual.

ieSurface water sample locations are shown on Figure 2 (refer toTable 3 for location designations and descriptions).

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t 2 'A VATIC SAMPLES

4

-" III SURFACE WATER — (Cont'd) ......:,-„~;

1a

i 'd.B. Evaluatio of'ata — Tables 7 and 8 ISurface water samples were analyzed monthly for gammaemitters (using gamma spectral analysis) 'during 1993;=—Tritium analyses wer'e performed quarterly. Quarterly =samples (i.e., analysis for tritium) were composite samples.The analytical results for the 1993 surface water samplesshowed no evidence of plant related radionuclide buildup inthe surface water in the vicinity of the site. Indicatorsamples were collected from the inlet canal at the James A.FitzPatrick facility. The control location samples werecollected at the inlet canal of Niagara Mohawk's OswegoSteam Station. These two locations are required to besampled by the Technical Specifications. Tables 7 and 8show the results of surface water s'amples analyzed during1993.

Gamma spectral analysis was performed on twenty four monthlycomposite samples (two locations) required 'by the TechnicalSpecifications. .In addition, three optional samplelocations were evaluated. These included the Nine MilePoint Nuclear Station Unit 1 and Unit 2 inlet canals and theCity of Oswego drinking water supply. The drinking watersupply composite samples consisted of twice per week grabsamples. Only two radionuclides were detected in samplesfrom the five locations over the course of 1993. Bothradionuclides were naturally occurring. K-40 was detectedconsistently in both indicator and control samples. Ra-226was detected intermittently in samples from all fivelocations.

I

Tritium samples are quarterly samples that are a compositeof the appropriate calendar months. Tritium was detected inall samples taken at all five locations. The City of Oswegodrinking water showed tritium concentrations ranging from180 to 230 pCi/liter with a mean of 212 pCi/liter. Tritiumconcentrations for the James A. FitzPatrick inlet canalranged from 200 to 280 pCi/liter and showed a meanconcentration of 242 pCi/liter. Inlet canal samples takenat Nine Mile Point Unit 1 and Unit 2 showed tritiumconcentrations ranging from 160 to 320 pCi/liter and 200 to330 pCi/liter respectively. The annual mean concentrationwas 212 pCi/liter and 242 pCi/liter respectively. At theTechnical Specification control location (Oswego SteamStation inlet canal), tritium was detected at concentrationsranging from 160 to 230 pCi/liter and a mean of 188pCi/liter.Previous annual mean results for tritium at the indicatorsample location (FitzPatrick inlet canal) have generallydecreased since 1976. Mean sample results reviewed from

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III SURFACE WATER (Cont'd)

t B. Evaluation of Data — Tables 7 and 8 (Cont'd)1976 through 1992 showed a peak average value of 627pCi/liter (1976) and a minimum value of 227 pCi/liter(1980). The annual mean tritium result at the indicatorlocation for 1993 was 242 pCi/liter.Mean tritium results for the control location (Oswego SteamStation) can not be evaluated with regard to long termhistorical data since sampling was only initiated at thislocation in 1985. Some idea of the, variability of controlsample data can be obtained, however, by review of previousdata from the City of Oswego drinking water samples. Thedrinking water samples are not likely to be affected by thestation because of the effects of the distance, lakecurrents, and the discharge of the Oswego River. Therefore,this previous sample data represents acceptable controlsample data for evaluation purposes.

s

Historical mean annual tritium results from previous citywater samples (1976-1984) and Oswego Steam Station samples(1985-1991) show that the tritium concentrations havedecreased. The maximum annual average was found in 1976(652 pCi/liter) and the minimum in 1982 (165 pCi/liter).Mean annual results from 1979 to 1991 have remainedrelatively consistent. The Oswego Steam Station annual meanresult for 1993 was 188 pCi/liter.The impact of tritium in water to members of the public isminimal. This can be evaluated by calculating a dose to thewhole body and maximum organ. Using Regulatory Guide 1.109methodology, ingestion of water at the indicator locationwould result in a dose of 0.025 mrem to the whole body and0.025 mrem to the child liver. The doses at the controllocation were 0.019 mrem whole body and '0.019 mrem to thechild liver. Drinking water sampled in Oswego is drawn fromLake Ontario at a location more distant that the controllocation. Doses from tritium at this location were 0.022mrem to the whole body and 0.022 mrem to the child liver.Doses received as a result of water ingestion areapproximately the same. The theoretical dose received fromthe indicator location was slightly higher, although wellwithin natural variability. For example, the whole body andorgan doses from control samples were greater during 1991.Doses from all water sampled are considered background dosesand are negligible.Tables 27 and 28 show historical environmental sample datafor surface water tritium.

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2. D A VATIC SAMPLES

III SURFACE WATER (Cont'd)

i B. Evaluation of Data — Tables 7 and 8 (Cont'd)Review of past environmental data for Cs-137 from 1979through 1992 shows that this radionuclide was detected onlyonce at the control location during 1979 at a concentrationof 2.5 pCi/liter. Cs-137 at the indicator location (JAFinlet canal) was detected only once during 1982 at aconcentration of 0.43 pCi/liter. The 1979 control sampleresult is suspect and may have been a result ofcontamination during handling or instrument background sinceCs-137 was not detected in the indicator inlet canal. Theone result from the indicator location (JAF inlet canal)during 1982 was detected in a January composite sample andmay have been a result of inlet canal tempering (theaddition of discharge water to the inletcanal) or instrument background. Cs-137 was not detectedduring 1993 in surface water samples.

Other plant related radionuclides detected during a reviewperiod of 1979 — 1992 include only Co-60. The controlsample location results'howed that Co-60 was detected oncein 1981 (the May composite sample). This result is suspectand, as noted above, may be a result of contamination duringhandling or may be instrument background. This result was1.4 pCi/liter. Results from the indicator location showedthat Co-60 was detected three times during 1982 and averaged1.9 pCi/liter. These positive results were attributed toinlet canal tempering and instrument background. Co-60 wasnot detected during 1993 in surface water samples.

Tables 25 and 26 show historical environmental sample datafor surface water using gamma spectral analysis.

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3.0 DIRECT RADIATION

16

3 ' DIRECT RADIATION

Sam le Collection Methodolo and Anal sisThermoluminescent dosimeters '(TLD's) are used to measuredirect radiation (gamma dose) in the environment. TLD's areobtained from Teledyne Isotopes on a quarterly basis and areread at Teledyne Isotopes'acility in Westwood, New Jersey.Control TLD's accompany the TLD's when they are being placedor collected and are shielded by lead when they are not beingused.. TLD data results are corrected for a transit dose byuse of the data from shipment control TLD's.

Five different types of areas are evaluated by environmentalTLD's. These areas include on-site areas (areas within thesite boundary not required by the Technical Specifications),the site boundary area in each of the sixteen meteorologicalsectors, an outer ring of TLD's located four to.five milesfrom the site in eight available land based meteorologicalsectors, special interest TLD's located at. sites of highpopulation density and control TLD's located at sites beyondsignificant influence of the site. Special interest TLD s arelocated at or near large industrial sites, schools, proximaltowns or communities or other special activity areas. ControlTLD's are located to the southwest, south, south-southeast andnortheast of the site at distances of 12.6 to 26.4 miles.TLD's used during 1993 were composed of rectangular teflonwafers impregnated with 25% CaSO4. Dy Phosphor. These wereplaced in polyethylene packages to ensure dosimeter integrity.TLD packages were placed in open webbed plastic holders andwere attached to supporting structures; usually trees orutility poles.Environmental TLD locations are shown on Figures 3 and 4(refer to Table 3 for location designations and descriptions).Evaluation of TLD Data — Tables 9A and 9BTLD's were collected and read once per quarter during the 1993sample year. The TLD results are, for the most part, anaverage of eight independent readings at each location and arereported in mrem per standard month (Table 9A) and in mrem perquarterly period (Table 9B).TLD's required by the Technical Specifications include twoTLD's at each location with four independent readings per TLD.TLD results included on Tables 9A and 9B are comprised ofTLD's required by the Technical Specifications and specialinterest TLD s not required by the Technical Specifications.During 1993, TLD's were collected during the weeks ofMarch 29, 1993, June 28, 1993, September 27, 1993, andDecember 27, 1993.

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'DXRECT RAD1ATION.„

-B.:-'.- Evaluation of TLD Data — Tables 9A and 9B (Cont'd)

Overall TLD results are evaluated by organizing environmental.TLD'.s into five different groups. These groups include: (1) .on-site TLD's (TLD's within the site boundary not required bythe Technical Specifications), (2) site boundary TLD s (one ineach of the sixteen 22 1/2 degree meteorological sectors), (3)a ring of TLD's four to five miles from the site in each ofthe land based „22 1/2 degree meteorological sectors, (4)special .interest TLD s in areas of high population density,and (5) control TLD's in areas beyond any significantinfluence of the generating facilities. Special interestTLD's are located at or near large industrial sites, schools,or proximal towns or communities. Control TLD's are located,to the southwest, south, south-southeast, and northeast

of'the..'iteat distances of 12.6 to 26.4 miles from the site.Most of the TLD locations required by the TechnicalSpecifications during 1993 were initiated in 1985 as a resultof the issuance of new Technical Specifications by the NRC.Therefore, these TLD results can only be compared to 1985—1992 results. Other TLDs, which include a few TLDs requiredby the Technical Specifications,(i.e., numbers 7, 14, 15, 18,23, 49, 56, and 58) and other optional TLDs, can be comparedto results prior to 1985 since these TLDs were establishedprior to 1985.On-site TLD's are TLD's at special interest areas and, withthe exception of TLD numbers 7 and 23, are not required by theTechnical Specifications. These are located near thegenerating facilities and at previous or existing on-site airsampling stations. TLD s located at the air sampling stationsinclude numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26. The resultsfor these TLD's are generally consistent with previous yearsresults. These results ranged from 3.1 to 13.6 mrem perstandard month and up to three times control TLD results.Other on-site TLD's include special interest TLD's locatednear the north shoreline of the Unit 1, Unit 2 and FitzPatrickfacilities, but in close proximity to radwaste facilities andthe Unit 1 reactor building. These TLD's include numbers 27,.28, 29, 30, 31, 39, and 47. Results for these TLD's during1993 were variable and ranged from 5.3 to 33.7 mrem perstandard month as a result of activities at the radwastefacilities and the operating modes of the generatingfacilities. Results for 1993 are consistent with the rangesof variability. noted in 1992 for TLD's at or near theselocations. TLD's in this group ranged up to approximately sixtimes control TLD results.

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t'3 0 'IRECT 'ADIATION

R iB. Evaluation-of TLD Data — Tables 9A and 9B (Cont'd)

t Additional on-site TLD's are located near the on-site EnergyCenter and the associated northeast, shoreline. — These TLD's"include numbers 18, 103, 106 and 107. TLD's 103, 106 and 107are .located to the east of the Energy Center and to the westof the Unit -1 facility.',-TLD number 18 is located on the westside of the Energy Center.. Results during 1993 showed theseTLD's ranged from 3.8 — 6.0 mrem per standard month and wereconsistent with the 1992 results.Site boundary TLD's are required* by'he TechnicalSpecifications and are located in the approximate area of thesite boundary with one in each of the sixteen 22 1/2 degree .meteorological sectors. These TLD's include numbers 75, 76 ..",77, 23, 78, 79, 80, 81, 82, 83, 84', 7, 18, 85, 86 and 87. "TLDnumbers 78, 79, 80, 81, 82, 83, 84, 7 and 18 showed resultsthat were consistent with control TLD results and ranged from3.3 to 6.0 mrem per standard month. Site boundary TLD'sduring .1993 were consistent with 1985-1992 results. TLDnumbers 75, 76, 77, 23, 85, 86, and 87 showed results thatranged up to three times the results of control TLD's. Theseresults ranged from 3.8 to 11.6 mrem per standard month. Thislatter group of -TLD's are located near the lake shoreline(approximately 100 feet from the shoreline), but are alsolocated in close proximity of the reactor building andradwaste facilities of Unit 1 and Unit 2 and the radwastefacilities of the FitzPatrick facility.A net site boundary dose can be estimated from available TLDresults and control TLD results. TLD results from TLD'slocated near the site boundary in sectors facing the landoccupied by members of the public (excluding TLD's near thegenerating facilities and facing Lake Ontario) are compared tocontrol TLD results. The site boundary TLD's include numbers78, 79, 80, 81, 82, 83, 84, 7 and 18. Control TLD's includenumbers 8, 14, 49, 111 and 113. Net site boundary doses foreach quarter in mrem per standard month are as follows:

Quarter et Site Bounder Dose*1 -0.42 +0.03 +0.24 +0. 0

*Dose in mrem per standard monthSite boundary TLD numbers 75, 76, 77, 23, 85, 86, and 87 wereexcluded from the net site boundary dose calculation sincethese TLD's are not representative of doses at areas where amember of the public may be located. These areas are near thenorth shoreline which are in close proximity to the generatingfacilities and are not accessible to members of the public.

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3 ' DIRECT RADIATIONEvaluation of TLD Data - Tables 9A and 9B(Cont'd)The third group of environmental TLD's are those TLD's locatedfour to five miles from the site in each of the land based22.5 degree meteorological sectors. These TLDs are requiredby the Technical Specifications. At this distance, TLD s arenot present in eight of the sixteen meteorological sectorsthat are located over Lake Ontario.Results for this group of TLD's during 1993 fluctuatedslightly as a result of changing naturally occurringconditions and the different concentrations of naturallyoccurring radionuclides in the ground at each of thelocations. These TLD's were established in 1985 and includenumbers 88, 89, 90, 91, 92, 93, 94 and 95. Results fluctuated .from 3.4 to 6.3 mrem per standard month. These results aregenerally consistent with control TLD results during 1993.Results for this group of TLDs were consistent with the 1985

1992 results. Results were also consistent with otheroff-site TLD results during 1993 and previous to 1993.The fourth group of environmental TLD's are those TLD'slocated near the site boundary and at special interest areassuch as industrial sites, schools, nearby communities, towns,off-site air sampling stations, the closest residence to thesite, and the off-site environmental laboratory. Many ofthese TLDs are required by the Technical Specifications.Others are optional. This group of TLD's include numbers 9,10( 11/ 12( 13( 15/ 19( 51/ 52/ 53/ 54/ 55/ 56/ 58/ 96/ 97/98, 99, 100, 101, 102, 108 and 109. TLD numbers 108 and 109are TLD locations that were established to assist in theevaluation of the critical residence. Results ranged from 3.2to 5.8 mrem per standard month. All the TLD results from thisgroup were within the general variation noted for the controlTLD's. Results during 1993 for TLD's established duringprevious years were consistent with results noted for thoseyears.

The fifth group of TLD's include those TLD's considered ascontrol TLD's. These TLD's are required by the TechnicalSpecifications and include numbers 14 and 49. Optionalcontrol locations are TLD numbers 8, 111, and 113 and wereadded to the program to expand the data base for controlTLD's. Results for 1993 ranged from 3.4 to 5.6 mrem perstandard month. Results from 1993 were consistent withprevious years results. However, an annual average increasewas noted in 1986. This increase may have been a result ofthe Chernobyl Nuclear Plant accident and was not noted during1987-1993.

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3 ~ 0 DIRECT RADIATION

Evaluation of TLD Data -- Tables 9A and 9B (Cont'd)

Review of past TLD results re uired b the TechnicalS ecifications show that these TLDs can be separated into fourgroups. These groups include site boundary TLDs in eachmeteorological sector (16 TLDs total), TLDs located off-sitein each land based sector at a distance of 4 to 5 miles (8TLDs total), TLDs located at special interest areas (6 TLDstotal) and TLDs located at control locations (2 TLDs total).As noted previously, since the present TechnicalSpecifications became effective in 1985, these TLDs, for themost part, can only be evaluated for 1985 — 1993.Technical Specification TLDs located at the site boundaryaveraged 6.2 mrem per standard month during 1985. During theperiod of 1986 — 1992 site boundary TLDs ranged from 4.8 — 7.0mrem per standard month. As noted previously, this group ofTLDs can fluctuate because several of these TLDs are locatedin close proximity to the generating facilities. An increasewas noted during 1986 although such an increase was noted forall TLDs including control TLDs. During 1993, site boundaryTLDs averaged 5.3 mrem per standard month.

Technical Specification TLDs located off-site at a distance of4 to 5 miles from the site in each of the land basedmeteorological sectors averaged 5.0 mrem per standard monthduring 1985. During the period of 1986 — 1992 off-site sectorTLDs ranged from 4.1 — 6.0 mrem per standard month. The 1986results demonstrated an increase for this group of TLDs.Results for 1993 for the group averaged 4.5 mrem'per standardmonth. This is generally consistent with previous yearsresults.Special interest Technical Specification TLDs are located atareas of high population density, such as major work sites,communities, schools, etc. and at residences near the site(critical receptor areas). This group of TLDs averaged 5.3mrem per standard month during 1985. During 1986, this samegroup of TLDs averaged 6.1 mrem. During the period of 1987—1992 these TLDs averaged between 4.1 — 5.3 mrem per standardmonth. 1993 results for these locations averaged 4.5 mrem perstandard month.

The final group of TLDs required by the TechnicalSpecifications is the control group. This group utilizes twoTLD locations positioned well beyond the site. Results from1985 for the control group averaged 5.4 mrem per standardmonth. During 1986, this same group of TLDs averaged 6.3 mremper standard month. A marked increase was noted in the secondquarter of 1986. The increase may have been a result of theChernobyl Nuclear Plant accident. Results for 1987 — 1992ranged from 3.9 — 5.4 mrem per standard month. Results for1993 averaged 4.3 mrem per standard month.

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3 ' DIRECT RADIATION

B. Evaluation of TLD Data — Tables 9A and 9B -(Cont'd.)

Tables 29 and 30A-30E show the historical environmental sampledata for environmental TLD's.During 1993, all environmental TLD groups required by theTechnical Specifications were generally consistent with theresults observed during 1992. Overall, environmental TLDresults for 1993 showed no significant impact from directradiation measured outside the site boundary.

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4 ~ 0 TERRESTRIAL SAMPLES

I "«'IR PARTICULATE/IODINEA. Sam le Collection and Methodolo

f

The air sampling stations required by the TechnicalSpecifications are located in the general area of the .siteboundary (within 0.7 miles) in sectors of highest calculatedmeteorological deposition factors (D/Q) based on historicalmeteorological data. These stations (R-l, R-2, and R-3) arelocated in the east, east-southeast, and southeast sectors asmeasured from the center of the Nine Mile Point Nuclear

'tationUnit 2 reactor building. The Technical Specificationsalso require that a fourth air sampling station be located inthe vicinity of a year round community having the highestcalculated deposition factor (D/Q) based on historical..'.meteorological data. This station is located in the southeastsector (R-4). A fifth station required by the TechnicalSpecifications is located at a site 16.4 miles from the sitein a northeast direction (R-5). This location is considereda control location.In addition to the Technical Specification required locations,there are six sampling stations located within the siteboundary (D1, G, H, I, J, and K). These locations generallysurround the area occupied by the three generating facilities,but are well within the site boundary.. One other air samplingstation is located off-site in the southwest sector and is inthe vicinity of the City of Oswego. Three remaining airsampling stations (D2, E and F) are located in the east—southeast, south-southeast and south sectors and range indistance from 7.2 to 9.0 miles.At each station, airborne particulates are collected by glassfiber filters and radioiodine by charcoal filters. Airparticulate glass fiber filters are approximately two inches(47 millimeters) in diameter and are placed in sample holdersin the intake line of a vacuum sampler. Directly down streamfrom the particulate filter is a 2 x 1 inch charcoal cartridgeused to absorb airborne radioiodine. The samplers runcontinuously and the charcoal cartridges and particulatefilters are changed on a weekly basis, or as required by dustloading. Gross beta analysis is performed for the individualparticulate filters on a weekly basis. Charcoal cartridgesare analyzed weekly for radioiodine by GeLi detector.The particulate filters are composited by location for gammaanalyses on a monthly basis after all weekly particulatefilters have been counted for gross beta activity.Air sampling stations are shown in Figures 3 and 4 (refer toTable 3 for location designations and.descriptions).

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4 ' TERRESTRIAL'AMPLES

I, AIR PARTICULATE/IODINE (Cont'd)B. Evaluation of Air Particulate Gross Beta — Tables 10 and 11

Tables 10 and 11 contain the results for the weekly airparticulate gross beta analysis for a total of nine off-siteand six on-site sample locations. Five of the nine off-sitelocations are required by the Technical Specifications. Thesesample locations are R-1, R-2, R-3, R-4 (all located near thesite boundary) and R-5 (located at a control location beyondany significant influence from the site). Data contained onTables 10 and 11 also shows the results'rom other airsampling locations not required by the TechnicalSpecifications. These locations are designated as D1 on-site,,G on-site, H on-site, I on-site, J on-site, K on-site,' D2..-off-site, E off-site, F off-site and G off-site locations. Atotal of 53 control samples from location R-.5 and 212indicator samples from locations R-'1, R-2, R-3, and R-4 werecollected and analyzed during 1993.

The minimum, maximum, and average gross beta results forsample locations required by the Technical Specifications arepresented below.

Location**

R-1R-2R-3R-4R-5 (control)

Minimum*

0. 0070. 0060.0050. 007.0. 007

Maximum*

0. 0210. 0230.0250.0210.022

AveracVe*N

0. 0140.0150.0140.0140.013

* — Concentration in pci/m3** — Locations required by the Technical Specifications

The observed- small increases and decreases in general grossbeta activity can be attributed to changes in the environment,especially seasonal changes. The concentration of naturallyoccurring radionuclides in the lower limits of the atmospheredirectly above land areas are affected by processes such aswind direction, snow cover, soil temperature and soil moisturecontent. Little change was noted in gross beta activity whichcorresponded with weapons testing as has been observed in pastyears. Review of air particulate gross beta concentrationsshows that no significant increases in concentration occurredduring 1993.

In general, the trend in air particulate gross beta activityhas been one of decreasing activity since 1977 (extent of thereview period). The mean gross beta concentration at controllocations has decreased from a level of 0.165 pCi/m3 in 1981to 0.012 in 1992. Results from indicator air samplinglocations ranged from 0.151 pCi/m'n 1981 to 0.012 pCi/m'n .

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4 ' - TERRESTRIAL SAMPLESAIR PARTICULATE/IODINE (Cont'd)

B. Evaluation of Air Particulate Gross Beta — Tables 10 and 111992. For both indicator locations and control location, thegross beta concentration during 1977 to 1987 fluctuated withthe detonation of thermonuclear weapons.

C.

Tables 31 and 32 show historical environmental sample data forair particulate gross beta levels.Evaluation of Monthl Air Particulate Com osites — Table 12Weekly air particulate samples were composited by location toform monthly composite samples. The monthly composite

samples'equiredby the Technical Specifications include R-1, R-2,R-3, R-4, and R-5. Other sample locations not required by theTechnical Specifications include D1 on-site, G on-site, Hon-site, I on-site, J on-site, K on-site, D2 off-site, Eoff-site, F off-site and G off-site locations. The results ofall monthly composite samples are included on Table 12.The results for the monthly composite samples showed positiveresults for Be-7, K-40, and Ra-226. All three of theseradionuclides are naturally occurring. Be-7 was found in allof the monthly composite samples from the locations requiredby the Technical Specifications. K-40 was foundintermittently in the monthly composite samples required bythe Technical Specifications. Ra-226 was also detectedintermittently in both indicator and control samples. Noother radionuclides were detected at Technical Specificationor optional locations using gamma spectral analysis during1993.

As a result of the Chernobyl Nuclear Plant accident in April1986, several radionuclides attributable to the fissionprocess were detected in air particulate samples during 1986.Detectable radionuclides included Cs-134, Cs-137, Nb-95,Ru-103, Ru-106, La-140 and I-131. These radionuclides werenot detected during 1993.

Co-60 concentrations in air particulate samples have shown ageneral decrease in both indicator and control samples. TheCo-60 detected has primarily been attributed to past weaponstesting fallout. The general decrease in Co-60 is due toecological cycling and nuclear decay of the Co-60 initiallyproduced by weapons tests. In 1977, Co-60 concentrations incontrol samples averaged 0.0172 pCi/m . A general decreasewas observed in the years subsequent to 1977 until 1985 whenno Co-60 was detected. From the period 1985-1993 no Co-60 wasdetected in control samples. Co-.60 concentrations inindicator samples have shown a similar decrease. In 1977, the

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4 "0 TERRESTRIAL SAMPLES

AIR PARTICULATE/IODINE (Contend)

C. Evaluation of Monthl Air Particulate Com osites — Table 12(Cont'd)

average concentration of Co-60 in indicator samples. was0.0179 pCi/m'. By 1982, this value had decreased to0.0005 pCi/m'. Slight increases were observed in 1983 and1984, but these anomolies were due to contamination duringhandling of the unused samples and not due to plant operations(this has been previously documented in the 1984 annualreport). Since 1984, no Co-60 has been detected in anyTechnical Specification indicator location.

During 1987, Co-60 was detected once at a concentration of,0.0017 pCi/m3 at an optional air monitoring station. However,the Co-60 detected during 1987 was a result of contaminationfrom improper handling of the sample, and not as a result ofeffluents from the site. This evaluation is contained in the1987 annual report. Co-60 was not detected during 1988..During 1989 Co-60 was detected at one on-site optionallocation during November at a concentration of 0.009 pCi/m3.The Co-60 was attributed to. operations at the FitzPatrickfacility and was presented in the 1989 annual report. Resultsfrom 1990-1993 showed that Co-60 was not detected from anyoptional indicator sample locations.Historically, the presence of Cs-137 has been variable and hasbeen present in air particulate samples since 1977. During1977, both indicator and control Cs-137 average concentrationswere approximately equal and averaged 0.0038 pCi/m . Sincethat time the concentration in both control and indicatorsamples has been steadily decreasing. As noted above for Co-60, the decreasing concentrations of Cs-137 are due toecological cycling and nuclear decay of Cs-137 which wasproduced during weapons testing. 1978 concentrations of Cs-137 in control and indicator locations both averaged 0.0017pCi/m, and steadily decreased to 0.0002 pCi/m in 1983. Cs-137 was not detected during 1984 and 1985. In 1986, Cs-137was detected as' result of the Chernobyl accident in April1986. Average concentrations during that year for in'dicatorand control samples were 0.0183 and 0.0193 pCi/m3respectively. During the period of 1987-1993 Cs-137 was notdetected at any indicator or control location.Prior to 1984, several radionuclides were detected that wereassociated with the 1980 Chinese weapons test and otherweapons tests prior to 1980. These radionuclides were notdetected after 1983 as a result of nuclear decay andecological cycling. These include Zr-95, Ce-141, Nb-95,Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140. In addition, La-140was detected once during 1983 and infrequently during 1978 and

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4 '0 TERRESTRIAL SAMPLES

I AIR PARTICULATE/IODINE (Cont'd)C. Evaluation of Monthl Air Particulate Com osites — Table 12

(Cont'd)

1981. La-140 was not detected during 1984 or 1985. During1986, however, several fission product radionuclides weredetected that were a result of the Chernobyl Nuclear

Plant'ccident.These included Cs-134, Cs-137, Nb-95, Ru-103,Ru-106, La-140 and I-131. All of these, with the exception ofCs-134 and particulate I-131, were detected subsequent to the1980 Chinese weapons test (1981 — 1983). These radionuclideswere not detected during 1984 — 1985. The concentrationsdetected during 1986 as a result of the Chernobyl accidentwere generally greater than the concentrations detected as aresult of the 1980 Chinese weapons test. The presence of theradionuclides from the Chernobyl facility, however, extendedover a very brief period (two months) while many of theradionuclides from the 1980 Chinese weapons test were presentfor approximately two years. During 1987 through 1993, noneof the radionuclides associated with the 1986 Chernobylaccident or past weapons testing were detected in airparticulate samples.During 1991, Zn-65 was detected at one of the optional on-sitelocations. Zn-65 was detected at the H-onsite location at aconcentration of 0.0046 pCi/m'uring the analysis of theFebruary air particulate composite sample. The airparticulate filters were then analyzed separately and it wasdetermined that the Zn-65 was deposited during week 5 of 1991(1/28/91 — 2/4/91) at a concentration of 0.0283 pCi/m3. Thepresence of Zn-65 in the sample was due to operations at theJames A. Fitzpatrick facility. Zn-65 was not detected at anyof the sample locations during 1992 or 1993.

During 1993, no radionuclides were detected in monthly airparticulate composite samples that could have been attributedto plant operations. Therefore, no dose calculations wereperformed.

Tables 33 and 34 show historical environmental sample data for.air particulate composites.During the 1993 sampling program, airborne radioiodine was notfound in any .of the fifty-three weekly samples from thecontrol location required by the Technical Specifications.LLD values at the control location ranged from 0.008 — 0.021pCi/m'.

I-131 has been detected in the past at control locations andwas attributed to past weapons testing and the Chernobylaccident. During 1976,.the mean off-site I-131 concentrationwas 0.60 pCi/m'. The 1977 mean I-131 concentration decreasedto 0.32 pCi/m and for 1978 the concentration decreased by a

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4 ~ 0 TERRESTRIAL SAMPLES

I AIR PARTICULATE/IODINE (Cont'd)D. Evaluation of Airborne Radioiodine — Tables 13 and 14

factor of ten to 0.03 pCi/m'. During 1979 — 1981 and 19831985,'-131 was not detected. I-131 was detected once during1982 at a concentration of 0.039 pCi/m'. Results from 1986showed that I-131 was detected at the control location. Thiswas a result of the 1986 Chernobyl Nuclear Plant accident.The I-131 mean result was 0.151 pCi/m'. I-131 was notdetected at the control location during the period 1987through 1993.

During 1993, the indicator locations required by the TechnicalSpecifications (approximate site boundary locations) showed nodetectable levels of I-131. LLD values for I-131 ranged from0.005 — 0.031 pCi/m3. I-131 was also not detected at any ofthe optional monitoring locations'not required by theTechnical Specifications) during 1993.

0

I-131 at indicator locations has been detected in the past andwas detected at a mean concentration of 0.33 and 0.31 pCi/m3during 1976 and 1977. The average concentration decreased to0.04 pCi/m during 1978 and was not detected during 1979. The1980-1982 average concentrations were 0.013, 0.029, and 0.016pCi/m~ which were reductions in view of previous I-131concentrations. During 1983, the mean I-131 concentration was0.028 pCi/m~ which represented a slight increase compared to1982. For the most part, I-131 in indicator and controlsamples was a result of I-131 from weapons testing. A smallportion of the concentrations detected for a few isolatedinstances may have been a result of operations at the site.The concentrations detected during 1983 at the on-site samplestations were a result of operations at the site. I-131 wasnot detected in any of the 1984 or 1985 samples. During 1986,I-131 was detected at the indicator locations at a meanconcentration of 0.119 pCi/m's a result of the ChernobylNuclear Plant accident. I-131 was found at a meanconcentration of 0.014 pCi/m'uring 1987 and was a result ofoperations at the site. I-131 was not found at the TechnicalSpecification required indicator locations during 1988 through1993.

Since I-131 was not detected at any of the indicator orcontrol locations during 1993, no dose calculations arepresented.

Tables 35 and 36 show the historical environmental sample datafor airborne radioiodine.

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4 0 TERRESTRIAL SAMPLES

I AIR PARTICULATE/IODINE (Cont'd)II MILK

A. Sam le Collection Methodolo and Anal sis

Milk samples are collected in polyethylene bottles from a bulkstorage tank at each sampled farm. Before the sample isdrawn, the tank contents are agitated from three to fiveminutes to assure a homogenous mixture of milk and butterfat.

'wogallons are collected during the first half and secondhalf of each month from each of the selected locations withinten miles of the site and from a control location. Thesamples are chilled and shipped fresh to the analytical.'.laboratory within thirty-six hours of collection in insulatedshipping containers.

The selection of milk sample locations is based on maximumdeposition factors (D/Q). Deposition factors are generatedfrom average historical meteorological data based on alllicensed reactors. The Technical Specifications require threesample locations within 5.0 miles of the site with the highestcalculated deposition factors. During 1993, there were nomilk sample locations within 5.0 miles that could be sampled.However, there were several optional locations beyond fivemiles that were sampled.A fourth sample location required by the TechnicalSpecifications is located in a least prevalent wind directionfrom the site. This location is in the southwest sector andserves as a control location.

Milk samples are collected twice per month (April — December)and analyzed for gamma emitters and I-131. Samples arecollected and analyzed in January — March in the event I-131is detected in November and December of the preceding year.

B.

The milk sample locations are found on Figure 2. (refer toTable 3 for location designations and descriptions).Evaluation of Milk Data - Tables 15 and 16Milk samples were collected from a total of five indicatorlocations (within 10 miles of the site) and one controllocation (beyond 10 miles from the site) during 1993. TheTechnical Specifications require that three locations besampled for milk within 5.0 miles of the site. During 1993,there were no milk sample locations within 5.0 miles of thesite. The locations that were sampled during 1993 are located

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4 ~ 0 . '", 'ERRESTRIAL 'AMPLES

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MILK (Cont! d)

B. Evaluation of Milk Data — Tables 15 and 16P

from 5.5 to 9.5 miles from the site. The only sample locationrequired by the Technical Specifications during 1993 was thecontrol location. -During 1993, two control locations wereutilized in - order to satisfy the Technical'pecificationrequirement. Location number 65 was utilized from Aprilthrough mid August and location number 73 was utilized frommid August through December. The reason two locations were

'tilizedwas that the original control location (number 65)had sold its herd during the sampling period. Sample locationdescriptions for all milk sample locations utilized during1993 are listed as follows:

Location No. Direction From Site Distance From Site miles

7505560

465 (Control)73 (Control)

ESEEEEESESWSW

(107 o )( 930)( 950)( 90O)(113')(220 )(234 o)

5.59.39.09.57.8

17.013 '

During 1993, milk samples were collected at each of the fiveindicator locations and the control location in the first halfand the second half of each month. Samples were collectedduring the months of April through December 1993. Since I-131was not detected during November and December of 1992, noadditional samples were collected in January through March of1993. For each sample, analyses were performed for gammaemitters (analysis by GeLi detector) and for I-131 using aresin extraction. Sample analysis results for gamma emittersare found on Table 15 and for I-131 on Table 16.Gamma spectral analyses of the bimonthly samples showed onlynaturally occurring radionuclides such as K-40 and Ra-226 tobe detected in milk samples during 1993. K-40 was detected inall indicator and control samples. Ra-226 occurredintermittently in milk samples. K-40 and Ra-226 are naturallyoccurring radionuclides and are found in many of theenvironmental media sampled.

During 1993, Cs-134 or Cs-137 were not detected in any controlor indicator location milk samples. Cs-137 had been detectedonce in 1988 and was attributed to the, use of silagecontaining trace amounts of Cs-137 from the 1986 ChernobylNuclear Plant accident.

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4 ' TERRESTRIAL SAMPLES

II MILK

t B.(Cont'd)

Evaluation of Milk Data - Tables 15 and 16No other radionuclides were detected in milk samples usinggamma spectral analysis.

Milk samples were collected and analyzed twice per monthfor'-131.I-131 was not detected during 1993 in any of the

indicator or control samples. All 1993 I-131 milk sampleresults are reported as the lower limit of detection (LLD).The LLD results for 1993 milk samples ranged from

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Ie4 ' TERRESTRIAL SAMPLES

II MILK (Cont'd)B. Evaluation of Milk Data — Tables 15 and 16

tli

accident. The continued reduction of Cs-137 levels is aresult of nuclear decay and ecological cycling.An evaluation of historical data for I-131 in milk samplesshows that annual mean results ranged from 0.19 pCi/liter to6.88 pCi/liter at the indicator locations during 1976 — 1978.I-131 during these years is a result of intermittent weaponstesting. During 1979 — 1985, I-131 in milk samples at theindicator locations was not detected except during 1980. Themean result during 1980 was 3.8 pCi/liter and was a result ofthe 1980 Chinese Weapons Test. Results from 1986 showed thatI-131 was detected at a mean concentration 'of 5.2 pCi/liter asa result of the Chernobyl accident. I-131 was not detectedduring the period 1987 through 1993 in milk samples.Historical data for I-131 from the control location showedthat I-131 was detected during 1980 at a mean concentration of1.4 pCi/liter. There was no detectable I-131 during theperiod of 1978 — 1985 with the exception of 1980. During1986, I-131 from the control location showed a meanconcentration of 13.6 pCi/liter as a result of the Chernobylaccident. I-131 was not detected during the period 1987through 1993 at the control location.Tables 37 and 38 show the historical environmental sample datafor milk.Cs-134, Cs-137, and I-131 were not detected in the bi-monthlymilk samples analyzed for 1993. Only naturally occurringradionuclides such as Ra-226 and K-40 were detected.Therefore, no doses to man have been calculated.

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TERRESTRIAL'SAMPLES

ZZI FOOD PRODUCTS

i A. Sam le Collection Methodolo and Anal sis'IFood products are collected once per year during the latesummer at the approximate height of the harvest season.Approximately one kilogram of a broadleaf vegetable or otherbroadleaf vegetation is collected from garden locations withthe highest deposition factors (D/Q) based on averagehistorical meteorological data. Five sample locations wereutilized from at least two sectors. Additional samples mayalso be obtained. Control samples are also collected fromavailable off-site locations 9 to 20 miles distant in a leastprevalent wind direction. Control samples are of the same orof a similar type of vegetation. All samples are shippedfresh as soon as possible after collection.Food product samples are analyzed for gamma emitters (gammaisotopic analysis). The gamma isotopic analysis also includesI-131-

Food product locations are shown on Figure 1 (refer to Table3 for location designations and descriptions).

B. Evaluation of Food Product Data — Tables 17A and 17B

Food product samples collected during 1993 were comprised ofgarden vegetables and other types of vegetation. Samples werecollected from five indicator locations and one controllocation. The indicator locations were represented by nearbygardens in areas of highest D/Q (deposition factor) valuesbased on historical meteorology and all site release points atoperating facilities. The control location was represented bya garden location 9-20 miles distant in a least prevalent winddirection. Garden vegetables were comprised of cabbage,lettuce, tomatoes, collard greens, squash leaves, and swisschard, which are all (except tomatoes) considered broadleafvegetables. Other broadleaf vegetation consisted of beetleaves, pepper leaves, bean leaves, grape leaves, and cucumberleaves. At the control location, one sample of each of thesame or of a similar type of vegetable or vegetation was.collected. Vegetables and vegetation were collected in thelate summer harvest season (mid-September 1993).Results for food products are shown on Tables 17A and 17B.Table 17A shows results in pCi/g (wet) while Table 17B resultsare in units of pCi/kg (wet). Only naturally occurringradionuclides were detected in indicator samples during 1993.K-40 was detected in all food product samples. Be-7 was alsofound in all but two of the vegetation samples. AcTh-228 andRa-226 were detected intermittently.. K-40, Be-7, Ra-22'6andAcTh-228 are all naturally occurring radionuclides. Cs-137was detected in one control sample of cucumber leaves during

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4.0 TERRESTRIAL SAMPLES

III FOOD PRODUCTS (Cont d)A. Evaluation of Food Product Data — Tables 17A and 17B (Cont'd)

1993. Cs-137 was not detected in any of the indicatorsamples. It is likely the Cs-137 was present due to weaponstesting fallout on -the soil and subsequent uptake by theplant. The concentration of Cs-137 in the control sample

was'.007pCi/g (wet). No other radionuclides were detected inthe 1993 samples of food products.

Review of past environmental data indicates that Cs-137 hasbeen detected intermittently during the years of 1976 — 1992at the indicator locations and during the years of 1980 — 1992at the control locations (control samples were not obtainedprior to 1980). Review of indicator sample results from 1976— 1992 showed that Cs-137 was not detected during 1976 — 1978,1981 — 1984, 1986 - 1987, or 1990 and 1992. During 1979 and1980, Cs-137 in fruits and/or vegetables showed annual meanconcentrations of 0.004 and 0.036 pCi/g (wet) respectively.Cs-137 was found at an indicator location during 1985 at. aconcentration of 0.047 pCi/g (wet). During 1988 and 1989Cs-137 was found at a concentration of 0.008 and 0.009 pCi/g(wet). Cs-137 was detected at a concentration of 0.040 pCi/g(wet) at an indicator location during 1991. Control sampleresults during 1980-1990 showed Cs-137 detected only onceduring 1980 at a concentration of 0.02 pCi/g (wet). Cs-137was not detected in indicator samples during 1992 or 1993. Asstated previously, Cs-137 was detected in one control sampleat a concentration of 0.007 pCi/g (wet) in 1993.

J

Tables 39 and 40 show historical environmental sample data forfood products.

IV LAND USE CENSUS

A.

A land use census is conducted to determine the utilization ofland in the vicinity of the site. The land use censusactually consists of two types of census. A milk animal.census is conducted to identify all milk animals within adistance of 10 miles from the site. A residence census isconducted to identify the closest residence in each of themeteorological sectors.

The milk animal census is an estimation of the number of cowsand goats within an approximate ten mile radius of the NineMile Point Site. A census is initiated once per year in thespring. The census is conducted by sending questionnaires toprevious milk animal owners and also by. road surveys to locateany possible new owners. In the event questionnaires are notanswered, then the owners are contacted by telephone or inperson. The local agricultural agency was also contacted.

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4 ~ 0 TERRESTRZAL SAMPLES

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IV ~ LAND

A.

B.

USE CENSUS (Cont'd)

A second type of census is a residence census. This census isconducted in accordance with the Technical Specifications inorder to identify the closest residence within three miles ineach of the 22.5 degree meteorological sectors. A residence,'or

the purposes of this census, is a residence that isoccupied on a part time basis (such as a summer camp), or ona full time, year round basis. For the residence census,several of the meteorological sectors are over Lake Ontariobecause the site is located at the shoreline. Therefore,there are only eight sectors over land where residences arelocated within 3 miles.

During 1993, a residence census was conducted to identify thenearest residence in each of the sixteen 22.5 de'greemeteorological sectors within a distance of five miles fromthe site in order to provide more comprehensive census data.At this distance, some of the meteorological sectors are overwater. These sectors include: N, NNE, NE, ENE, Wg WNW/ NW,and NNW.

Evaluation of Data — Tables 18 and 19

The number of milk animals located vithi an approximate tenmile radius of the site was estimated to be 1036 cows and 10goats for the 1993 census. The number of cows decreased by 84and the number of goats increased by 3 with respect to'he1992 census. One new milk location and several locationswhere milk animals were no longer present were identifiedduring the 1993 census. One control sampling location wasdiscontinued approximately half-way through the grazing seasonbecause the herd was sold off. However, a new controllocation was identified and added to the 1993 samplingprogram. There were no other changes made to the milksampling program. Most of the goats found on the census weremilking goats. However, any milk produced was utilized by theowners and was not available for the sampling program. Theresults of the milk animal census are found on Table 18. Milkanimal locations are shown on Figure 2.

The results of the 1993 residence census showing theapplicable sectors and degrees and distance of each of thenearest residences are found on Table 19. The nearestresidences are shown in Figure 1. No changes were noted in1993.

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5 0 INTERLABORATORY COMPARISON PROGRAM

Section 3.6.21 and Section 3.12.3 of the TechnicalSpecifications for the Nine Mile Point Nuclear Station Unit 1and Unit 2, respectively, require ,that a summary of theresults obtained as part of an Interlaboratory ComparisonProgram be included in the Annual Radiological EnvironmentalOperating Report. Presently, the only NRC approvedInterlaboratory Comparison Program is the USEPA Cross CheckProgram. Table 20 shows the results of the EPA's

reference'esults

and the licensee's results. Some of the EPA referencesamples have been analyzed by the site. Other EPA referencesamples have been analyzed by a vendor who normally analyzesthose types of sample media for the site. Participation inthe EPA Cross Check Program includes sample media for whichenvironmental samples are routinely collected, as required byTable 3.6.20 — 1 and Table 3.12.1 — 1 of the Technical., ~Specifications and for which intercomparison samples areavailable from the EPA. Where many samples are available fromthe EPA, a QC sample to program sample ratio of ten percent isutilized, where applicable.Results from the EPA are presented in terms of normalizeddeviations from.a known value (NDKV). Laboratory results areconsidered acceptable by EPA if the NDKV for each sample isbetween plus or minus 3 NDKV. All analyses but one performedby the Site Environmental Laboratory during 1993 were within3NDKV. One sample analyzed by the Site EnvironmentalLaboratory was outside three normalized deviations. Thesample QA-93-078 was a water sample analyzed for mixed gamma.The sample was analyzed for Co-60, Zn-65, Ru-106, Cs-134, Cs-137, and Ba-133. Five of the radionuclide activities werewithin 1.0 normalized deviations, while the Ru-106 activitywas -3.13 from the normalized deviations.

The USEPA known activity for Ru-106 was 119 + 12 pCi/1. TheSite Environmental Laboratory reported a mean result of97 + 9 pCi/1. The Environmental Laboratory staff routinelyuses a factor of 1.13 to correct an i+consistency in thepublished gamma yield factor. However, in this case, theresults were not corrected prior to submittal to the EPA forevaluation. As noted, the other five radionuclides measuredin this sample were within one standard deviation from theknown, indicating no systematic error. All other analysesperformed by the Site Environmental Laboratory and the vendorlaboratory during 1993 were acc'eptable.

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6.0 HIST RICALEM''IR M4ENTALSAMPLE DATA

39

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6 ~ 0 HISTORICAL ENVIRONMENTAL SAMPLE DATA

Tables 21 — 40 show historical environmental sample data forcritical radionuclides or radionuclides routinely detected inenvironmental sample media. Data show the minimum, maximum,and mean for each year evaluated. The data only considerdetectable quantities and do not consider lower limit ofdetection (LLD) quantities. Data on Tables 21 — 40 wereobtained from previous Annual Radiological EnvironmentalOperating Report tables.

40

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HAN ES AND EX EPTI N T THE PR RAIVI

41

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Environmental air sample equipment at R-4 off-sitesampling station was found to be inoperable from 7/6/93at 1030 hours to 7/7/93 at 1400 hours. It was determinedthat during the monthly thermostat and operability checkof this station the pump was left off. The pump wasrestarted at the time of discovery.

>

'-.7''0 'HANGES AND EXCEPTIONS"TO THE PROGRAM'I

~~ ~ ~

~ ~

A. . Chan es to the 1993 Sam le Pro ra.1.'. During 1993, milk sampling location 65 was discontinued

„.- after the first collection in August 1993. The herd atthis location was sold off by the owner. Location 65 wasthe control location and the Technical Specification

..required location. It was replaced with location number73. Location number 73 meets the requirements of acontrol location as defined in Technical Specifications,

I and was utilized beginning with the second coll'ectionduring August 1993.B. Exce tions to the 1993 Sam le Pro ram

Exceptions to the 1993 sample program concerns those samples..~...or monit