Text

2009 Annual Radiological Environmental Operating Report
	ML101260508
Person / Time
Site:	FitzPatrick
Issue date:	12/31/2009
From:	; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
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ML101260512	List: JAFP-10-0056, 2009 Annual Radiological Environmental Operating Report; JAFP-10-0056, James A. FitzPatrick - Transmittal of 2009 Annual Radiological Environmental Operating Report; ML101260507;
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J AMES A.F ITZ P ATRICK N UCLEAR P OWER P LANT 2009 A NNUAL R ADIOLOGICAL ENVIRONMENTAL O PERATING R EPORT A NNUAL RADIOLOGICAL E NVIRONMENTAL O PERATING R EPORTJanuary 1, 2009 - December 31, 2009for JAMES A.FITZ PATRICK NUCLEAR POWER PLANT ENTERGY NUCLEAR FITZ PATRICK , LLC ENTERGY NUCLEAR OPERATIONS , I NC.Facility Operating License No. DPR-59Docket No. 50-333 iTABLE OF CONTENTS Page1.0 PURPOSE..............................................................................................................................1-

12.0 INTRODUCTION

..................................................................................................................2-12.1 Program History.........................................................................................................2-1 2.2 Site Description..........................................................................................................2

-22.3 Program Objectives....................................................................................................2-23.0 PROGRAM DESCRIPTION.................................................................................................3-13.1 Sample Collection Methodology.................................................................................3-6

3.2 Analyses

Performed..................................................................................................3-12

3.3 Sample

Locations......................................................................................................3-12 3.4 Land Use Census......................................................................................................3-26

3.5 Changes

to the REMP Program...............................................................................3-27

3.6 Deviation

and Exceptions to the Program................................................................3-28

3.7 Statistical

Methodology............................................................................................3-29

3.8 Compliance

with Required Lower Limits of Detection (LLD).................................3-323.9 Regulatory Limits.....................................................................................................3-344.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICALPOSITION FORMAT............................................................................................................4-15.0 DATA EVALUATION AND DISCUSSION.......................................................................5-15.1 Aquatic Program.........................................................................................................5-5

5.2 Terrestrial

Program...................................................................................................5-13 5.3 Conclusion................................................................................................................5-325.4 References................................................................................................................5-346.0 REPORT PERIOD ANALYTICAL RESULTS TABLES....................................................6-1

7.0 HISTORICAL

DATA TABLES............................................................................................7-1

8.0 QUALITY

ASSURANCE/QUALITY CONTROL PROGRAM..........................................8-1

9.0 GRAPHICAL

PRESENTATIONS........................................................................................9-1 iiLIST OF TABLES PageTable 3.0-1 Required Sample Collection and Analysis..................................................................3-2Table 3.3-1 Environmental Sample Locations.............................................................................3-14 Table 3.8-1 Required Detection Capabilities for Environmental Sample AnalysisLower Limit of Detection (LLD) .............................................................................3-33Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary..........................4-2 Table 6-1Concentrations of Gamma Emitters in Shoreline Sediment Samples.....................6-2 Table 6-2Concentrations of Gamma Emitters in Fish Samples FitzPatrick............................................................................................................6-3 Nine Mile Point....................................................................................................6-4 Oswego Harbor....................................................................................................6-5Table 6-3Concentrations of Tritium in Surface Water SamplesQuarterly Composite Samples..................................................................................6-6Table 6-4Concentrations of Gamma Emitters in Surface Water Samples Oswego Steam Station.........................................................................................6-7 Oswego City Water..............................................................................................6-8 FitzPatrick............................................................................................................6-9 Nine Mile Point Unit 1.......................................................................................6-10 Nine Mile Point Unit 2.......................................................................................6-11Table 6-5Environmental Airborne Particulate Samples Gross Beta Activity Offsite Sample Locations (Jan-Jun).................................................................6-12(Jul-Dec).................................................................6-13Table 6-6Environmental Airborne Particulate Samples Gross Beta Activity Onsite Sample Locations (Jan-Jun).................................................................6-14(Jul-Dec).................................................................6-15Table 6-7Environmental Charcoal Cartridge Samples I-131 Activity Offsite Sample Locations (Jan-Jun).................................................................6-16(Jul-Dec).................................................................6-17Table 6-8Environmental Charcoal Cartridge Samples I-131 Activity Onsite Sample Locations (Jan-Jun).................................................................6-18(Jul-Dec).................................................................6-19 iiiLIST OF TABLES (Continued)

PageTable 6-9Concentrations of Gamma Emitters in Quarterly Composites ofJAF/NMPNS Site Air Particulate SamplesOffsite Sample Locations - 1st & 2nd Qtrs......................................................6-203rd & 4th Qtrs.......................................................6-21Onsite Sample Locations - 1st & 2nd Qtrs......................................................6-223rd & 4th Qtrs.......................................................6-23Table 6-10 Direct Radiation Measurement Results.....................................................................6-24 Table 6-11 Concentrations of Iodine-131 and Gamma Emitters in MilkSample Location No.55 .....................................................................................6-26 Sample Location No.76 .....................................................................................6-27 Sample Location No.77 (Control) .....................................................................6-28Table 6-12 Concentrations of Gamma Emitters in Food Products......................................6-29 Table 6-13 Milk Animal Census........................................................................................6-31 Table 6-14 Residence Census............................................................................................6-32Historical Environmental Sample DataTable 7-1Shoreline SedimentControl.................................................................7-2Table 7-2Indicator...............................................................7-3Table 7-3FishControl.................................................................7-4Table 7-4Indicator...............................................................7-5Table 7-5Surface WaterControl.................................................................7-6Table 7-6Indicator...............................................................7-7Table 7-7Surface Water TritiumControl.................................................................7-8Table 7-8 Indicator...............................................................7-9Table 7-9Air Particulate Gross Beta Control................................................................7-10Table 7-10Indicator..............................................................7-11Table 7-11 Air ParticulatesControl................................................................7-12Table 7-12Indicator..............................................................7-13 ivLIST OF TABLES (Continued)

PageHistorical Environmental Sample Data (Continued)Table 7-13 Air RadioiodineControl................................................................7-14Table 7-14Indicator..............................................................7-15Table 7-15 Environmental TLDControl................................................................7-16Table 7-16Site Boundary......................................................7-17Table 7-17Offsite Sectors.....................................................7-18Table 7-18Special Interest....................................................7-19Table 7-19Onsite Indicator...................................................7-20Table 7-20Offsite Indicator...................................................7-21Table 7-21 MilkControl................................................................7-22Table 7-22Indicator..............................................................7-23Table 7-23 Food ProductsControl................................................................7-24Table 7-24Indicator..............................................................7-25Table 8-1Interlaboratory Intercomparison Program.........................................................8-7 vLIST OF FIGURES PageFigure 3.3-1 New York State Map...............................................................................................3-19Figure 3.3-2 Off-Site Environmental Station and TLD Locations Map........................................3-20 Figure 3.3-3 Onsite Environmental Station and TLD Locations Map...........................................3-21 Figure 3.3-4 Milk and Surface Water Sample Locations Map......................................................3-22 Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline SedimentSample Locations Map ............................................................................................3-23Figure 3.3-6 Nearest Residence Locations Map............................................................................3-24 Figure 3.3-7 On-Site Ground Water Monitoring Wells Map........................................................3-25 Figure 9.1Graph - Fish (Cs-137).................................................................................................9-2Figure 9.2Graph - Surface Water - Tritium.................................................................................9-3 Figure 9.3Graph - Air Particulate Filter Gross Beta, Annual......................................................9-4 Figure 9.4Graph - Air Particulate Filter Gross Beta, Weeks 1-26...............................................9-5 Figure 9.5Graph - Air Particulate Filter Gross Beta, Weeks 27-52.............................................9-6 Figure 9.6Graph - Air Particulate Filter Composite Co-60.........................................................9-7 Figure 9.7Graph - Air Particulate Filter Composite Cs-137........................................................9-8 Figure 9.8Graph - Air Charcoal I-131.........................................................................................9-9Figure 9.9Graph - Milk Cs-137.................................................................................................9-10Figure 9.10 Graph - Milk I-131...................................................................................................9-11Figure 9.11 Graph - TLD Data....................................................................................................9-12 1 - 11.0PURPOSEThe Annual Radiological Environmental Operating Report is published in accordance with theJames A. FitzPatrick Nuclear Power Plant Offsite Dose Calculation Manual (ODCM), Part I,Section 6.1. The ODCM requires that the results from the annual Radiological Environmental Monitoring Program (REMP) be provided to the Nuclear Regulatory Commission by May 15 th ofeach year.This report describes the Radiological Environmental Monitoring Program (REMP), theimplementation of the program, and the results obtained as required by the Offsite Dose Calculation Manual (ODCM). The report also contains the analytical results tables, dataevaluation, dose assessment, and data trends for each environmental sample media. Also includedare results of the land use census, historical data, and the Environmental Laboratorys performance in the Quality Assurance Intercomparison.The REMP is a comprehensive surveillance program, which is implemented to assess the impactof site operations on the environment and compliance with 10CFR20, 40CFR190 and 10CFR72.

Samples are collected from the aquatic and terrestrial pathways applicable to the site. The aquatic pathways include Lake Ontario fish, surface waters and lakeshore sediment. The terrestrialpathways include airborne particulate and radioiodine, milk, food products and direct radiation.During 2009 there were 1,971 analyses performed on environmental media collected as part of theREMP. These results demonstrated that there is no significant or measurable radiological impactfrom the operation of the James A. FitzPatrick Nuclear Power Plant. The 2009 results for allpathways sampled are consistent with the previous five-year historical results and exhibited no adverse trends.In summary, the analytical results from the 2009 Radiological Environmental Monitoring Programdemonstrate that the routine operation at the James A. FitzPatrick site had no significant or measurable radiological impact on the environment. The program continues to demonstrate that the dose to a member of the public, as a result of the operation of the James A. FitzPatrick NuclearPower Plant, remains significantly below the federally required dose limits specified in 10CFR20,40CFR190 and 10CFR72.

2-

12.0INTRODUCTION

The James A. FitzPatrick Nuclear Power Plant is owned and operated by Entergy NuclearFitzPatrick, LLC (ENF), Entergy Nuclear Operations, Inc. (ENO). This report is submitted in accordance with Offsite Dose Calculation Manual, Part I, Section 6.1. This report covers the calendar year 2009.2.1PROGRAM HISTORYEnvironmental monitoring at the Nine Mile Point site has been ongoing since 1964. The programincludes five years of preoperational data, which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required preoperational environmental site testing program. This pre-operational data serves as a reference point to compare later data obtained during reactor operation. In 1969, the Nine Mile Point Unit 1 reactor, a 615 megawatt Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrickNuclear Power Plant, owned and operated at that time by the New York Power Authority, began full power operation. The FitzPatrick plant, an 892 megawatt (rated) BWR, occupies the east sector of the Nine Mile Point site, approximately 0.57 miles east of Nine Mile Point Unit 1. In 1988, the Nine Mile Point Unit 2 reactor, also owned and operated by Niagara Mohawk, began full power operation. This 1207 megawatt BWR is located between the Nine Mile Point Unit 1 and FitzPatrick sites.In 1985, the individual Plant Effluent Technical Specifications were standardized to the genericRadiological Effluent Technical Specifications, much of which was common to the two reactors, and subsequently Nine Mile Point Unit 2. Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the Radiological Environmental Monitoring Program is shared, but each utility reviews and publishestheir own annual report. On November 21, 2000 the ownership and operation of the James A.

FitzPatrick Nuclear Power Plant was transferred from the New York Power Authority to Entergy Nuclear FitzPatrick, LLC and Entergy Nuclear Operations, Inc. The Facility Operating License No.

DPR-59 and Docket No. 50-333 remained the same. On November 7, 2001, the ownership of the Nine Mile Point Unit I and II facilities was transferred to Constellation Nuclear. These facilities are operated by Nine Mile Point Nuclear Station, LLC.In summary, three Boiling Water Reactors, which together generate 2714 megawatts, haveoperated collectively at the Nine Mile Point site since 1988. A large database of environmental results from the exposure pathways have been collected and analyzed to evaluate the potential impact from reactor operations.

2-22.2SITE DESCRIPTIONThe Nine Mile Point site is located on the southeast shore of Lake Ontario in the town of Scriba,approximately 6.2 miles northeast of the city of Oswego. The nearest metropolitan area is located approximately 36 miles southeast of the site. The James A. FitzPatrick Nuclear Power Plant andsupport buildings occupy a small shoreline portion of the 702 acre Entergy site, which is partially wooded. The land, soil of glacier deposits, rises gently from the lake in all directions. Oswego County is a rural environment, with about 15% of the land devoted to agriculture.2.3PROGRAM OBJECTIVESThe objectives of the Radiological Environmental Monitoring Program are to:1.Measure and evaluate the effects of plant operation on the environs and to verify theeffectiveness of the controls on radioactive material sources.2.Monitor natural radiation levels in the environs of the James A. FitzPatrick Nuclear PowerPlant site.3.Demonstrate compliance with the requirements of applicable federal regulatory agencies,including Technical Specifications and the Offsite Dose Calculation Manual.

3-1 3.0PROGRAM DESCRIPTIONTo achieve the objectives listed in Section 2.3, an extensive sampling and analysis program isconducted every year. The James A. FitzPatrick Nuclear Power Plant (JAFNPP) RadiologicalEnvironmental Monitoring Program (REMP) consists of sampling and analysis of various mediathat include:AirFishFood ProductsMilkShoreline SedimentSurface WatersGround WatersIn addition, direct radiation measurements are performed using thermoluminescent dosimeters(TLDs). These sampling programs are outlined in Table 3.0-1. The JAF REMP samplinglocations are selected and verified by an annual Land Use Census. The accuracy and precision of the program is assured by participation in an Interlaboratory Comparison Quality Assurance Program (ICQAP).Sample collections for the radiological program are accomplished by a dedicated siteenvironmental staff from both the Nine Mile Point Nuclear Stations (NMPNS) and James A.

FitzPatrick Nuclear Power Plant (JAFNPP). The site staff is assisted by a contractedenvironmental engineering company, EA Engineering, Science and Technology, Inc. (EA).

3-2TABLE 3.0-1REQUIRED SAMPLE COLLECTION AND ANALYSISExposure Pathwayand/or SampleNumber of Samples (a) and LocationsSampling andCollection Frequency(a)Type and Frequencyof AnalysisAIRBORNERadioiodineAnd ParticulatesSamples from 5 locations:a.3 Samples from offsite locations in different sectors of thehighest calculated site average D/Q (based on all licensed sitereactors.).b.1 sample from the vicinity of a community having the highestcalculated site average D/Q (based on all licensed site reactors).c.1 sample from a control location 9 to 20 miles distant and in theleast prevalent wind direction(d).Continuous sampleoperation with samplecollection weekly, or asrequired by dustloading, whichever ismore frequent.Radioiodine Canisters:Analyze weekly for I-131.Particulate Samples:Gross beta radioactivityfollowing filter change(b)composite (by location for gamma isotopic quarterly (asa minimum).Direct Radiation(e) 32 stations with two or more dosimeters placed as follows:a.An inner ring of stations in the general area of the site boundary.

b.An outer ring, in the 4 to 5 mile range from the site, with astation in each of the land based sectors. There are 16 landbased sectors in the inner ring, and 8 land based sectors in theouter ring.c.The balance of the stations (8) are placed in special interest areassuch as population centers, nearby residences, schools, and in 2or 3 areas to serve as control stations.QuarterlyGamma dose monthly orquarterly.

3-3TABLE 3.0-1 (Continued)REQUIRED SAMPLE COLLECTION AND ANALYSISExposure Pathwayand/or SampleNumber of Samples (a) and LocationsSampling andCollection Frequency(a)Type and Frequencyof AnalysisWATERBORNESurface(f)a.1 sample upstream.(d)b.1 sample from the sites most downstream cooling water intake.Composite sample overa one month period(g).Gamma isotopic analysismonthly. Composite for Tritium analysis quarterly(c).Sediment fromShoreline1 sample from a downstream area with existing or potentialrecreational value.Twice per year.Gamma isotopic analysissemiannually (c).INGESTIONMilka.Samples from milk animals in 3 locations within 3.5 milesdistant having the highest calculated site average D/Q. If thereare none, then 1 sample from milk animals in each of 3 areas 3.5to 5.0 miles distant having the highest calculated site average D/Q (based on all licensed site reactors)(h).b.1 sample from milk animals at a control location (9 to 20 milesdistant and in a less prevalent wind direction)(d).Twice per month, Aprilthrough December(samples will becollected in January through March if I-131 is detected in Novemberand December of thepreceding year).Gamma isotopic and I-131analysis twice per monthwhen milch animals are onpasture (April through December); monthly (January through March), if required(c).

3-4TABLE 3.0-1 (Continued)REQUIRED SAMPLE COLLECTION AND ANALYSISExposure Pathwayand/or SampleNumber of Samples (a) and LocationsSampling andCollection Frequency(a)Type and Frequencyof AnalysisFISHa.1 sample of each of 2 commercially or recreationally importantspecies in the vicinity of a site discharge point.b.1 sample of each of 2 species (same as in a. above or of a specieswith similar feeding habits) from an area at least 5 miles distantfrom the site (d).Twice per year.Gamma isotopic(c) analysis ofedible portions.

FOOD PRODUCTSa.In lieu of the garden census as specified in Part 1, Section 5.2,samples of at least 3 different kinds of broad leaf vegetation (such as vegetables) grown nearest each of two different offsite locations of highest predicted site average D/Q (based on alllicensed site reactors).One (1) sample of each of the similar broad leaf vegetationgrown at least 9.3 miles distant in a least prevalent winddirection sector(d).Once during harvestseason.Gamma isotopic(c) analysis ofedible portions. (Isotopic to include I-131).

3-5NOTES FOR TABLE 3.0-1(a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media ofchoice at the most desired location or time. In these instances, suitable alternative media and locationsmay be chosen for the particular pathway in question. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in theODCM) for all licensed site reactors.(b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allowfor radon and thoron daughter decay. If gross beta activity in air is greater than 10 times a historicalyearly mean of control samples, gamma isotopic analysis shall be performed on the individualsamples.(c) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclidesthat may be attributable to the effluents from the plant.(d) The purpose of these samples is to obtain background information. If it is not practical to establishcontrol locations in accordance with the distance and wind direction criteria, other sites which providevalid background data may be substituted.(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose ratecontinuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of thistable, a thermoluminescent dosimeter may be considered to be one phosphor and two or morephosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.(f) The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The"downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.(g) Composite samples should be collected with equipment (or equivalent) which is capable of collectingan aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g.,monthly) in order to assure that a representative sample is obtained.(h) A milk sampling location as required in Table 3.0-1 is defined as a location having at least 10 milkingcows present at a designated milk sample location. It has been found from past experience, and as aresult of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes, which eliminates a stable supply of milk forsamples as a result of suckling calves and periods when the adult animals are dry. In the event that 3milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer.

3-63.1SAMPLE COLLECTION METHODOLOGY3.1.1SHORELINE SEDIMENTSShoreline sediment is collected at one area of existing or potential recreational value. Onesample is also collected from a location beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately one inch. The samples areplaced in plastic bags, sealed and shipped to the lab for analysis. Sediment samples areanalyzed for gamma emitting radionuclides.Shoreline sediment sample locations are shown in Section 3.3, Figure 3.3-5.3.1.2FISHSamples of available fish species that are commercially or recreationally important to LakeOntario; such as Lake Trout, Salmon, Walleye and Smallmouth Bass, are collected twiceper year, once in the spring and again in the fall. Indicator samples are collected from a combination of the two onsite sample transects located offshore from the site. One set of control samples are collected at an offsite sample transect located offshore 8-10 miles westof the site. Available species are selected using the following guidelines:1.A minimum of two species that are commercially or recreationally important are to becollected from each sample location. Samples selected are limited to edible and/orsport species when available.2.Samples are composed of the edible portion only.Selected fish samples are frozen immediately after collection and segregated by speciesand location. Samples are shipped frozen in insulated containers for analysis. Edible portions of each sample are analyzed for gamma emitting radionuclides.Fish collection locations are shown in Section 3.3, Figure 3.3-5.3.1.3SURFACE WATERSurface water samples are taken from the respective inlet canals of the James A.Fitzpatrick Nuclear Power Plant (JAFNPP) and NRGs Oswego Steam Station. The JAFNPP facility draws water from Lake Ontario on a continuous basis. This is used for the downstream or indicator sampling point for the Nine Mile Point site. The OswegoSteam Station inlet canal removes water from Lake Ontario at a point approximately 7.6miles west of the site. This upstream location is considered a control location because of the distance from the site, as well as the result of the lake current patterns and current patterns from the Oswego River located nearby.

3-7Samples from the JAFNPP facility are composited from automatic sampling equipmentwhich discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitters. Samples from the Oswego SteamStation are also obtained using automatic sampling equipment and collected in a holdingtank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionuclides.A portion of the monthly sample from each of the locations is saved and composited toform quarterly composite samples, which are analyzed for tritium.In addition to the sample results for the JAFNPP and Oswego Steam Station collectionsites, data is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and from the City of Oswego drinking water supply. The latter three locations are not required by the ODCM. These locations are optional sample points, which arecollected and analyzed to enhance the surface water sampling program. Monthlycomposite samples from these three locations are analyzed for gamma emitting nuclides, and quarterly composite samples are analyzed for tritium.Surface water sample locations are shown in Section 3.3 on Figure 3.3-4.3.1.4AIR PARTICULATE / IODINEThe air sampling stations required by the ODCM are located in the general area of the siteboundary. The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated deposition factor (D/Q) based on historical meteorological data. These stations (R-1, R-2, and R-3) are located in the E, ESE, and SEsectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 ReactorBuilding. The ODCM also require that a fourth air sampling station be located in the vicinity of a year-round community. This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCM is acontrol location designated as Station R-5. Station R-5 is located 16.2 miles from the sitein the NE meteorological sector.In addition to the five ODCM required locations, there are ten additional sampling stations.Six of these sampling stations are located within the site boundary and are designated asOnsite Stations D1, G, H, I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP. One air sampling station is located offsite in the southwest sector in the vicinity of the City of Oswego and is designated as Station G Offsite. Threeremaining air sampling stations are located in the ESE, SSE, and SSW sectors and range indistance from 7.1 to 9.0 miles. These are designated as Offsite Stations D2, E and F respectively.

3-8Each station collects airborne particulates using glass fiber filters (47 millimeter diameter)and radioiodine using charcoal cartridges (2x1 inch). The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis. Samplevolume is determined by use of calibrated gas flow meters located at the sample discharge.Gross beta analysis is performed on each particulate filter. Charcoal cartridges are analyzed for radioiodine using gamma spectral analysis. The particulate filters are composited quarterly by location and analyzed for gamma emitting radionuclides.Air sampling station locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.3.1.5TLD (DIRECT RADIATION)Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose)in the environment. Environmental TLDs are supplied and processed quarterly by the AREVA NP Environmental Laboratory. The laboratory utilizes a Panasonic based systemusing UD-814 dosimeters, which are constructed of rectangular teflon wafers impregnatedwith 25% CaSO 4:Dy phosphor. Each dosimeter contains three calcium sulfate elementsand one lithium borate element.

1.Environmental TLDsEnvironmental TLDs are placed in five different geographical regions around site toevaluate effects of direct radiation as a result of plant operations. The following is adescription of the five TLD geographical categories used in the NMPNS and JAFNPPEnvironmental Monitoring Program and the TLDs that make up each region:

TLD GeographicalCategoryDescriptionOnsiteTLDs placed at various locations within the site boundary, withthree exceptions, are not required by the ODCM. (TLD locationscomprising this group are: 3, 4, 5, 6, 7*, 18*, 23*, 24, 25, 26, 27,28, 29, 30, 31, 39, 47, 103, 106 and 107)Site BoundaryAn inner ring of TLDs placed in the general area of the siteboundary in each of the sixteen meteorological sectors. Thiscategory is required by the ODCM. (TLD locations comprising this group are: 7*, 18*, 23*, 75*, 76*, 77*, 78*, 79*, 80*, 81*,

82*, 83*, 84*, 85*, 86*, and 87*)

3-9 TLD GeographicalCategoryDescriptionOffsiteAn outer ring of TLDs placed 4 to 5 miles from the site in each ofthe 8 land based meteorological sectors. This category is requiredby the ODCM. (TLD locations comprising this group are 88*,89*, 90*, 91*, 92*, 93*, 94*, and 95*)Special InterestTLDs placed in special interest areas of high population densityand use. These TLDs are located at or near large industrial sites,schools, or nearby towns or communities. This category is required by the ODCM. (TLD locations comprising this group are: 9, 10, 11, 12, 13, 15*, 19, 51, 52, 53, 54, 55, 56*, 58*, 96*,97*, 98, 99, 100, 101, 102, 108, and 109)ControlTLDs placed in areas beyond significant influence of the site andplant operations. These TLDs are located to the SW, S and NE ofthe site at distances of 12.6 to 24.7 miles. This category is alsorequired by the ODCM. (TLD locations comprising this group are 8*, 14*, 49*, 111, 113)* TLD location required by the ODCMAlthough the ODCM requires a total of 32 TLD stations; environmental TLDs are alsoplaced at additional locations not required by the ODCM, within the Onsite, Special Interest and Control TLD categories to supplement the ODCM required DirectRadiation readings.Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed inpolyethylene packages to ensure dosimeter integrity and placed in open webbed plasticholders and attached to supporting structures, such as utility poles.Environmental TLD locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3-10 2.Independent Spent Fuel Storage Installation (ISFSI)In order to provide adequate spent fuel storage capacity at the FitzPatrick plant,Entergy constructed an Independent Spent Fuel Storage Installation (ISFSI) onsite. On April 25, 2002, the ISFSI facility was placed in service.TLDs are used to monitor direct radiation levels in the vicinity of the ISFSI facility.Twelve TLD locations were established around the ISFSI pad on the perimeter fence.Six additional TLD locations are located at varying distances from the pad to determine dose rates at points of interest relative to the storage area and are designated as optionallocations. Background data was collected starting in October, 2000 at eight of the TLDlocations on the perimeter fence. The remaining locations were established in October

2001.Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed inpolyethylene packages to ensure dosimeter integrity and placed in the field using asupporting structure such as a fence or other immovable object.ISFSI TLD locations are shown in Section 3.3, Table 3.3.1.3.1.6MILKMilk samples are routinely collected from farms during the sampling year. These farmsinclude indicator locations and one control location. Samples are normally collected Aprilthrough December of the sample year. If plant related radionuclides are detected in samples in November and December of the previous year, milk collections are continuedinto the following year starting in January. If plant related radionuclides are not detectedin the November and December samples, then milk collections do not commence until April of the following sampling year. Milk samples were not collected in January throughMarch of 2009 as there were no positive detections of plant related radionuclides insamples collected during November and December of 2008.The ODCM also requires that a sample be collected from a control location nine to twentymiles from the site and in a less prevalent wind direction. This location is in the southsector at a distance of 16 miles and serves as the control location.Milk samples are collected in polyethylene bottles from a bulk storage tank at eachsampled farm. Before the sample is drawn, the tank contents are agitated to assure ahomogenous mixture of milk and butter fat. The samples are chilled, preserved, and shipped fresh to the analytical laboratory within thirty-six hours of collection in insulatedshipping containers.The milk sample locations are shown in Section 3.3, Figure 3.3-4. (Refer to Section 3.3,Table 3.3-1 for location designation and descriptions.)

3-113.1.7FOOD PRODUCTS (VEGETATION)Food products are collected once per year during the late summer harvest season. Aminimum of three different kinds of broad leaf vegetation (edible or inedible) are collectedfrom two different indicator garden locations. Sample locations are selected from available gardens identified in the annual census that have the highest estimated deposition values (D/Q) based on historical site meteorological data. Control samples are alsocollected from available locations greater than 15.4 miles distance from the site in a lessprevalent wind direction. Control samples are of the same or similar type of vegetation when available.Food product samples are analyzed for gamma emitters using gamma isotopic analysis.Food product locations are shown in Section 3.3, Figure 3.3-5.3.1.8GROUND WATER MONITORING PROGRAMThe Nuclear Energy Institute (NEI) Ground Water Protection Initiative was established todetermine the potential impact Nuclear Power Plants may have on the surroundingenvironment due to unplanned releases of radioactive liquids. Under NEI 07-07, IndustryGround Water Protection Initiative- Final Guidance Document, August 2007, ground water monitoring is accomplished through sampling of the water table around the plant and analyzing it for gamma emitters and tritium. In November of 2007, JAF drilled 5 groundwater wells along the north edge of the property next to the lake (See Section 3.3, Figure3.3-7). Samples obtained from these wells are analyzed on a quarterly basis to determine gamma emitters and tritium concentrations. Ground water samples are analyzed for gamma emitters using gamma isotopic analysis and tritium using liquid scintillationdetector. For 2009, tritium was not detected in any of the 5 ground water wells. Groundwater results are documented in the Annual Radiological Effluent Release Report for 2009.On November 17, 2009, CR-JAF-2009-04166 documented detectable amounts of tritiumin the Reactor Building Perimeter Drain Sump. The Reactor Building Perimeter DrainSump is normally a nonradioactive system. Its source is currently not known. Starting in March 2010, additional monitoring wells are being drilled in the area of the reactor building and nearby SSCs. The purpose of these wells is to provide detailed site-specificdata that will assist in determining the source of tritium detected in the Reactor BuildingPerimeter Drain Sump.Tritium or gamma emitters have not been detected in any of the five ground watermonitoring wells since their installation in November of 2007.

3-123.2ANALYSES PERFORMEDEnvironmental sample analyses are performed at the James A. FitzPatrick Nuclear Power Plant(JAFNPP) Environmental Laboratory or by a contract laboratory. The following analyses were performed:1.Air Particulate Filter - Gross Beta2.Air Particulate Filter Composites - Gamma Spectral Analysis 3.Airborne Radioiodine - Gamma Spectral Analysis 4.Direct Radiation using Thermoluminescent Dosimeters (TLDs) - Analyses performed by acontractor laboratory - AREVA NP Environmental Laboratory.5.Fish - Gamma Spectral Analysis6.Food Products (vegetation) - Gamma Spectral Analysis7.Milk - Gamma Spectral Analysis and I-131 8.Shoreline Sediment - Gamma Spectral Analysis 9.Special Samples (soil, food, bottom sediment, etc.) - Gamma Spectral Analysis 10.Surface Water Monthly Composites - Gamma Spectral Analysis, I-131 11.Surface Water Quarterly Composite - Tritium 12.Ground Water Quarterly Samples - Tritium3.3SAMPLE LOCATIONSSection 3.3 provides maps illustrating sample locations. Sample locations referenced as lettersand numbers on the report period data tables are consistent with designations plotted on the maps.This section also contains an environmental sample location reference table (Table 3.3-1). Thistable contains the following information:1.Sample Medium2.Location Designation, (this column contains the key for the sample location and is consistentwith the designation on the sample location maps and on the sample results data tables)3.Location Description4.Degrees and Distance of the sample location from the site 3-133.3.1LIST OF FIGURESFigure 3.3-1 New York State MapFigure 3.3-2 Off-Site Environmental Station and TLD Locations Map Figure 3.3-3 Onsite Environmental Station and TLD Locations Map Figure 3.3-4 Milk and Surface Water Sample Locations Map Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment SampleLocations MapFigure 3.3-6 Nearest Residence Locations Map Figure 3.3-7 On-Site Ground Water Monitoring Wells Map 3 - 14TABLE 3.3-1ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUM MAPDESIGNATIONFIGURENUMBERLOCATION DESCRIPTIONDEGREES & DISTANCE (1) & (2)Shoreline Sediment 05*Figure 3.3-5 Sunset Bay84ºat 1.2 miles06Figure 3.3-5 Langs Beach, Control232°at 4.8 milesFish 02*Figure 3.3-5 Nine Mile Point Transect290°at 0.4 miles 03*Figure 3.3-5 FitzPatrick Transect62°at 0.8 miles 00*Figure 3.3-5 Oswego Transect237°at 5.9 milesSurface Water 03*Figure 3.3-4 FitzPatrick Inlet53°at 0.6 miles 08*Figure 3.3-4 Oswego Steam Station Inlet236°at 7.6 miles09Figure 3.3-4 NMP Unit 1 Inlet319°at 0.3 miles10Figure 3.3-4 Oswego City Water240°at 7.8 miles11Figure 3.3-4 NMP Unit 2 Inlet (Split intake with two locations)336°at 0.3 miles353°at 0.3 milesAir Radioiodine and R-1*Figure 3.3-2 R-1 Station, Nine Mile Point Road92°at 1.8 milesParticulates R-2*Figure 3.3-3 R-2 Station, Lake Road107°at 1.1 miles R-3*Figure 3.3-3 R-3 Station, Co. Rt. 29133°at 1.4 miles R-4*Figure 3.3-3 R-4 Station, Village of Lycoming, Co. Rt. 29145°at 1.8 miles R-5*Figure 3.3-2 R-5 Station, Montario Point Rd.42°at16.2 milesD-1Figure 3.3-3 D1 Onsite Station73°at 0.3 milesGFigure 3.3-3 G Onsite Station244°at 0.7 milesHFigure 3.3-3 H Onsite Station74°at 0.8 milesIFigure 3.3-3 I Onsite Station96°at 0.8 milesJFigure 3.3-3 J Onsite Station110°at 0.9 milesKFigure 3.3-3 K Onsite Station133°at 0.5 milesGFigure 3.3-2 G Offsite Station, Saint Paul Street226°at 5.4 milesD-2Figure 3.3-2 D2 Offsite Station, Rt. 64118°at 9.0 milesEFigure 3.3-2 E Offsite Station, Rt. 4162°at 7.1 milesFFigure 3.3-2 F Offsite Station, Dutch Ridge Road192°at 7.7 miles(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to thenearest 1/10 of a mile.(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.* Sample location required by ODCM 3 - 15TABLE 3.3-1 (Continued)ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUM MAPDESIGNATIONFIGURENUMBERLOCATION DESCRIPTIONDEGREES & DISTANCE (1) & (2)Thermoluminescent3Figure 3.3-3 D1 Onsite71°at 0.3 milesDosimeters (TLD)4Figure 3.3-3 D2 Onsite143°at 0.4 miles(Continued)5Figure 3.3-3 E Onsite180°at 0.3 miles6Figure 3.3-3 F Onsite213°at 0.5 miles 7*Figure 3.3-3 G Onsite245°at 0.7 miles 8*Figure 3.3-2 R-5 Offsite Control42°at16.2 miles9Figure 3.3-2 D1 Offsite - State Route 380°at11.4 miles10Figure 3.3-2 D2 Offsite118°at 9.0 miles11Figure 3.3-2 E Offsite162°at 7.1 miles12Figure 3.3-2 F- Offsite192°at 7.6 miles13Figure 3.3-2 G Offsite226°at 5.4 miles 14*Figure 3.3-2 DeMass Rd., SW Oswego - Control227°at12.5 miles 15*Figure 3.3-2 Pole 66, W. Boundary - Bible Camp240°at 0.9 miles 18*Figure 3.3-3 Energy Info. Center - Lamp Post, SW268°at 0.4 miles19Figure 3.3-2 East Boundary - JAF, Pole 983°at 1.4 miles 23*Figure 3.3-3 H Onsite73°at 0.8 miles24Figure 3.3-3 I Onsite95°at 0.8 miles25Figure 3.3-3 J Onsite109°at 0.9 miles26Figure 3.3-3 K Onsite132°at 0.5 miles27Figure 3.3-3 N. Fence, N. of Switchyard, JAF60°at 0.4 miles28Figure 3.3-3 N. Light Pole,N. of Screenhouse, JAF68°at 0.5 miles29Figure 3.3-3 N. Fence, N. of W. Side65°at 0.5 miles30Figure 3.3-3 N. Fence, (NW) JAF57°at 0.4 miles31Figure 3.3-3 N. Fence, (NW) NMP-1279°at 0.2 miles39Figure 3.3-3 N. Fence, Rad. Waste-NMP-1298°at 0.2 miles47Figure 3.3-3 N. Fence, (NE) JAF69°at 0.6 miles 49*Figure 3.3-2 Phoenix, NY-Control168°at19.7 miles51Figure 3.3-2 Liberty & Bronson Sts., E of OSS234°at 7.3 miles52Figure 3.3-2 E. 12th & Cayuga Sts., Oswego School227°at 5.9 miles53Figure 3.3-2 Broadwell & Chestnut Sts. Fulton H.S.183°at13.7 miles(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

Sample location required by ODCM 3 - 16TABLE 3.3-1 (Continued)ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUM MAPDESIGNATIONFIGURENUMBERLOCATION DESCRIPTIONDEGREES & DISTANCE (1) & (2)Thermoluminescent54Figure 3.3-2 Mexico High School115°at 9.4 milesDosimeters (TLD)55Figure 3.3-2 Gas Substation Co. Rt. 5-Pulaski75°at13.0 miles(Continued) 56*Figure 3.3-2 Rt. 104-New Haven Sch. (SE Corner)124°at 5.2 miles 58*Figure 3.3-2 Co Rt. 1A-Alcan (E. of E. Entrance Rd.)222°at 3.0 miles 75*Figure 3.3-3 Unit 2, N. Fence, N. of Reactor Bldg.354°at 0.1 miles 76*Figure 3.3-3 Unit 2, N. Fence, N. of Change House25°at 0.1 miles 77*Figure 3.3-3 Unit 2, N. Fence, N. of Pipe Bldg.36°at 0.2 miles 78*Figure 3.3-3 JAF. E. of E. Old Lay Down Area85°at 1.0 miles 79*Figure 3.3-3 Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd.120°at 1.2 miles 80*Figure 3.3-3 Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd.136°at 1.5 miles 81*Figure 3.3-3 Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29159°at 1.6 miles 82*Figure 3.3-3 Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29180°at 1.6 miles 83*Figure 3.3-3 Lakeview Rd., Tree 0.45 mi. N. of Miner Rd.203°at 1.2 miles 84*Figure 3.3-2 Lakeview Rd., N., Pole #6117, 200ft. N. of Lake Rd.226°at 1.1 miles 85*Figure 3.3-3 Unit 1, N. Fence, N. of W. Side of Screen House292°at 0.2 miles 86*Figure 3.3-3 Unit 2, N. Fence, N of W. Side of Screen House311°at 0.1 miles 87*Figure 3.3-3 Unit 2, N. Fence, N. of E. Side of Screen House333°at 0.1 miles 88*Figure 3.3-2 Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 197°at 4.5 miles 89*Figure 3.3-2 Leavitt Rd., Pole #16, 0.4 mi. S. of Rt.1112°at 4.3 miles 90*Figure 3.3-2 Rt. 104, Pole #300, 150 ft. E. of Keefe Rd.135°at 4.2 miles 91*Figure 3.3-2 Rt 51A, Pole #59, 0.8 mi. W. of Rt. 51157°at 4.9 miles 92*Figure 3.3-2 Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104183°at 4.4 miles 93*Figure 3.3-2 Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104206°at 4.4 miles 94*Figure 3.3-2 Rt. 1, Pole #82, 250 ft. E. of Kocher Rd. (Co. Rt. 63)224°at 4.4 miles 95*Figure 3.3-2 Alcan W access Rd., Joe Fultz Blvd, Pole #21239°at 3.7 miles 96*Figure 3.3-2 Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2199°at 3.6 miles 97*Figure 3.3-3 Rt. 29, Pole #50, 200ft. N. of Miner Rd.145°at 1.8 miles 98Figure 3.3-2 Lake Rd., Pole #145, 0.15 mi. E. of Rt 29102°at 1.2 miles(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.(2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

Sample location required by ODCM 3 - 17 TABLE 3.3-1 (Continued) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MEDIUM MAP DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION DEGREES & DISTANCE (1) & (2) Thermoluminescent 99 Figure 3.3-2 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R1 92°at 1.8 miles Dosimeters (TLD) 100 Figure 3.3-3 Rt. 29 & Lake Rd., Env. Station R2 106°at 1.1 miles (Continued) 101 Figure 3.3-3 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 133°at 1.4 miles 102 Figure 3.3-2 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 175°at 11.9 miles 103 Figure 3.3-3 EIC, East Garage Rd., Lamp Post 268°at 0.4 miles 104 Figure 3.3-2 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake rd. 102°at 1.4 miles 105 Figure 3.3-3 Lake view Rd. Pole #36, 0.5 mi. S. of Lake Rd. 199°at 1.4 miles 106 Figure 3.3-3 Shoreline Cove, W. of NMP-1, Tree on W. Edge 274°at 0.3 miles 107 Figure 3.3-3 Shoreline Cove, W. of NMP-1, 30 ft SSW of #106 273°at 0.3 miles 108 Figure 3.3-3 Lake Rd., Pole #142, 300 ft E. of Rt. 29 S. 105°at 1.1 miles 109 Figure 3.3-3 Tree North of Lake Rd., 300 ft E. of Rt. 29 N 104°at 1.1 miles 111 Figure 3.3-2 Control, State Route 38, Sterling NY 214°at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 175°at 11.9 miles 113 Figure 3.3-2 Control, Baldwinsville, NY 178°at 24.7miles Cows Milk 76 Figure 3.3-4 Indicator Location 120°at 6.3 miles 55 Figure 3.3-4 Indicator Location 97°at 8.7 miles 77* Figure 3.3-4 Control Location 190°at 16.0 miles Food Products 133* Figure 3.3-5 Indicator Location 83°at 1.6 miles 48** Figure 3.3-5 Indicator Location 83°at 1.5 miles 69** Figure 3.3-5 Indicator Location 124°at 2.3 miles 144** Figure 3.3-5 Indicator Location 139°at 1.6 miles C2* Figure 3.3-5 Control Location 222°at 15.4 miles 484* Figure 3.3-5 Indicator Location 132°at 1.4 miles Nearest Residence (NMP) Based on NMP Unit 2 Centerline - Refer to Figure 3.3-5 Nearest Residence (JAF) Based on JAF Centerline - Refer to Figure 3.3-6 (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline (2) Degrees and Distances updated by Global Positioning System (GPS) in 2006.

Sample location required by ODCM

- Optional sample 3 - 18TABLE 3.3-1 (Continued)ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUMLOCATIONDESIGNATIONFIGURE NUMBERLOCATION DESCRIPTION I-1*ISFSI West Fence, South End of Storage Pad I-2*ISFSI West Fence, Center of Storage PadThermoluminescentDosimeters (TLD) I-3*ISFSI West Fence, North End of Storage Pad I-4*ISFSI North Fence, West End of Storage Pad I-5*ISFSI North Fence, Center of Storage Pad I-6*ISFSI North Fence, East End of Storage Pad I-7*ISFSI East Fence, North End of Storage Pad I-8*ISFSI East Fence, Center of Storage Pad I-9*ISFSI East Fence, South End of Storage Pad I-10*ISFSI South Fence, East End of Storage Pad I-11*ISFSI South Fence, Center of Storage Pad I-12*ISFSI South Fence, West End of Storage PadI-13HISFSI Building and Grounds Garage, East of PadI-14HISFSI Tree ~100 yards South of Pad I-15HISFSI Transmission Line Tower South of Pad at East /West Access RdI-16HISFSI Perimeter Fence ~100 yards West of Pad on Pad CenterlineI-17HISFSI North Fence of Main Switch Yard on Pad CenterlineI-18HISFSI North Inner Perimeter Fence at Lake Shore on Pad CenterlineMW-5Figure 3.3-7North West edge of propertyMW-6Figure 3.3-7North / North West edge of propertyGround WaterMonitoring WellsMW-7Figure 3.3-7North edge of propertyMW-8Figure 3.3-7North / North East edge of propertyMW-9Figure 3.3-7North East edge of property* Sample location required by ODCMH indicates Optional TLD location BUFFALO BUFFALO ROCHESTER ROCHESTER SYRACUSE UTICA ALBANY 135 MI.135 MI.38 MI.3 8 M I.230 MI.2 3 0 MI.CANADA CANADA PENNSYLVANIA PENNSYLVANIA NEW JERSEY CONNECTICUT CONNECTICUT MASSACHUSETTS MASSACHUSETTS VERMONT NEW YORK CITY NEW YORK CITY LAKE ONTARIO FIGURE 3.3-1 FIGURE 3.3-1NEW YORK STATE MAPNEW YORKNEW YORK NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1

Nine Mile Point Nuclear Station Unit - 2

James A. FitzPatrick Nuclear Power Plant NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1

Nine Mile Point Nuclear Station Unit - 2

James A. FitzPatrick Nuclear Power Plant 3-19

ONSITE ENVIRONMENTAL STATION AND TLD LOCATIONS KEY: ENVIRONMENTAL STATIONS TLD LOCATIONS Transmission Lines Main Switch Yard90° E270° W S 0°N 180°11.25°33.75°56.25°78.75°101.25°123.75°146.25°168.75°191.25°213.75°236.25°258.75°281.25°303.75°348.75°NNE NE ENE ESE SE SSE SSW SW WSW WNW NW NNW Entergy Nuclear Northeast Constellation Nuclear Unit 1 Unit 2 James. A. FitzPatrick Nuclear Power Plant 9 Mile Point Nuclear Station MET Tower 1 Mile Radius 0.5 Mile Radius Sunset Bay Boat Launch Breakwall Lycoming Site Map Miles S witc h y ard Training CenterMinerRoadLakeviewR oadRte.1ABibleC amp ParkhurstRoad C o.Rte.29SunsetBayRoadSunsetParkRoad L a keRoadRailroad Shooting Range Laydown Area Training Center Cooling Tower Security Checkpoint Security Checkpoint 326.25°18 7 103 107 106 31 85 39 86 87 75 76 77 30 27 29 28 47 23 3 78 24 25 109 100 108 26 4 5 6 79 101 80 97 81 82 105 83 84 G R4 R3 R2 J I H D1 K 3-21

N LAKE ONTARIO LAKE ONTARIO OSWEGO COUNTY NEW YORK A C D E F G H NEAREST RESIDENCE KEY: NEAREST RESIDENCE LOCATIONS FIGURE 3.3-6 LOCATIONS - JAF 1 MI. 1.5 MI. 2 MI. BASED ON JAF CENTERLINE B 1 1A 29 29 1 104 Lake V iew Rd.L a k e V i e w R d.Bay Shore Dr.

B a y S h o r e D r.Shore Oaks Dr.

S h o r e O a k s D r.Parkhurst Rd.

P a r k h u r s t R d.Nine Mile Point Rd.

N i n e M i l e P o i n t R d.Dennis Rd.

D e n n i s R d.Miner Rd.Miner Rd.Lycoming Lycoming North North Scriba Scriba Lake Rd.Lake Rd.Sunset Bay Rd.

Sunset Bay Rd.JAF Site JA F Site NMP Site N MP Site W E Woolson Rd.

Woolson Rd.

Keefe Rd.K e e f e R d.Middle Rd.

Middle Rd.Cliff Rd.Cliff Rd.Bible Camp Bible C am p C re amery Rd.C r e a m e r y R d.S C R I B A N E W H A V E N Scale of Miles 0 1 0 78.75 0 101.25 0 123.75 0 146.25 0 168.75 0 191.25 0 213.75 0 236.25 0 258.75 E ESE ESE SE SSE SSE S SSW SSW SW WSW 3-24

3 - 263.4LAND USE CENSUSThe ODCM requires that a milch animal census and a residence census be conducted annually outto a distance of five miles. Milch animals are defined as any animal that is routinely used toprovide milk for human consumption.The milch animal census is an estimation of the number of cows and goats within an approximateten mile radius of the Nine Mile Point Site. The census is done once per year in the summer. It isconducted by sending questionnaires to previous milch animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service was alsocontacted to provide any additional information.The residence census is conducted each year to identify the closest residence in each of the 22.5degree meteorological sectors out to a distance of five miles. A residence, for the purposes of thiscensus, is a residence that is occupied on a part time basis (such as a summer camp), or on a fulltime, year round basis. Several of the site meteorological sectors are over Lake Ontario, therefore, there are only eight sectors over land where residences are located within five miles.In addition to the milch animal and residence census, a garden census is performed. The census isconducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by theODCM if broadleaf vegetation sampling and analysis are performed.

3 - 273.5CHANGES TO THE REMP PROGRAMThe following changes were implemented during the 2009 sampling program:3.5.1MILK SAMPLING PROGRAMDuring the report period, sample Location No. 76 was discontinued as the herd was sold.The last samples were collection on 08/10/09.

3 - 283.6DEVIATION AND EXCEPTIONS TO THE PROGRAMThe noted exceptions to the 2009 sample program address only those samples or monitoringrequirements which are required by the ODCM, Part I, Table 5.1-1. This section satisfies the reporting requirements of ODCM, Part I, Section 5.1.1.c.1.3.6.1ODCM Program DeviationsThe following are deviations from the program specified by the ODCM:1.The air sampling pumps at the R-3 offsite and R-4 offsite environmental samplingstations were inoperable for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months each during the sampling period of 10/20/09 to10/27/09. The sample pump out of service time was determined based on the samplepump run time integrator. The inoperability of the pump was due to loss of power tothe sampler. No corrective actions were required to restore unit to service.2.The air sampling pumps at the R-1 offsite and R-2 offsite environmental samplingstations were inoperable for 6.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months each during the sampling period 12/1/09 to12/8/09. The sample pump out of service time was determined based on the samplepump run time integrator. The inoperability of the pump was due to loss of power tothe sampler due to adverse weather conditions. No corrective actions were requiredto restore unit to service.3.The air sampling pumps at the R-3 offsite and R-4 offsite environmental samplingstations were inoperable for 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months each. The air sampling pump at the R-5 offsiteenvironmental sampling station was inoperable for 10.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . This occurred duringthe sampling period 12/8/09 to 12/15/09. The sample pump out of service time wasdetermined based on the sample pump run time integrator. The inoperability of thepump was due to loss of power to the sampler due to adverse weather conditions. Nocorrective actions were required to restore unit to service.3.6.2Air Sampling Station Operability AssessmentThe ODCM required air sampling program consists of 5 individual sampling locations.The collective operable time period for the air monitoring stations was 43,771 hours0.00892 days 0.214 hours 0.00127 weeks 2.933655e-4 months out of a possible 43,800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months . The air sampling availability factor for the report period was 99.93%.

3 - 293.7STATISTICAL METHODOLOGYThere are a number of statistical calculation methodologies used in evaluating the data from theenvironmental monitoring program. These methodologies include determination of standarddeviation, the mean and associated error for the mean, and the lower limit of detection (LLD).3.7.1ESTIMATION OF THE MEAN AND STANDARD DEVIATIONThe mean (X) and standard deviation (s) were used in the reduction of the data generatedby the sampling and analysis of the various media in the JAFNPP RadiologicalEnvironmental Monitoring Program (REMP). The following equations were utilized tocompute the mean (X) and the standard deviation (s):

1.Mean N X X i n i1 Where, X = estimate of the mean i = individual sample N, n = total number of samples with positive indications X i = value for sample i above the lower limit of detection.

3 - 30 2.Standard Deviation 2/1)1 (2)(1N X i X n i s Where, X = mean for the values of X s = standard deviation for the sample population3.7.2ESTIMATION OF THE MEAN & THE ESTIMATED ERROR FOR THE MEANIn accordance with program policy, when the initial count indicates the presence of a plantrelated radionuclide(s) in a sample, two recounts of the sample may be required. When aradionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one positive sample result exists, the mean ofthe sample results and the estimated error for the mean are reported in the Annual Report.The following equations were utilized to estimate the mean (X) and the associatedpropagated error.

1.Mean N X X i n i1 Where, X= estimate of the mean i= individual sampleN,n= total number of samples with positive indications

X i= value for sample i above the lower limit of detection 3 - 31 2.Error of the Mean (Reference 18) 2/1 1)(2n i ERROR MEAN ERROR N Where, ERROR MEAN

= propagated error i = individual sample ERROR = 1 sigma* error of the individual analysis N, n = number of samples with positive indications

Sigma ()Sigma is the Greek letter used to represent the mathematical term StandardDeviation.Standard Deviation is a measure of dispersion from the arithmetic mean of a setof numbers.3.7.3LOWER LIMIT OF DETECTION (LLD)The LLD is the predetermined concentration or activity level used to establish a detectionlimit for the analytical procedures.The LLDs are specified by the ODCM for radionuclides in specific media and are determinedby taking into account the overall measurement methods. The equation used to calculate the LLD is:)(exp)()22.2 ()()(66.4 t Y V E S LLD bWhere:LLD = the a priori lower limit of detection, as defined above (in picocuries per unit m ass orvolume)S b = the standard deviation of the background counting rate or of the counting rate of ablank sample, as appropriate (in counts per minute)E = the counting efficiency (in counts per disintegration)V = the sample size (in units of mass or volume) 2.22 = the number of disintegrations per minute per picocurie 3 - 32Y = the fractional radiochemical yield (when applicable) = the radioactive decay constant for the particular radionuclidet = the elapsed time between sample collection (or end of the sample collection period)and time of countingThe ODCM LLD formula assumes that:1.The counting times for the sample and background are equal 2.The count rate of the background is approximately equal to the count rate of the sample In the ODCM program, LLDs are used to ensure that minimum acceptable detectioncapabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). Table 3.8-1 lists the ODCM program required LLDsfor specific media and radionuclides as specified by the NRC. The LLDs actually achievedare routinely lower than those specified by the ODCM.3.8COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)ODCM, Part 1, Table 5.1-3 specifies the detection capabilities for environmental sample analysis (seereport Table 3.8-1). ODCM, Part 1, Section 6.1 requires that a discussion of all analyses for whichthe required LLDs specified were not routinely achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.3.8.1All sample analyses performed in 2009 as required by the ODCM, achieved the LowerLimit of Detection (LLD) as specified by ODCM, Part 1, Table 5.1-3. See report Table 3.8-1 for required LLD values.

3 - 33TABLE 3.8-1REQUIRED DETECTION CAPABILITIES FORENVIRONMENTAL SAMPLE ANALYSISLOWER LIMIT OF DETECTION (LLD)Analysis Water(pCi/l)AirborneParticulate or Gases(pCi/m 3)Fish(pCi/kg, wet)Milk(pCi/l)FoodProducts(pCi/kg, wet)Sediment(pCi/kg, dry)Gross Beta40.01H-33000 (a)Mn-5415130Fe-5930260Co-58, Co-6015130Zn-6530260Zr-95, Nb-9515I-13115 (a)0.07160Cs-134150.051301560150Cs-137180.061501880180Ba/La-1401515(a)No drinking water pathway exists at the Nine Mile Point site under normal operating conditions due tothe direction and distance of the nearest drinking water intake. Therefore, an LLD value of 3000pCi/liter is used for H-3 and an LLD value of 15 pCi/liter is used for I-131.

3 - 343.9REGULATORY LIMITSTwo federal agencies, the Nuclear Regulatory Commission and Environmental ProtectionAgency, have responsibility for regulations promulgated for protecting the public fromradiation and radioactivity beyond the site boundary.3.9.1The Nuclear Regulatory Commission (NRC):The NRC, in 10 CFR 20.1301, limits the levels of radiation in unrestricted areasresulting from the possession or use of radioactive materials such that they limit any individual to a dose of:less than or equal to 100 mrem per year to the total bodyIn addition to this dose limit, the NRC has established design objectives for nuclearplant licensees. Conformance to these guidelines ensures that nuclear power reactoreffluents are maintained as far below the legal limits as is reasonably achievable.The NRC; in 10CFR 50, Appendix I, establishes design objectives for the dose to amember of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:less than or equal to 3 mrem per year to the total body orless than or equal to 10 mrem per year to any organThe air dose due to release of Noble gases in gaseous effluents is restricted to:less than or equal to 10 mrad per year for gamma radiation orless than or equal to 20 mrad per year for beta radiationThe dose to a member of the general public from Iodine-131, tritium, and all particulateradionuclides with half-lives greater than 8 days in gaseous effluents is limited to:less than or equal to 15 mrem per year to any organThe NRC, in 10CFR72.104(a), establishes criteria for radioactive materials in effluentsand direct radiation from an Independent Spent Fuel Storage Installation (ISFSI).

3 - 35During normal operations and anticipated occurrences, the annual dose equivalent toany real individual who is located beyond the controlled area must not exceed:25 mrem per year to the total body75 mrem per year to the thyroidand25 mrem per year to any other organ as a result of :1.Planned discharges of radioactive material, radon and its decay products excepted,to the environment2.Direct radiation from ISFSI 3.Any other radiation from fuel cycle operation in the region3.9.2Environmental Protection Agency (EPA)The EPA, in 40CFR190.10, Subpart B, sets forth the environmental standards for theuranium fuel cycle. During normal operation, the annual dose to any member of thepublic from the entire uranium fuel cycle shall be limited to:less than or equal to 25 mrem per year to the total bodyless than or equal to 75 mrem per year to the thyroidandless than or equal to 25 mrem per year to any other organ 4 - 14.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMATAll sample data is summarized in table form. The tables are titled Radiological EnvironmentalMonitoring Program Annual Summary and use the following format as specified in the NRCBranch Technical Position:Column1.Sample Medium2.Type and Number of Analyses Performed3.Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1. This wordingindicates that inclusive data is based on 4.66 S b (sigma) of background (See Section 3.7).4.The mean and range of the positive measured values of the indicator locations.5.The mean, range, and location of the highest indicator annual mean. Location designations arekeyed to Table 3.3-1 in Section 3.3.6.The mean and range of the positive measured values of the control locations.7.The number of non-routine reports sent to the Nuclear Regulatory Commission.

NOTE: Only positive measured values are used in statistical calculations.

4 - 2 TABLE 4.0-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2009*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGENUMBER OFNON-ROUTINEREPORTSShoreline Sediment(pCi/kg-dry)GSA (4): Cs-134 Cs-137 150 180<LLD<LLD<LLD<LLD<LLD<LLD 0 0Fish(pCi/kg-wet)GSA (18): (h)Mn-54Fe-59Co-58 Co-60Zn-65 Cs-134 Cs-137 130 260 130 130 260 130 150<LLD<LLD

<LLD

<LLD<LLD<LLD<LLD

<LLD

<LLD<LLD<LLD<LLD

<LLD<LLD

<LLD

<LLD<LLD 0 0 0 0 0 0 0 4 - 3TABLE 4.0-1 (continued)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2009*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGENUMBER OFNON-ROUTINEREPORTSSurface Water(pCi/liter)H-3 (8):H-3GSA (24):Mn-54Fe-59Co-58 Co-60 Zn-65Zr-95Nb-95 I-131 Cs-134 Cs-137Ba/La-1403000(c)15 30 15 15 30 15 1515(c)15 18 15<LLD<LLD<LLD<LLD<LLD

<LLD<LLD

<LLD<LLD<LLD

<LLD

<LLD<LLD<LLD<LLD<LLD<LLD<LLD

<LLD

<LLD<LLD<LLD

<LLD

<LLD<LLD<LLD<LLD<LLD<LLD<LLD

<LLD

<LLD<LLD<LLD

<LLD

<LLD 0 0 0 0 0

0 0

0 0 0 0 0 4 - 4TABLE 4.0-1 (continued)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2009*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGENUMBER OFNON-ROUTINEREPORTSTLD (mrem perstandard month)Gamma Dose (140)(d) 4.7 (120/120) (i) 3.1 - 11.7 TLD #85 (g): 10.9 (4/4) 0.2 miles at 292 o 9.5 - 11.73.9 (20/20) (i) 3.2 - 4.8 0Air Particulates (pCi/m 3)Gross Beta (260)

I-131 (260)

GSA (20): Cs-134 Cs-137 0.01 0.07 0.05 0.060.016 (208/208)0.006 - 0.032<LLD<LLD<LLDR-1 0.017 (52/52)1.8 miles at 92 o0.008 - 0.032<LLD<LLD<LLD0.016 (52/52)0.007 - 0.030<LLD<LLD<LLD 0 0 0 0Milk(pCi/liter)GSA (45): (e) (h)Cs-134 Cs-137Ba/La-140I-131 (45)

I-131 15 18 15 1<LLD<LLD

<LLD<LLD<LLD<LLD

<LLD<LLD 0 0 0 0Food Products(pCi/kg-wet)GSA (21): (h)

I-131 Cs-134 Cs-137 60 60 80<LLD<LLD

<LLD<LLD<LLD

<LLD 0 0 0

4 - 5TABLE NOTES

= Data for Table 4.0-1 is based on ODCM required samples only.(a) = LLD values as required by the ODCM. LLD units are specified in the medium column.

(b) = Location is distance in miles and direction in compass degrees based on NMP-2 reactor center-line rounded to the nearest1/10 mile. Units in this column are specified in medium column.(c) = The ODCM specifies an I-131 and tritium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and3000 pCi/liter respectively.(d) = The ODCM does not specify a particular LLD value to environmental TLDs.

(e) = The ODCM criteria for indicator milk sample locations include locations within

5.0 miles

of the site. There are no milksample locations within 5.0 miles of the site. Therefore, the only sample location required by the ODCM is the controllocation. There were two optional locations for 2009.(f) = Fraction of number of detectable measurements to total number of measurements. Mean and range results are based ondetectable measurements only.(g) = This dose is not representative of doses to a member of the public since this area is located near the north shoreline whichis in close proximity to the generating facility and is not accessible to members of the public (See Section 5.2.4, TLDs).(h) = Data includes results from optional samples in addition to samples required by the ODCM.

(i) = Indicator TLD locations are: #7, 15, 18, 23, 56, 58, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93,94, 95, 96, 97 and 98. Control TLDs are all TLDs located beyond the influence of the site (TLD #: 8, 14, 49, 111, and 113).

5 - 15.0DATA EVALUATION AND DISCUSSIONIntroductionEach year the results of the annual Radiological Environmental Monitoring Program (REMP) areevaluated considering plant operations at the site, the natural processes in the environment, and thearchive of historical environmental radiological data. A number of factors are considered in the course of evaluating and interpreting the annual environmental radiological data. This interpretation can be made using several methods including trend analysis, population dose estimates, risk estimates to the general population based on significance of environmental concentrations, effectiveness of plant effluent controls, and specific research areas. The report not only presents the data collected during the 2009 sample program but also assesses the significance of radionuclides detected in the environment. It is important to note that detection of a radionuclide is not, of itself, an indication of environmental significance. Evaluation of the impactof the radionuclide in terms of potential increased dose to man, in relation to natural background,is necessary to determine the true significance of any detection.Units of MeasureSome of the units of measure used in this report are explained below.

Radioactivity is the number of atoms in a material that decay per unit of time. Each time an atomdecays, radiation is emitted. Thecurie (Ci) is the unit used to describe the activity of a materialand indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of37 billion atoms per second.Smaller units of the curie are used in this report. Two common units are themicrocurie (uCi),which is one millionth (0.000001) of a curie, and the picocurie (pCi), which is one trillionth(0.000000000001) of a curie. The picocurie (pCi) is the unit of radiation that is routinely used in this report. The mass, or weight, of radioactive material that would result in one curie of activity depends on the disintegration rate or half-life. For example, one gram of radium-226 contains one curie of activity, but it would require about 1.5 million grams of natural uranium to equal one curie. Radium-226 is more radioactive than natural uranium on a weight or mass basis.Dose/Dose to ManThe dose or dose equivalent, simply put, is the amount of ionizing energy deposited or absorbed inliving tissue. The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized ionization that can be up to 20 times the amount of ionization for the same energy imparted as from gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of radiation. When the quality factor is multiplied by the absorbed dose, the result is the doseequivalent, which is an estimate of the possible biological damage resulting from exposure to anytype of ionizing radiation. The dose equivalent is measured in rem (roentgen equivalent man). In terms of environmental radiation, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One millirem (mrem) is equal to 0.001 of a rem.

5 - 2The term dose to man refers to the dose or dose equivalent that is received by members of thegeneral public at or beyond the site boundary. The dose is calculated based on concentrations ofradioactive material measured in the environment. The primary pathways that contribute to thedose to man are; the inhalation pathway, the ingestion pathway, and direct radiation.DiscussionThere are three separate groups of radionuclides that were measured in the environment in themedia analyzed for the 2009 sampling program. The first of these groups consists of theradionuclides that are naturally occurring. The environment contains a significant inventory ofnaturally occurring radioactive elements. The components of natural or background radiationinclude the decay of radioactive elements in the earths crust, a steady stream of high-energyparticles from space called cosmic radiation, naturally-occurring radioactive isotopes in the humanbody like potassium-40, medical procedures, man-made phosphate fertilizers (phosphates anduranium are often found together in nature), and household items like televisions. In the UnitedStates, a persons average annual exposure from background radiation is 360 mrem, as illustratedon the following Background Radiation Chart.Background RadiationRadiation Exposure in the U.S.(Percent of Total Effective Dose)NCRP 93, 1987

<A number of radionuclides are present in the environment due to sources such as cosmic radiationand fallout from nuclear weapons testing. These radionuclides are expected to be present in manyof the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of theradionuclides normally present include:Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphereBeryllium-7, present as a result of the interaction of cosmic radiation with the upperatmospherePotassium-40 and Radium-226, naturally occurring radionuclides found in the human bodyand throughout the environmentFallout radionuclides from nuclear weapons testing, includingCesium-137, and Strontium-90 5 - 3Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturallyoccurring and are abundant, positive results for these radionuclides are reported in some cases inSection 6.0 of this report. Comparisons of program samples to natural background radiation aremade throughout this section to help put program results into perspective and to aid the reader indetermining what, if any, significant impact is demonstrated by the REMP results.The second group of radionuclides that were detected are a result of the detonation ofthermonuclear devices in the earths atmosphere. Atmospheric nuclear testing during the early1950s produced a measurable inventory of radionuclides presently found in the lower atmosphereas well as in ecological systems. In 1963 an Atmospheric Test Ban Treaty was signed. Since thetreaty, the global inventory of man-made radioactivity in the environment has been greatlyreduced through the decay of short lived radionuclides and the removal of radionuclides from thefood chain by such natural processes as weathering and sedimentation. This process is referred toin this report as ecological cycling. Since 1963, several atmospheric weapons tests have beenconducted by the Peoples Republic of China and underground weapons testing by India, Pakistan& North Korea. In some cases, the usual radionuclides associated with nuclear detonations weredetected for several months following the test, and then after a peak detection period, diminishedto a point where most could not be detected. Although reduced in frequency, atmospheric testingcontinued into the 1980's. The resulting fallout or deposition from these most recent tests hasinfluenced the background radiation in the vicinity of the site and was evident in many of thesample media analyzed over the years. The highest weapons testing concentrations were noted insamples collected for the 1981 REMP. Cs-137 was the major byproduct of this testing and is stilloccasionally detected in a few select number of environmental media.The third group of radionuclides that may be detected in the environment are those that are relatedto nuclear power technology. These radionuclides are the byproduct of the operation of lightwater reactors. These byproduct radionuclides are the same as those produced in atmosphericweapons testing and found in the Chernobyl fallout. This commonality makes a determination ofthe source of these radionuclides that may be detected in environmental samples difficult todetermine. During 2009, there were no plant-related radionuclides detected in the REMP samples.A number of factors must be considered in performing radiological sample data evaluation andinterpretation. The evaluation is made using several approaches including trend analysis and doseto man. An attempt has been made not only to report the data collected during 2009, but also toassess the significance of the radionuclides detected in the environment as compared to natural andother man-made radiation sources. It is important to note that detected concentrations ofradionuclides in the local environment as a result of mans technology are very small and are of noor little significance from an environmental or dose to man perspective.The 1987 per capita average dose was determined to be 360 mrem per year from all sources, asnoted in NCRP Report No. 93 (Reference 14). This average dose includes such exposure sourcesas natural radiation, occupational exposure, weapons testing, consumer products and nuclearmedicine. The 1987 per capita dose rate due to natural sources was 295 mrem per year. The percapita radiation dose from nuclear power production nationwide is less than one mrem per year.

5 - 4The natural background gamma radiation in the environs of the Nine Mile Point site, resultingfrom radionuclides in the atmosphere and in the ground, accounts for approximately 60-65 mremper year. This dose is a result of radionuclides of cosmic origin (for example, Be-7) and ofprimordial origin (Ra-226, K-40, and Th-232). A dose of 60 mrem per year, as a backgrounddose, is significantly greater than any possible doses as a result of routine operations at the siteduring 2009.The results of each sample medium are discussed in detail in Sections 5.1 and 5.2. This includes asummary of the results, the estimated environmental impact, a detailed review of any relevantdetections with a dose to man estimate where appropriate, and an analysis of possible long termand short term trends.During routine implementation of the REMP, additional or optional environmental pathway mediaare sampled and analyzed. These samples are obtained to:Expand the area covered by the program beyond that required by the ODCMProvide more comprehensive monitoring than is currently requiredMonitor the secondary dose to man pathwaysMaintain the analytical data base established when the plants began commercial operationThe optional samples that are collected will vary from year to year. In addition to the optionalsample media, additional locations are sampled and analyzed for those pathways required by theODCM. These additional sample locations are obtained to ensure that a variety of environmentalpathways are monitored in a comprehensive manner. Data from additional sample locations thatare associated with the required ODCM sample media are included in the data presentation andevaluation. When additional locations are included, the use of this data is specifically noted inSections 5.1 and 5.2.Section 6.0 contains the analytical results for the sample media addressed in the report. Tables areprovided for each required sample medium analyzed during the 2009 program.Section 7.0, titled Historical Data, contains statistics from previous years environmentalsampling. The process of determining the impact of plant operation on the environment includesthe evaluation of past analytical data to determine if trends are changing or developing. As state-of-the-art detection capabilities improve, data comparison is difficult in some cases. For example,Lower Limits of Detections (LLDs) have improved significantly since 1969 due to technologicaladvances in laboratory procedures and analytical equipment.

5 - 55.1AQUATIC PROGRAMThe aquatic program consists of samples collected from three environmental pathways. Thesepathways are:Shoreline SedimentFishSurface WatersSection 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collectedfor the 2009 sampling period.5.1.1SHORELINE SEDIMENT RESULTSA.Results SummaryShoreline sediment samples were obtained in April and October of 2009 at oneoffsite control location (Langs Beach located near Oswego Harbor) and at one indicator location (Sunset Bay) which is an area east of the site considered to have recreational value.A total of four sediment samples were collected for the 2009 sample program, twoindicator and two control. These results continue to show a downward trend over the last 10 years. Cs-137 was not detected in samples collected from the Sunset Bayindicator location and the Langs Beach control location during 2009.The one naturally-occurring radionuclide detected was K-40 and was not related toplant operations. No other plant-related radionuclides were detected in the 2009shoreline sediment samples.The following is a graph of the average Cs-137 concentration in shoreline sedimentsamples over the previous 17 years. This graph illustrates a general downward trendin the Cs-137 concentrations since 1993.

5 - 6Shoreline Sediment Cs-137 00.050.10.150.20.250.30.3519931994199519961997199819992000200120022003200420052006200720082009pCi/gram (dry)CONTROLINDICATORControl< LLD ValueIndicator <LLD ValueB.Data Evaluation and DiscussionShoreline sediment samples are routinely collected twice per year from the shorelineof Lake Ontario. Samples are collected from one indicator location (Sunset Bay),and one control location (Langs Beach). Samples were collected from both theindicator and control locations in April and October 2009. The results of thesesample collections are presented in Section 6.0, Table 6-1, Concentrations ofGamma Emitters in Shoreline Sediment Samples - 2009. Potassium-40 (K-40) wasthe only significant radionuclide detected in the sediment samples.C.Dose EvaluationThe calculated potential whole body and skin doses which may result from themeasured Cs-137 concentrations in previous years are extremely small and areinsignificant when compared to natural background doses.The radiological impact of Cs-137 measured in the shoreline sediment can beevaluated on the basis of dose to man. In the case of shoreline sediments, the criticalpathway is direct radiation to the whole body and skin. Using the parametersprovided in Regulatory Guide 1.109, the potential dose to man in mrem per year canbe calculated. The following regulatory guide values were used in calculating thedose to man:A teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or on the shoreline,The sediment has a mass of 40 kg/m2 (dry) to a depth of 2.5 cm,The shoreline width factor is 0.3, andThe maximum 2009 LLD concentration of <0.068 pCi/g (dry).

5 - 7Using these conservative parameters, the potential dose to the maximum exposedindividual (teenager) would be 0.00024 mrem/year to the whole body and 0.00027mrem/year to the skin. This calculated dose is very small and is insignificant whencompared to the natural background annual exposure of approximately 60 mrem as measured by control TLDs in the vicinity of the site.D.Data TrendsCs-137 was not detected at the indicator and control sample locations for 2009 aswell as 2008.The previous five years of data show a stable mean concentration values measured atthe indicator locations. Over the five year period, mean concentrations ranged from ahigh of 0.08 pCi/g (dry) in 2005 to a low value of 0.04 pCi/g (dry) measured in 2004and again in 2007. Cesium-137 was not detected in the control location samples overthis same five year period.The general absence of Cs-137 in the control samples is attributed to the differencesin the sediment types between the two sample locations. Few shoreline regions westof the site contain fine sediment and/or sand which would be representative of the indicator location. It is difficult to obtain control samples that are comparable inphysical and chemical characteristics to the indicator samples. Other factors, whichinclude changing lake level and shoreline erosion, further complicate attempts atconsistency in shoreline sediment sampling. Recent soil samples from locationsbeyond any expected influence from the site have contained levels of Cs-137 equal to or greater than the concentrations found in the 2009 shoreline sediment samples. TheCs-137 is commonly found in soil samples and is attributed to weapons testingfallout. Shoreline samples containing soil or sediment are likely to contain Cs-137.The previous ten year data trend for indicator shoreline samples showed a overalldownward trend in concentration measured at the indicator sample locations. Over the previous ten year period of 1999 through 2008, mean concentrations at theindicator location ranged from a maximum of 0.08 pCi/g (dry) in 1999 and 2005 to aminimum of 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cs-137 was notdetected at the indicator location for 2008 and 2009. This continues to support thelong term decreasing trend in Cs-137 concentration in shoreline sediment samples.

Cesium-137 was not detected in the control samples collected over the previous ten years.Shoreline sediment sampling at the indicator location commenced in 1985. Prior to1985, no data was available for long term trend analysis.Section 7.0, Tables 7-1 and 7-2 illustrate historical environmental data for shorelinesediment samples.

5 - 85.1.2FISH SAMPLE RESULTSA.Results SummaryA total of 18 fish samples were collected for the 2009 sample program. Speciescollected were: smallmouth bass, brown trout, and walleye. The analytical results for the 2009 fish samples showed no detectable concentration of radionuclide that wouldbe attributable to plant operations at the site or past atmospheric weapons testing.Since 2003 no Cs-137 has been measured in fish samples. Over the previous 20 years prior to 2003, Cs-137 has been detected at a combination of both the indicator and/or control locations. (Refer to Tables 7-3 and 7-4). These low levels of Cs-137represented no significant dose to man or impact on the environment.The 2009 fish sample results demonstrate that plant operations at the Nine Mile PointSite have no measurable radiological environmental impact on the upper levels of theLake Ontario food chain. The 2009 results are consistent with previous years resultsin that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last 24 years. Cs-137 was not detected in fish samples collected in 2003 to 2009 from indicator locations. The period of 2000 through 2009as a group are the lowest results measured since the beginning of the SiteEnvironmental Monitoring Program in 1969.B.Data Evaluation and DiscussionFish collections were made utilizing gill nets at one location greater than five milesfrom the site (Oswego Harbor area) and at two locations in the vicinity of the lake discharges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samplesserved as control samples while the NMPNS and JAFNPP samples served asindicator samples. All samples were analyzed for gamma emitters. Section 6.0, Table 6-2 shows individual results for all the samples collected in 2009 in units of pCi/g (wet).The spring fish collection was made up of 9 individual samples representing threeseparate species. Walleye, smallmouth bass, and brown trout were collected.The total fall fish collection was comprised of 9 individual samples representingthree individual species. Walleye, smallmouth bass, and brown trout were collected.Cs-137 was not detected in any of the fish species collected for the 2009 sampleprogram.

5 - 9C.Dose EvaluationFish represent the highest level in the aquatic food chain and have the potential to bea contributor to the dose to man from the operations at the site. The lack ofdetectable concentrations of plant-related radionuclides in the 2009 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway. Some Lake Ontario fish species may be considered animportant food source due to the local sport fishing industry. Therefore, these fishare an integral part of the human food chain.D.Data TrendsThe Cs-137 data for fish samples over the previous five years (2004 through 2008)show that the number of positive detections has decreased over this period relative to historical data. There were no positive detections of Cs-137 over the previous fiveyear period at the indicator locations. The graph below illustrates the mean controland indicator Cs-137 concentrations for 2009 and the previous fourteen years.ANNUAL MEAN CONCENTRATION FISH Cs-137 00.0050.010.0150.020.025199519961997199819992000200120022003200420052006200720082009pCi/gram (wet)INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUEThe fifteen year data trend shows a consistent level of Cs-137 measured in fishbetween 1995 and 1998. After 1998, the number of positive detections drops off as noted in the five year trend. The 1995 through 2009 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program.The general long-term decreasing trend for Cs-137, illustrated in the graph below, ismost probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected in fish since 1976 are considered to be the result of weapons testingfallout. The general downward trend in concentrations will continue as a function ofadditional ecological cycling and radiological decay.

5 - 10ANNUAL MEAN CONCENTRATION FISH Cs-137 00.250.50.75 11.251.519741979198419891994199920042009pCi/gram (wet)INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUESection 7.0, Tables 7-3 and 7-4 show historical environmental sample data for fish.5.1.3SURFACE WATER (LAKE)A.Results SummaryThe ODCM requires that monthly surface water samples be taken from the respectiveinlet water supplies of the JAFNPP and NRG Energy's Oswego Steam Station. Inconjunction with the required samples, three additional Lake Ontario surface water locations are sampled and analyzed. These additional locations are the Oswego City Water Intake, the NMP1 Intake and the NMP2 Intake. Gamma spectral analysis wasperformed on 24 monthly composite samples from the ODCM locations and on 36monthly composite samples collected from the additional sample locations. The results of the gamma spectral analyses showed that only naturally-occurring radionuclides were detected in the 60 samples from the five locations collected for the 2009 SamplingProgram. The two naturally-occurring radionuclide detected were K-40 and Ra-226and were not related to plant operations. Monthly composite samples showed no presence of plant-related gamma emitting isotopes in the waters of Lake Ontario as a result of plant operations.The monthly surface water samples are composited on a quarterly basis and areanalyzed for tritium. A total of 20 samples were analyzed for tritium as part of the 2009 REMP program. The results for the 2009 samples showed one positive detection oftritium. This result for an optional location was just slightly higher than the detectionlimit for the analysis. The other three results for this location were below the detection limit. There is no indication of a long-term buildup of tritium concentrations in the surface waters adjacent to the site.

5 - 11B.Data Evaluation and DiscussionGamma spectral analysis was performed on monthly composite samples from five LakeOntario sampling locations. No plant-related radionuclides were detected in 2009 samples. This is consistent with historical data, which has not shown the presence ofplant-related radionuclides in surface water samples.Tritium samples are quarterly samples that are a composite of the applicable monthlysamples for a given location. Tritium samples analyzed for the 2009 sample program were analyzed to an instrument detection level of at least 500 pCi/l.The tritium results for the JAFNPP inlet canal samples contained no positive detections.The 2009 results had LLD values that ranged from <410 pCi/l to <422 pCi/l. TheODCM Control location (Oswego Steam Station inlet canal) results showed no positivedetections and the sample results had LLD values in the range of <410 pCi/l to <415pCi/l.Tritium was detected in one of the twelve optional Lake Ontario samples collected inthe 2009 program. Tritium was detected in the Nine Mile Point Unit 1 inlet samplecollected during the first quarter of 2009. The positive detection of tritium may have been the result of the NMP-1 Emergency Condenser tests performed during this period.The concentration, 397 pCi/l, was barely above the detection limit. The testing of theNMP-1 Emergency Condenser could have attributed to the positive detection. Thetritium concentration is within the historical variations for levels of tritium occurring inLake Ontario.The Oswego City Water inlet is sampled to monitor drinking water quality and isrepresentative of a control location due to its distance from the site. The city water inlet is located 7.8 miles west of the site in an upstream direction based on the currentpatterns in the lake.The following is a summary of LLD results for the 2009 sample program:Tritium Concentration pCi/literSampleLocationMinimum Maximum Mean (Annual)JAF Inlet (Indicator)*<410<422<414Oswego Steam Inlet (Control)*<410<415<411NMP #1 Inlet 397<411<406NMP #2 Inlet<406<415<411Oswego City Water Supply<406<415<411* Sample location required by ODCMThe above LLD values are below the ODCM required LLD value of 3000 pCi/l.Analytical results for surface water samples are found in Section 6.0, Tables 6-3through 6-4.

5 - 12C.Dose EvaluationThe radiological impact to members of the public from low levels of tritium in water isinsignificant. This can be illustrated by calculating a dose to the whole body andmaximum organ using the maximum LLD value and Regulatory Guide 1.109 methodology. Based on a water ingestion rate of 510 liters/yr and a concentration of 422 pCi/l, the calculated dose would be less than 0.044 mrem to the child whole bodyand less than 0.044 mrem to the child liver (critical age group/organ).D.Data TrendsThere are no data trends for gamma emitters such as Cs-137 and Co-60 as historicallythese radionuclides have not been detected in lake water samples.Tritium results for the 2009 lake water samples were consistent with results from theprevious five years for both the indicator and control locations. The mean measuredtritium concentrations for the previous five year period of 2004 - 2008 were less than the LLD for the indicator and the control location. The mean 2009 tritium concentrations were <411 pCi/l for the control and <414 pCi/l for the indicator location.The previous five year data indicates no significant trends in either the indicator or thecontrol mean concentrations. This previous five year data set is consistent with long term tritium results measured at the site. The indicator data from the previous ten year period, 1999 through 2008, are representative of natural variations in environmentaltritium concentrations with no significant levels of tritium measured. The 1999 meancontrol value of 365 pCi/l is the highest concentration measured since 1987 and is within the variability of results measured over the life of the program. The ten year historical results are consistent between the control and indicator locations with no largevariation in the measured results.The following graph illustrates the concentrations of tritium measured in Lake Ontarioover the previous 20 years at both an indicator and control location. Prior to 1985, theOswego City Water Supply results were used as control location data as this locationclosely approximates the Oswego Steam Station, the current control location. There is no existing preoperational data for comparison to recent data.

5 - 13Surface Water - Tritium 0 50100150200 250 30035040019901991199219931994199519961997199819992000200120022003200420052006200720082009pCi/lINDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE1975-1984: Oswego City Water Control Site1985-2008: Oswego Steam Station Control SiteHistorical data for Surface Water Tritium is presented in Section 7.0, Tables 7-7 and 7-8.5.2TERRESTRIAL PROGRAMThe terrestrial program consists of samples collected from four environmental pathways. Thesepathways are:Airborne particulate and radioiodine,Direct Radiation,Milk, andFood ProductsSection 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrial samplescollected for the 2009 reporting period.5.2.1AIR PARTICULATE GROSS BETAA.Results SummaryWeekly air samples were collected and analyzed for particulate gross beta activity. Forthe 2009 program, a total of 52 samples were collected from control location R-5 and 208 samples were collected from indicator locations R-1, R-2, R-3, and R-4. These five locations are required by the ODCM. Additional air sampling locations are maintained and are discussed in Section 5.2.1.B below. The mean gross beta concentration for samples collected from the control location (R-5) in 2009 was 0.016 pCi/m

3. The meangross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2009 was 0.016 pCi/m

3. The consistency between the indicator andcontrol mean values, demonstrates that there are no increased airborne radioactivity 5 - 14levels in the general vicinity of the site. The indicator results are consistent withconcentrations measured over the last fifteen years. This consistency demonstrates that the natural baseline gross beta activity has been reached. The man-made radionuclide contribution to the natural background from atmospheric weapons testing and Chernobyl can no longer be detected above the background concentrations of naturallyoccurring beta emitting radionuclides.B.Data Evaluation and DiscussionThe air monitoring system consists of fifteen sample locations, six onsite and nineoffsite. Each location is sampled weekly for particulate gross beta activity. A total of 780 samples were collected and analyzed as part of the 2009 program. Five of the nine offsite locations are required by the ODCM. These locations are designated as R-1, R-2, R-3, R-4, and R-5. R-5 is a control location required by the ODCM and is locatedbeyond any local influence from the site. In addition, optional offsite and onsite airsample locations are maintained from which weekly samples are collected. The optional offsite locations are designated as D-2, E, F and G. The optional onsite locations are designated as D-1, G, H, I, J and K.Gross beta analysis requires that the samples be counted no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months aftercollection. This allows for the decay of short half-life naturally-occurring radionuclides, thereby increasing the sensitivity of the analysis for plant-related radionuclides.Section 6.0, Tables 6-5 and 6-6 present the weekly gross beta activity results forsamples collected from the offsite and onsite locations.The mean annual gross beta indicator concentrations for the ODCM indicator stations(R-1, R-2, R-3 and R-4) was 0.016 pCi/m3. The offsite ODCM control station (R-5) annual mean gross beta concentration was 0.016 pCi/m3. The minimum, maximum and average gross beta results for sample locations required by the ODCM were as follows:Concentration pCi/m 3LocationMinimumMaximumMeanR-10.0080.0320.017R-20.0060.0290.016R-30.0070.0260.016 R-40.0070.0270.016 R-5 (control)0.0070.0300.016R1 - R4 Indicator StationsMin 0.006Max 0.032 Mean 0.016 5 - 15The mean weekly gross beta concentrations measured in 2009 are illustrated in thefollowing graphs: Air Particulate Filter - Gross Beta 0.005 0.010 0.015 0.020 0.025 0.030 0.0351234567891011121314151617181920212223242526Week No.pCi/m 3INDICATOR (R1, R2, R3, R4)CONTROL (R5) Air Particulate Filter - Gross Beta0.0050.0100.0150.0200.0250.0300.0352728293031323334353637383940414243444546474849505152Week No.pCi/m 3INDICATOR (R1, R2, R3, R4)CONTROL (R5)The fluctuations observed in the gross beta activity over the year can be attributed tochanges in the environment, especially seasonal changes. The concentrations ofnaturally-occurring radionuclides in the lower levels of the atmosphere directly above the land are affected by time-related processes such as wind direction, precipitation, snow cover, soil temperature and soil moisture content.

5 - 16C.Dose EvaluationDose calculations are not performed based on gross beta concentrations. Dose to manas a result of radioactivity in air is calculated using the specific radionuclide and theassociated dose factor. See Section 5.2.2.C for dose calculations from air concentrations. The dose received by man from air gross beta concentration is a component of the natural background.D.Data TrendsWith the exception of the 1986 sample data, which was affected by the Chernobylaccident, the general trend in air particulate gross beta activity has been one ofdecreasing activity since 1981, when the mean control value was 0.165 pCi/m

3. The1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.The mean gross beta concentration measured in 1988 to 2009 are illustrated in thefollowing graph:Air Particulate Filter - Gross Beta 00.05 0.10.15 0.20.25 0.30.3519691979198419891994199920042009pCi/m 3INDICATORCONTROLChernobyl AccidentThe trend for the previous five years represents a base line concentration or naturalbackground level for gross beta concentrations. This trend is stable with minorfluctuations due to natural variations. The change in concentrations over the period of 1998 through 2009 is very small. This is illustrated by the following graph.

5 - 17Air Particulate Filter - Gross Beta 0 0.004 0.008 0.012 0.016 0.021994199519961997199819992000200120022003200420052006200720082009pCi/m 3INDICATORCONTROLFor the operational period of 1998 to 2009, the mean annual gross beta concentration atthe control station (R-5) has remained steady with a narrow range of 0.014 pCi/m 3 to0.019 pCi/m

3. The mean annual concentrations for the indicator stations for this sametime period were similar to the control and ranged from a minimum of 0.015 pCi/m 3 toa maximum mean of 0.019 pCi/m 3 in 2005.Historical data of air particulate gross beta activity are presented in Section 7.0, Tables7-9 and 7-10.5.2.2MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS)A.Results SummaryFifteen air monitoring stations are maintained around the Nine Mile Point Site. Five ofthe 15 air monitoring stations are required by the ODCM and are located offsite near the site boundary and offsite as a control location. Ten additional air sampling stationsare also maintained as part of the sampling program. Together, these fifteen continuousair sampling stations make up a comprehensive environmental monitoring network for measuring radioactive air particulate concentrations in the environs of the site.

Annually, the air monitoring stations provide 780 individual air particulate samples which are assembled by location into 60 quarterly composite samples. The quarterlycomposites are analyzed using gamma spectroscopy.No plant-related gamma emitting radionuclides were detected in any of the airparticulate filter samples collected during 2009.The gamma analysis results for the quarterly composite samples routinely showedpositive detections of Be-7, K-40, and Ra-226. Each of these radionuclides is naturally occurring.

5 - 18B.Data Evaluation DiscussionA total of fifteen air sampling stations are in continuous operation and located bothonsite and in the offsite sectors surrounding the Nine Mile Point Site. Five of thefifteen monitoring stations are required by the ODCM and the remaining ten are optional to provide an effective monitoring network. Composite air filter samples are assembled for each of the fifteen sampling locations. Each of the weekly air particulatefilters collected for the quarter is assembled by location to form quarterly compositesamples. The quarterly composite samples required by the ODCM are composite samples assembled for R-1, R-2, R-3, R-4 and R-5. Other sample locations not required by the ODCM, for which analytical results have been provided, include sixonsite locations and four offsite locations. The analytical results for the 60 airparticulate filter composites in 2009 showed no detectable activity of plant related radionuclides.The results of the quarterly composite samples are presented in Section 6.0, Table 6-9.C.Dose EvaluationThe calculated dose as a result of plant effluents is not evaluated due to the fact that noplant related radionuclides were detected in 2009. The monthly air particulate sampling program demonstrated no offsite dose to man from this pathway as a result of operations of the plants located at the Nine Mile Point Site(NMP).D.Data TrendsNo plant related radionuclides were detected during 2009 at the offsite air monitoringlocations.The ten year database of air particulate composite analysis shows that there is nobuildup or routine presence of plant related radionuclides in particulate form in theatmosphere around the site. Historically Co-60 was detected in each of the years from1977 through 1984 at both the indicator and control locations, with the exception of 1980 when Co-60 was not detected at the control location. The presence of Co-60 in the air samples collected during these years was the result of atmospheric weaponstesting. Co-60 was again detected in an offsite 2000 indicator sample and was the onlypositive detection of Co-60 since 1984. The detection of Co-60 in the one 2000 sample was an isolated event associated with effluents from the NMP1 facility. There have been no subsequent measurable concentrations of Co-60 in the environmentsurrounding the NMP site.

5 - 19Historical data shows that Cs-137 is the fission product radionuclide most frequentlydetected in the air particulate filter composites. Cs-137 was detected in each of theyears from 1977 through 1983 at both the control and indicator sampling locations.The presence of Cs-137 in the air samples collected during these years was the result of atmospheric weapons testing. Cs-137 was again detected in 1986 as a result of theChernobyl accident. Since 1986 there have been no detections of Cs-137 in theenvironment surrounding the NMP site.After 1986, no plant related or fallout radionuclides were detected in any of the offsiteair particulate composite samples with the exception of the isolated detection of Co-60in 2000 in a single sample. A review of the past five years data for air particulate filtercomposites indicates no plant related radiological impact on the environment. All previous historical positive detections of fission product radionuclides were associatedwith atmospheric weapons testing or the Chernobyl accident, with the exception of the2000 detection noted above.Historical data for air particulate results are presented in Section 7.0, Tables 7-11 and 7-12.5.2.3AIRBORNE RADIOIODINE (I-131)A.Results SummaryIodine-131 (I-131) was not detected in any of the 780 samples analyzed for the 2009program. No radioiodine (I-131) has been measured offsite at the constant air monitoring stations since 1987.B.Data Evaluation and DiscussionAirborne radioiodine (I-131) is monitored at the fifteen air sampling stations also usedto collect air particulate samples. There are nine offsite locations, five of which are required by the ODCM. The offsite locations required by the ODCM are designated asR-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influencefrom the plant. Ten air sampling locations are also maintained in addition to thoserequired by the ODCM. Six of these stations D-1, G, H, I, J and K are located onsite.D-2, E, F and G are the optional stations located offsite. Samples are collected using activated charcoal cartridges. They are analyzed weekly for I-131.The analytical data for radioiodine are presented in Section 6.0, Tables 6-7 and 6-8.C.Dose EvaluationThe calculated dose as a result of I-131 was not evaluated due to the fact I-131 was notdetected during 2009. The I-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located at Nine Mile Point.

5 - 20D.Data TrendsNo radioiodine has been detected in samples collected from the air sampling locationsrequired by the ODCM since 1987.There has been no positive detection of I-131 in air samples collected over the last tenyears. This demonstrates that there is no measurable environmental impact or positivetrend for iodine buildup due to plant operations during the period from 1998 through2009. I-131 has previously been detected in samples collected in 1986 and 1987. The 1986 detection of I-131 was the result of the Chernobyl accident and the 1987 detection was the result of plant operations.I-131 has been detected in the past at control locations. Control samples collectedduring 1976 had a mean I-131 concentration of 0.60 pCi/m

3. During 1977 this meandecreased to 0.32 pCi/m 3, and further decreased by a factor of ten to 0.03 pCi/m 3 in1978. I-131 was not detected in samples collected from the control location during1979 - 1981 and 1983 to 1985. I-131 was detected once at the control location during1982 at a concentration of 0.039 pCi/m 3.Iodine-131 has been detected in samples collected from the onsite indicator locationsduring 1980 to 1983 and 1986 to 1987. The mean concentrations ranged from 0.013pCi/m 3 in 1980 to a maximum of 0.119 pCi/m 3 in 1986. The maximum mean indicatorI-131 concentration of 0.119 pCi/m 3 was the result of the Chernobyl accident. I-131was detected in a total of 75 weekly samples collected during the 1986 sample program.The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m 3 to amaximum of 0.36 pCi/m

3. Each positive detection of I-131 in samples collected in1986 was the direct result of the Chernobyl Nuclear accident.Historical data for I-131 are presented in Section 7.0, Tables 7-13 and 7-14.5.2.4DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)A.Results SummaryThermoluminescent dosimeters (TLDs) are used to measure direct radiation (gammadose) in the environment. As part of the 2009 environmental monitoring program,TLDs were placed at a total of 72 different environmental TLD locations (32 requiredby the ODCM and 40 optional locations). These TLDs were placed, collected and read each quarter of 2009. As a result of placing two TLDs at each location, the results presented in this report are the average of two TLD readings obtained for a givenlocation.

5 - 21The TLDs were placed in the following five geographical locations around the siteboundary:Onsite (areas within the site boundary, includes TLD #s 3, 4, 5, 6, 7, 23, 24,25, 26; TLD #s 18, 27, 28, 29, 30, 31, 39, 47, 103, 106, 107 are excluded)Site Boundary (area of the site boundary in each of the 16 meteorologicalsectors: Only includes TLD results that are not affected by radwaste buildingdirect shine, includes TLD #s 7, 18, 78, 79, 80, 81, 82, 83, 84; TLD #s: 23, 75, 76, 77, 85, 86, 87 are excluded)Offsite Sector (area four to five miles from the site in each of the eight landbased meteorological sectors, includes TLD #s: 88, 89, 90, 91, 92, 93, 94, 95)Special Interest (areas of high population density, includes TLD #s 15, 56,58, 96, 97, 98)Control (areas beyond significant influence of the site, includes TLD #s 8, 14, 49)All geographical locations are required by the ODCM with the exception of the Onsitearea which was optional. Description of the five geograpical categories and the designation of specific TLD locations that make up each category is presented inSection 3.1.5, TLD (Direct Radiation) of this report.A summary of the 2009 dose rates for each of the five geographical locations is asfollows:Dose in mrem per standard monthGeographic CategoryMinMaxMeanOnsite (Optional)3.113.64.9Site Boundary (Inner Ring) *3.14.53.9Offsite Sectors (Outer Ring) *3.34.53.9Special Interest *3.14.53.8Control *3.24.84.0* Geographical locations required by the ODCMComparison of annual mean dose rates associated with each geographical locationindicate that there is no statistical difference in annual dose as a function of distance from the site boundary. The measured annual dose rate at the nearest resident to the sitewas consistent with the dose rates measured at the site boundary and control locations.The results for the Site Boundary, Offsite Sectors and Special Interest (Offsite) were well within expected normal variation when compared to the Control TLD results.

5 - 22The results for the 2009 environmental TLD monitoring program indicate that therewas no significant increase in dose rates as a result of operations at the site. The Hydrogen Water Chemistry system and the Independent Spent Fuel Storage Installation(ISFSI) in use at the Fitzpatrick plant did not measurably increase the ambient radiationexposure rate beyond the site boundary.B.Data Evaluation and DiscussionDirect Radiation (Gamma Dose) measurements were taken at 72 differentenvironmental locations during 2009, 32 of which are required by the ODCM. These locations are grouped into five geographical location categories for evaluation ofresults. The five categories include: Onsite, Site Boundary, Offsite Sector, SpecialInterest and Control locations. All categories are required by the ODCM with the exception of the Onsite TLDs. Onsite TLDs are placed at various locations within the site boundary to provide additional information on direct radiation levels at and aroundthe NMP1, NMP2 and JAFNPP facilities.Onsite TLD results ranged from 3.1 to 13.6 mrem per standard month resulting in anaverage dose rate of 4.9 mrem per standard month in 2009.Site Boundary TLD results ranged from 3.1 to 11.7 mrem per standard month in 2009.This range included all TLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location requiredby the ODCM was 11.7 mrem per standard month. This TLD, (TLD 85) represents thesite boundary maximum dose and is located in the WNW sector along the lake shore in close proximity to the NMP 2 plant. The TLD locations along the lakeshore close to the plants (TLD #s 23, 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildingsand radwaste shipping activities. These locations and are not accessible to members ofthe public and the TLD results for these areas are not representative of dose rates measured at the remaining site boundary locations. The remaining Site Boundary TLD locations, which are located away from the plant ranged from 3.1 to 4.5 mrem perstandard month resulting in an average dose rate of 3.9 mrem per standard month.Offsite Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in eachof the 8 land based meteorological sectors ranged from 3.3 to 4.5 mrem per standardmonth with an average dose rate of 3.9 mrem per standard month.Special Interest TLDs from all locations ranged from 3.1 to 4.5 mrem per standardmonth with a 2009 annual average dose rate of 3.8 mrem per standard month.

5 - 23The Control TLD group required by the ODCM utilizes locations positioned wellbeyond the site. 2009 Control TLD results ranged from 3.2 to 4.8 mrem per standard month with an annual average dose rate of 3.9 mrem per standard month. These resultsinclude both the ODCM required control TLDs and the additional control TLDs.TLD analysis results are presented in Section 6.0, Table 6-10.C.Dose Evaluation2009 annual mean dose rates for each geographic location required by the ODCM(excluding TLD #s 23, 75, 76, 77, 85, 86, 87) are as follows:Site Boundary: 3.9 mrem per standard month (TLD #s: 7,18, 78, 79, 80, 81, 82, 83, 84)Offsite Sectors: 3.9 mrem per standard month (TLD #s: 88, 89, 90, 91, 92, 93, 94, 95)Special Interest: 3.8 mrem per standard month (TLD #s: 15, 56, 58, 96, 97, 98)Control: 4.0 mrem per standard month (TLD #s 8, 14, 49)The measured mean dose rate in the proximity of the closest resident was 4.1 mrem perstandard month (TLD #s: 108, 109) which is consistent with the control measurements of 4.0 mrem per standard month.The mean annual dose for each of the geographic location categories demonstrates thatthere is no statistical difference in the annual dose as a function of distance from the site.

The TLD program verifies that operations at the site do not measurably contribute to thelevels of direct radiation present in the offsite environment.D.Data TrendsA comparison of historical TLD results can be made using the different geographicalcategories of measurement locations. These include Site Boundary TLDs located in each of the 16 meteorological sectors, TLDs located offsite in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDslocated at control locations. Site Boundary, Offsite Sector and Special Interest TLDlocations became effective in 1985; therefore, trends for these results can only be evaluated from 1985 to the present.The following graph illustrates TLD results for the Control, Site Boundary, OffsiteSectors and Special Interest groups from 1994 through 2009:

5 - 24TLD Data - Yearly Mean 0 1 2 3 4 5 61994199519961997199819992000200120022003200420052006200720082009mRem/Standard MonthControlSite BoundaryOffsiteSpecialsTLDs located at the site boundary averaged 3.9 mrem per standard month during 2009(Site Boundary average results do not include TLDs influenced by radwaste buildingsand radwaste shipping activities: TLDs 23, 75, 76, 77, 85, 86, 87). This result is consistent with the previous five year average of 4.2 mrem per standard month.Offsite Sector TLDs averaged 3.9 mrem per standard month during 2009. This result isalso consistent with the previous five year average of 4.1 mrem per standard month for offsite sectors.Special Interest TLD locations averaged 3.8 mrem per standard month during 2009which is consistent with the previous five year average of 4.1 mrem per standard month.The last group of TLD locations required by the ODCM is the Control Group. Thisgroup utilized TLD locations positioned well beyond the site. 2009 control results from all Control TLDs averaged 3.9 mrem per standard month, consistent with the previous five year average of 4.2 mrem per standard month. The 2009 TLD program results,when compared to the previous ten years, showed no significant trends relative toincreased dose rates in the environment.

5 - 255.2.5MILKA.Results SummaryA total of 45 milk samples were collected during the 2009 program and analyzed forgamma emitting radionuclides using gamma spectroscopy. In addition, each sample undergoes an iodine extraction procedure to determine the presence of Iodine-131 (I-131).I-131, a possible plant related radionuclide, is measured to evaluate the cow/milk dosepathway to man. I-131 was not detected in any of the 45 milk samples collected in2009 from the three milk sample locations.Gamma spectral analyses of the milk samples showed only naturally occurringradionuclides, such as K-40, were detected in milk samples collected during 2009. K-40 was detected in all indicator and control samples. K-40 is a naturally occurringradionuclide and is found in many environmental sample media.The 2009 results demonstrate that routine operations of the Nine Mile Point Siteresulted in no measurable contribution to the dose to the public from the cow/milkpathway.Location #76 was discontinued after the 08/10/09 samples as the herd was sold.B.Sampling OverviewMilk samples were collected from two indicator locations and one control location.The ODCM requires that three sample locations be within five miles of the site. Basedon the milk animal census, there were no adequate milk sample locations within five miles of the site in 2009. Samples were collected from three farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway.The two indicator locations ranged from 6.3 to 8.7 miles from the site. The controlsamples were collected from a farm located 16.0 miles from the site and in a low frequency wind sector (upwind). The geographic location of each sample location islisted below:Location No.Direction From SiteDistance (Miles)76SE6.355E8.777 (Control)SSW16.0 5 - 26Indicator location #55 and Control location #77 were sampled from April throughDecember. Indicator location #76 was sampled from April through August. Samplingoccurs during the first and second half of each month. Samples were not required to becollected during January through March of 2009 as a result of I-131 not having been detected in samples collected during November and December of 2008, as stipulated inthe ODCM.C.Data Evaluation and DiscussionEach milk sample is analyzed for gamma emitters using gamma spectral analysis. TheI-131 analysis is performed using resin extraction followed by spectral analysis for eachsample. I-131 and gamma analysis results for milk samples collected during 2009 are provided in Section 6.0, Table 6-11.Iodine-131 was not detected in any indicator or control milk samples analyzed during2009. All I-131 milk results were reported as Lower Limits of Detection (LLD). Noplant-related radionuclides were detected in any milk sample collected in 2009. K-40 was the most abundant radionuclide detected, and found in every indicator and controlsample collected. K-40 is a naturally-occurring radionuclide and is found in many ofthe environmental media samples. Cs-137 was not detected in any indicator or control milk sample collected in 2009.D.Dose EvaluationThe calculated dose as a result of plant effluents is not evaluated due to the fact that noplant related radionuclides were detected.The dose to man from naturally occurring concentrations of K-40 in milk and otherenvironmental media can be calculated. This calculation illustrates that the dosereceived due to exposure from plant effluents is negligible compared to the dosereceived from naturally occurring radionuclides. Significant levels of K-40 have been measured in environmental samples. A 70 kilogram (154 pound) adult containsapproximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation,consumption, etc.). The dose to bone tissue is about 20 mrem per year as a result ofinternal deposition of naturally-occurring K-40.E.Data TrendsManmade radionuclides are not routinely detected in milk samples. In the past twentyyears, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicatoractivities for those years were 8.6, 7.4 and 10.0 pCi/liter, respectively. I-131 wasmeasured in two milk samples collected in 1997 from a single sample location, havinga mean concentration of 0.35 pCi/liter and was of undetermined origin. The previousdetection was in 1986 with a mean concentration of 13.6 pCi/liter. The 1986 activitywas a result of the Chernobyl accident.

5 - 27The comparison of 2009 data to historical results over the operating life of the plantsshows that Cs-137 and I-131 levels have decreased significantly since 1988.Historical data of milk sample results for Cs-137 and I-131 are presented in Section 7.0,Tables 7-21 and 7-22.5.2.6FOOD PRODUCTS (VEGETATION)A.Results SummaryThere were no plant-related radionuclides detected in the 21 food product samplescollected and analyzed for the 2009 program.Detectable levels of naturally occurring K-40 were measured in all control andindicator samples collected for the 2009 program. Be-7 a naturally-occurringradionuclide, was also detected intermittently in samples collected in 2009. These results are consistent with the levels measured in 2008 and previous years.The results of the 2009 sampling program demonstrate that there is no measurableimpact on the dose to the public from the garden pathway as a result of plant operations.B.Data Analysis and DiscussionFood product samples were collected from five indicator locations and one controllocation. The indicator locations are represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and an annual gardencensus. The control location was a garden 15 miles away in a predominately upwinddirection.Food product samples collected during 2009 did not include any varieties considered tobe an edible broadleaf vegetables. Non-edible vegetation consisting of squash leaves,collard greens, rhubarb, grape leaves, pumpkin leaves, corn leaves, horseradish leaves, cabbage and swiss chard were collected for the 2009 program. The leaves of these plants were sampled as representative of broadleaf vegetation which is a measurementof radionuclide deposition. In addition to the broadleaf vegetation, tomato sampleswere collected from all locations except #144. Samples were collected during the late summer/fall harvest season. Each sample was analyzed for gamma emitters using gamma spectroscopy.The analysis of food product samples collected during 2009 did not detect any plant-related radionuclides. Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

5 - 28Naturally-occurring Be-7, K-40, Ra-226 and AcTh-228 were detected in food productsamples. The results for naturally-occurring radionuclides are consistent with the data of prior years.Analytical results for food products are found in Section 6.0, Table 6-12.C.Dose EvaluationThe calculated dose as a result of plant effluents is not evaluated due to the fact that noplant-related radionuclides were detected. The food product sampling programdemonstrated no measurable offsite dose to man from this pathway as a result ofoperations of the plants located at Nine Mile Point.D.Data TrendsFood product/vegetation sample results for the last five years demonstrate that there isno chronic deposition or buildup of plant-related radionuclides in the garden food products in the environs near the site.The last positive indication was for Cs-137 which was detected at one indicator locationin 1999 with a concentration of 0.007 pCi/g (wet).Historically, Cs-137 had been detected in ten separate years since 1976 ranging from amaximum mean concentration of 0.047 pCi/g (wet) in 1985 to a minimum of 0.006 pCi/g (wet) in 1994. The trend for Cs-137 is a general reduction in concentration to non detectable levels in samples collected during the 2000 through 2009 sample programs.Historical data of food product results are presented in Section 7.0, Tables 7-23 and 7-24.5.2.7LAND USE CENSUS RESULTSA.Results SummaryThe ODCM requires that an annual land use census be performed to identify potentialnew locations for milk sampling and for calculating the dose to man from plant effluents. In 2009, a milk animal census, a nearest resident census and a garden survey were performed.The results of the closest residence census conducted in 2009 required no change toFitzpatrick ODCMs closest resident location.

5 - 29A garden census, not required by the ODCM, is performed to identify appropriategarden sampling locations and dose calculation receptors. Garden samples were collected from a number of locations identified in the census as active for 2009. SeeTable 3.3-1 for 2009 sampling locations.B.Data Evaluation and DiscussionA land use census is conducted each year to determine the utilization of land in thevicinity of the Nine Mile Point site. The land use census consists of two types of surveys. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. The census, covering areas out to a distance of 10miles exceeds the 5 mile distance required by the ODCM. A resident census isconducted and is designed to identify the nearest resident in each meteorological sector out to a distance of 5 miles.The milk animal census is an estimation of the number of cows and goats within anapproximate 10 mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk animal owners and also by road surveys to locate any possible newlocations. In the event the questionnaires are not answered, the owners are contacted bytelephone or in person. The local county agricultural extension service is also contacted as an additional source of information concerning new milk animal locations in the vicinity of the site.The number of milk animals located within an approximate 10 mile radius of the sitewas estimated to be 406 cows and no goats based on the 2009 land use census. The number of cows has decreased by 10 when compared to the 2008 census. The results ofthe milk animal census are found in Section 6.0, Table 6-13.The second type of census conducted is a residence census. The census is conducted inorder to identify the closest residence within 5 miles in each of the 22.5 degree land-based meteorological sectors. There are only eight sectors over land where residencesare located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-14. There were no changes identified in the 2009 census for the closest resident in theland based meteorological sectors. The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

5 - 305.2.8DIRECT RADIATION, THERMOLUMINESCENT DOSIMETERS (TLD)Independent Spent Fuel Storage Installation (ISFSI)A.Results SummaryThermoluminescent Dosimeters (TLDs) are used to measure direct radiation (gammadose) in the localized environment of the ISFSI pad. Eighteen TLD locations are inplace around the perimeter of the ISFSI pad. TLDs were placed at these locations prior to loading the first storage casks for baseline dose rate determination in the general areaof the pad.On April 25, 2002, the ISFSI facility was placed in service with the installation of thefirst storage cask on the pad. Two subsequent storage casks were moved to the storagefacility on May 8, 2002 and May 21, 2002. A second series of six storage casks wereadded to the storage facility starting on September 6, 2005. The sixth and last cask inthis series was placed in the storage facility on November 12, 2005 bringing the total number of casks in storage to nine. During the Fall of 2009, 6 casks were safely loadedand stored on the storage pad bringing the total number of casks in storage to fifteen.The tenth cask was moved to the storage facility on July 14, 2009 and the fifteenth cask was moved to the storage facility on October 5, 2009.The increase in dose rate is limited to the general area of the storage facility. Theimplementation and loading of the ISFSI project has resulted in no increase in dose atthe site boundary or to the public. The analysis of offsite doses from direct radiation measurements, presented in Section 5.2.4 of this report, concludes that there is nosignificant difference in annual dose to the public at or beyond the site boundary. Themeasured annual dose rate at the nearest residence to the site was consistent with the dose rates measured at the site boundary and the offsite control locations. The resultsfor the Site Boundary, Offsite Sectors, and Special Interest (offsite) were well withinexpected normal variation when compared to the Control TLD results. The results for the 2009 environmental TLD monitoring program indicate that there is no significantincrease in dose rates as a result of operations at the site. The use of hydrogen injectionand the implementation of the Independent Spent Fuel Storage Installation (ISFSI) atthe FitzPatrick plant did not measurably increase the ambient radiation exposure rate ator beyond the site boundary. The lack of a dose rate increase at or beyond the site boundary is consistent with design calculations performed to evaluate compliance with10 CFR72.104(a).The measured results of the 2009 TLD monitoring program demonstrate compliancewith the offsite dose limits to members of the public specified in 40CFR190 and10CFR72.104(a).

5 - 31B.Program DesignAn array of eight TLD locations was established around the perimeter of the ISFSI pad18 months prior to facility usage. Six months prior to the facility becoming operational,an additional 10 TLD locations were established at areas of interest on the facility perimeter. These preoperational TLDs were used for baseline dose rate determination.

The TLDs are placed, collected and read each quarter. Two dosimeters are placed ateach location and the average of the two dosimeters is reported. The quarterly resultsare compared to baseline data to assess the contribution to ambient dose rates in the vicinity of the storage facility from casks as they are placed on the storage pad.C.Dose EvaluationA maximum dose rate of 23.8 mrem per standard month above the baseline dose ratewas measured at the south perimeter fence. The lowest measured dose rate of 2009 was1.9 mrem per standard month above the baseline dose rate and was also measured at thesouthern perimeter fence.An evaluation of Site Boundary TLDs and Control TLDs results for 2009 shows thatthere is no increase in dose rate at or beyond the site boundary. A detailed discussion ofthis evaluation is found in Section 5.2.4. The Environmental TLD results for this period show no significant difference in control and site boundary dose rates compared to 2008.2009 DOSE IN MREM PER STANDARD MONTHMinimumMaximumMeanSite Boundary3.14.53.9Control3.24.83.9 5 - 3

25.3CONCLUSION

The Radiological Environmental Monitoring Program (REMP) is an ongoing programimplemented to measure and document the radiological impact of JAFNPP operations on the localenvironment. The program is designed to detect and evaluate small changes in the radiologicalenvironment surrounding the site. Environmental media representing food sources consumed at the higher levels of the food chain, such as fish, food products and milk, are part of acomprehensive sampling program. Results of all samples are reviewed closely to determine anypossible impact to the environment or to man. In addition, program results are evaluated for possible short and long term historical trends.The federal government has established dose limits to protect the public from radiation andradioactivity. The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit isset forth in Section 1301, Part 20, Title 10 of the U.S. Code of Federal Regulations (10CFR20).The Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations(40CFR190). Radiation exposure to members of the public, calculated based on the results of theREMP, is extremely small. The dose to members of the public from operations at the Nine Mile Point site, based on environmental measurement and calculations made from effluent releases, isdetermined to be a fraction of limits set forth by the NRC and EPA.The results of the 2009 REMP continue to clearly demonstrate that there is no significant shortterm or chronic long term radiological impact on the environment in the vicinity of the Nine MilePoint site. No unusual radiological characteristics were measured or observed in the localenvironment. The REMP continues to demonstrate that the effluents from the site to the environment contribute no significant or even measurable radiation exposures to the general publicas confirmed by the sampling and analysis of environmental media from recognizedenvironmental pathways. Based on TLD results there was no measurable increase in radiation levels beyond the site boundary as a result of the hydrogen water chemistry programs.Environmental radiation levels measured at the nearest residence are at the background level basedon control station TLD results. The only measurable radiological impact on the environment continues to be the result of atmospheric weapons testing conducted in the early 1980s and the1986 accident at the Chernobyl Nuclear Power Plant. Both of these source terms havecontributed to a measurable inventory of Cs-137 in the environment. The results for the 2009 sample program demonstrate that the concentrations of man-made radionuclides continue to decline. This reduction in environmental background concentrations will allow for the siteenvironmental program to become more sensitive to the measurable impact of plant operations onthe environment as time goes on.The REMP did not detect any plant-related radionuclide in the sample media collected during2009. However, tritium was detected in one optional location, NMP1 intake, and may have been attributed to the NMP1 Emergency Condenser test performed during the first quarter of 2009. Thelevel of tritium found was within the historical variations for levels of tritium occurring in LakeOntario. Dose from man-made sources in the environment is very small when compared to the dose originating from naturally-occurring sources of radioactivity.

5 - 33Radiation from naturally-occurring radionuclides such as K-40 and Ra-226 contributed the vastmajority of the total annual dose to members of the general public. The dose to members of the public, resulting from plant operations, is extremely small in comparison to the dose contributionfrom natural background levels and sources other than the plants. The whole body dose inOswego County due to natural sources is approximately 50 - 60 mrem per individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man, attributable to site operation, remains insignificant.Based upon the overall results of the 2009 Radiological Environmental Monitoring Program, itcan be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of thesite.

5 - 3

45.4REFERENCES

1.U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Dosesto Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliancewith 10 CFR Part 50, Appendix I, March 1976.2.U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Dosesto Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, October 1977 (Revision 1).3.U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, Environmental TechnicalSpecifications for Nuclear Power Plants, December, 1975.4.U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, AnAcceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.5.National Council on Radiation Protection and Measurements (NCRP), EnvironmentalRadiation Measurements, NCRP Report No. 50, 1975.6.National Council on Radiation Protection and Measurements (NCRP), Natural BackgroundRadiation in the United States, NCRP Report No. 45, 1975.7.National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from theEnvironment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.8.National Council on Radiation Protection and Measurments (NCRP), Radiation Exposure fromConsumer Products and Miscellaneous Sources, NCRP Report No. 56, 1977.9.International Commission on Radiological Protection (ICRP), Radionuclide Release into theEnvironment: Assessment of Doses to Man, ICRP Publication 29, 1979.10.Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, FirstEdition, American Nuclear Society, La Grange Park, Ill., 1980.11.Schleien, Bernard. The Health Physics and Radiological Health Handbook. Scinta, Inc., SilverSpring, Maryland, 1992.12.U.S. Department of Health and Human Services. Preparedness and Response in RadiationAccidents, National Center for Devices and Radiological Health, Rackville, Maryland 20857,August 1983.13.National Council on Radiation Protection and Measurments (NCRP), Ionizing RadiationExposure of the Population of the United States, NCRP Report No. 93, 1987.14.National Council on Radiation Protection and Measurements (NCRP), Exposure of thePopulation in the United States and Canada from National Background Radiation, NCRPReport No. 94, 1987 6 - 16.0REPORT PERIOD ANALYTICAL RESULTS TABLESEnvironmental sample data is summarized in table format. Tables are provided for select samplemedia and contain data based on actual values obtained over the year. These values are comprised ofboth positive values and LLD (Lower Limit of Detection) values where applicable.The LLD is the smallest concentration of radioactive material in a sample that will be detected with95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal (see Section 3.7.3 for detailed explanation).When the initial count of a sample indicates the presence of radioactivity, two recounts are normallyperformed. When a radionuclide is positively identified in two or more counts, the analytical resultsfor that radionuclide are reported as the mean of the positive detections and the associated error forthat mean (see Section 3.7.2 for methodology).Many of the tables are footnoted with the term "Plant Related Radionuclides". Plant RelatedRadionuclides are radionuclides that are produced in the reactor; as a result of plant operation, either through the activation or fission process.

6 - 2Others 04/22/0922480 +/- 660< 44.0< 46.0< 43.2< 66.5< LLD10/22/0921980 +/- 1040< 79.0< 85.4< 68.4< 123.1< LLD04/22/0912850 +/- 540< 50.7< 28.6< 39.6< 128.7< LLD10/22/0910130 +/- 711< 57.7< 44.1< 57.8< 167.7< LLD

Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclidesCollection DateSample Location ***

K-40Lang's Beach (06, Control)Sunset Bay (05) *Co-60Cs-134Cs-137Zn-65GAMMA EMITTERSTABLE 6-1CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2009Results in Units of pCi/kg (dry) +/- 1 Sigma 6 - 3Others 6/17/2009Brown Trout3943 +/-451 < 69 < 55 < 169 < 63 < 63 < 47 < 165< LLD6/17/2009Walleye3858 +/-470 < 50 < 47 < 159 < 63 < 55 < 54 < 146< LLD 6/18/2009Smallmouth Bass3805 +/-495 < 67 < 59 < 139 < 77 < 53 < 57 < 196< LLD 9/22/2009Brown Trout5173 +/-719 < 78 < 91 < 254 < 101 < 61 < 92 < 232< LLD 9/22/2009Walleye5252 +/-684 < 88 < 99 < 223 < 69 < 105 < 74 < 236< LLD9/22/2009Smallmouth Bass8266 +/-733 < 80 < 105 < 252 < 105 < 91 < 105 < 208< LLD

Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclidesTABLE 6-2CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2009Results in Units of pCi/kg (wet) +/- 1 SigmaFITZPATRICK * (03)***

Cs-137Cs-134Zn-65GAMMA EMITTERSCo-58K-40Mn-54DateDescriptionFe-59Co-60 6 - 4Others 6/17/2009Brown Trout4081 +/-503 < 62 < 80 < 231 < 61 < 64 < 58 < 124< LLD6/17/2009Walleye3469 +/-537 < 58 < 66 < 216 < 83 < 59 < 84 < 200< LLD 6/18/2009Smallmouth Bass6730 +/-676 < 85 < 58 < 256 < 111 < 83 < 84 < 220< LLD 9/22/2009Brown Trout3605 +/-553 < 75 < 78 < 51 < 101 < 63 < 53 < 186< LLD 9/22/2009Walleye4030 +/-658 < 86 < 108 < 168 < 26 < 88 < 69 < 246< LLD9/22/2009Smallmouth Bass4500 +/-597 < 61 < 69 < 158 < 85 < 69 < 69 < 122< LLD

Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides Date K-40 Zn-65Results in Units of pCi/kg (wet) +/- 1 SigmaGAMMA EMITTERS Cs-134NINE MILE POINT * (02)***DescriptionCo-58 Mn-54TABLE 6-2 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2009 Cs-137Fe-59Co-60 6 - 5Others 6/16/2009Brown Trout4272 +/-498 < 49 < 36 < 136 < 63 < 52 < 42 < 178< LLD6/16/2009Walleye5112 +/-625 < 92 < 40 < 215 < 86 < 72 < 67 < 198< LLD 6/16/2009Smallmouth Bass5891 +/-696 < 71 < 91 < 259 < 88 < 100 < 105 < 235< LLD 9/23/2009Brown Trout5552 +/-611 < 73 < 71 < 217 < 93 < 91 < 89 < 140< LLD 9/23/2009Walleye3359 +/-488 < 49 < 56 < 181 < 69 < 71 < 55 < 178< LLD9/24/2009Smallmouth Bass5352 +/-636 < 75 < 67 < 180 < 78 < 77 < 69 < 159< LLD

Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclidesTABLE 6-2 (Continued)

K-40CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2009Results in Units of pCi/kg (wet) +/- 1 SigmaFe-59Co-60Cs-134GAMMA EMITTERSOSWEGO HARBOR (CONTROL) * (00)***Description DateMn-54Cs-137Zn-65Co-58 6 - 6STATION CODEPERIODTRITIUMFirst Quarter01/05/0903/31/09< 414FITZPATRICK*Second Quarter03/31/0906/29/09<410(03, INLET)***Third Quarter06/29/0909/30/09<422Fourth Quarter09/30/0912/28/09<411First Quarter12/26/0803/27/09<415OSWEGO STEAM STATION*Second Quarter03/27/0906/26/09<410(08, CONTROL)***Third Quarter06/26/0909/25/09<406Fourth Quarter09/25/0912/30/09<411First Quarter12/26/0803/27/09397

+/-128NINE MILE POINT UNIT 1**Second Quarter03/27/0906/26/09<410(09, INLET)***Third Quarter06/26/0909/25/09<406Fourth Quarter09/25/0912/30/09<411First Quarter12/26/0803/27/09<415NINE MILE POINT UNIT 2**Second Quarter03/27/0906/26/09<410(11, INLET)***Third Quarter06/26/0909/25/09<406Fourth Quarter09/25/0912/30/09<411First Quarter12/26/0803/27/09<415OSWEGO CITY WATER**Second Quarter03/27/0906/26/09<410(10)***Third Quarter06/26/0909/25/09<406Fourth Quarter09/25/0912/30/09<411

Sample location required by ODCM ** Optional Sample location*** Corresponds to sample location noted on Figure 3.3-4DATETABLE 6-3CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2009(QUARTERLY COMPOSITE SAMPLES)Results in Units of pCi/l +/- 1 Sigma 6 - 7NUCLIDEI-131< 0.73< 0.47< 0.80< 0.65< 0.63< 0.65Cs-134< 4.39< 3.27< 4.07< 2.83< 3.70< 2.73Cs-137< 3.62< 4.01< 3.62< 4.07< 4.82< 3.52Zr-95< 7.10< 8.00< 7.04< 8.90< 9.40< 7.18Nb-95< 5.08< 5.68< 5.62< 6.11< 6.70< 4.76Co-58< 4.27< 4.76< 4.46< 4.73< 5.37< 4.77Mn-54< 3.57< 4.31< 3.61< 3.97< 5.51< 3.99Fe-59< 11.38< 16.15< 12.49< 14.24< 18.49< 13.18Zn-65< 9.23< 10.35< 6.41< 6.05< 13.43< 8.27Co-60< 3.67< 4.73< 4.02< 3.65< 5.10< 3.58K-40395.3 +/- 26.4474.4 +/- 32.2422.1 +/- 27.1429.4 +/- 28.1431.8 +/- 33.1352.4 +/- 24.6Ba/La-140< 12.52< 11.59< 10.72< 11.69< 13.62< 11.67NUCLIDEI-131< 0.84< 0.52< 0.70< 0.71< 0.69< 0.79Cs-134< 3.66< 2.86< 3.25< 4.70< 2.38< 2.11Cs-137< 3.32< 3.71< 3.15< 4.19< 3.38< 3.31Zr-95< 6.57< 7.76< 6.71< 8.65< 6.77< 6.84Nb-95< 4.98< 5.27< 4.69< 6.37< 4.68< 4.73Co-58< 4.00< 4.54< 3.53< 5.06< 3.79< 3.61Mn-54< 3.54< 4.06< 3.09< 4.54< 3.68< 3.31Fe-59< 11.98< 13.73< 10.69< 14.05< 11.90< 11.90Zn-65< 7.38< 5.46< 7.20< 11.04< 4.62< 8.32Co-60< 3.21< 4.02< 2.77< 4.18< 3.40< 3.73K-4075.3 +/- 15.0429.2 +/- 27.2< 31.2351.1 +/- 27.8425.5 +/- 24.2173.7 +/- 18.4Ba/La-140< 10.59< 10.51< 10.24< 11.48< 10.86< 12.23

Sample Location required by ODCM*** Corresponds to sample location noted on Figure 3.3-4NOVEMBERDECEMBERJULYAUGUSTSEPTEMBEROCTOBEROSWEGO STEAM STATION * (08, CONTROL)***JANUARYFEBRUARYMARCHAPRILMAYJUNETABLE 6-4CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2009Results in Units of pCi/liter +/- 1 Sigma 6 - 8NUCLIDEI-131< 11.79< 13.44< 11.82< 11.77< 11.94< 14.63Cs-134< 2.11< 5.09< 2.50< 2.25< 2.55< 4.34Cs-137< 2.87< 4.49< 3.84< 2.88< 3.68< 4.13Zr-95< 5.74< 8.78< 6.99< 5.48< 8.07< 7.88Nb-95< 4.37< 5.35< 5.07< 4.61< 5.18< 4.51Co-58< 3.25< 4.63< 3.64< 3.43< 3.77< 3.84Mn-54< 2.77< 4.22< 3.43< 2.92< 3.65< 3.36Fe-59< 9.02< 12.52< 12.30< 10.32< 8.94< 10.81Zn-65< 3.86< 11.67< 9.87< 7.03< 4.85< 8.44Co-60< 2.89< 5.09< 3.55< 3.27< 3.31< 4.14K-40376.3 +/- 19.6193.4+/-25.9173.7+/-19.4367.1+/-20.6324.6+/-23.446.1+/-14.6Ba/La-140< 8.99< 10.58< 9.60< 8.58< 7.22< 13.56NUCLIDEI-131< 14.48< 11.04< 14.85< 14.73< 11.02< 8.97Cs-134< 3.52< 3.00< 3.84< 3.47< 1.79< 1.42Cs-137< 3.52< 2.63< 3.14< 3.27< 2.57< 1.84Zr-95< 6.74< 5.87< 6.27< 5.97< 5.56< 3.62Nb-95< 3.98< 3.80< 4.50< 4.43< 3.45< 2.73Co-58< 3.80< 3.14< 3.53< 4.33< 2.95< 2.01Mn-54< 3.03< 2.78< 3.17< 3.14< 3.13< 1.82Fe-59< 12.68< 8.37< 10.50< 9.58< 8.24< 6.11Zn-65< 7.91< 4.10< 6.47< 8.90< 3.58< 4.37Co-60< 3.57< 3.10< 3.63< 3.28< 2.84< 2.00K-40141.0 +/- 17.9379.5+/-19.9111.9+/-15.4< 37.4414.8+/-18.582.8+/-9.1Ba/La-140< 10.64< 7.77< 10.85< 9.27< 8.20< 7.33

Sample Location required by ODCM*** Corresponds to sample location noted on Figure 3.3-4TABLE 6-4 (continued)CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2009Results in Units of pCi/liter +/- 1 SigmaOSWEGO CITY WATER** (10)***JANUARYFEBRUARYMARCHAPRILMAYJUNENOVEMBERDECEMBERJULYAUGUSTSEPTEMBEROCTOBER 6 - 9NUCLIDEI-131< 0.46< 0.41< 0.41< 0.67< 0.45< 0.51Cs-134< 5.28< 1.93< 2.64< 2.74< 1.91< 1.80Cs-137< 5.06< 2.58< 3.21< 2.69< 3.07< 1.49Zr-95< 8.63< 5.59< 7.15< 4.71< 4.94< 3.00Nb-95< 6.32< 3.23< 4.80< 3.29< 2.56< 1.84Co-58< 5.01< 3.23< 3.97< 3.01< 3.28< 1.74Mn-54< 4.54< 2.83< 3.75< 2.91< 2.79< 1.56Fe-59< 16.96< 6.89< 10.94< 6.61< 8.55< 4.46Zn-65< 6.88< 6.29< 5.91< 7.52< 4.12< 3.51Co-60< 5.67< 3.14< 4.18< 2.46< 2.69< 1.67K-40454.5 +/- 33.841.9+/-9.6477.0+/-28.439.0+/-10.444.4+/-10.041.7+/-6.5Ba/La-140< 13.06< 6.55< 9.55< 6.16< 7.46< 3.49NUCLIDEI-131< 0.62< 0.40< 0.57< 0.66< 0.55< 0.53Cs-134< 2.33< 1.96< 2.75< 2.24< 2.55< 1.71Cs-137< 2.94< 2.42< 3.19< 2.98< 3.25< 2.34Zr-95< 4.71< 5.82< 6.88< 5.88< 7.34< 4.49Nb-95< 3.70< 3.63< 3.72< 4.09< 4.35< 2.84Co-58< 3.05< 2.93< 3.77< 3.54< 3.73< 2.33Mn-54< 2.45< 2.49< 3.90< 2.75< 3.70< 2.34Fe-59< 8.47< 8.29< 7.20< 8.11< 10.55< 7.43Zn-65< 7.31< 5.14< 7.03< 5.96< 8.16< 2.68Co-60< 3.56< 2.40< 3.50< 2.75< 3.37< 2.53K-40< 25.524.7+/-10.055.3+/-12.8< 29.6106.5+/-17.6< 22.9Ba/La-140< 6.92< 6.96< 7.42< 7.66< 8.00< 4.99

Sample Location required by ODCM*** Corresponds to sample location noted on Figure 3.3-4TABLE 6-4 (continued)CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2009Results in Units of pCi/liter +/- 1 SigmaFITZPATRICK* (03, INLET)***JANUARYFEBRUARYMARCHAPRILMAYJUNENOVEMBERDECEMBERJULYAUGUSTSEPTEMBEROCTOBER 6 - 10NUCLIDEI-131< 10.20< 12.61< 7.80< 14.28< 10.33< 10.78Cs-134< 2.25< 2.79< 1.64< 4.34< 3.52< 1.98Cs-137< 3.02< 3.62< 2.02< 4.31< 3.18< 2.79Zr-95< 5.77< 7.06< 4.57< 8.65< 7.81< 5.54Nb-95< 3.92< 4.66< 2.73< 5.53< 4.78< 4.04Co-58< 3.56< 4.26< 2.34< 3.05< 4.10< 3.16Mn-54< 3.03< 3.89< 2.12< 4.00< 3.22< 2.70Fe-59< 7.50< 12.71< 6.79< 10.47< 9.50< 7.86Zn-65< 7.49< 9.50< 5.32< 8.23< 8.38< 6.27Co-60< 2.68< 4.06< 2.06< 3.76< 3.35< 2.53K-4031.4 +/- 12.0428.2+/-24.932.2+/-9.6< 39.9126.5+/-16.634.6+/-10.2Ba/La-140< 9.43< 8.93< 5.49< 13.30< 9.50< 8.26NUCLIDEI-131< 14.37< 10.44< 14.74< 12.25< 9.95< 10.05Cs-134< 2.52< 2.96< 3.52< 2.20< 2.79< 1.51Cs-137< 3.50< 2.59< 3.29< 2.98< 2.37< 1.98Zr-95< 6.73< 5.43< 7.01< 5.62< 5.07< 4.07Nb-95< 5.06< 3.26< 3.97< 3.87< 3.65< 2.69Co-58< 4.08< 2.89< 3.49< 3.24< 3.00< 2.12Mn-54< 3.70< 3.16< 2.99< 2.95< 2.42< 2.02Fe-59< 11.34< 8.73< 9.01< 8.53< 8.70< 6.08Zn-65< 8.43< 7.00< 7.21< 3.95< 5.57< 4.69Co-60< 3.76< 2.84< 3.82< 2.91< 2.47< 1.98K-40417.8 +/- 24.5< 34.3< 48.632.2+/-10.220.5+/-10.024.5+/-6.8Ba/La-140< 11.40< 8.68< 10.95< 7.97< 8.13< 6.47 ** Optional Sample Location*** Corresponds to sample location noted on Figure 3.3-4NOVEMBERDECEMBERJULYAUGUSTSEPTEMBEROCTOBERNINE MILE POINT UNIT 1 ** (09, INLET)***JANUARYFEBRUARYMARCHAPRILMAYJUNETABLE 6-4 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2009Results in Units of pCi/liter +/- 1 Sigma 6 - 11NUCLIDEI-131< 13.61< 11.81< 9.90< 11.47< 14.52< 14.78Cs-134< 4.21< 2.54< 2.30< 1.84< 2.94< 2.83Cs-137< 3.58< 3.63< 3.19< 2.37< 4.14< 3.78Zr-95< 7.82< 6.25< 5.50< 5.30< 8.87< 7.96Nb-95< 5.27< 4.84< 3.99< 3.60< 5.72< 5.38Co-58< 4.28< 3.89< 3.48< 3.17< 4.51< 4.93Mn-54< 3.57< 4.07< 2.61< 2.57< 4.60< 4.00Fe-59< 12.15< 10.19< 9.82< 8.25< 14.98< 12.52Zn-65< 7.96< 10.18< 8.31< 3.24< 10.98< 9.35Co-60< 3.70< 4.33< 3.19< 2.25< 4.50< 4.47K-40197.0 +/- 18.6110.3+/-17.2< 34.339.4+/-9.6426.1+/-30.4479.4+/-27.5Ba/La-140< 12.06< 9.40< 7.75< 6.32< 11.82< 13.13NUCLIDEI-131< 12.17< 12.47< 14.90< 13.84< 11.87< 12.61Cs-134< 2.22< 3.83< 4.38< 3.41< 1.93< 1.83Cs-137< 2.96< 3.77< 3.21< 3.43< 2.91< 2.41Zr-95< 5.62< 6.23< 8.08< 7.16< 5.91< 5.56Nb-95< 4.17< 4.25< 5.40< 4.65< 4.10< 3.23Co-58< 3.27< 4.46< 4.48< 4.00< 3.38< 2.77Mn-54< 2.80< 3.22< 3.59< 3.36< 3.28< 2.41Fe-59< 9.61< 10.49< 12.51< 12.65< 11.73< 7.75Zn-65< 4.37< 8.54< 8.61< 7.72< 7.29< 3.12Co-60< 2.59< 3.55< 4.04< 3.70< 3.28< 2.16K-40< 34.4161.6+/-18.5181.6+/-20.2137.9+/-17.7142.6+/-17.1108.7+/-12.0Ba/La-140< 9.38< 11.10< 9.29< 12.09< 9.25< 7.61 ** Optional Sample Location*** Corresponds to sample location noted on Figure 3.3-4NOVEMBERDECEMBERJULYAUGUSTSEPTEMBEROCTOBERNINE MILE POINT UNIT 2 ** (11, INLET)***JANUARYFEBRUARYMARCHAPRILMAYJUNETABLE 6-4 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2009Results in Units of pCi/liter +/- 1 Sigma 6 - 12Week EndDate01/06/090.020+/-0.0010.020+/-0.0010.020+/-0.0010.020+/-0.0010.021+/-0.0020.020+/-0.0010.021+/-0.0020.022+/-0.0020.019+/-0.00101/13/090.018+/-0.0010.017+/-0.0010.017+/-0.0010.015+/-0.0010.017+/-0.0010.013+/-0.0010.017+/-0.0010.013+/-0.0010.015+/-0.00101/20/090.024+/-0.0020.024+/-0.0020.026+/-0.0020.025+/-0.0020.028+/-0.0020.025+/-0.0020.024+/-0.0020.024+/-0.0020.028+/-0.00201/27/090.023+/-0.0020.029+/-0.0020.026+/-0.0020.023+/-0.0020.024+/-0.0020.022+/-0.0010.025+/-0.0020.025+/-0.0020.025+/-0.00202/03/090.027+/-0.0020.026+/-0.0020.024+/-0.0020.023+/-0.0020.026+/-0.0020.023+/-0.0010.021+/-0.0010.023+/-0.0020.025+/-0.00202/10/090.023+/-0.0020.021+/-0.0010.018+/-0.0010.020+/-0.0010.025+/-0.0020.022+/-0.0010.019+/-0.0010.023+/-0.0020.021+/-0.00102/17/090.014+/-0.0010.012+/-0.0010.014+/-0.0010.012+/-0.0010.011+/-0.0010.011+/-0.0010.014+/-0.0010.012+/-0.0010.013+/-0.00102/24/090.019+/-0.0010.013+/-0.0010.014+/-0.0010.016+/-0.0010.015+/-0.0010.016+/-0.0010.018+/-0.0010.017+/-0.0010.016+/-0.00103/03/090.019+/-0.0010.021+/-0.0010.019+/-0.0010.019+/-0.0010.019+/-0.0010.017+/-0.0010.024+/-0.0020.021+/-0.0010.027+/-0.00203/10/090.024+/-0.0020.024+/-0.0020.022+/-0.0020.022+/-0.0020.021+/-0.0010.024+/-0.0020.019+/-0.0020.024+/-0.0020.024+/-0.00203/17/090.020+/-0.0010.023+/-0.0020.021+/-0.0010.023+/-0.0010.021+/-0.0010.020+/-0.0010.023+/-0.0020.022+/-0.0010.026+/-0.00203/24/090.024+/-0.0020.023+/-0.0020.022+/-0.0010.022+/-0.0020.022+/-0.0010.022+/-0.0010.021+/-0.0010.021+/-0.0010.021+/-0.00103/31/090.017+/-0.0010.015+/-0.0010.015+/-0.0010.012+/-0.0010.013+/-0.0010.016+/-0.0010.016+/-0.0010.015+/-0.0010.016+/-0.00104/07/090.010+/-0.0010.012+/-0.0010.009+/-0.0010.011+/-0.0010.010+/-0.0010.010+/-0.0010.011+/-0.0010.010+/-0.0010.010+/-0.00104/14/090.019+/-0.0010.017+/-0.0010.018+/-0.0010.018+/-0.0010.018+/-0.0010.018+/-0.0010.017+/-0.0010.018+/-0.0010.019+/-0.00104/21/090.025+/-0.0020.023+/-0.0020.019+/-0.0010.017+/-0.0010.021+/-0.0020.023+/-0.0020.022+/-0.0010.020+/-0.0010.024+/-0.00204/28/090.015+/-0.0010.014+/-0.0010.012+/-0.0010.014+/-0.0010.012+/-0.0010.013+/-0.0010.013+/-0.0010.014+/-0.0010.015+/-0.00105/05/090.018+/-0.0010.006+/-0.0010.018+/-0.0010.016+/-0.0010.020+/-0.0020.015+/-0.0010.019+/-0.0010.017+/-0.0010.016+/-0.00105/12/090.013+/-0.0010.006+/-0.0010.011+/-0.0010.012+/-0.0010.013+/-0.0010.014+/-0.0010.014+/-0.0010.011+/-0.0010.012+/-0.00105/19/090.014+/-0.0010.008+/-0.0010.014+/-0.0010.015+/-0.0010.014+/-0.0010.016+/-0.0010.016+/-0.0010.019+/-0.0010.017+/-0.00105/27/090.019+/-0.0010.016+/-0.0010.018+/-0.0010.017+/-0.0010.016+/-0.0010.017+/-0.0010.017+/-0.0010.019+/-0.0010.017+/-0.00106/02/090.012+/-0.0010.009+/-0.0010.010+/-0.0010.010+/-0.0010.009+/-0.0010.007+/-0.0010.009+/-0.0010.008+/-0.0010.009+/-0.00106/09/090.010+/-0.0010.010+/-0.0010.010+/-0.0010.012+/-0.0010.011+/-0.0010.010+/-0.0010.010+/-0.0010.010+/-0.0010.008+/-0.00106/16/090.013+/-0.0010.013+/-0.0010.010+/-0.0010.010+/-0.0010.012+/-0.0010.015+/-0.0010.013+/-0.0010.011+/-0.0010.012+/-0.00106/23/090.008+/-0.0010.007+/-0.0010.008+/-0.0010.007+/-0.0010.007+/-0.0010.009+/-0.0010.011+/-0.0010.008+/-0.0010.007+/-0.00106/30/090.013+/-0.0010.013+/-0.0010.015+/-0.0010.017+/-0.0010.017+/-0.0010.017+/-0.0010.017+/-0.0010.013+/-0.0010.016+/-0.001

Sample location required by ODCM ** Optional sample locationE **F **TABLE 6-5ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2009GROSS BETA ACTIVITY pCi/ m 3+/- 1 SigmaR-1 *R-2 *R-3 *R-4

G **R-5 *D-2 **

6 - 13Week EndDate07/07/090.012+/-0.0010.010+/-0.0010.008+/-0.0010.012+/-0.0010.010+/-0.0010.010+/-0.0010.010+/-0.0010.009+/-0.0010.009+/-0.00107/14/090.011+/-0.0010.009+/-0.0010.008+/-0.0010.010+/-0.0010.010+/-0.0010.011+/-0.0010.010+/-0.0010.008+/-0.0010.009+/-0.00107/21/090.014+/-0.0010.011+/-0.0010.012+/-0.0010.012+/-0.0010.012+/-0.0010.011+/-0.0010.012+/-0.0010.011+/-0.0010.012+/-0.00107/28/090.016+/-0.0010.014+/-0.0010.019+/-0.0010.017+/-0.0010.017+/-0.0010.016+/-0.0010.015+/-0.0010.018+/-0.0010.016+/-0.00108/04/090.019+/-0.0010.018+/-0.0010.018+/-0.0010.020+/-0.0010.019+/-0.0010.016+/-0.0010.018+/-0.0010.016+/-0.0010.019+/-0.00108/11/090.018+/-0.0010.014+/-0.0010.015+/-0.0010.017+/-0.0010.013+/-0.0010.017+/-0.0010.017+/-0.0010.014+/-0.0010.016+/-0.00108/18/090.032+/-0.0020.027+/-0.0020.025+/-0.0020.027+/-0.0020.030+/-0.0020.025+/-0.0020.028+/-0.0020.027+/-0.0020.025+/-0.00208/25/090.014+/-0.0010.014+/-0.0010.016+/-0.0010.015+/-0.0010.012+/-0.0010.013+/-0.0010.017+/-0.0010.015+/-0.0010.017+/-0.00109/01/090.014+/-0.0010.012+/-0.0010.013+/-0.0010.012+/-0.0010.011+/-0.0010.011+/-0.0010.011+/-0.0010.013+/-0.0010.011+/-0.00109/09/090.021+/-0.0010.020+/-0.0010.018+/-0.0010.020+/-0.0010.021+/-0.0010.020+/-0.0010.020+/-0.0010.022+/-0.0010.021+/-0.00109/15/090.020+/-0.0020.018+/-0.0010.018+/-0.0020.018+/-0.0010.016+/-0.0010.017+/-0.0010.021+/-0.0020.018+/-0.0020.019+/-0.00209/22/090.012+/-0.0010.015+/-0.0010.012+/-0.0010.011+/-0.0010.013+/-0.0010.014+/-0.0010.011+/-0.0010.013+/-0.0010.015+/-0.00109/29/090.014+/-0.0010.011+/-0.0010.013+/-0.0010.013+/-0.0010.013+/-0.0010.010+/-0.0010.013+/-0.0010.012+/-0.0010.016+/-0.00110/06/090.008+/-0.0010.009+/-0.0010.007+/-0.0010.008+/-0.0010.009+/-0.0010.006+/-0.0010.008+/-0.0010.010+/-0.0010.007+/-0.00110/13/090.012+/-0.0010.015+/-0.0010.011+/-0.0010.015+/-0.0010.013+/-0.0010.013+/-0.0010.010+/-0.0010.014+/-0.0010.013+/-0.00110/20/090.013+/-0.0010.012+/-0.0010.012+/-0.0010.011+/-0.0010.011+/-0.0010.013+/-0.0010.012+/-0.0010.013+/-0.0010.013+/-0.00110/27/090.019+/-0.0010.017+/-0.0010.015+/-0.0010.019+/-0.0010.014+/-0.0010.017+/-0.0010.016+/-0.0010.014+/-0.0010.015+/-0.00111/03/090.011+/-0.0010.010+/-0.0010.010+/-0.0010.009+/-0.0010.011+/-0.0010.010+/-0.0010.009+/-0.0010.009+/-0.0010.011+/-0.00111/10/090.017+/-0.0010.017+/-0.0010.016+/-0.0010.016+/-0.0010.019+/-0.0010.018+/-0.0010.015+/-0.0010.016+/-0.0010.017+/-0.00111/17/090.014+/-0.0010.012+/-0.0010.014+/-0.0010.012+/-0.0010.011+/-0.0010.011+/-0.0010.014+/-0.0010.011+/-0.0010.014+/-0.00111/24/090.027+/-0.0020.021+/-0.0020.025+/-0.0020.026+/-0.0020.021+/-0.0020.019+/-0.0010.024+/-0.0020.026+/-0.0020.023+/-0.00212/01/090.016+/-0.0010.013+/-0.0010.015+/-0.0010.013+/-0.0010.015+/-0.0010.016+/-0.0010.016+/-0.0010.015+/-0.0010.016+/-0.00112/08/090.015+/-0.0010.016+/-0.0010.017+/-0.0010.014+/-0.0010.019+/-0.0010.016+/-0.0010.016+/-0.0010.016+/-0.0010.017+/-0.00112/15/090.018+/-0.0010.017+/-0.0010.017+/-0.0010.020+/-0.0020.022+/-0.0020.021+/-0.0010.020+/-0.0010.018+/-0.0010.021+/-0.00212/22/090.021+/-0.0010.019+/-0.0010.021+/-0.0020.018+/-0.0010.020+/-0.0010.019+/-0.0010.018+/-0.0010.023+/-0.0020.019+/-0.00112/29/090.012+/-0.0010.014+/-0.0010.012+/-0.0010.014+/-0.0010.012+/-0.0010.013+/-0.0010.012+/-0.0010.016+/-0.0010.012+/-0.001

Sample location required by ODCM ** Optional sample locationTABLE 6-5 (Continued)ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2009GROSS BETA ACTIVITY pCi/ m 3+/- 1 SigmaR-1 *R-2 *R-3 *R-4

G **R-5 *D-2 **E **F **

6 - 14 Week End Date01/05/090.022

+/-0.0020.024

+/-0.0020.023

+/-0.0020.024

+/-0.0020.021

+/-0.00201/12/090.019

+/-0.0010.018

+/-0.0010.016

+/-0.0010.019

+/-0.0010.016

+/-0.0010.018

+/-0.00101/19/090.021

+/-0.0010.023

+/-0.0020.024

+/-0.0020.021

+/-0.0010.021

+/-0.0010.025

+/-0.00201/26/090.028

+/-0.0020.027

+/-0.0020.026

+/-0.0020.029

+/-0.00202/02/090.026

+/-0.0020.026

+/-0.0020.028

+/-0.0020.026

+/-0.0020.029

+/-0.0020.025

+/-0.00202/09/090.021

+/-0.0010.020

+/-0.0010.023

+/-0.0020.023

+/-0.0020.020

+/-0.0010.023

+/-0.00102/16/090.016

+/-0.0010.013

+/-0.0010.015

+/-0.0010.011

+/-0.0010.016

+/-0.00102/23/090.014

+/-0.0010.015

+/-0.0010.016

+/-0.0010.018

+/-0.0010.013

+/-0.00103/02/090.021

+/-0.0010.021

+/-0.0010.019

+/-0.0010.020

+/-0.00103/09/090.024

+/-0.0020.023

+/-0.0020.028

+/-0.0020.023

+/-0.0020.026

+/-0.0020.020

+/-0.00103/16/090.027

+/-0.0020.024

+/-0.0020.023

+/-0.0020.022

+/-0.0010.023

+/-0.0010.020

+/-0.00103/23/090.023

+/-0.0020.023

+/-0.0010.023

+/-0.0020.022

+/-0.0010.020

+/-0.0010.024

+/-0.00203/30/090.018

+/-0.0010.016

+/-0.0010.017

+/-0.0010.016

+/-0.00104/06/090.012

+/-0.0010.011

+/-0.0010.009

+/-0.0010.010

+/-0.0010.011

+/-0.00104/13/090.013

+/-0.0010.016

+/-0.0010.019

+/-0.0010.016

+/-0.0010.015

+/-0.0010.016

+/-0.00104/20/090.022

+/-0.0010.022

+/-0.0010.021

+/-0.0010.025

+/-0.0020.023

+/-0.00204/27/090.009

+/-0.0010.010

+/-0.0010.012

+/-0.0010.010

+/-0.0010.011

+/-0.0010.013

+/-0.00105/04/090.018

+/-0.0010.019

+/-0.0010.016

+/-0.0010.020

+/-0.0010.017

+/-0.0010.016

+/-0.00105/11/090.015

+/-0.0010.012

+/-0.0010.013

+/-0.0010.009

+/-0.00105/18/090.012

+/-0.0010.014

+/-0.0010.017

+/-0.0010.013

+/-0.0010.015

+/-0.0010.014

+/-0.00105/26/090.019

+/-0.0010.019

+/-0.0010.016

+/-0.0010.018

+/-0.0010.020

+/-0.00106/01/090.007

+/-0.0010.008

+/-0.0010.007

+/-0.0010.009

+/-0.0010.008

+/-0.00106/08/090.012

+/-0.0010.010

+/-0.0010.008

+/-0.0010.009

+/-0.0010.010

+/-0.00106/15/090.010

+/-0.0010.010

+/-0.0010.009

+/-0.0010.010

+/-0.0010.012

+/-0.00106/22/090.009

+/-0.0010.009

+/-0.0010.005

+/-0.0010.009

+/-0.0010.006

+/-0.0010.008

+/-0.00106/29/090.014

+/-0.0010.014

+/-0.0010.012

+/-0.0010.014

+/-0.001 ** Optional sample locationD-1 **G **H **I **TABLE 6-6ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2009GROSS BETA ACTIVITY pCi/ m 3+/- 1 SigmaJ **K **

6 - 15 Week End Date07/06/090.010

+/-0.0010.010

+/-0.0010.012

+/-0.0010.010

+/-0.00107/13/090.010

+/-0.0010.010

+/-0.0010.009

+/-0.0010.010

+/-0.0010.008

+/-0.0010.009

+/-0.00107/20/090.013

+/-0.0010.010

+/-0.0010.014

+/-0.0010.010

+/-0.0010.011

+/-0.00107/27/090.016

+/-0.0010.015

+/-0.0010.016

+/-0.0010.017

+/-0.00108/03/090.018

+/-0.0010.017

+/-0.0010.018

+/-0.0010.017

+/-0.0010.014

+/-0.00108/10/090.017

+/-0.0010.013

+/-0.0010.016

+/-0.0010.017

+/-0.0010.013

+/-0.00108/17/090.024

+/-0.0020.025

+/-0.0020.024

+/-0.0020.023

+/-0.0020.024

+/-0.0020.023

+/-0.00208/24/090.022

+/-0.0020.019

+/-0.0010.022

+/-0.0010.019

+/-0.0010.021

+/-0.00108/31/090.012

+/-0.0010.010

+/-0.0010.012

+/-0.0010.009

+/-0.0010.011

+/-0.00109/08/090.022

+/-0.0010.019

+/-0.0010.017

+/-0.0010.018

+/-0.00109/14/090.020

+/-0.0020.022

+/-0.0020.023

+/-0.0020.022

+/-0.0020.020

+/-0.0020.018

+/-0.00209/21/090.013

+/-0.0010.012

+/-0.0010.013

+/-0.0010.014

+/-0.0010.011

+/-0.00109/28/090.013

+/-0.0010.014

+/-0.0010.013

+/-0.0010.014

+/-0.0010.013

+/-0.0010.014

+/-0.00110/05/090.011

+/-0.0010.008

+/-0.0010.010

+/-0.0010.011

+/-0.0010.009

+/-0.0010.010

+/-0.00110/12/090.011

+/-0.0010.010

+/-0.0010.011

+/-0.0010.010

+/-0.0010.011

+/-0.00110/19/090.012

+/-0.0010.011

+/-0.0010.012

+/-0.0010.013

+/-0.0010.011

+/-0.0010.013

+/-0.00110/26/090.022

+/-0.0020.015

+/-0.0010.015

+/-0.0010.020

+/-0.0010.017

+/-0.00111/02/090.008

+/-0.0010.009

+/-0.0010.012

+/-0.0010.010

+/-0.0010.008

+/-0.00111/09/090.014

+/-0.0010.014

+/-0.0010.016

+/-0.0010.014

+/-0.00111/16/090.017

+/-0.0010.016

+/-0.0010.017

+/-0.0010.015

+/-0.0010.014

+/-0.0010.015

+/-0.00111/23/090.021

+/-0.0010.027

+/-0.0020.026

+/-0.0020.023

+/-0.0020.010

+/-0.0010.008

+/-0.00111/30/090.017

+/-0.0010.017

+/-0.0010.022

+/-0.0020.019

+/-0.0010.019

+/-0.0010.018

+/-0.00112/07/090.017

+/-0.0010.016

+/-0.0010.014

+/-0.0010.016

+/-0.0010.017

+/-0.0010.010

+/-0.00112/14/090.021

+/-0.0010.023

+/-0.0020.020

+/-0.0010.023

+/-0.0020.019

+/-0.0010.017

+/-0.00112/21/090.020

+/-0.0010.020

+/-0.0010.019

+/-0.00112/28/090.011

+/-0.0010.012

+/-0.0010.011

+/-0.0010.015

+/-0.0010.010

+/-0.0010.011

+/-0.001 ** Optional sample locationTABLE 6-6 (Continued)ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2009GROSS BETA ACTIVITY pCi/ m 3+/- 1 SigmaJ **K **D-1 **G **H **I **

6 - 16 Week End Date01/06/09 < 0.033 < 0.032 < 0.017 < 0.014 < 0.018 < 0.021 < 0.024 < 0.030 < 0.02001/13/09 < 0.017 < 0.034 < 0.016 < 0.014 < 0.020 < 0.021 < 0.026 < 0.019 < 0.02501/20/09 < 0.016 < 0.012 < 0.016 < 0.020 < 0.018 < 0.024 < 0.019 < 0.016 < 0.02101/27/09 < 0.021 < 0.015 < 0.011 < 0.020 < 0.021 < 0.023 < 0.018 < 0.022 < 0.01602/03/09 < 0.022 < 0.020 < 0.013 < 0.012 < 0.020 < 0.020 < 0.028 < 0.019 < 0.01702/10/09 < 0.020 < 0.014 < 0.016 < 0.019 < 0.014 < 0.020 < 0.022 < 0.021 < 0.01902/17/09 < 0.022 < 0.016 < 0.022 < 0.018 < 0.018 < 0.014 < 0.018 < 0.022 < 0.02002/24/09 < 0.019 < 0.020 < 0.017 < 0.019 < 0.017 < 0.020 < 0.025 < 0.014 < 0.02103/03/09 < 0.017 < 0.014 < 0.015 < 0.016 < 0.019 < 0.022 < 0.024 < 0.019 < 0.01003/10/09 < 0.021 < 0.012 < 0.016 < 0.019 < 0.019 < 0.026 < 0.026 < 0.015 < 0.01603/17/09 < 0.019 < 0.017 < 0.016 < 0.008 < 0.016 < 0.021 < 0.025 < 0.016 < 0.02103/24/09 < 0.022 < 0.019 < 0.014 < 0.026 < 0.022 < 0.023 < 0.012 < 0.015 < 0.02603/31/09 < 0.023 < 0.024 < 0.022 < 0.014 < 0.014 < 0.017 < 0.023 < 0.023 < 0.01604/07/09 < 0.030 < 0.025 < 0.030 < 0.020 < 0.005 < 0.005 < 0.026 < 0.027 < 0.02504/14/09 < 0.012 < 0.012 < 0.018 < 0.014 < 0.024 < 0.020 < 0.025 < 0.014 < 0.01304/21/09 < 0.018 < 0.012 < 0.019 < 0.022 < 0.026 < 0.027 < 0.016 < 0.019 < 0.01704/28/09 < 0.023 < 0.020 < 0.020 < 0.014 < 0.020 < 0.024 < 0.020 < 0.014 < 0.01005/05/09 < 0.021 < 0.026 < 0.027 < 0.022 < 0.048 < 0.027 < 0.018 < 0.024 < 0.02305/12/09 < 0.023 < 0.028 < 0.015 < 0.030 < 0.035 < 0.055 < 0.036 < 0.024 < 0.01505/19/09 < 0.031 < 0.025 < 0.025 < 0.021 < 0.029 < 0.028 < 0.014 < 0.018 < 0.01805/27/09 < 0.023 < 0.022 < 0.017 < 0.013 < 0.027 < 0.022 < 0.021 < 0.013 < 0.02706/02/09 < 0.020 < 0.021 < 0.026 < 0.016 < 0.033 < 0.041 < 0.016 < 0.016 < 0.02906/09/09 < 0.020 < 0.018 < 0.012 < 0.019 < 0.021 < 0.019 < 0.025 < 0.020 < 0.02206/16/09 < 0.021 < 0.022 < 0.017 < 0.016 < 0.020 < 0.018 < 0.024 < 0.020 < 0.01906/23/09 < 0.006 < 0.019 < 0.026 < 0.018 < 0.016 < 0.027 < 0.029 < 0.019 < 0.02006/30/09 < 0.016 < 0.014 < 0.016 < 0.011 < 0.016 < 0.023 < 0.020 < 0.016 < 0.016

ODCM Required Sample Location ** Optional Sample LocationTABLE 6-7ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2009I-131 ACTIVITY pCi/ m 3+/- 1 SigmaR-1 *R-2 *R-3 *R-4 *R-5 *G **D-2 **F **

E **

6 - 17 Week End Date07/07/09 < 0.023 < 0.026 < 0.019 < 0.029 < 0.032 < 0.006 < 0.025 < 0.018 < 0.02207/14/09 < 0.028 < 0.014 < 0.015 < 0.021 < 0.028 < 0.029 < 0.028 < 0.023 < 0.02107/21/09 < 0.029 < 0.023 < 0.019 < 0.022 < 0.018 < 0.031 < 0.026 < 0.018 < 0.02107/28/09 < 0.024 < 0.026 < 0.019 < 0.019 < 0.015 < 0.038 < 0.024 < 0.021 < 0.02108/04/09 < 0.021 < 0.024 < 0.028 < 0.028 < 0.023 < 0.022 < 0.019 < 0.032 < 0.03208/11/09 < 0.018 < 0.018 < 0.015 < 0.023 < 0.019 < 0.029 < 0.030 < 0.025 < 0.01908/18/09 < 0.024 < 0.014 < 0.018 < 0.022 < 0.024 < 0.019 < 0.026 < 0.021 < 0.02408/25/09 < 0.036 < 0.021 < 0.019 < 0.017 < 0.024 < 0.022 < 0.029 < 0.005 < 0.01409/01/09 < 0.017 < 0.019 < 0.013 < 0.020 < 0.023 < 0.016 < 0.019 < 0.018 < 0.01509/09/09 < 0.018 < 0.014 < 0.013 < 0.014 < 0.018 < 0.022 < 0.019 < 0.015 < 0.01109/15/09 < 0.026 < 0.023 < 0.027 < 0.022 < 0.033 < 0.036 < 0.035 < 0.028 < 0.02909/22/09 < 0.020 < 0.016 < 0.014 < 0.017 < 0.018 < 0.021 < 0.024 < 0.015 < 0.01409/29/09 < 0.018 < 0.021 < 0.015 < 0.023 < 0.014 < 0.033 < 0.032 < 0.023 < 0.02410/06/09 < 0.018 < 0.018 < 0.022 < 0.025 < 0.024 < 0.035 < 0.027 < 0.019 < 0.01910/13/09 < 0.030 < 0.016 < 0.023 < 0.013 < 0.014 < 0.022 < 0.029 < 0.020 < 0.02110/20/09 < 0.020 < 0.017 < 0.010 < 0.012 < 0.017 < 0.021 < 0.016 < 0.017 < 0.01510/27/09 < 0.020 < 0.018 < 0.020 < 0.018 < 0.019 < 0.019 < 0.023 < 0.019 < 0.01811/03/09 < 0.030 < 0.016 < 0.026 < 0.021 < 0.025 < 0.031 < 0.033 < 0.027 < 0.02911/10/09 < 0.021 < 0.030 < 0.031 < 0.017 < 0.028 < 0.029 < 0.028 < 0.021 < 0.01711/17/09 < 0.019 < 0.012 < 0.016 < 0.019 < 0.018 < 0.022 < 0.021 < 0.020 < 0.01811/24/09 < 0.029 < 0.016 < 0.029 < 0.014 < 0.016 < 0.035 < 0.028 < 0.024 < 0.02312/01/09 < 0.018 < 0.016 < 0.014 < 0.014 < 0.017 < 0.021 < 0.023 < 0.018 < 0.01612/08/09 < 0.020 < 0.015 < 0.016 < 0.023 < 0.018 < 0.023 < 0.019 < 0.023 < 0.01212/15/09 < 0.022 < 0.019 < 0.004 < 0.020 < 0.017 < 0.020 < 0.020 < 0.023 < 0.01512/22/09 < 0.029 < 0.029 < 0.022 < 0.019 < 0.028 < 0.034 < 0.025 < 0.022 < 0.02112/29/09 < 0.036 < 0.025 < 0.029 < 0.029 < 0.033 < 0.037 < 0.036 < 0.032 < 0.033

ODCM Required Sample Location ** Optional Sample LocationTABLE 6-7 (Continued)ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2009I-131 ACTIVITY pCi/ m 3+/- 1 SigmaR-1 *R-2 *R-3 *R-4 *R-5 *G **D-2 **F **

E **

6 - 18Week EndDate01/05/09 < 0.037 < 0.017 < 0.017 < 0.018 < 0.022 < 0.02701/12/09 < 0.019 < 0.014 < 0.019 < 0.020 < 0.016 < 0.03001/19/09 < 0.010 < 0.018 < 0.019 < 0.020 < 0.024 < 0.01701/26/09 < 0.019 < 0.015 < 0.015 < 0.019 < 0.021 < 0.023 02/02/09 < 0.021 < 0.020 < 0.013 < 0.020 < 0.024 < 0.02602/09/09 < 0.018 < 0.015 < 0.018 < 0.021 < 0.015 < 0.02202/16/09 < 0.023 < 0.020 < 0.018 < 0.015 < 0.019 < 0.02202/23/09 < 0.024 < 0.018 < 0.016 < 0.016 < 0.017 < 0.01903/02/09 < 0.016 < 0.013 < 0.013 < 0.022 < 0.027 < 0.011 03/09/09 < 0.019 < 0.016 < 0.010 < 0.018 < 0.017 < 0.01903/16/09 < 0.020 < 0.021 < 0.017 < 0.017 < 0.017 < 0.01603/23/09 < 0.020 < 0.018 < 0.020 < 0.015 < 0.016 < 0.025 03/30/09 < 0.016 < 0.017 < 0.021 < 0.020 < 0.025 < 0.01804/06/09 < 0.024 < 0.003 < 0.014 < 0.021 < 0.022 < 0.01704/13/09 < 0.019 < 0.019 < 0.015 < 0.023 < 0.024 < 0.02404/20/09 < 0.022 < 0.026 < 0.024 < 0.015 < 0.019 < 0.01404/27/09 < 0.017 < 0.012 < 0.004 < 0.018 < 0.022 < 0.021 05/04/09 < 0.027 < 0.021 < 0.026 < 0.023 < 0.015 < 0.02605/11/09 < 0.023 < 0.026 < 0.018 < 0.005 < 0.027 < 0.02505/18/09 < 0.014 < 0.021 < 0.014 < 0.026 < 0.031 < 0.03405/26/09 < 0.013 < 0.016 < 0.005 < 0.023 < 0.020 < 0.01806/01/09 < 0.020 < 0.020 < 0.026 < 0.024 < 0.028 < 0.03406/08/09 < 0.027 < 0.021 < 0.021 < 0.028 < 0.019 < 0.02906/15/09 < 0.016 < 0.023 < 0.017 < 0.020 < 0.019 < 0.01606/22/09 < 0.017 < 0.019 < 0.025 < 0.022 < 0.031 < 0.03006/29/09 < 0.026 < 0.019 < 0.019 < 0.023 < 0.027 < 0.019 ** Optional Sample LocationD-1 **G **H **I **J **K **TABLE 6-8ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2009I-131 ACTIVITY pCi/ m 3+/- 1 Si g ma 6 - 19Week EndDate07/06/09 < 0.024 < 0.025 < 0.026 < 0.018 < 0.020 < 0.02507/13/09 < 0.025 < 0.027 < 0.018 < 0.023 < 0.028 < 0.025 07/20/09 < 0.027 < 0.019 < 0.015 < 0.025 < 0.029 < 0.025 07/27/09 < 0.023 < 0.015 < 0.018 < 0.020 < 0.026 < 0.030 08/03/09 < 0.029 < 0.025 < 0.024 < 0.020 < 0.022 < 0.019 08/10/09 < 0.021 < 0.027 < 0.005 < 0.017 < 0.028 < 0.027 08/17/09 < 0.028 < 0.030 < 0.018 < 0.025 < 0.029 < 0.025 08/24/09 < 0.031 < 0.019 < 0.021 < 0.022 < 0.015 < 0.034 08/31/09 < 0.017 < 0.018 < 0.023 < 0.016 < 0.018 < 0.01909/08/09 < 0.017 < 0.015 < 0.010 < 0.015 < 0.022 < 0.01509/14/09 < 0.031 < 0.033 < 0.026 < 0.024 < 0.024 < 0.031 09/21/09 < 0.018 < 0.016 < 0.022 < 0.023 < 0.026 < 0.022 09/28/09 < 0.021 < 0.023 < 0.028 < 0.027 < 0.027 < 0.021 10/05/09 < 0.026 < 0.025 < 0.005 < 0.024 < 0.006 < 0.023 10/12/09 < 0.026 < 0.016 < 0.018 < 0.020 < 0.024 < 0.022 10/19/09 < 0.016 < 0.015 < 0.016 < 0.019 < 0.017 < 0.020 10/26/09 < 0.029 < 0.021 < 0.022 < 0.014 < 0.019 < 0.03211/02/09 < 0.013 < 0.016 < 0.022 < 0.019 < 0.019 < 0.02211/09/09 < 0.020 < 0.023 < 0.023 < 0.023 < 0.019 < 0.007 11/16/09 < 0.024 < 0.021 < 0.014 < 0.019 < 0.019 < 0.038 11/23/09 < 0.024 < 0.013 < 0.019 < 0.021 < 0.019 < 0.026 11/30/09 < 0.021 < 0.018 < 0.025 < 0.017 < 0.011 < 0.021 12/07/09 < 0.021 < 0.018 < 0.018 < 0.015 < 0.016 < 0.022 12/14/09 < 0.017 < 0.020 < 0.021 < 0.026 < 0.028 < 0.031 12/21/09 < 0.026 < 0.014 < 0.019 < 0.024 < 0.031 < 0.02812/28/09 < 0.015 < 0.012 < 0.014 < 0.019 < 0.018 < 0.023 ** Optional sample locationH **I **J **K **D-1 **G **TABLE 6-8 (Continued)ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2009I-131 ACTIVITY pCi/ m 3+/- 1 Si g ma 6 - 20Be-7121.7+/-13.7133.1+/

-13.7119.4+/-14.9112.3+/-14.7135.2+/-14.6128.6+/

-13.4133.9+/

-14.9132.1+/

-15.0113.1+/-14.0Cs-134< 1.8< 2.5< 2.3< 2.5< 1.4< 1.8< 1.6< 1.6< 2.3Cs-137< 1.2< 1.4< 1.0< 1.7< 1.4< 1.1< 1.2< 1.8< 1.6Zr-95< 4.3< 4.5< 3.6< 3.0< 3.4< 4.4< 2.6< 5.3< 4.1Nb-95< 0.8< 4.0< 3.8< 3.8< 2.4< 2.9< 3.1< 2.3< 4.1Co-58< 2.0< 2.3< 2.0< 2.8< 1.7< 1.7< 2.5< 2.0< 2.0Mn-54< 0.4< 1.8< 2.0< 1.7< 1.4< 1.5< 1.4< 2.0< 2.2Zn-65< 1.1< 3.0< 5.3< 3.5< 3.8< 2.4< 1.1< 4.4< 3.2Co-60< 1.6< 1.7< 2.1< 1.6< 2.1< 1.5< 2.0< 2.1< 0.6K-40< 5.9< 5.947.2

+/-10.368.3+/-12.4< 15.9< 4.7< 5.8< 17.2< 24.2Be-7100.3+/-11.1110.2+/

-13.4120.9+/-12.8110.6+/-12.2123.5+/-12.885.5+/

-10.8101.1+/

-12.4121.1+/

-12.9119.8+/-13.9Cs-134< 1.5< 1.6< 1.4< 1.8< 2.3< 1.4< 1.7< 2.0< 2.2Cs-137< 1.3< 0.8< 1.1< 1.0< 1.4< 1.1< 1.2< 0.8< 1.3Zr-95< 4.0< 2.9< 3.6< 4.0< 2.2< 2.2< 2.9< 0.8< 2.5Nb-95< 1.8< 3.0< 1.8< 3.3< 2.2< 1.8< 3.3< 1.8< 3.6Co-58< 1.9< 1.7< 1.8< 0.5< 1.6< 1.9< 1.7< 1.8< 1.8Mn-54< 1.9< 1.2< 1.1< 1.8< 1.5< 1.2< 1.2< 1.7< 1.0Zn-65< 0.8< 3.5< 2.4< 3.4< 3.9< 2.8< 4.5< 3.6< 4.4Co-60< 1.1< 1.4< 1.8< 1.9< 0.4< 1.7< 1.4< 0.5< 2.4K-40< 14.9< 5.2< 15.6< 25.4< 4.3< 11.8< 14.1< 4.5< 15.4

ODCM Required Sample Loction** Optional Sample LocationOFFSITE SAMPLE LOCATIONS - 1ST QTR 2009OFFSITE SAMPLE LOCATIONS - 2ND QTR 2009E **F **G **E **F **G **TABLE 6-9CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2009Results in Units of 10E-3 pCi/ m 3+/- 1 Sigma D-2 **R-1 *R-2 *R-3 *R-4 *R-5 *D-2 **R-3 *R-4 *R-5

NuclideNuclideR-1 *R-2

6 - 21Be-7131.5+/-12.7112.4+/

-12.1114.5+/-12.8102.5+/-11.2115.3+/-13.4123.2+/

-14.495.4+/

-11.2108.7+/

-11.4104.7+/-12.0Cs-134< 2.0< 1.8< 1.2< 1.4< 1.8< 2.0< 2.1< 1.7< 1.6Cs-137< 1.7< 1.0< 1.0< 0.8< 1.2< 1.9< 1.4< 0.3< 1.0Zr-95< 3.5< 4.3< 3.7< 3.1< 3.6< 5.4< 2.1< 4.1< 2.3Nb-95< 3.1< 4.1< 2.7< 1.7< 3.9< 4.9< 2.8< 2.3< 1.9Co-58< 1.5< 1.8< 1.4< 1.7< 2.3< 2.2< 1.9< 1.6< 1.4Mn-54< 1.6< 1.1< 1.2< 1.7< 1.8< 2.0< 1.3< 0.8< 1.4Zn-65< 3.9< 3.6< 2.8< 2.3< 4.2< 4.1< 3.3< 2.9< 1.0Co-60< 1.7< 1.4< 1.4< 1.5< 2.1< 1.7< 1.8< 1.2< 2.3K-40< 11.6< 17.0< 5.2< 14.933.7

+/-8.259.1+/-9.7< 11.1< 15.1< 5.1Be-7104.8+/-12.078.5+/

-11.789.3+/-11.952.8+/-12.189.5+/-11.171.4+/

-10.5105.4+/

-11.786.0+/

-12.395.1+/-12.7Cs-134< 1.5< 2.6< 2.0< 2.2< 1.7< 1.4< 1.9< 2.0< 2.1Cs-137< 0.7< 1.6< 1.0< 1.3< 0.8< 0.9< 1.0< 1.4< 1.6Zr-95< 2.8< 4.9< 4.7< 3.4< 0.9< 2.8< 3.2< 3.3< 5.2Nb-95< 3.5< 3.6< 3.5< 3.9< 2.0< 1.8< 2.7< 4.7< 3.2Co-58< 2.2< 2.2< 1.5< 1.7< 2.0< 1.2< 2.2< 1.5< 2.0Mn-54< 1.6< 1.9< 1.7< 1.7< 1.2< 1.3< 1.9< 1.7< 2.2Zn-65< 3.6< 3.6< 4.4< 5.0< 2.8< 2.4< 4.7< 4.4< 5.1Co-60< 0.5< 1.6< 1.9< 2.4< 1.4< 0.5< 0.5< 1.9< 1.9K-40< 4.6< 21.2< 26.259.1

+/-11.1< 5.2< 18.0< 16.3< 23.470.5

+/-12.2

ODCM Required Sample Loction** Optional Sample LocationOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2009Results in Units of 10E-3 pCi/ m 3+/- 1 SigmaOFFSITE SAMPLE LOCATIONS - 3RD QTR 2009TABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESE **F **G **E **F **G **OFFSITE SAMPLE LOCATIONS - 4TH QTR 2009NuclideR-1 *R-2 *R-3 *R-4 *R-5 *D-2 **R-4 *R-5 *D-2 **NuclideR-1 *R-2 *R-3

6 - 22Be-7141.4 +/- 14.1139.9 +/- 15.6133.4 +/- 15.2124.8 +/- 15.0132.9 +/- 14.1127.5 +/- 12.9Cs-134< 1.1< 1.9< 1.9< 2.1< 2.0< 1.1Cs-137< 1.8< 1.3< 1.4< 1.6< 1.1< 0.9Zr-95< 3.3< 3.6< 4.2< 4.9< 3.8< 3.1Nb-95< 2.7< 3.4< 3.5< 3.8< 2.8< 3.6Co-58< 1.6< 2.9< 2.7< 2.9< 1.9< 2.0Mn-54< 1.1< 1.7< 1.7< 1.8< 1.2< 1.1Zn-65< 3.9< 5.0< 4.2< 5.8< 3.7< 3.1Co-60< 2.0< 2.1< 2.7< 1.3< 2.2< 1.2K-40< 15.8< 17.465.4 +/- 12.960.4 +/- 10.8< 4.5< 12.9Be-7128.3 +/- 13.2129.2 +/- 12.4109.9 +/- 12.0141.4 +/- 13.798.2 +/- 12.7134.6 +/- 13.1Cs-134< 2.2< 1.4< 1.7< 1.7< 1.4< 1.7Cs-137< 1.2< 1.3< 1.0< 0.8< 1.3< 1.0Zr-95< 2.7< 3.3< 2.9< 2.2< 2.5< 3.0Nb-95< 3.2< 3.3< 2.7< 2.2< 0.8< 2.8Co-58< 2.0< 1.3< 0.5< 1.5< 2.1< 1.7Mn-54< 1.5< 1.0< 0.4< 1.4< 1.9< 1.0Zn-65< 2.3< 4.3< 3.4< 2.4< 4.8< 3.3Co-60< 1.5< 1.1< 1.4< 0.4< 0.5< 1.1K-40< 4.2< 17.3< 5.1< 15.1< 5.2< 11.1** Optional Sample LocationNuclideD-1 **G **H **I **J **K **D-1 **G **H **ONSITE SAMPLE LOCATIONS - 2ND QTR 2009I **J **K **

NuclideTABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2009Results in Units of 10E-3 pCi/ m 3+/- 1 SigmaONSITE SAMPLE LOCATIONS - 1ST QTR 2009 6 - 23Be-7140.2 +/- 13.9130.4 +/- 12.3123.9 +/- 12.5127.5 +/- 12.6143.0 +/- 15.2118.1 +/- 13.3Cs-134< 1.7< 1.6< 1.4< 1.7< 2.6< 2.3Cs-137< 1.2< 0.3< 1.0< 0.8< 1.4< 1.2Zr-95< 4.2< 3.4< 3.7< 3.3< 1.0< 3.5Nb-95< 3.9< 1.9< 1.9< 2.3< 3.8< 3.8Co-58< 2.5< 1.3< 1.4< 2.4< 2.6< 2.3Mn-54< 0.9< 1.0< 1.2< 1.3< 2.0< 1.7Zn-65< 2.3< 2.9< 1.0< 3.1< 5.3< 4.5Co-60< 1.5< 1.2< 1.4< 0.5< 1.6< 1.2K-40< 14.5< 4.4< 5.1< 12.346.6 +/- 10.250.8 +/- 9.6Be-788.9 +/- 11.184.4 +/- 11.287.8 +/- 10.9103.7 +/- 13.867.3 +/- 11.687.8 +/- 10.6Cs-134< 1.4< 2.2< 1.9< 1.6< 1.9< 1.2Cs-137< 0.8< 1.3< 1.3< 1.3< 1.9< 1.0Zr-95< 3.1< 2.2< 3.2< 5.4< 4.2< 2.4Nb-95< 2.0< 2.7< 3.6< 3.6< 3.5< 3.6Co-58< 2.3< 2.4< 2.5< 2.7< 1.9< 2.2Mn-54< 1.4< 1.1< 1.7< 2.0< 1.8< 1.4Zn-65< 3.5< 2.4< 4.2< 4.4< 3.4< 2.7Co-60< 1.8< 1.2< 0.5< 2.2< 2.1< 0.5K-40< 14.6< 12.2< 16.449.2 +/- 10.745 +/- 10.3< 21.4** Optional Sample LocationONSITE SAMPLE LOCATIONS - 4TH QTR 2009NuclideD-1 **G **H **I **J **K **Results in Units of 10E-3 pCi/ m 3+/- 1 SigmaONSITE SAMPLE LOCATIONS - 3RD QTR 2009NuclideD-1 **G **H **I **J **K **TABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2009 6 - 24LOCATION NUMBER3D1 Onsite8.71+/-0.3510.61+/-0.4513.55+/-0.5412.84+/-0.5269°at0.2 miles4D2 Onsite3.92+/-0.214.42+/-0.194.51+/-0.244.13+/-0.20140°at0.4 miles5E Onsite3.95+/-0.254.37+/-0.264.66+/-0.244.04+/-0.25175°at0.4 miles6F Onsite3.19+/-0.213.62+/-0.204.14+/-0.253.68+/-0.24210°at0.5 miles7*G Onsite3.13+/-0.163.43+/-0.173.75+/-0.173.48+/-0.20250°at0.7 miles8*R-5 Offsite Control4.29+/-0.274.44+/-0.274.84+/-0.314.68+/-0.2642°at16.4 miles9D1 Offsite3.47+/-0.173.80+/-0.224.07+/-0.193.91+/-0.1880°at11.4 miles10D2 Offsite3.35+/-0.163.87+/-0.233.80+/-0.233.76+/-0.22117°at9.0 miles11E Offsite3.33+/-0.243.83+/-0.224.04+/-0.263.71+/-0.21160°at7.2 miles12F- Offsite3.46+/-0.213.92+/-0.224.00+/-0.223.74+/-0.18190°at7.7 miles13G Offsite3.75+/-0.273.87+/-0.184.13+/-0.234.00+/-0.17225°at5.3 miles14*DeMass Rd SW Oswego - Control3.68+/-0.234.12+/-0.234.16+/-0.233.99+/-0.19226°at12.6 miles15*Pole 66 W Boundary - Bible Camp3.09+/-0.163.36+/-0.183.64+/-0.243.52+/-0.23237°at0.9 miles18*Energy Info Center - Lamp Post SW3.82+/-0.264.13+/-0.254.52+/-0.264.30+/-0.19265°at0.4 miles19East Boundary - JAF Pole 93.75+/-0.194.20+/-0.254.50+/-0.204.30+/-0.2281°at1.3 miles23*H Onsite4.38+/-0.214.86+/-0.215.17+/-0.264.83+/-0.2470°at0.8 miles24I Onsite3.82+/-0.174.18+/-0.234.54+/-0.244.27+/-0.2598°at0.8 miles25J Onsite3.75+/-0.174.09+/-0.214.26+/-0.204.04+/-0.21110°at0.9 miles26K Onsite3.41+/-0.193.94+/-0.314.18+/-0.203.97+/-0.24132°at0.5 miles27N Fence N of Switchyard JAF17.93+/-1.2219.18+/-1.2920.47+/-1.3220.13+/-1.5560°at0.4 miles28N Light Pole N of Screenhouse JAF22.63+/-1.2928.22+/-1.5626.36+/-1.6928.62+/-1.9768°at0.5 miles29N Fence N of W Side26.14+/-1.4124.27+/-1.7724.55+/-1.6224.52+/-1.6665°at0.5 miles30N Fence (NW) JAF11.31+/-0.7212.58+/-0.9112.01+/-0.7612.18+/-0.7857°at0.4 miles31N Fence (NW) NMP-17.33+/-0.387.62+/-0.417.38+/-0.437.70+/-0.36276°at0.2 miles39N Fence Rad Waste-NMP-111.44+/-0.5912.45+/-0.7312.26+/-0.6413.53+/-0.84292°at0.2 miles47N Fence (NE) JAF6.77+/-0.457.26+/-0.476.68+/-0.316.97+/-0.3169°at0.6 miles49*Phoenix NY-Control3.24+/-0.213.49+/-0.333.55+/-0.173.41+/-0.19163°at19.8 miles51Liberty & Bronson Sts E of OSS4.07+/-0.224.01+/-0.284.05+/-0.244.13+/-0.21233°at7.4 miles52E 12th & Cayuga Sts Oswego School3.79+/-0.273.86+/-0.323.73+/-0.203.77+/-0.21227°at5.8 miles53Broadwell & Chestnut Sts Fulton HS3.91+/-0.234.25+/-0.364.13+/-0.274.11+/-0.23183°at13.7 miles54Liberty St & Co Rt 16 Mexico HS3.69+/-0.213.69+/-0.283.81+/-0.203.85+/-0.20115°at9.3 miles55Gas Substation Co Rt 5-Pulaski3.48+/-0.224.14+/-0.193.94+/-0.233.80+/-0.2175°at13.0 miles56*Rt 104-New Haven Sch (SE Corner)3.40+/-0.223.79+/-0.323.69+/-0.183.51+/-0.20123°at5.3 miles58*Co Rt 1A-Alcan (E of E Entrance Rd)4.06+/-0.184.53+/-0.244.39+/-0.234.18+/-0.21220°at3.1 miles75*Unit 2 N Fence N of Reactor Bldg7.36+/-0.407.53+/-0.377.25+/-0.417.52+/-0.435°at0.1 miles76*Unit 2 N Fence N of Change House5.31+/-0.325.77+/-0.325.66+/-0.255.60+/-0.2425°at0.1 miles77*Unit 2 N Fence N of Pipe Bldg6.04+/-0.326.56+/-0.306.54+/-0.306.36+/-0.2745°at0.2 miles(1) Direction and distance based on NMP-2 reactor centerline.

TLD required by ODCMTABLE 6-10DIRECT RADIATION MEASUREMENT RESULTS - 2009Results in Units of mrem/std. Month +/- 1 SigmaFIRST QUARTERSECOND QUARTERTHIRD QUARTERFOURTH QUARTERDEGREES & DISTANCE (1) 6 - 25LOCATION NUMBER78*JAF E of E Old Lay Down Area3.95+/-0.274.39+/-0.284.49+/-0.194.19+/-0.2690°at1.0 m iles79*Co Rt 29 Pole #63 02 mi S of Lake Rd3.45+/-0.193.88+/-0.263.92+/-0.253.76+/-0.17115°at1.1 m iles80*Co Rt 29 Pole #54 07 mi S of Lake Rd3.53+/-0.214.25+/-0.234.09+/-0.213.93+/-0.21133°at1.4 m iles81*Miner Rd Pole #16 05 mi W of Rt 293.59+/-0.203.96+/-0.244.01+/-0.173.92+/-0.18159°at1.6 m iles82*Miner Rd Pole # 1-1/2 11 mi W of Rt 293.46+/-0.183.91+/-0.314.00+/-0.233.79+/-0.17181°at1.6 m iles83*Lakeview Rd Tree 045 mi N of Miner Rd3.47+/-0.163.97+/-0.293.95+/-0.223.74+/-0.21200°at1.2 m iles84*Lakeview Rd N Pole #6117 200ft N of Lake Rd3.69+/-0.224.35+/-0.344.12+/-0.194.14+/-0.25225°at1.1 m iles85*Unit 1 N Fence N of W Side of Screen House9.46+/-0.5311.38+/-0.9211.20+/-0.6811.66+/-0.60294°at0.2 m iles86*Unit 2 N Fence N of W Side of Screen House7.23+/-0.458.45+/-0.558.12+/-0.558.87+/-0.52315°at0.1 m iles87*Unit 2 N Fence N of E Side of Screen House7.84+/-0.398.01+/-0.488.39+/-0.498.33+/-0.45341°at0.1 m iles88*Hickory Grove Rd Pole #2 06 mi N of Rt 13.62+/-0.224.02+/-0.214.19+/-0.213.88+/-0.2297°at4.5 m iles89*Leavitt Rd Pole #16 04 mi S of Rt13.75+/-0.194.43+/-0.194.40+/-0.244.37+/-0.21111°at4.1 m iles90*Rt 104 Pole #300 150 ft E of Keefe Rd3.54+/-0.214.28+/-0.244.06+/-0.193.99+/-0.18135°at4.2 m iles91*Rt 51A Pole #59 08 mi W of Rt 513.27+/-0.173.95+/-0.283.84+/-0.203.60+/-0.17156°at4.8 m iles92*Maiden Lane Rd Power Pole 06 mi S of Rt 1043.89+/-0.214.54+/-0.314.39+/-0.284.07+/-0.23183°at4.4 m iles93*Rt 53 Pole 1-1 120 ft S of Rt 1043.80+/-0.214.03+/-0.213.87+/-0.213.89+/-0.19205°at4.4 m iles94*Rt 1 Pole #82 250 ft E of Kocher Rd (Co Rt 63)3.50+/-0.173.66+/-0.213.65+/-0.233.72+/-0.21223°at4.7 m iles95*Alcan W access Rd Joe Fultz Blvd Pole #213.31+/-0.183.58+/-0.243.32+/-0.243.49+/-0.22237°at4.1 m iles96*Creamery Rd 03 mi S of Middle Rd Pole 1-1/23.60+/-0.203.89+/-0.213.88+/-0.263.85+/-0.27199°at3.6 m iles97*Rt 29 Pole #50 200ft N of Miner Rd3.50+/-0.254.07+/-0.293.84+/-0.173.89+/-0.20143°at1.8 m iles98Lake Rd Pole #145 015 mi E of Rt 293.68+/-0.224.22+/-0.243.97+/-0.293.87+/-0.17101°at1.2 m iles99NMP Rd 04 mi N of Lake Rd Env Station R13.81+/-0.204.25+/-0.244.27+/-0.214.11+/-0.2088°at1.8 m iles100Rt 29 & Lake Rd Env Station R23.75+/-0.264.29+/-0.254.05+/-0.203.94+/-0.19104°at1.1 m iles101Rt 29 07 mi S of Lake Rd Env Station R33.43+/-0.223.85+/-0.323.76+/-0.233.72+/-0.24132°at1.5 m iles102EOF/Env Lab Rt 176 E Driveway Lamp Post3.65+/-0.193.92+/-0.213.82+/-0.213.68+/-0.16175°at11.9 miles103EIC East Garage Rd Lamp Post4.18+/-0.214.52+/-0.244.43+/-0.254.31+/-0.19267°at0.4 m iles104Parkhurst Rd Pole #23 01 mi S of Lake rd3.52+/-0.274.05+/-0.193.96+/-0.303.81+/-0.20102°at1.4 m iles105Lake view Rd Pole #36 05 mi S of Lake Rd3.67+/-0.194.20+/-0.284.06+/-0.213.93+/-0.25198°at1.4 m iles106Shoreline Cove W of NMP-1 Tree on W Edge4.61+/-0.255.22+/-0.265.21+/-0.335.19+/-0.59274°at0.3 m iles107Shoreline Cove W of NMP-1 30 ft SSW of #1064.50+/-0.245.03+/-0.274.90+/-0.265.02+/-0.27272°at0.3 m iles108Lake Rd Pole #142 300 ft E of Rt 29 S3.69+/-0.184.25+/-0.264.12+/-0.234.08+/-0.18104°at1.1 m iles109Tree North of Lake Rd 300 ft E of Rt 29 N3.86+/-0.174.27+/-0.294.18+/-0.214.05+/-0.20103°at1.1 m iles111State Route 38 Sterling NY - Control3.53+/-0.213.86+/-0.233.72+/-0.223.71+/-0.25166°at26.4 miles112EOF/Env Lab Oswego County Airport3.82+/-0.293.90+/-0.283.99+/-0.203.88+/-0.18175°at11.9 miles113Baldwinsville NY - Control3.42+/-0.213.74+/-0.223.73+/-0.193.58+/-0.25214°at21.8 milesTABLE 6-10 (Continued)DIRECT RADIATION MEASUREMENT RESULTS - 2009Results in Units of mrem/std. Month +/- 1 SigmaFIRST QUARTERSECOND QUARTERTHIRD QUARTERFOURTH QUARTERDEGREES & DISTANCE (1)(1) Direction and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6 - 26DateOthers 04/06/09< 0.613< 7.45< 6.461424 +/- 78.0< 8.18<LLD04/20/09< 0.444< 6.38< 4.751438 +/- 66.8< 6.17<LLD05/04/09< 0.456< 6.27< 6.461549 +/- 82.6< 6.44<LLD05/17/09< 0.584< 11.87< 7.451790 +/- 102.5< 6.97<LLD06/08/09< 0.669< 7.21< 6.161560 +/- 82.8< 5.91<LLD06/22/09< 0.436< 7.33< 6.011396 +/- 78.1< 4.57<LLD07/06/09< 0.549< 9.39< 8.081374 +/- 93.1< 7.09<LLD07/20/09< 0.721< 4.21< 6.741477 +/- 81.5< 7.39<LLD08/10/09< 0.645< 9.74< 8.021648 +/- 96.6< 9.85<LLD08/24/09< 0.544< 7.69< 5.521633 +/- 86.3< 5.88<LLD09/08/09< 0.613< 5.15< 6.521763 +/- 80.7< 6.55<LLD09/21/09< 0.423< 4.34< 6.911713 +/- 81.6< 7.91<LLD10/05/09< 0.444< 6.37< 6.641516 +/- 77.0< 5.81<LLD10/19/09< 0.564< 6.12< 6.601558 +/- 80.7< 6.44<LLD11/02/09< 0.490< 5.22< 5.821360 +/- 78.8< 5.57<LLD11/15/09< 0.747< 10.65< 8.791453 +/- 98.8< 11.25<LLD12/07/09< 0.556< 9.67< 6.721428 +/- 79.3< 7.59<LLD12/21/09< 0.519< 6.98< 6.201486 +/- 81.4< 7.15<LLD ** Sample Location is Optional*** Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclidesI-131Cs-134Cs-137Ba/La-140K-40CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2009Results in Units of pCi/liter +/- 1 SigmaSample Location ** No. 55 ***TABLE 6-11 6 - 27DateOthers 04/06/09< 0.638< 9.78< 7.401210 +/- 84.7< 9.87<LLD04/20/09< 0.439< 9.30< 8.351466 +/- 97.8< 11.44<LLD05/04/09< 0.629< 7.59< 8.621166 +/- 84.2< 10.50<LLD05/17/09< 0.571< 4.40< 5.881855 +/- 82.8< 7.10<LLD06/08/09< 0.748< 6.33< 7.671375 +/- 89.2< 11.12<LLD06/22/09< 0.414< 8.32< 8.161533 +/- 92.9< 6.46<LLD07/06/09< 0.549< 5.77< 8.901832 +/- 106.8< 12.24<LLD07/20/09< 0.730< 4.94< 7.671371 +/- 91.7< 1.80<LLD08/10/09< 0.660< 5.33< 6.201710 +/- 95.1< 7.96<LLD ** Sample Location is Optional*** Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclidesCONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2009Results in Units of pCi/liter +/- 1 SigmaI-131Cs-134Cs-137Ba/La-140Sample Location ** No.76 ***TABLE 6-11 (Continued)

K-40 NOTE: Sample location discontinued as herd was sold.

6 - 28DateOthers 04/06/09< 0.564< 5.89< 5.241361 +/- 59.8< 5.50<LLD04/20/09< 0.471< 3.78< 4.591459 +/- 57.4< 5.05<LLD05/04/09< 0.530< 6.38< 5.651626 +/- 71.2< 5.41<LLD05/18/09< 0.544< 9.39< 10.011561 +/- 96.5< 12.89<LLD06/08/09< 0.631< 4.42< 5.021553 +/- 70.7< 5.41<LLD06/22/09< 0.493< 3.68< 4.801417 +/- 67.0< 6.03<LLD07/06/09< 0.614< 8.18< 4.961401 +/- 79.5< 5.55<LLD07/20/09< 0.631< 6.09< 5.841379 +/- 66.6< 5.71<LLD08/10/09< 0.549< 7.46< 6.701466 +/- 77.7< 5.60<LLD08/24/09< 0.605< 6.16< 5.451500 +/- 68.5< 4.76<LLD09/08/09< 0.565< 5.47< 7.971805 +/- 106.5< 11.05<LLD09/21/09< 0.450< 9.00< 8.902008 +/- 110.6< 11.64<LLD10/05/09< 0.480< 3.80< 5.421537 +/- 66.9< 4.88<LLD10/19/09< 0.606< 5.85< 5.841448 +/- 67.5< 6.00<LLD11/02/09< 0.471< 7.84< 7.401241 +/- 85.5< 6.46<LLD11/16/09< 0.700< 3.40< 4.971448 +/- 69.1< 6.13<LLD12/07/09< 0.668< 4.16< 4.351456 +/- 68.4< 6.44<LLD12/21/09< 0.648< 7.89< 5.191534 +/- 71.0< 3.57<LLD

Sample Location is required by the ODCM*** Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclidesCONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2009Results in Units of pCi/liter +/- 1 SigmaSample Location

No.77 (Control) ***TABLE 6-11(Continued)Ba/La-140K-40I-131Cs-134Cs-137 6 - 29Location ***DateDescriptionOthers Culeton09/09/09Collard Greens268 +/- 663252 +/- 217 < 19.1 < 26.9 < 19.6 < 65.3< LLD 133*09/09/09Rhubarb Leaves160 +/- 513075 +/- 200 < 16.4 < 13.8 < 16.6 < 46.8< LLD09/09/09Tomatoes < 862054 +/- 138 < 11.9 < 13.8 < 11.0 < 33.7< LLD09/09/09Swiss Chard < 1625876 +/- 335 < 23.1 < 26.6 < 23.0 < 75.1< LLDLocation ***DateDescriptionOthers O'Connor09/08/09Corn Leaves1889 +/- 1974403 +/- 401 < 45.2 < 58.4 < 50.6 < 124.3< LLD 484*09/08/09Pumpkin Leaves1855 +/- 1334198 +/- 259 < 25.5 < 21.4 < 30.1 < 39.8< LLD09/08/09Cabbage404 +/- 805175 +/- 272 < 24.0 < 20.9 < 24.8 < 61.0< LLD09/08/09Tomatoes < 1302510 +/- 182 < 14.7 < 13.1 < 16.1 < 53.6< LLDLocation ***DateDescriptionOthers Lawton09/09/09Squash Leaves789 +/- 762364 +/- 170 < 18.0 < 22.7 < 18.4 < 44.4< LLD 69**09/09/09Tomatoes < 732334 +/- 145 < 12.8 < 17.0 < 10.1 < 37.7< LLDLocation ***DateDescriptionOthers Kronenbitter09/09/09Grape Leaves984 +/- 1042730 +/- 231 < 27.6 < 28.8 < 22.7 < 76.6< LLD 48**09/09/09Tomatoes < 1052250 +/- 170 < 12.6 < 13.0 < 19.1 < 46.2< LLD

Sample Location Required by the ODCM ** Sample location is Optional*** Corresponds to Sample Location noted on Figure 3.3-5 Plant Related RadionuclidesBe-7K-40I-131Cs-134Cs-137Zn-65Results in Units of pCi/kg (wet) +/- 1 sigmaTABLE 6-12CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2009Be-7K-40I-131Cs-134Cs-137Zn-65Be-7K-40I-131Cs-134Cs-137Zn-65Cs-137Zn-65Be-7K-40I-131Cs-134 6 - 30Location ***DateDescriptionOthers Whaley09/08/09Corn Leaves1456 +/- 1414289 +/- 312 < 32.4 < 37.3 < 23.5 < 79.0< LLD144**09/08/09Squash Leaves1193 +/- 924619 +/- 225 < 20.3 < 14.6 < 16.8 < 51.0< LLD09/08/09Cabbage < 2223483 +/- 274 < 27.9 < 37.2 < 34.4 < 50.9< LLD09/08/09Horseradish690 +/- 1064084 +/- 308 < 26.8 < 43.5 < 25.0 < 85.4< LLDLocation ***DateDescriptionOthers Flack09/15/09Tomatoes < 682571 +/- 108 < 7.5 < 6.8 < 8.7 < 26.0< LLDC2 (Control) *09/15/09Squash Leaves598 +/- 453581 +/- 122 < 10.6 < 14.8 < 11.2 < 27.8< LLD09/15/09Horseradish268 +/- 443108 +/- 151 < 12.1 < 18.6 < 13.3 < 35.5< LLD 09/15/09Rhubarb95 +/- 313595 +/- 125 < 9.7 < 8.1 < 9.4 < 31.0< LLD09/15/09Pumpkin Leaves1901 +/- 692455 +/- 113 < 10.9 < 13.6 < 11.4 < 27.9< LLD

Sample Location Required by the ODCM ** Sample location is Optional*** Corresponds to Sample Location noted on Figure 3.3-5 Plant Related RadionuclidesBe-7K-40I-131Cs-134Cs-137Zn-65Cs-137Zn-65Results in Units of pCi/kg (wet) +/- 1 sigmaBe-7K-40I-131Cs-134TABLE 6-12 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2009 6 - 31 TABLE 6-13MILK ANIMAL CENSUS 2009 Town orArea(a)LocationDesignation (1)Degrees (2)Distance (2)(Miles)Number ofMilk AnimalsNew Haven 9 64 78 98°108°128°4.8 7.8 8.0 40C 36C 0CMexico 14 60 76*

55*21 72 50 125°91°120°97°112°100°93°9.1 9.5 6.2 8.8 10.4 9.6 8.7 55C 15C 24C 54C 80C 34C 0C Granby(Control)77**190° 16.0 68C MILKING ANIMAL TOTALS: 406 Cows (including control locations) 0 Goats MILKING ANIMAL TOTALS: 338 Cows (excluding control locations) 0 GoatsNOTES:C CowsG Milking Goats

Milk sample location** Milk sample control location(1)Reference Figure 3.3-4 (2)Degrees and distance are based on NMP-2 Reactor Building centerline (a) Census performed out to a distance of approximately 10 miles 6 - 32 TABLE 6-142009 RESIDENCE CENSUSMeteorological Sector LocationMap Location (1)Degrees (2)Distance (2)N*---NNE*---NE*---ENE*---EWest Sunset Bay / Lake RoadA100°1.3 milesESELake RoadB104°1.1 milesSECounty Route 29C125°1.4 milesSSECounty Route 29 / Miner RoadD158°1.7 milesSMiner RoadE171°1.6 milesSSWLakeview RoadF208°1.2 milesSWLakeview RoadG217°1.1 milesWSWBayshore DriveH237°1.4 milesW*---WNW*---NW*---NNW*---NOTES:

This meteorological sector is over Lake Ontario. There is no residence within five miles(1)Corresponds to Figure 3.3-5(2)Degrees and distance are based on NMP-2 Reactor Building centerline 7 - 17.0 HISTORICAL DATA TABLESSample Statistics from Previous Environmental SamplingThe mean, minimum value and maximum value were calculated for selected sample mediums andisotopes.Special Considerations:

1. Sample data listed as 1969 was taken from the NINE MILE POINT, PREOPERATION SURVEY,1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWERCORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.2. Sample results listed as 1974 and 1975 were taken from the respective Annual RadiologicalEnvironmental Operating Reports for Nine Mile Point Unit 1 Nuclear Station. Sample results listed as 1986 through the current year were taken from the respective James A. FitzPatrick Nuclear Power Plant Annual Radiological Environmental Operating Reports.3. Only measured values were used for statistical calculations.

4. The term MDL was used prior to 1979 to represent the concept of Lower Limit of Detection(LLD). MDL = Minimum Detectable Level.

7 - 2TABLE 7-1HISTORICAL ENVIRONMENTAL SAMPLE DATASHORELINE SEDIMENTResults in pCi/g (dry)LOCATION: CONTROL *IsotopeCs-134Cs-137Co-60YearMin.Max.MeanMin. Max. Mean Min.Max. Mean1969******

- - - - 1974******

- - - - 1975******

- - - - 1986<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1987<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD <LLD <LLD 0.027 0.027 0.027<LLD<LLD<LLD 1994<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD* Langs Beach - beyond influence of the site in a westerly direction.** No data. Sample not required until new technical specifications implemented in 1985.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 3TABLE 7-2HISTORICAL ENVIRONMENTAL SAMPLE DATASHORELINE SEDIMENTResults in pCi/g (dry)LOCATION: INDICATOR *IsotopeCs-134Cs-137Co-60 Year Min.Max.Mean Min.Max.Mean Min.Max.Mean1969******

- - - - 1974******

- - - - 1975******

- - - - 1986<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1987<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD <LLD <LLD 0.25 0.32 0.29<LLD<LLD<LLD 1990<LLD <LLD <LLD 0.28 0.30 0.29<LLD<LLD<LLD 1991<LLD <LLD <LLD 0.12 0.14 0.13<LLD<LLD<LLD 1992<LLD <LLD <LLD 0.12 0.14 0.13<LLD<LLD<LLD 1993<LLD <LLD <LLD 0.18 0.46 0.32<LLD<LLD<LLD 1994<LLD <LLD <LLD 0.06 0.37 0.22<LLD<LLD<LLD 1995<LLD <LLD <LLD 0.14 0.15 0.15<LLD<LLD<LLD 1996<LLD <LLD <LLD 0.15 0.17 0.16<LLD<LLD<LLD 1997<LLD <LLD <LLD 0.11 0.17 0.14<LLD<LLD<LLD 1998<LLD <LLD <LLD 0.06 0.06 0.06<LLD<LLD<LLD 1999<LLD <LLD <LLD 0.06 0.10 0.08<LLD<LLD<LLD 2000<LLD <LLD <LLD 0.06 0.07 0.06<LLD<LLD<LLD 2001<LLD <LLD <LLD 0.06 0.07 0.07<LLD<LLD<LLD 2002<LLD <LLD <LLD 0.05 0.05 0.05<LLD<LLD<LLD 2003<LLD <LLD <LLD 0.04 0.05 0.05<LLD<LLD<LLD 2004<LLD <LLD <LLD 0.04 0.04 0.04<LLD<LLD<LLD 2005<LLD <LLD <LLD 0.06 0.09 0.08<LLD<LLD<LLD 2006<LLD <LLD <LLD 0.06 0.06 0.06<LLD<LLD<LLD 2007<LLD <LLD <LLD 0.04 0.04 0.04<LLD<LLD<LLD 2008<LLD <LLD <LLD

<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

Sunset Beach - closest offsite location with recreational value.** No data. Sample not required until new technical specifications implemented in 1985.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 4TABLE 7-3HISTORICAL ENVIRONMENTAL SAMPLE DATAFISHResults in pCi/g (wet)LOCATION: CONTROL *IsotopeCs-137Year Min. Max. Mean1969No DataNo DataNo Data19740.940.940.941975<MDL<MDL<MDL19860.0210.0320.02519870.0170.0400.03119880.0230.0530.03419890.0280.0430.03419900.0330.0790.04519910.0210.0340.02919920.0190.0260.02219930.0300.0360.03319940.0140.0310.02219950.0170.0230.01919960.0180.0220.02019970.0120.0300.02119980.0130.0130.013 1999<LLD<LLD<LLD20000.0210.0210.021 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD

Control location was at an area beyond the influence of the site (westerly direction). 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 5TABLE 7-4HISTORICAL ENVIRONMENTAL SAMPLE DATAFISHResults in pCi/g (wet)LOCATION: INDICATOR * (NMP/JAF)Isotope Cs-137 Year Min. Max. Mean19690.010.130.0619740.084.400.5719751.101.701.3819860.0090.0510.02819870.0240.0630.03319880.0220.0540.03219890.0200.0440.03419900.0270.0930.04019910.0180.0450.02919920.0140.0300.02419930.0180.0350.02819940.0150.0230.01919950.0160.0220.01919960.0160.0250.02019970.0140.0230.01819980.0210.0210.02119990.0180.0210.020 2000<LLD<LLD<LLD 2001<LLD<LLD<LLD20020.0160.0160.016 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD* Indicator locations are in the general area of the NMP-1 and J.A. FitzPatrick cooling water dischargestructures. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 6TABLE 7-5HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATERResults in pCi/literLOCATION: CONTROL Isotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969******1974******1975******1986<LLD<LLD<LLD<LLD<LLD<LLD 1987<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD

No gamma analysis performed (not required). Location was the City of Oswego Water Supply for 1969 - 1984 and the Oswego Steam Station inletcanal for 1985 - Present. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 7TABLE 7-6HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATERResults in pCi/literLOCATION: INDICATOR Isotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969******1974******1975******

1986<LLD<LLD<LLD<LLD<LLD<LLD 1987<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD

No gamma analysis performed (not required). Indicator location was the NMP 1 Inlet Canal for the period 1969 - 1973, and the JAF Inlet Canal for1974 - Present. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 8TABLE 7-7HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUMResults in pCi/literLOCATION: CONTROL *IsotopeTritium Year Min. Max. Mean1969No DataNo DataNo Data1974<MDL<MDL<MDL19753114143621986250550373198714027021019882404603201989143217186199026032029019911802001901992190310243199316023018819942502502501995230230230 1996<LLD<LLD<LLD 1997<LLD<LLD<LLD199819019019019992205103652000196237212 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD

Control location is the City of Oswego, drinking water for 1969 - 1984 and the Oswego Steam Stationinlet canal for 1985 - Present. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP

.

7 - 9TABLE 7-8HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUMResults in pCi/literLOCATION: INDICATOR *IsotopeTritium Year Min. Max. Mean1969No DataNo DataNo Data197438050044019751244823351986260500380198716041032219884304804601989135288225199022029025019912503903101992240300273199320028024219941802602201995320320320 1996<LLD<LLD<LLD1997160160160199819019019019991802702332000161198185 2001<LLD<LLD<LLD2002297297297 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD

Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the JAF Inlet Canal for 1974-Present.1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 10TABLE 7-9HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR PARTICULATE GROSS BETAResults in pCi/m 3LOCATION: CONTROL *IsotopeGross Beta Year Min. Max. Mean19690.1300.5400.33419740.0010.8080.12119750.0080.2940.08519860.0080.2720.03919870.0090.0370.02119880.0080.0390.01819890.0070.0390.01719900.0030.0270.01319910.0070.0280.01419920.0060.0200.01219930.0070.0220.01319940.0080.0250.01519950.0060.0230.01419960.0080.0230.01419970.0060.0250.01319980.0040.0340.01419990.0100.0320.01720000.0060.0270.01520010.0060.0340.01620020.0080.0270.01620030.0040.0320.01520040.0080.0320.01620050.0080.0340.01920060.0070.0330.01620070.0080.0280.01620080.0070.0310.01520090.0070.0300.016

Locations used for 1977 - 1984 were C offsite, D1 offsite, D2 offsite, E offsite, F offsite, and G offsite.Control location R-5 offsite was used for 1985-Present (formerly C offsite location). 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 11 TABLE 7-10HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR PARTICULATE GROSS BETAResults in pCi/m 3LOCATION: INDICATOR *IsotopeGross Beta Year Min. Max. Mean19690.1300.5200.32019740.0030.8850.05819750.0010.4560.06719860.0070.2890.03919870.0090.0400.02119880.0070.0400.01819890.0070.0410.01719900.0060.0230.01419910.0060.0330.01519920.0050.0240.01319930.0050.0230.01419940.0060.0240.01519950.0040.0310.01419960.0060.0250.01319970.0010.0180.01019980.0020.0400.01519990.0090.0390.01720000.0050.0330.01520010.0040.0370.01620020.0060.0260.01620030.0050.0350.01520040.0030.0360.01620050.0070.0410.01920060.0050.0350.01520070.0070.0280.01620080.0040.0300.01620090.0060.0320.016*Locations used for 1969 - 1973 were D1 onsite, D2 onsite, E onsite, F onsite and G onsite. Locations used for1974 - 1984 were D1 onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite and K onsite, as applicable. 1985 - Present: locations were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operationalfor the JAFNPP

.

7 - 12 TABLE 7-11HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATESResults in pCi/m 3LOCATION: CONTROL **Isotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969******1974******1975******19860.00750.03110.0193<LLD<LLD<LLD 1987<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD*No data available (not required prior to 1977).** Locations included composites of offsite air monitoring locations for 1977 - 1984. Sample location included only R-5 air monitoring location for 1985 - Present.1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 13TABLE 7-12HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATESResults in pCi/m 3LOCATION: INDICATOR **Isotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969******1974******1975******19860.00690.03640.0183<LLD<LLD<LLD 1987<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD0.00480.00480.0048 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD*No data available (not required prior to 1977).** Locations included composites of onsite air monitoring locations for 1977 - 1984. Sample locations included R-1through R-4 air monitoring locations for 1985 - Present. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 14 TABLE 7-13HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR RADIOIODINEResults in pCi/m 3LOCATION: CONTROL *Isotope Iodine-131 Year Min. Max. Mean1969******1974******1975<MDL<MDL<MDL19860.0410.3320.151 1987<LLD<LLD<LLD 1988<LLD<LLD<LLD 1989<LLD<LLD<LLD 1990<LLD<LLD<LLD 1991<LLD<LLD<LLD 1992<LLD<LLD<LLD 1993<LLD<LLD<LLD 1994<LLD<LLD<LLD 1995<LLD<LLD<LLD 1996<LLD<LLD<LLD 1997<LLD<LLD<LLD 1998<LLD<LLD<LLD 1999<LLD<LLD<LLD 2000<LLD<LLD<LLD 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD*Locations D1 offsite, D2 offsite, E offsite, F offsite and G offsite used for 1976 - 1984. Location R-5 offsiteused for 1985 - Present.** No results - I-131 analysis not required.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 15 TABLE 7-14HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR RADIOIODINEResults in pCi/m 3LOCATION: INDICATOR *Isotope Iodine-131 Year Min. Max. Mean1969******1974******19750.250.300.2819860.0230.3600.11919870.0110.0180.014 1988<LLD<LLD<LLD 1989<LLD<LLD<LLD 1990<LLD<LLD<LLD 1991<LLD<LLD<LLD 1992<LLD<LLD<LLD 1993<LLD<LLD<LLD 1994<LLD<LLD<LLD 1995<LLD<LLD<LLD 1996<LLD<LLD<LLD 1997<LLD<LLD<LLD 1998<LLD<LLD<LLD 1999<LLD<LLD<LLD 2000<LLD<LLD<LLD 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD

Locations used for 1976 - 1984 were D1 onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite,J onsite and K onsite, as applicable. Locations used for 1985 - Present, were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.** No results - I-131 analysis not required.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 16 TABLE 7-15HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem/standard monthLOCATION: CONTROL **

Year Min. Max.Mean Preop197419751976 1977 1978 1979 1980 1981 1982 1983 1984 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 (1)2.7 4.8 3.2 4.0 3.3 3.3 3.8 3.5 3.8 4.9 4.75.3 (5.5)*

4.6 (4.6)*

4.4 (4.8)*

2.9 (2.9)*

3.7 (3.7)*

3.8 (3.8)*

2.6 (2.6)*

3.4 (3.4)*

3.1 (3.1)*

3.4 (3.4)*

3.7 (3.9)*

3.7 (3.7)*

3.6 (3.7)*

3.7 (3.7)*

3.6 (3.9)*

3.4 (3.4)*

3.3 (3.3)*

3.3 (3.4)*

3.3 (3.3)*

3.2 (3.2)*

3.3 (3.3)*

3.2 (3.2)*

(1)8.9 6.0 7.2 8.0 4.7 5.7 5.8 5.9 6.1 7.2 8.27.5 (7.2)*

6.6 (5.8)*

6.8 (6.8)*

6.4 (5.6)*

6.0 (5.9)*

5.4 (5.3)*

5.0 (4.7)*

5.6 (5.2)*

5.0 (4.6)*

5.7 (4.9)*

5.6 (5.6)*

6.2 (5.2)*

5.6 (4.8)*

7.1 (4.7)*

7.3 (5.5)*

5.4 (5.0)*

5.5 (5.2)*

5.5 (4.8)*

5.9 (5.9)*

5.1 (4.5)*

5.3 (5.3)*

5.8 (5.8)*

5.1 (5.1)*

4.8 (4.8)*

(1)5.6 5.5 5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.26.3 (6.3)*

5.4 (5.2)*

5.6 (5.4)*

4.7 (4.6)*

4.8 (4.6)*

4.5 (4.3)*

4.1 (3.9)*

4.4 (4.3)*

4.1 (3.9)*

4.4 (4.2)*

4.3 (4.2)*

4.7 (4.6)*

4.4 (4.2)*

4.6 (4.4)*

4.7 (4.3)*

4.4 (4.4)*

4.3 (4.1)*

4.2 (4.2)*

4.3 (4.5)*

4.1 (4.0)*

4.1 (4.3)*

4.4 (4.6)*

4.1 (4.3)*

3.9 (4.0)*

Data in parentheses is RETS control data and is determined using TLDs #8, 14 and 49. ** TLD #8 and 14 established 1974, TLD #49 established 1980, TLD #111 established 1988, TLD #113 established 1991.

(1) Data not available. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for JAFNPP.

7 - 17 TABLE 7-16HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION: SITE BOUNDARY **

Year Min. Max.MeanPreop***1974***1975***19865.46.85.919874.75.95.319885.06.15.419894.55.24.819904.55.44.819914.35.54.819923.74.64.219933.84.84.319942.84.94.019953.55.14.419963.25.34.119973.55.94.619983.75.14.419993.37.54.720003.66.84.520013.65.34.520023.55.14.320033.24.94.320043.36.44.420053.44.84.220063.54.74.120073.25.44.320083.24.84.020093.14.53.9* Data not available (not required prior to 1985).TLD #23, 75, 76, 77, 85, 86 and 87 are in close proximity to operational buildings along the north boundary. This boundaryis the lakeshore and is considered to be generally not accessible to the public. These locations are not used in the siteboundary dose determination. 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.** TLDs used for statistics: 7, 18, 78, 79, 80, 81, 82, 83 & 84.

7 - 18 TABLE 7-17HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION: OFFSITE SECTORS **

Year Min. Max.MeanPreop***1974***1975***19864.68.66.019874.36.05.219883.87.05.319892.56.84.919903.66.34.719913.65.84.719922.95.04.119933.46.34.519943.05.14.019953.25.24.319963.25.34.219973.55.84.419983.55.04.219993.65.64.420003.46.64.520013.65.44.420023.15.34.220033.44.84.120043.26.74.420053.24.74.020063.34.44.020073.15.14.220083.24.53.820093.34.53.9* Data not available (not required prior to 1985).** Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 19 TABLE 7-18HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION: SPECIAL INTEREST **

Year Min. Max.MeanPreop***1974***1975***19864.88.26.119873.56.05.119883.96.65.319892.16.44.919903.26.34.819912.95.64.419923.04.84.119933.25.84.519942.94.84.119953.64.84.219963.25.14.219973.56.24.619983.75.64.419993.67.14.620003.67.34.720013.85.44.420023.55.54.220033.45.54.320043.05.94.220053.45.14.120063.55.34.120073.05.84.320083.15.14.020093.14.53.8* Data not available (not required prior to 1985).** Include TLD numbers 8, 15, 56, 58, 96, 97 and 98.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 20 TABLE 7-19HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION: ONSITE INDICATOR **

Year Min. Max.MeanPreop***19743.110.65.719754.616.07.319864.716.17.019874.011.45.819884.411.96.019892.713.16.019903.612.95.519913.211.65.419923.25.64.319933.113.65.219942.814.35.119953.528.66.219963.132.66.419973.528.88.119983.628.86.219993.328.46.620003.716.55.620013.814.55.620023.513.65.320033.212.95.320043.313.25.420053.414.15.420063.514.45.320073.214.85.620083.213.85.220093.113.64.9* No data available.** Includes TLD numbers 3, 4, 5, 6 and 7 (1970 - 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26 (1974- Present).1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 21 TABLE 7-20HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION: OFFSITE INDICATOR **

Year Min. Max.MeanPreop***19742.48.95.319754.57.15.519865.07.66.119874.46.65.219884.26.65.419892.86.44.619903.86.14.819913.45.84.519923.15.24.119933.25.75.019943.05.14.119953.95.74.419963.35.54.119973.76.24.719983.95.64.519993.87.14.620003.87.34.620013.75.94.620023.65.54.420033.15.54.420043.26.54.520053.65.14.220063.95.34.220073.44.94.320083.34.54.020093.34.13.8*No data available.** Includes TLD numbers 9, 10, 11, 12 and 13.

1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 22 TABLE 7-21HISTORICAL ENVIRONMENTAL SAMPLE DATAMILKResults in pCi/literLOCATION: CONTROL **Isotope Cs-137 I-131 Year Min.Max.Mean Min.Max.Mean1969******1974******1975******19865.312.48.40.829.013.6 1987<LLD<LLD<LLD<LLD<LLD<LLD 1988<LLD<LLD<LLD<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD<LLD<LLD<LLD 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD* No data available (sample not required).** Location used was an available milk sample location in a least prevalent wind direction greater than ten miles fromthe site.1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 23 TABLE 7-22HISTORICAL ENVIRONMENTAL SAMPLE DATAMILKResults in pCi/literLOCATION: INDICATORIsotope Cs-137 I-131 Year Min.Max.Mean Min.Max.Mean1969******19741.63910.50.702.001.2319756.022160.012.990.3719866.111.18.60.330.05.219875.59.47.4<LLD<LLD<LLD198810.010.010.0<LLD<LLD<LLD 1989<LLD<LLD<LLD<LLD<LLD<LLD 1990<LLD<LLD<LLD<LLD<LLD<LLD 1991<LLD<LLD<LLD<LLD<LLD<LLD 1992<LLD<LLD<LLD<LLD<LLD<LLD 1993<LLD<LLD<LLD<LLD<LLD<LLD 1994<LLD<LLD<LLD<LLD<LLD<LLD 1995<LLD<LLD<LLD<LLD<LLD<LLD 1996<LLD<LLD<LLD<LLD<LLD<LLD 1997<LLD<LLD<LLD0.250.440.35 1998<LLD<LLD<LLD<LLD<LLD<LLD 1999<LLD<LLD<LLD<LLD<LLD<LLD 2000<LLD<LLD<LLD<LLD<LLD<LLD 2001<LLD<LLD<LLD<LLD<LLD<LLD 2002<LLD<LLD<LLD<LLD<LLD<LLD 2003<LLD<LLD<LLD<LLD<LLD<LLD 2004<LLD<LLD<LLD<LLD<LLD<LLD 2005<LLD<LLD<LLD<LLD<LLD<LLD 2006<LLD<LLD<LLD<LLD<LLD<LLD 2007<LLD<LLD<LLD<LLD<LLD<LLD 2008<LLD<LLD<LLD<LLD<LLD<LLD 2009<LLD<LLD<LLD<LLD<LLD<LLD* No data available (sample not required). 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational forthe JAFNPP.

7 - 24 TABLE 7-23HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTSResults in pCi/g (wet)LOCATION: CONTROL *Isotope Cs-137 Year Min. Max. Mean1969******1974******1975******

1986<LLD<LLD<LLD 1987<LLD<LLD<LLD 1988<LLD<LLD<LLD 1989<LLD<LLD<LLD 1990<LLD<LLD<LLD 1991<LLD<LLD<LLD 1992<LLD<LLD<LLD19930.0080.0080.008 1994<LLD<LLD<LLD 1995<LLD<LLD<LLD 1996<LLD<LLD<LLD 1997<LLD<LLD<LLD 1998<LLD<LLD<LLD 1999<LLD<LLD<LLD 2000<LLD<LLD<LLD 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD

Locations was an available food product sample location in a least prevalent wind direction greater than ten milesfrom the site.** No data available (control samples not required). 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

7 - 25 TABLE 7-24HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTSResults in pCi/g (wet)LOCATION: INDICATOR *Isotope Cs-137 Year Min. Max. Mean1969******19740.040.340.1421975<MDL<MDL<MDL 1986<LLD<LLD<LLD 1987<LLD<LLD<LLD19880.0080.0080.00819890.0110.0110.011 1990<LLD<LLD<LLD19910.0390.0390.039 1992<LLD<LLD<LLD 1993<LLD<LLD<LLD19940.0060.0120.01019950.0110.0120.012 1996<LLD<LLD<LLD19970.0130.0130.013 1998<LLD<LLD<LLD19990.0070.0070.007 2000<LLD<LLD<LLD 2001<LLD<LLD<LLD 2002<LLD<LLD<LLD 2003<LLD<LLD<LLD 2004<LLD<LLD<LLD 2005<LLD<LLD<LLD 2006<LLD<LLD<LLD 2007<LLD<LLD<LLD 2008<LLD<LLD<LLD 2009<LLD<LLD<LLD *Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.** No data available (control samples not required). 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.

8-18.0QUALITY ASSURANCE / QUALITY CONTROL PROGRAM8.1 PROGRAM DESCRIPTIONThe Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licenseeparticipate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparisonsamples are commercially available. Participation in an Interlaboratory Comparison Program ensuresthat independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the JAFEnvironmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated inAtlanta, Georgia.Analytics supplies sample media as blind sample spikes, which contain certified levels ofradioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by theJAF Environmental Laboratory using standard laboratory procedures. Analytics issues a statistical summary report of the results. The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratorys performance.The JAF Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratoryblanks provides a means to detect and measure radioactive contamination of analytical samples.

The analysis of analytical blanks also provides information on the adequacy of backgroundsubtraction. Laboratory blank results are analyzed using control charts.

8-28.2PROGRAM SCHEDULESAMPLEMEDIALABORATORYANALYSISSAMPLE PROVIDERECKERT & ZIEGLERANALYTICSWaterGross Beta3WaterTritium5WaterI-1314WaterMixed Gamma4AirGross Beta3AirI-1314AirMixed Gamma2MilkI-1313MilkMixed Gamma3SoilMixed Gamma1VegetationMixed Gamma2TOTAL SAMPLE INVENTORY348.3ACCEPTANCE CRITERIAEach sample result is evaluated to determine the accuracy and precision of the laboratorys analysisresult. The sample evaluation method is discussed below.8.3.1SAMPLE RESULTS EVALUATIONSamples provided by Analytics are evaluated using what is specified as the NRC method.This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

8-3An Environmental Laboratory analytical result is evaluated using the following calculation:The value for the error resolution is calculated. The error resolution = Reference Result Reference Results Error (1 sigma)Using the appropriate row under the Error Resolution column in Table 8.3.1 below, acorresponding Ratio of Agreement interval is given.The value for the ratio is then calculated. Ratio= QC Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable. TABLE 8.3.1ERROR RESOLUTIONRATIO OF AGREEMENT< 4No Comparison4 to 70.5 to 2.08 to 150.6 to 1.6616 to 500.75 to 1.3351 to 2000.8 to 1.25>2000.85 to 1.18This acceptance test is generally referred to as the NRC method. The acceptance criteria iscontained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as theprocedurally required assessment method and requires the generation of a deviation fromQA/QC program report when results are unacceptable.

8-48.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-1.8.4.1ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTSThirty-four QA blind spike samples were analyzed as part of Analytics 2009 InterlaboratoryComparison Program. The following sample media were evaluated as part of the comparison program.Air Charcoal Cartridge: I-131Air Particulate Filter: Mixed Gamma Emitters, Gross BetaWater: I-131, Mixed Gamma Emitters, Tritium, Gross BetaSoil: Mixed Gamma EmittersMilk: I-131, Mixed Gamma EmittersVegetation: Mixed Gamma EmittersThe JAF Environmental Laboratory performed 130 individual analyses on the 34 QAsamples. Of the 130 analyses performed, 129 were in agreement using the NRC acceptancecriteria for a 99.2% agreement ratio.There was one nonconformity in the 2009 program.8.4.1.1ECKERT & ZIEGLER ANALYTICS SAMPLE NONCONFORMITYEckert & Ziegler Analytics Sample 6570-05, Fe-59 on Air FilterNonconformity No. 2009-02 Corrective Action No. CR-JAF-2009-01758A spiked mixed gamma on an air particulate filter sample supplied by Eckert & ZieglerAnalytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine radionuclides were quantified within the acceptable range.

The mean result for Fe-59 was determined to be outside the QA Acceptance Criteria resulting in sample nonconformity and subsequent corrective action. The filter was analyzed threetimes using three different detectors. An average Fe-59 value of 153 pCi was reported. Theknown result for the sample was 121 pCi as determined by the supplier. All nine radionuclides values quantified at the E-lab were biased high when compared to reference values.

8-5INITIAL RESULTS ON FILTER (NON-CONFORMITY ON Fe-59)Sample Media:Filter Sample Date:3/19/2009Analytics #:E56570-05Sample Units:pCiRadionuclideJAFREFERENCE%RecoveryCe-141131+/- 1.3115 +/- 1.92114%Cr-51435+/- 7.9370 +/- 6.18118%Cs-134134+/- 2.0114 +/- 1.9118%Cs-137150+/- 1.8135 +/- 2.25111%Co-58168+/- 2.0145 +/- 2.41116%Mn-54191+/- 2.1155 +/- 2.59123%Fe-59153+/- 2.3121 +/- 2.02126%Zn-65233+/- 3.9189 +/- 3.16123%Co-60193+/- 1.7173 +/- 2.88112%Reviewed JAF E-lab data from prior years and observed a high bias for this media starting in2008. In November of 2007, a new 16SF source geometry was purchased. The 16SF sourcegeometry is a quarterly composite filter geometry. It was very similar to the old 16SFgeometry. However, the petri dish used in our new 16SF source geometry is slightly deeper and the filters used in our new source geometry arent as tightly packed as the old model.

Sample geometry should match source geometry as close as possible to ensure accurate measurements are obtained. Existing guidance for preparing a QC filter composite sample directs the use of extra material to ensure filters are compressed; however this was for the old 16SF source geometry. Extra material to compress the filters when preparing the QC filter composite sample is no longer needed. We have stopped using extra material to compress QC filters when preparing for analysis.To validate the cause and resolution for exceeding 25% error on Fe-59, the QC sample wasprepared again without using additional packing material. The results were in good agreement and are presented below.REANALYSIS ON FILTER WITH OUT PACKING MATERIALSample Media: FilterSample Date:3/19/2009Analytics #:E56570-05Sample Units:pCiRadionuclideJAFREFERENCE%RecoveryCe-141107+/- 4.2 115 +/-1.9293%Cr-51326+/- 34.0 370 +/-6.1888%Cs-134120+/- 3.2 114 +/-1.9106%Cs-137131+/- 2.8 135 +/-2.2597%Co-58141+/- 4.1 145 +/-2.4197%Mn-54164+/- 3.4 155 +/-2.59106%Fe-59126+/- 6.1 121 +/-2.02104%Zn-65202+/- 6.5 189 +/-3.16107%Co-60174+/- 2.8 173 +/-2.88100%

8-6The E-lab Guidance for the Processing and Reporting of Blind Spike Quality AssuranceSamples was updated in the Procedures Reference and Laboratory Manual. In addition, a section was added to the guidance document concerning impact of future geometry changes to the JAF E-lab QA program. The following results were obtained on next available QA Spiked Air Particulate Filter.Note: The geometry change did not have an impact on client filters as they are notcompressed prior to analysis. Additionally, no plant related radionuclides have been detectedin client air particulate filter composites in the past 2 years.BLIND QA SPIKE SAMPLE FOLLOWING CHANGESample Media:Filter Sampl e Da te: 9/17/2009Analytics #:E6838-05Sample Units:pCiRadionuclideJAFREFERENCE %RecoveryCe-141232 +/- 2.1 234 +/-3.9199%Cr-51180 +/- 8.2 188 +/-3.1596%Cs-134111 +/- 2.3 105 +/-1.75106%Cs-137156 +/- 2.2 158 +/-2.6399%Co-5883.3 +/- 1.7 84.8+/-1.4298%Mn-54185 +/- 2.5 176 +/-2.93105%Fe-59136 +/- 2.7 126 +/-2.1108%Zn-65192 +/- 4.2 174 +/-2.9110%Co-60132 +/- 1.7 137 +/-2.2896%

8-78.4.2NUMERICAL RESULTS TABLES06/18/2009E6758-05Filter1.15E+02+/-1.90E+001.18E+02+/-1.92E+001.16E+02+/-1.91E+00Mean =1.16E+02+/-1.10E+00 06/18/2009 E6723-09Filter1.05E+02+/-1.82E+001.04E+02+/-1.81E+001.07E+02+/-1.83E+00Mean =1.05E+02+/-1.05E+0012/10/2009E6960-05Filter1.08E+02+/-2.56E+001.07E+02+/-2.55E+001.07E+02+/-2.54E+00Mean =1.07E+02+/-1.47E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=UnacceptableGROSS BETA9.80E+01+/-1.64E+00ARATIO (1)1.08AJAF E-LAB RESULTSpCi +/-1 sigmaGROSS BETA1.08E+021.80E+00 DATESAMPLEID NO.MEDIUMANALYSISTABLE 8-1INTERLABORATORY INTERCOMPARISON PROGRAMGross Beta Analysis of Air Particulate FilterREFERENCE LAB*pCi +/-1 sigma

+/-GROSS BETA9.88E+01A+/-1.65E+001.071.09 8-83/19/2009E6568-05WaterH-34.81E+03+/-1.64E+024.94E+03+/-1.65E+024.86E+03+/-1.65E+02Mean =4.87E+03+/-9.51E+016/18/2009E6757-05WaterH-39.39E+02+/-1.32E+029.55E+02+/-1.32E+029.95E+02+/-1.33E+02Mean =9.63E+02+/-7.64E+019/17/2009E6842-05WaterH-31.05E+03+/-1.34E+029.10E+02+/-1.33E+021.01E+03+/-1.33E+02Mean =9.91E+02+/-7.70E+0112/10/2009E6957-09WaterH-31.49E+04+/-2.30E+021.45E+04+/-2.28E+021.43E+04+/-2.27E+02Mean =1.46E+04+/-1.32E+0212/10/2009E6958-09WaterH-31.45E+04+/-2.28E+021.43E+04+/-2.26E+021.45E+04+/-2.28E+02Mean =1.44E+04+/-1.31E+02(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable9.71E+029.91E+02+/-1.66E+011.00JAF E-LAB RESULTSpCi/liter +/-1 sigma1.09+/-1.62E+010.99A ASAMPLEID NO.MEDIUMANALYSIS Tritium Analysis of Water A4.48E+03+/-7.48E+01REFERENCE LAB*pCi/liter +/-1 sigmaTABLE 8-1 (Continued)

DATERATIO (1)+/-2.33E+021.04A1.40E+04+/-2.33E+021.03A1.40E+04 8-903/19/2009E6571-05Water2.34E+02+/-2.40E+002.33E+02+/-2.40E+002.31E+02+/-2.40E+00Mean =2.33E+02+/-1.39E+0006/18/2009E6763-05Water2.59E+02+/-2.60E+002.61E+02+/-2.60E+002.55E+02+/-2.60E+00Mean =2.58E+02+/-1.50E+0009/17/2009E6841-05Water2.20E+02+/-2.30E+002.15E+02+/-2.30E+002.20E+02+/-2.30E+00Mean =2.18E+02+/-1.33E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable AGROSS BETA2.35E+023.92E+000.99

+/-RATIO (1)TABLE 8-1 (Continued)MEDIUMANALYSISREFERENCE LAB*pCi/liter +/-1 sigmaJAF E-LAB RESULTSpCi/liter +/-1 sigmaGross Beta Analysis of Water DATESAMPLE ID NO.2.23E+02+/-3.72E+000.98AGROSS BETA2.77E+02+/-4.63E+000.93AGROSS BETA 8-103/19/2009E6544-09Air8.30E+01+/-1.55E+008.60E+01+/-3.04E+008.50E+01+/-3.21E+00Mean =8.47E+01+/-1.56E+006/18/2009E6761-05Air9.20E+01+/-2.57E+008.79E+01+/-2.49E+008.90E+01+/-1.34E+00Mean =8.96E+01+/-1.27E+009/17/2009E6840-05Air8.98E+01+/-2.63E+008.74E+01+/-2.98E+008.67E+01+/-3.04E+00Mean =8.80E+01+/-1.67E+009/17/2009E683109Air9.24E+01+/-2.74E+009.17E+01+/-1.69E+009.13E+01+/-2.93E+00Mean =9.18E+01+/-1.45E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=UnacceptableI-1319.47E+01+/-1.58E+00ARATIO (1)I-131 AMEDIUMANALYSISREFERENCE LAB*pCi +/-1 sigmaJAF E-LAB RESULTSpCi +/-1 sigmaTABLE 8-1 (Continued)I-131 Gamma Analysis of Air Charcoal DATESAMPLE ID NO.9.19E+011.54E+00

+/-0.950.967.93E+01+/-1.32E+001.07AI-1319.17E+01+/-1.53E+001.00A I-131 8-113/19/2009E6569-05Water1.22E+02+/-4.90E+001.24E+02+/-3.61E+001.23E+02+/-3.67E+00Mean =1.23E+02+/-2.37E+004.11E+02+/-2.53E+013.73E+02+/-1.68E+014.27E+02+/-1.82E+01Mean =4.04E+02+/-1.18E+011.26E+02+/-3.99E+001.28E+02+/-3.13E+001.25E+02+/-3.33E+00Mean =1.26E+02+/-2.02E+001.46E+02+/-4.33E+001.42E+02+/-3.03E+001.36E+02+/-3.11E+00Mean =1.41E+02+/-2.04E+001.63E+02+/-4.38E+001.53E+02+/-3.03E+001.53E+02+/-3.35E+00Mean =1.56E+02+/-2.10E+001.69E+02+/-4.50E+001.69E+02+/-3.34E+001.73E+02+/-3.40E+00Mean =1.70E+02+/-2.18E+001.35E+02+/-4.85E+001.39E+02+/-3.46E+001.35E+02+/-3.81E+00Mean =1.36E+02+/-2.36E+002.13E+02+/-8.07E+002.12E+02+/-5.69E+001.97E+02+/-6.25E+00Mean =2.07E+02+/-3.90E+001.88E+02+/-3.69E+001.89E+02+/-2.63E+001.88E+02+/-2.70E+00Mean =1.88E+02+/-1.76E+007.20E+01+/-2.15E+006.87E+01+/-1.07E+007.04E+01+/-9.82E-01Mean =7.04E+01+/-8.65E-01(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=Unacceptable ACe-1411.20E+02+/-

+/-2.01E+00 6.46E+00 1.98E+003.87E+021.19E+02+/-1.97E+021.03Cs-137JAF E-LAB RESULTSpCi/liter +/-1 sigmaTABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAM ACr-51Cs-134Gamma Analysis of Water DATESAMPLEID NO.MEDIUMANALYSIS AZn-65 ACo-58 A 2.36E+00 2.52E+001.41E+021.51E+02+/-1.04 A1.05 3.30E+00 3.01E+00 A AFe-59 A 2.70E+00 2.11E+001.62E+021.27E+021.07

+/-A1.021.05I-131**1.15E+006.90E+01+/-Mn-54Co-601.80E+02

+/-+/-+/-1.051.06+/-1.04REFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)1.00 8-126/18/2009E6722-09Water2.19E+02+/-7.10E+002.18E+02+/-7.42E+002.22E+02+/-4.21E+00Mean =2.20E+02+/-3.70E+002.77E+02+/-3.12E+012.93E+02+/-3.14E+013.09E+02+/-2.02E+01Mean =2.93E+02+/-1.62E+011.24E+02+/-4.58E+001.27E+02+/-4.80E+001.38E+02+/-3.13E+00Mean =1.30E+02+/-2.45E+001.40E+02+/-4.66E+001.44E+02+/-4.73E+001.45E+02+/-3.01E+00Mean =1.43E+02+/-2.43E+006.74E+01+/-3.96E+007.12E+01+/-4.14E+007.54E+01+/-2.55E+00Mean =7.13E+01+/-2.09E+001.07E+02+/-4.23E+001.07E+02+/-4.51E+001.07E+02+/-2.87E+00Mean =1.07E+02+/-2.27E+001.02E+02+/-5.50E+009.63E+01+/-5.65E+009.66E+01+/-3.75E+00Mean =9.83E+01+/-2.91E+001.41E+02+/-8.34E+001.57E+02+/-8.56E+001.39E+02+/-5.26E+00Mean =1.46E+02+/-4.35E+002.53E+02+/-4.63E+002.43E+02+/-4.72E+002.42E+02+/-2.99E+00Mean =2.46E+02+/-2.42E+008.41E+01+/-4.42E+009.26E+01+/-4.28E+009.55E+01+/-3.98E+00Mean =9.07E+01+/-1.83E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=UnacceptableTABLE 8-1 (Continued)RATIO (1)+/-3.60E+00INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Water DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigma1.02ACr-513.04E+02+/-5.08E+000.96ACe-1412.16E+02Cs-1341.26E+02+/-2.10E+001.02ACs-1371.46E+02+/-2.43E+001.03A0.98A1.03ACo-586.98E+01Mn-541.04E+02+/-1.74E+00+/-1.17E+00Fe-599.29E+01+/-1.55E+001.04AZn-651.33E+02+/-2.22E+001.06A1.10A1.03ACo-602.37E+02I-131**8.83E+01+/-1.47E+00+/-3.95E+00 8-139/17/2009E6837-05Water2.77E+02+/-3.61E+002.69E+02+/-6.49E+002.61E+02+/-6.66E+00Mean =2.69E+02+/-3.33E+002.24E+02+/-1.26E+012.10E+02+/-2.22E+012.20E+02+/-2.82E+01Mean =2.18E+02+/-1.27E+011.26E+02+/-2.15E+001.21E+02+/-4.13E+001.25E+02+/-5.23E+00Mean =1.24E+02+/-2.33E+001.77E+02+/-2.40E+001.76E+02+/-4.67E+001.79E+02+/-5.37E+00Mean =1.77E+02+/-2.50E+009.64E+01+/-1.91E+009.90E+01+/-4.02E+009.12E+01+/-4.23E+00Mean =9.55E+01+/-2.05E+002.14E+02+/-2.64E+002.08E+02+/-5.07E+002.04E+02+/-5.96E+00Mean =2.09E+02+/-2.75E+001.55E+02+/-2.73E+00 1.52E+02+/-5.29E+001.48E+02+/-6.36E+00Mean =1.52E+02+/-2.90E+002.14E+02+/-4.25E+002.25E+02+/-8.57E+002.05E+02+/-9.89E+00Mean =2.15E+02+/-4.59E+001.55E+02+/-1.73E+001.53E+02+/-3.42E+001.58E+02+/-4.11E+00Mean =1.55E+02+/-1.87E+001.00E+02+/-1.19E+009.91E+01+/-3.05E+001.01E+02+/-2.92E+00Mean =1.00E+02+/-1.46E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=UnacceptableI-131**9.84E+01+/-1.64E+00Zn-651.95E+02+/-3.26E+00Co-601.54E+02+/-2.57E+00 A1.01A1.02A1.101.08AMn-541.98E+02Fe-591.41E+02+/-2.36E+00+/-3.30E+00Co-589.54E+01+/-1.59E+001.05A1.00A1.00A1.05ACs-1371.77E+02+/-2.96E+001.18E+02+/-1.97E+00Cs-1342.64E+02+/-4.40E+00Cr-512.12E+02+/-TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Water DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/liter +/-1 sigma 3.54E+00Ce-141REFERENCE LAB*pCi/liter +/-1 sigma1.03ARATIO (1)1.02A 8-1412/10/2009E6959-09Water2.14E+02+/-8.89E+002.14E+02+/-4.58E+002.01E+02+/-9.53E+00Mean =2.10E+02+/-4.60E+005.40E+02+/-4.35E+015.37E+02+/-2.11E+015.36E+02+/-4.64E+01Mean =5.38E+02+/-2.23E+012.62E+02+/-7.33E+002.60E+02+/-3.69E+002.67E+02+/-7.12E+00Mean =2.63E+02+/-3.62E+001.64E+02+/-5.87E+001.82E+02+/-3.00E+001.77E+02+/-5.71E+00Mean =1.74E+02+/-2.91E+002.18E+02+/-6.96E+002.14E+02+/-3.28E+002.28E+02+/-6.54E+00Mean =2.20E+02+/-3.37E+001.99E+02+/-6.21E+001.94E+02+/-3.12E+001.93E+02+/-6.25E+00Mean =1.95E+02+/-3.12E+001.85E+02+/-8.16E+001.90E+02+/-3.99E+002.02E+02+/-8.10E+00Mean =1.92E+02+/-4.06E+003.82E+02+/-1.34E+013.72E+02+/-6.54E+003.96E+02+/-1.32E+01Mean =3.83E+02+/-6.64E+002.62E+02+/-5.43E+002.60E+02+/-2.61E+002.58E+02+/-5.18E+00Mean =2.60E+02+/-2.65E+009.41E+01+/-2.11E+009.37E+01+/-5.70E+009.05E+01+/-6.83E+00Mean =9.28E+01+/-3.05E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=UnacceptableTABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Water DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)Ce-1412.04E+02+/-3.41E+001.03ACr-515.54E+02+/-9.25E+001.03A0.97A0.96ACs-1342.55E+02Cs-1371.81E+02+/-3.02E+00+/-4.26E+00Co-582.13E+02+/-3.56E+001.07AMn-541.79E+02+/-3.00E+001.03A1.09A1.10AFe-591.79E+02Zn-653.48E+02+/-5.82E+00+/-3.00E+00Co-602.58E+02+/-4.31E+00I-131**9.61E+01+/-1.61E+001.01A0.97A 8-153/19/2009E6545-09MILK9.19E+01+/-8.41E+008.83E+01+/-8.48E+009.86E+01+/-3.75E+009.36E+01+/-3.55E+00Mean =9.31E+01+/-3.25E+003.18E+02+/-4.44E+013.02E+02+/-4.52E+012.94E+02+/-2.04E+013.04E+02+/-1.74E+01Mean =3.05E+02+/-1.72E+018.97E+01+/-7.19E+009.17E+01+/-7.67E+009.25E+01+/-2.94E+009.26E+01+/-2.99E+00Mean =9.16E+01+/-2.83E+001.10E+02+/-7.56E+009.81E+01+/-7.53E+001.09E+02+/-3.15E+001.05E+02+/-3.17E+00Mean =1.06E+02+/-2.89E+001.10E+02+/-7.89E+001.19E+02+/-8.32E+001.19E+02+/-3.47E+001.17E+02+/-3.48E+00Mean =1.16E+02+/-3.12E+001.42E+02+/-8.51E+001.22E+02+/-8.28E+001.42E+02+/-3.61E+00 1.30E+02+/-3.49E+00Mean =1.34E+02+/-3.22E+001.02E+02+/-9.68E+008.94E+01+/-9.85E+001.13E+02+/-4.35E+001.01E+02+/-4.29E+00Mean =1.01E+02+/-3.78E+001.48E+02+/-1.58E+011.51E+02+/-6.52E+001.63E+02+/-6.63E+00Mean =1.54E+02+/-6.11E+001.43E+02+/-6.60E+001.55E+02+/-6.91E+001.34E+02+/-2.73E+001.46E+02+/-2.91E+00Mean =1.45E+02+/-2.59E+008.63E+01+/-2.54E+001.02E+02+/-7.17E+008.14E+01+/-5.34E+007.73E+01+/-3.59E+00Mean =8.68E+01+/-2.49E+00(1) Ratio = Reported/AnalyticsA=Acceptable* Sample provided by Eckert & Ziegler Analytics, Inc.U=Unacceptable** Result determined by Resin Extraction/Gamma Spectral Analysis.REFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)+/-1.58E+00TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Milk DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/liter +/-1 sigma0.98ACr-513.05E+02+/-5.10E+001.00ACe-1419.49E+01Cs-1349.37E+01+/-1.57E+000.98ACs-1371.11E+02+/-1.86E+000.98A0.95A1.05ACo-581.19E+02Mn-541.28E+02+/-2.13E+00+/-1.99E+00Fe-599.99E+01+/-1.67E+001.02AZn-651.56E+02+/-2.60E+001.01A0.99A1.09ACo-601.42E+02I-131**7.93E+01+/-1.32E+00+/-2.38E+00 8-166/18/2009E6759-05MILK2.99E+02+/-3.04E+003.00E+02+/-6.52E+002.95E+02+/-8.38E+00Mean =2.98E+02+/-3.68E+004.17E+02+/-1.11E+013.91E+02+/-2.61E+013.79E+02+/-3.51E+01Mean =3.96E+02+/-1.50E+011.78E+02+/-2.04E+001.55E+02+/-8.58E+001.72E+02+/-6.73E+00Mean =1.68E+02+/-3.70E+001.95E+02+/-2.14E+001.97E+02+/-5.28E+001.85E+02+/-6.96E+00Mean =1.92E+02+/-3.00E+009.71E+01+/-1.59E+008.91E+01+/-3.95E+009.06E+01+/-5.74E+00Mean =9.23E+01+/-2.38E+001.45E+02+/-1.95E+001.42E+02+/-4.54E+001.41E+02+/-6.56E+00Mean =1.43E+02+/-2.74E+001.30E+02+/-2.27E+001.29E+02+/-5.47E+001.26E+02+/-7.83E+00Mean =1.28E+02+/-3.27E+001.91E+02+/-3.66E+001.86E+02+/-8.64E+001.82E+02+/-1.26E+01Mean =1.86E+02+/-5.24E+003.18E+02+/-2.05E+003.11E+02+/-4.92E+003.10E+02+/-6.99E+00Mean =3.13E+02+/-2.93E+009.17E+01+/-8.96E-019.38E+01+/-2.70E+009.50E+01+/-2.56E+00Mean =9.35E+01+/-1.28E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=Unacceptable2.29E+001.04A1.05AI-131**Mn-541.37E+02+/-1.02E+02+/-Co-580.92A1.00A+/-1.70E+00Co-603.12E+025.21E+00+/-2.93E+001.06AFe-591.22E+02+/-2.04E+00Zn-651.75E+029.19E+01+/-1.53E+00 A1.01A1.00A1.00ACs-1341.66E+02+/-2.77E+00Cs-1371.92E+02+/-3.20E+00TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMJAF E-LAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigma ACr-51Gamma Analysis of MilkANALYSIS DATESAMPLEID NO.MEDIUMRATIO (1)Ce-1414.00E+02+/-6.69E+002.84E+02+/-4.74E+001.050.99 8-179/17/2009E6839-05MILK2.84E+02+/-7.55E+002.74E+02+/-3.93E+002.86E+02+/-7.43E+00Mean =2.81E+02+/-3.77E+002.16E+02+/-2.57E+011.93E+02+/-1.55E+012.13E+02+/-2.86E+01Mean =2.07E+02+/-1.38E+011.17E+02+/-7.61E+001.30E+02+/-2.57E+001.27E+02+/-4.73E+00Mean =1.25E+02+/-3.11E+001.71E+02+/-4.94E+001.77E+02+/-2.88E+001.79E+02+/-5.63E+00Mean =1.76E+02+/-2.67E+001.06E+02+/-4.03E+001.01E+02+/-2.28E+009.29E+01+/-4.75E+00Mean =1.00E+02+/-2.21E+002.15E+02+/-5.51E+002.22E+02+/-3.20E+002.04E+02+/-5.98E+00Mean =2.14E+02+/-2.91E+001.49E+02+/-5.67E+001.59E+02+/-3.40E+001.56E+02+/-6.85E+00Mean =1.55E+02+/-3.17E+002.16E+02+/-9.24E+002.21E+02+/-5.43E+002.19E+02+/-1.07E+01Mean =2.19E+02+/-5.05E+001.59E+02+/-3.67E+001.62E+02+/-2.13E+001.57E+02+/-4.26E+00Mean =1.59E+02+/-2.00E+009.36E+01+/-1.14E+009.12E+01+/-2.82E+008.91E+01+/-2.98E+00Mean =9.13E+01+/-1.42E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=AcceptableU=Unacceptable0.94AGamma Analysis of MilkINTERLABORATORY INTERCOMPARISON PROGRAM DATESAMPLE ID NO.1.01TABLE 8-1 (Continued)MEDIUMANALYSISJAF E-LAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)Ce-1412.75E+02+/-4.59E+001.02A 2.06E+00Cr-512.21E+02+/-3.69E+00 ACs-1371.85E+02+/-3.09E+000.95ACs-1341.23E+02+/-

ACo-589.94E+01+/-1.66E+00Mn-542.06E+02+/-3.44E+00Fe-591.47E+02+/-2.46E+00Zn-652.04E+02+/-3.40E+000.93ACo-601.60E+02I-131**9.86E+01+/-1.65E+00+/-2.68E+001.00A1.05A1.07A1.01A1.04 8-183/19/2009E6570-05FILTER1.33E+02+/-1.69E+001.31E+02+/-3.28E+001.30E+02+/-1.52E+00Mean =1.31E+02+/-1.33E+004.28E+02+/-1.01E+014.63E+02+/-1.94E+014.15E+02+/-9.20E+00Mean =4.35E+02+/-7.91E+001.33E+02+/-2.20E+001.33E+02+/-5.10E+001.36E+02+/-2.40E+00Mean =1.34E+02+/-2.02E+001.52E+02+/-2.14E+001.44E+02+/-4.55E+001.53E+02+/-2.15E+00Mean =1.50E+02+/-1.82E+001.70E+02+/-2.30E+001.65E+02+/-4.94E+001.69E+02+/-2.27E+00Mean =1.68E+02+/-1.97E+001.89E+02+/-2.46E+001.92E+02+/-5.32E+001.93E+02+/-2.52E+00Mean =1.91E+02+/-2.13E+001.58E+02+/-2.81E+001.42E+02+/-5.72E+001.58E+02+/-2.76E+00Mean =1.53E+02+/-2.31E+002.33E+02+/-4.53E+002.29E+02+/-9.63E+002.37E+02+/-4.59E+00Mean =2.33E+02+/-3.86E+001.95E+02+/-1.96E+001.89E+02+/-4.34E+001.95E+02+/-2.04E+00Mean =1.93E+02+/-1.73E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable1.12AZn-651.89E+02Co-601.73E+02+/-2.88E+00+/-3.16E+001.23A1.26U1.23AFe-591.21E+02+/-2.02E+00Mn-541.55E+02+/-2.59E+001.16ACs-1371.35E+02Co-581.45E+02+/-2.41E+00+/-2.25E+001.18A1.18A1.11ACs-1341.14E+02+/-1.90E+00Cr-513.70E+02+/-6.18E+00REFERENCE LAB*pCi +/-1 sigmaRATIO (1)Ce-1411.15E+02+/-1.92E+001.14ASAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi +/-1 sigmaTABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Air Particulate Filter DATE 8-199/17/2009E6838-05FILTER2.36E+02+/-4.09E+002.30E+02+/-1.95E+002.30E+02+/-4.44E+00Mean =2.32E+02+/-2.11E+001.67E+02+/-1.58E+011.79E+02+/-8.12E+001.94E+02+/-1.69E+01Mean =1.80E+02+/-8.17E+001.04E+02+/-4.61E+001.13E+02+/-2.18E+001.17E+02+/-4.64E+00Mean =1.11E+02+/-2.30E+001.57E+02+/-4.36E+001.51E+02+/-2.28E+001.61E+02+/-4.39E+00Mean =1.56E+02+/-2.20E+008.50E+01+/-3.53E+008.42E+01+/-1.83E+008.08E+01+/-3.39E+00Mean =8.33E+01+/-1.74E+001.84E+02+/-4.87E+001.77E+02+/-2.57E+001.93E+02+/-5.02E+00Mean =1.85E+02+/-2.48E+001.40E+02+/-5.35E+001.41E+02+/-2.90E+001.28E+02+/-5.32E+00Mean =1.36E+02+/-2.69E+001.88E+02+/-8.32E+001.98E+02+/-4.35E+001.90E+02+/-8.48E+00Mean =1.92E+02+/-4.22E+001.38E+02+/-3.45E+001.32E+02+/-1.86E+001.26E+02+/-3.32E+00Mean =1.32E+02+/-1.71E+00(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable0.96AZn-651.74E+02Co-601.37E+02+/-2.28E+00+/-2.90E+001.05A1.08A 1.10AFe-591.26E+02+/-2.10E+00Mn-541.76E+02+/-2.93E+000.98ACs-1371.58E+02Co-588.48E+01+/-1.42E+00+/-2.63E+000.96A1.06A0.99ACs-1341.05E+02+/-1.75E+000.99ACr-511.88E+02+/-3.15E+00Ce-1412.34E+02+/-3.91E+00TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Air Particulate Filter DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi +/-1 sigmaREFERENCE LAB*pCi +/-1 sigmaRATIO (1) 8-206/18/2009E6760-05SOIL4.58E-01+/-1.18E-024.39E-01+/-2.42E-024.33E-01+/-2.36E-02Mean =4.43E-01+/-8.95E-036.89E-01+/-6.85E-026.78E-01+/-1.11E-016.46E-01+/-1.05E-01Mean =6.71E-01+/-4.19E-022.94E-01+/-9.32E-032.50E-01+/-1.93E-022.69E-01+/-1.69E-02Mean =2.71E-01+/-6.82E-033.86E-01+/-1.02E-023.76E-01+/-2.09E-024.04E-01+/-1.85E-02Mean =3.89E-01+/-7.43E-031.38E-01+/-7.57E-031.37E-01+/-1.65E-021.61E-01+/-1.47E-02Mean =1.45E-01+/-5.84E-032.35E-01+/-9.13E-032.16E-01+/-2.13E-022.34E-01+/-1.69E-02Mean =2.28E-01+/-7.17E-032.14E-01+/-1.06E-021.88E-01+/-2.34E-022.16E-01+/-2.02E-02Mean =2.06E-01+/-8.17E-033.19E-01+/-1.57E-023.18E-01+/-3.37E-023.30E-01+/-3.01E-02Mean =3.22E-01+/-1.20E-025.23E-01+/-9.15E-034.97E-01+/-1.87E-024.78E-01+/-1.56E-02Mean =4.99E-01+/-6.50E-03(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable0.98ACo-605.07E-01+/-8.47E-031.13AFe-591.99E-01Zn-652.86E-01+/-4.78E-03+/-3.32E-030.97A1.02A1.04AMn-542.23E-01+/-3.72E-03Co-581.50E-01+/-2.51E-030.96ACs-1342.70E-01Cs-1374.06E-01+/-6.78E-03+/-4.51E-030.96A1.03A1.00ACr-516.52E-01+/-1.09E-02Ce-1414.62E-01+/-7.72E-03TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Soil DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1) 8-216/18/2009E6762-05VEG3.93E-01+/-1.26E-023.96E-01+/-1.46E-023.87E-01+/-6.92E-033.94E-01+/-1.20E-02Mean =3.93E-01+/-5.94E-034.88E-01+/-5.04E-025.19E-01+/-5.88E-025.33E-01+/-3.28E-026.47E-01+/-5.81E-02Mean =5.47E-01+/-2.56E-022.63E-01+/-1.09E-022.64E-01+/-1.50E-022.75E-01+/-7.31E-032.50E-01+/-8.19E-03Mean =2.63E-01+/-5.39E-032.65E-01+/-1.05E-022.72E-01+/-1.32E-022.50E-01+/-6.74E-032.66E-01+/-7.82E-03Mean =2.63E-01+/-4.94E-031.21E-01+/-7.80E-031.23E-01+/-1.06E-021.18E-01+/-5.01E-031.20E-01+/-7.39E-03Mean =1.21E-01+/-3.98E-031.97E-01+/-9.87E-031.91E-01+/-1.29E-021.86E-01+/-6.51E-032.05E-01+/-8.74E-03Mean =1.95E-01+/-4.89E-031.68E-01+/-1.13E-021.83E-01+/-1.47E-021.64E-01+/-8.18E-031.71E-01+/-1.12E-02Mean =1.72E-01+/-5.79E-032.37E-01+/-1.93E-022.52E-01+/-2.30E-022.33E-01+/-1.35E-022.73E-01+/-1.38E-02Mean =2.49E-01+/-8.92E-034.40E-01+/-1.03E-024.27E-01+/-1.32E-024.28E-01+/-6.96E-034.16E-01+/-7.77E-03Mean =4.28E-01+/-4.93E-03(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=Unacceptable0.95ACo-604.50E-01+/-7.52E-030.98AFe-591.77E-01Zn-652.53E-01+/-4.23E-03+/-2.96E-030.91A0.98A0.97AMn-541.98E-01+/-3.31E-03Co-581.33E-01+/-2.22E-030.95ACs-1342.39E-01Cs-1372.77E-01+/-4.63E-03+/-3.99E-030.96A0.95A1.10ACr-515.78E-01+/-9.65E-03Ce-1414.10E-01+/-6.85E-03Gamma Analysis of Vegetation DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1)TABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAM 8-229/17/2009E6832-09VEG6.92E-01+/-1.50E-026.91E-01+/-9.31E-037.15E-01+/-1.55E-02Mean =6.99E-01+/-7.83E-035.12E-01+/-5.80E-025.44E-01+/-3.83E-025.69E-01+/-6.52E-02Mean =5.42E-01+/-3.18E-023.72E-01+/-1.25E-023.42E-01+/-7.99E-033.59E-01+/-1.24E-02Mean =3.58E-01+/-6.45E-034.76E-01+/-1.32E-024.57E-01+/-8.28E-034.44E-01+/-1.27E-02Mean =4.59E-01+/-6.70E-032.42E-01+/-1.08E-022.50E-01+/-6.69E-032.43E-01+/-1.04E-02Mean =2.45E-01+/-5.47E-035.32E-01+/-1.44E-025.44E-01+/-9.24E-035.47E-01+/-1.41E-02Mean =5.41E-01+/-7.39E-033.88E-01+/-1.56E-023.97E-01+/-1.01E-023.71E-01+/-1.54E-02Mean =3.85E-01+/-8.05E-035.74E-01+/-2.50E-025.40E-01+/-1.58E-025.28E-01+/-2.40E-02Mean =5.47E-01+/-1.27E-024.01E-01+/-1.01E-023.97E-01+/-6.33E-033.99E-01+/-9.63E-03Mean =3.99E-01+/-3.83E-03(1) Ratio = Reported/Analytics* Sample provided by Eckert & Ziegler Analytics, Inc.A=AcceptableU=UnacceptableTABLE 8-1 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Vegetation DATESAMPLEID NO.MEDIUMANALYSISJAF E-LAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1)Ce-1416.54E-01+/-1.09E-021.22ACr-515.26E-01+/-8.78E-031.07A1.03A1.04ACs-1342.93E-01Cs-1374.40E-01+/-7.35E-03+/-4.89E-03Co-582.37E-01+/-3.96E-031.10AMn-544.91E-01+/-8.20E-031.03A1.10A1.13AFe-593.50E-01Zn-654.85E-01+/-8.10E-03+/-5.85E-031.04ACo-603.82E-01+/-6.38E-03 8-2

38.5 REFERENCES

8.5.1 Radioactivity

and Radiochemistry, The Counting Room: Special Edition, 1994 CaretakerPublications, Atlanta, Georgia.8.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill,New York (1969).

9 - 19.0GRAPHICAL PRESENTATIONSThis section includes graphic representation of selected sample results.For graphic representation, results reported LLD are considered to be at the "Zero" level of activity.Sample location results specified as "Indicator" and "Control" on the graphs can be referenced back toSection 3.3 for specific locations.

9 - 2James A. FitzPatrick N.P.P. Fish Cs-137Figure 9.1 0 0.01 0.02 0.03 0.04 0.05 0.0619901991199219931994199519961997199819992000200120022003200420052006200720082009pCi/gram (wet)INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 3James A. FitzPatrick N.P.P.Surface Water - TritiumFigure 9.2 0 50 100 150 200 250 300 350 40019901991199219931994199519961997199819992000200120022003200420052006200720082009pCi/lINDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 4James A. FitzPatrick N.P.P. Air Particulate Filter - Gross Beta Figure 9.3 0 0.005 0.01 0.015 0.02 0.02519901991199219931994199519961997199819992000200120022003200420052006200720082009 pCi/m 3INDICATORCONTROL 9 - 5James A. FitzPatrick N.P.P. Air Particulate Filter - Gross BetaFigure 9.40.0050.0100.0150.0200.0250.0300.0351234567891011121314151617181920212223242526Week No.pCi/m 3INDICATOR (R1, R2, R3, R4)CONTROL (R5) 9 - 6James A. FitzPatrick N.P.P. Air Particulate Filter - Gross BetaFigure 9.5 0.005 0.010 0.015 0.020 0.025 0.030 0.0352728293031323334353637383940414243444546474849505152 Week No.pCi/m 3INDICATOR (R1, R2, R3, R4)CONTROL (R5) 9 - 7James A. FitzPatrick N.P.P.Air Particulate Filter Composite Co-60Figure 9.6 0 0.001 0.002 0.003 0.004 0.005 0.00619901991199219931994199519961997199819992000200120022003200420052006200720082009 pCi/m 3INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 8James A. FitzPatrick N.P.P. Air Particulate Filter Composite Cs-137Figure 9.7 0.01 0.0105 0.011 0.0115 0.01219901991199219931994199519961997199819992000200120022003200420052006200720082009 pCi/m 3INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 9James A. FitzPatrick N.P.P. Air Charcoal I-131Figure 9.8 0 0.2 0.4 0.6 0.8 1 1.219901991199219931994199519961997199819992000200120022003200420052006200720082009 pCi/m 3INDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE

.

9 - 10James A. FitzPatrick N.P.P.Milk Cs-137Figure 9.9 0 0.2 0.4 0.6 0.8 1 1.219901991199219931994199519961997199819992000200120022003200420052006200720082009pCi/lINDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 11James A. FitzPatrick N.P.P. Milk I-131Figure 9.10 0 0.05 0.1 0.15 0.2 0.25 0.3 0.35 0.419901991199219931994199519961997199819992000200120022003200420052006200720082009pCi/lINDICATORCONTROLINDICATOR <LLD VALUECONTROL <LLD VALUE 9 - 12James A. FitzPatrick N.P.P.

TLD DataFigure 9.11 0 1 2 3

4 5

6 719901991199219931994199519961997199819992000200120022003200420052006200720082009mRem/Standard MonthControlSite BoundaryOffsiteSpecials

JAFP-10-0056, 2009 Annual Radiological Environmental Operating Report

Contents

Text

12.0 INTRODUCTION

3.2 Analyses

3.3 Sample

3.5 Changes

3.6 Deviation

3.7 Statistical

3.8 Compliance

SUMMARY

5.2 Terrestrial

7.0 HISTORICAL

8.0 QUALITY

9.0 GRAPHICAL

12.0INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.0 miles

25.3CONCLUSION

45.4REFERENCES

SUMMARY

38.5 REFERENCES

8.5.1 Radioactivity

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JAFP-10-0056, 2009 Annual Radiological Environmental Operating Report

Text

12.0 INTRODUCTION

3.2 Analyses

3.3 Sample

3.5 Changes

3.6 Deviation

3.7 Statistical

3.8 Compliance

SUMMARY

5.2 Terrestrial

7.0 HISTORICAL

8.0 QUALITY

9.0 GRAPHICAL

12.0INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.0 miles

25.3CONCLUSION

45.4REFERENCES

SUMMARY

38.5 REFERENCES

8.5.1 Radioactivity

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