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{{Adams
#REDIRECT [[JAFP-14-0061, 2013 Annual Radiological Environmental Operating Report]]
| number = ML14133A172
| issue date = 05/13/2014
| title = 2013 Annual Radiological Environmental Operating Report
| author name = Adner C M
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000333
| license number = DPR-059
| contact person =
| case reference number = JAFP-14-0061
| document type = Annual Operating Report, Environmental Monitoring Report, Letter
| page count = 170
}}
 
=Text=
{{#Wiki_filter:Entergy JAFP-14-0061 May 13, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.O. Box 110 Lycoming.
NY 13093 Tel 315-342-3840 Chris M. Adner Regulatory Assurance Manager
 
==Subject:==
2013 Annual Radiological Environmental Operating Report James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
 
==Dear Sir or Madam:==
This letter transmits the James A. FitzPatrick Nuclear Power Plant's (JAF) Annual Radiological Environmental Operating Report, for the period of January 1, 2013, through December 31 ,2013. This document is submitted in accordance with the Reporting Requirements of the Technical Specifications, Section 5.6.2, and Appendix H of the Technical Requirements Manual, "Offsite Dose Calculation Manual (ODCM)", Part 1, Section 6.1, Annual Radiological Environmental Operating Report. There are no commitments contained in this letter. If you have any questions concerning the enclosed report, please contact Robert Heath, Chemistry Manager, at (315) 349-6635.
Chris M. Adner Regulatory Assurance Manager CAiRH/dc
 
==Enclosure:==
 
2013 Annual Radiological Environmental Operating Report cc: Next Page cc: Mr. William Dean Regional Administrator, Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Resident Inspector's Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. Doug Pickett, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Supervisor, Town of Scriba Route 8, Box 382 Oswego, NY 13126 JAFP-14-0061 Page 2 of 2 A NNUAL RADIOLOGICAL E NVIRONMENTAL O PERATING R EPORTJanuary 1, 2013 - December 31, 2013for 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
-12.2 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...................................................................................................... 3-13 3.4 Land Use Census ...................................................................................................... 3-27
 
===3.5 Changes===
to the REMP Program ............................................................................... 3-27
 
===3.6 Deviation===
and Exceptions to the Program ................................................................ 3-27
 
===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
......................................................................................................... 5-65.2 Terrestrial Program ................................................................................................... 5-1 45.3 Conclusion ................................................................................................................ 5-335.4 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 .......................................... 8-18.1 Program Description ................................................................................................... 8-1
 
===8.2 Program===
Schedule ....................................................................................................... 8-28.3 Acceptance Criteria..................................................................................................... 8-28.4 Program Results Summary ......................................................................................... 8-4
 
===8.5 References===
................................................................................................................ 8-179.0 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-Offsite Sample Locations- 2013 Gross Beta Activity(Jan-Jun) ................................................................. 6-12(Jul-Dec) ................................................................. 6-13Table 6-6Environmental Airborne Particulate Samples-Onsite Sample Locations- 2013 Gross Beta Activity(Jan-Jun) ................................................................. 6-14(Jul-Dec) ................................................................. 6-15Table 6-7Environmental Charcoal Cartridge Samples-Offsite Sample Locations- 2013 I-131 Activity(Jan-Jun) ................................................................. 6-16(Jul-Dec) ................................................................. 6-17Table 6-8Environmental Charcoal Cartridge Samples-Onsite Sample Locations- 2013 I-131 Activity(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. 77 (Control)  .................................................................... 6-27Table 6-12 Concentrations of Gamma Emitters in Food Products ......................................6-28 Table 6-13 Milk Animal Census ........................................................................................6-29 Table 6-14 Residence Census ............................................................................................6-30Historical 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 ..............................................................7-25Quality Assurance / Quality Control ProgramTable 8-1Program Schedule ................................................. 8-2Table 8-2Resolution / Ratio of Agreement ........................... 8-3Table 8-3Interlaboratory Intercomparison ProgramGross Beta Analysis of Air Particulate Filter ..................................................... 8-5Tritium Analysis of Water ................................................................................. 8-5 Gross Beta Analysis of Water ........................................................................... 8-6 I-131 Gamma Analysis of Air Charcoal
............................................................. 8-6Gamma Analysis of Water ................................................................................ 8-7 Gamma Analysis of Milk .................................................................................. 8-9 Gamma Analysis of Air Particulate Filter .........................................................8-12 Gamma Analysis of Soil ...................................................................................8-14Gamma Analysis of Vegetation ........................................................................8-16 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
................................................................................. 9-3Figure 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 James A. FitzPatrick Nuclear Power Plant 2013 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 Laboratory's 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 2013 there were 1799 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 2013 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 2013 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 2013.2.1PROGRAM HISTORYEnvironmental monitoring at the Nine Mile Point site has been ongoing since 1964. The programincludes five years of pre-operational data, which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required pre-operational 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 628 megawatt electric (MWe) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A.FitzPatrick Nuclear Power Plant, owned and operated at that time by the New York Power Authority, began full power operation. The FitzPatrick plant, an 892 MWe (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 Nine Mile Point Nuclear Station, LLC, began full power operation. This 1363 MWe 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 (REMP) is shared, but each utility reviews andpublishes their 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 Energy Nuclear Group. These facilities are operated by Nine Mile Point Nuclear Station, LLC.In summary, three Boiling Water Reactors, which together generate 2883 MWe, have operatedcollectively at the Nine Mile Point site since 1988. A large database of environmental results fromthe 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 and support 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 (REMP) 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 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).
3-2 TABLE 3.0-1REQUIRED SAMPLE COLLECTION AND ANALYSISExposure Pathwayand/or SampleNumber of Samples (a) and LocationsSampling andCollection Frequency(a)Type and Frequencyof Analysis AIRBORNERadioiodineand 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 sample operation with samplecollection weekly or asrequired by dustloading, whichever ismore frequentRadioiodine Canisters:Analyze weekly for I-131Particulate Samples:Gross beta radioactivityfollowing filter change(b),composite (by location) forgamma isotopic(c) quarterly(as a 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 a stationin each of the land based sectors. There are 16 land basedsectors in the inner ring, and 8 land based sectors in the outerringc.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 stationsQuarterlyGamma 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 AnalysisINGESTIONMilka.Samples from milch animals in 3 locations within 3.5 milesdistant having the highest calculated site average D/Q. If there are none, then 1 sample from milch animals in each of 3 areas 3.5 to 5.0 miles distant having the highest calculated site averageD/Q (based on all licensed site reactors)(h)b.1 sample from milch animals at a control location (9 to 20 milesdistant and in a less prevalent wind direction)(d)Twice per month, April through December (samples will be collected in Januarythrough March if I-131is detected in November and December of the preceding year)Gamma isotopic and I-131analysis twice per month when milch animals are on pasture (April throughDecember); monthly (Januarythrough March), if required(c)Fisha.1 sample of each of 2 commercially or recreationally importantspecies in the vicinity of a site discharge pointb.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 distant from the site (d)Twice per yearGamma 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 offsitelocations of highest predicted site average D/Q (based on all licensed site Reactors)One (1) sample of each of the similar broad leaf vegetationgrown at least 9.3 miles distant in a least prevalent wind direction sector(d)Once during harvest seasonGamma isotopic (c) analysis ofedible portions.  (Isotopic toinclude I-131) 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 AnalysisWATERBORNESurface(f)a.1 sample upstream(d)b.1 sample from the site's most downstream cooling waterintakeComposite sample over aone month period(g)Gamma isotopic analysis monthly.Composite for Tritiumanalysis quarterly(c)Sediment fromShoreline1 sample from a downstream area with existing or potentialrecreational valueTwice per yearGamma isotopicanalysis semi-annually(c) 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 andlocations may 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 historicaldata (specified in the ODCM) for all licensed site reactors.(b) Particulate sample filters should be analyzed for gross beta 24 hours or more after sampling to allowfor radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed onthe individual samples.(c) Gamma isotopic analysis means the identification and quantification of gamma emittingradionuclides that 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 whichprovide valid 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 ofthis table, a thermoluminescent dosimeter may be considered to be one phosphor and two or morephosphors in a packet 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 significantinfluence 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 aliquoit at time intervals which are very short (e.g., hourly) relative to the compositing period(e.g., monthly) in order to ensure that a representative sample is obtained.(h) A milk sampling location, as required in Table 5.1-1 of the ODCM, is defined as a location having atleast 10 milking cows present at a designated milk sample location. It has been found from pastexperience, and as a result 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 eliminatesa stable supply of milk for samples as a result of suckling calves and periods when the adult animalsare dry. In the event that 3 milk 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 Brown Trout, Chinook Salmon, Smallmouth Bass, and Walleye, arecollected twice per 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 offshore8-10 miles west of 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.
3-73.1.3SURFACE WATERSurface water samples are taken from the respective inlet canals of the James A.FitzPatrick Nuclear Power Plant (JAFNPP) and NRG's Oswego Steam Station. The JAFNPP facility draws water from Lake Ontario on a continuous basis. This is used forthe "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 7.6 miles 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 currentpatterns from the Oswego River located nearby.Samples from the JAFNPP facility are composited from automatic sampling equipmentwhich discharges into a compositing tank or bottles. Samples are collected monthly fromthe compositor and analyzed for gamma emitters. Samples from the Oswego SteamStation are also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emittingradionuclides.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 arenot required by the ODCM. These locations are optional sample points, which arecollected and analyzed to enhance the surface water sampling program. Monthly composite 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.
3-83.1.4AIR 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 historicalmeteorological 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 Reactor Building. The ODCM also requires 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 distanceof 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 site in 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 as Onsite 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 sectorin 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 in distance from 7.1 to 9.0 miles. These are designated as Offsite Stations D2, E and F respectively.Each 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.
3-93.1.5TLD (DIRECT RADIATION)Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose)in the environment. Environmental TLDs are supplied and processed quarterly by theAREVA NP Environmental Laboratory. The laboratory utilizes a Panasonic based system using UD-814 dosimeters, which are constructed of rectangular teflon wafers impregnated with 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 a description of the five TLD geographical categories used in the NMPNS and JAFNPP Environmental 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*)OffsiteAn outer ring of TLDs placed 4 to 5 miles from the site in each ofthe 8 land based meteorological sectors. This category is required by 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 groupare: 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 ODCM 3-10Although the ODCM requires a total of 32 TLD stations; environmental TLDs are alsoplaced at additional locations not required by the ODCM, within the Onsite, SpecialInterest 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.
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.
3-113.1.6MILKMilk samples are routinely collected from farms during the sampling year. These farmsinclude one indicator location and one control location. Samples are normally collectedApril through December of the sample year. If plant related radionuclides are detected insamples in November and December of the previous year, milk collections are continuedinto the following year starting in January. If plant related radionuclides are not detected in the November and December samples, then milk collections do not commence untilApril of the following sampling year. Milk samples were not collected in January throughMarch of 2013 as there were no positive detections of plant related radionuclides in samples collected during November and December of 2012.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 a homogenous mixture of milk and butter fat. The samples are chilled, preserved, andshipped 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.)3.1.7FOOD 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 collected from 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 9.3 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.
3-123.1.8GROUND 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, Industry Ground Water Protection Initiative Final Guidance Document, August 2007, ground water monitoring is accomplished through sampling of the water table around the plant andanalyzing 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. Starting in March 2010, 16 additional monitoring wells were drilled in the area of the reactor building and nearby SSC's (see Section 3.3, Figure 3.3-7). In August 2013, 3 additional monitoring wells and2 piezometers were installed on site.Samples obtained from these wells are analyzed on a quarterly basis to determine gammaemitters and tritium concentrations. Ground water samples are analyzed for gammaemitters using gamma isotopic analysis and tritium using liquid scintillation detector.Ground water results are documented in the Annual Radiological Effluent Release Reportfor 2013.3.2ANALYSES 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 - Environmental Dosimetry Company5.Fish - Gamma Spectral Analysis6.Food Products (vegetation) - Gamma Spectral Analysis 7.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 - Tritium 3-133.3SAMPLE 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.Map 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 Description 4.Degrees and Distance of the sample location from the site\3.3.1LIST 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 MapFigure 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 - 14 TABLE 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 Inlet237°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 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 - 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°at0.4 miles5Figure 3.3-3 E Onsite180°at0.3miles6Figure 3.3-3 F Onsite213°at0.5 miles  7*Figure 3.3-3 G Onsite245°at0.7 miles  8*Figure 3.3-2 R-5 Offsite Control42°at16.2 miles9Figure 3.3-2 D1 Offsite - State Route 380°at11.4miles10Figure 3.3-2 D2 Offsite118°at9.0 miles11Figure 3.3-2 E Offsite162°at7.1miles12Figure 3.3-2 F- Offsite192°at7.6miles13Figure 3.3-2 G Offsite226°at5.4 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°at0.9 miles  18*Figure 3.3-3 Energy Info. Center - Lamp Post, SW268°at0.4miles19Figure 3.3-2 East Boundary - JAF, Pole 983°at1.4 miles  23*Figure 3.3-3 H Onsite73°at0.8 miles24Figure 3.3-3 I Onsite95°at0.8 miles25Figure 3.3-3 J Onsite109°at0.9 miles26Figure 3.3-3 K Onsite132°at0.5 miles27Figure 3.3-3 N. Fence, N. of Switchyard, JAF60°at0.4 miles28Figure 3.3-3 N. Light Pole,N. of Screenhouse, JAF68°at0.5 miles29Figure 3.3-3 N. Fence, N. of W. Side65°at0.5 miles30Figure 3.3-3 N. Fence, (NW) JAF57°at0.4 miles31Figure 3.3-3 N. Fence, (NW) NMP-1279°at0.2 miles39Figure 3.3-3 N. Fence, Rad. Waste-NMP-1298°at0.2 miles47Figure 3.3-3 N. Fence, (NE) JAF69°at0.6 miles  49*Figure 3.3-2 Phoenix, NY-Control 168°at19.7 miles51Figure 3.3-2 Liberty & Bronson Sts., E of OSS234°at7.3 miles52Figure 3.3-2 E. 12th & Cayuga Sts., Oswego School227°at5.9 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°at5.2 miles  58*Figure 3.3-2 Co Rt. 1A-Novelis (E. of E. Entrance Rd.)222°at3.0 miles  75*Figure 3.3-3 Unit 2, N. Fence, N. of Reactor Bldg.354°at0.1 miles  76*Figure 3.3-3 Unit 2, N. Fence, N. of Change House25°at0.1 miles  77*Figure 3.3-3 Unit 2, N. Fence, N. of Pipe Bldg.36°at0.2 miles  78*Figure 3.3-3 JAF. E. of E. Old Lay Down Area85°at1.0miles  79*Figure 3.3-3 Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd.120°at1.2 miles  80*Figure 3.3-3 Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd.136°at1.5 miles  81*Figure 3.3-3 Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29159°at1.6miles  82*Figure 3.3-3 Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29180°at1.6 miles  83*Figure 3.3-3 Lakeview Rd., Tree 0.45 mi. N. of Miner Rd.203°at1.2 miles  84*Figure 3.3-2 Lakeview Rd., N., Pole #6117, 200ft. N. of Lake Rd.226°at1.1 miles  85*Figure 3.3-3 Unit 1, N. Fence, N. of W. Side of Screen House292°at0.2 miles  86*Figure 3.3-3 Unit 2, N. Fence, N of W. Side of Screen House311°at0.1 miles  87*Figure 3.3-3 Unit 2, N. Fence, N. of E. Side of Screen House333°at0.1 miles  88*Figure 3.3-2 Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 197°at4.5 miles  89*Figure 3.3-2 Leavitt Rd., Pole #16, 0.4 mi. S. of Rt.1112°at4.3 miles  90*Figure 3.3-2 Rt. 104, Pole #300, 150 ft. E. of Keefe Rd.135°at4.2 miles  91*Figure 3.3-2 Rt 51A, Pole #59, 0.8 mi. W. of Rt. 51157°at4.9 miles  92*Figure 3.3-2 Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104183°at4.4miles  93*Figure 3.3-2 Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104206°at4.4 miles  94*Figure 3.3-2 Rt. 1, Pole #82, 250 ft. E. of Kocher Rd. (Co. Rt. 63)224°at4.4 miles  95*Figure 3.3-2 Novelis W access Rd., Joe Fultz Blvd, Pole #21239°at3.7 miles  96*Figure 3.3-2 Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2199°at3.6miles  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°at1.2 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 - 17TABLE 3.3-1 (Continued)ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUM MAPDESIGNATIONFIGURENUMBERLOCATION DESCRIPTIONDEGREES & DISTANCE (1) & (2)Thermoluminescent99Figure 3.3-2 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R192°at  1.8 milesDosimeters (TLD)100Figure 3.3-3 Rt. 29 & Lake Rd., Env. Station R2106°at1.1 miles(Continued)101Figure 3.3-3 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3133°at1.4 miles102Figure 3.3-2 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post175°at11.9 miles103Figure 3.3-3 EIC, East Garage Rd., Lamp Post268°at0.4 miles104Figure 3.3-2 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake rd.102°at1.4 miles105Figure 3.3-3 Lake view Rd. Pole #36, 0.5 mi. S. of Lake Rd.199°at1.4 miles106Figure 3.3-3 Shoreline Cove, W. of NMP-1, Tree on W. Edge274°at0.3 miles107Figure 3.3-3 Shoreline Cove, W. of NMP-1,  30 ft SSW of #106273°at0.3 miles108Figure 3.3-3 Lake Rd., Pole #142, 300 ft E. of Rt. 29 S.105°at1.1 miles109Figure 3.3-3 Tree North of Lake Rd., 300 ft E. of Rt. 29 N104°at1.1 miles111Figure 3.3-2 Control, State Route 38, Sterling NY214°at21.8 miles112Figure 3.3-2 EOF/Env. Lab, Oswego County Airport175°at11.9 miles113Figure 3.3-2 Control, Baldwinsville, NY178°at24.7milesCow's Milk  55Figure 3.3-4 Indicator Location97°at8.7 miles  77*Figure 3.3-4 Control Location190°at16.0milesFood Products  48**Figure 3.3-5 Indicator Location - Kronenbitter83°at1.5miles133**Figure 3.3-5 Indicator Location - Culeton83°at1.6miles144*Figure 3.3-5 Indicator Location - Whaley139°at1.6 miles484*Figure 3.3-5 Indicator Location  - O'Connor132°at1.4miles C2*Figure 3.3-5 Control Location - Flack222°at15.4 milesNearest Residence (NMP) Based on NMP Unit 2 Centerline - Refer to Figure 3.3-5Nearest 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 DESCRIPTIONThermoluminescentDosimeters (TLD)  I-1*ISFSI West Fence, South End of Storage Pad  I-2*ISFSI West Fence, Center of Storage Pad  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 PadI-15HISFSI Transmission Line Tower South of Pad at East /West Access RoadI-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 Centerline* Sample location required by ODCMH    Indicates Optional TLD location 3 - 19TABLE 3.3-1 (Continued)ENVIRONMENTAL SAMPLE LOCATIONSSAMPLE MEDIUMLOCATIONDESIGNATIONFIGURE NUMBERLOCATION DESCRIPTIONMW-1AFigure 3.3-7Southwest of Reactor BuildingGround WaterMW-1BFigure 3.3-7Southwest of Reactor BuildingMonitoring WellsMW-2AFigure 3.3-7Northwest of Reactor BuildingMW-2BFigure 3.3-7Northwest of Reactor BuildingMW-3AFigure 3.3-7Northwest of Reactor BuildingMW-3BFigure 3.3-7Northwest of Reactor BuildingMW-4AFigure 3.3-7Northeast of Reactor BuildingMW-4BFigure 3.3-7Northeast of Reactor BuildingMW-5Figure 3.3-7Northwest edge of propertyMW-6Figure 3.3-7North / Northwest edge of propertyMW-7Figure 3.3-7North edge of propertyMW-8Figure 3.3-7North / Northeast edge of propertyMW-9Figure 3.3-7Northeast edge of propertyMW-10AFigure 3.3-7Southeast of Reactor BuildingMW-10BFigure 3.3-7Southeast of Reactor BuildingMW-13Figure 3.3-7West of Reactor BuildingMW-14Figure 3.3-7East of Reactor BuildingMW-15Figure 3.3-7South of Reactor BuildingMW-16Figure 3.3-7Northwest of Reactor Building PZ-17Figure 3.3-7North / Northeast of Reactor Building PZ-18Figure 3.3-7North of Reactor Building MW-19Figure 3.3-7Northeast Edge of Property MW-20Figure 3.3-7Southeast Edge of Property MW-21Figure 3.3-7South of Reactor BuildingMW-CST(A)Figure 3.3-7West of Reactor BuildingMW-CST(B)Figure 3.3-7West of Reactor Building BUFFALO B U F F A L O ROCHESTER R O C H E S T E R SYRACUSE S Y R A C U S E UTICA U T I C A ALBANY A L B A N Y 135 MI.1 3 5 M I.38 MI.38 MI.230 MI.230 M I.CANADA C A N A D A PENNSYLVANIA P E N N S Y L V A N I A NEW JERSEY N E W J E R S E Y CONNECTICUT C O N N E C T I C U T MASSACHUSETTS M A S S A C H U S E T T S VERMONT V E R M O N T NEW YORK CITY N E W Y O R K C I T Y LAKE ONTARIO L A K E O N T A R I O F I G U R E 3.3-1 N E W Y O R K S T A T E M A PNEW YORK N E W Y O R K NINE MILE POINT SITE:
Nine Mile Point Nuclear Station Unit - 1
 
Nine Mile Point Nuclear Station Unit - 2
 
James A. FitzPatrick Nuclear Power Plant N I N E M I L E P O I N T S I T E: N i n e M i l e P o i n t N u c l e a r S t a t i o n U n i t - 1 N i n e M i l e P o i n t N u c l e a r S t a t i o n U n i t - 2 J a m e s A. F i t z P a t r i c k N u c l e a r P o w e r P l a n t 3-19 3-1 9 FIGURE 3.3-2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS KEY: o TLD LOCATION 6. ENVIRONMENTAL STATION Oswego County New York SCALE IN MILES o 2 3 4 5 Lake Ontario 123. 3-20 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 yard Training CenterMinerRoadLakeviewR oadRte.1ABibleCamp ParkhurstRoad Co.Rte.29SunsetBayRoad SunsetParkRoad 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 FIGURE 3.3-4 MILK AND SURFACE WATER SAMPLE LOCATIONS KEY: o SURFACE WATER LOCATION 6.. MILK SAMPLE LOCATION Oswego County New York SCALE IN MILES o 2 3 4 5 Iwswl Isswl 3-22 Lake Ontario 168.75° 75 . 101.25° 123.75° 146.25° FIGURE 3.3-5 NEAREST RESIDENCE, FOOD PRODUCT FISH, AND SHORELINE SEDIMENT SAMPLE LOCATIONS KEY: o FISH !:::. FOOD PRODUCT D SHORELINE NEAREST RESIDENCE SEDIMENT 0 (Based on NMP-Unit 2 Centerline)
Oswego County New York SCALE IN MILES o 2 3 4 5 10 MI. 258.75° Iwswl 236.25° Isswl 3-23 Lake Ontario
..... rRd. 168.75° 123.75° 146.25° ISSEI N LAKE ONTARIO L A K E O N T A R I O OSWEGO COUNTY O S W E G O C O U N T Y N E W Y O R K 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 1 A 29 2 9 29 2 9 1 104 1 0 4 Lake V iew Rd.Lake View Rd.Bay Shore Dr.
Bay Shore Dr.Shore Oaks Dr.Shore Oaks Dr.
Parkhurst Rd.
P arkh urst R d.Nine Mile Point  Rd.
Nine Mile Poin t  Rd.Dennis Rd.
Dennis Rd.
Miner Rd.M i n e r R d.Lycoming L y c o m i n g North N o r t h Scriba S c r i b a Lake Rd.L a k e R d.Sunset Bay Rd.
S u n s e t B a y R d.JAF Site J A F S i t e NMP Site N M P S i t e W E Woolson Rd.
W o o l s o n R d.Keefe Rd.K eefe Rd.Middle Rd.
M i d d l e R d.Cliff Rd.C l i f f R d.Bible Camp B i b l e C a m p C re amery Rd.Cre amery Rd.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 E S E SE S E SSE S S E S SSW S S W SW S W WSW W S W 3-24 3-2 4
---L A KF j O N T.t UUO t , * " * ! , m PZ-!.7 o ___ 1-l I W-2 (A) MVIl-2 (8) CST-iB) C ST -(A) I-...e-+-r T MW-1 (A)
MW-1 (tI) 0 (E H l/! -1 (A) 1 J.( F I G U R E 3 , 3-7 n nnunn J A O N I TE GROU , N O WA T ER MO N I T OR I NG WELLS -Ws il L=U on ? 1 08 YARDS 1 58 SCA L a oo o 3-273.4LAND 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 tolocate 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 also contacted 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 this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, 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 resultsare used only to identify appropriate sample locations. The garden census is not required by theODCM if broadleaf vegetation sampling and analysis are performed.3.5CHANGES TO THE REMP PROGRAMBased upon the results of the 2013 Land Use Census, there were no changes to the 2013 samplingprogram.3.6DEVIATION AND EXCEPTIONS TO THE PROGRAMThe noted exceptions to the 2013 sample program address only those samples or monitoringrequirements which are required by the ODCM, Part I, Table 5.1-1. This section satisfies thereporting requirements of ODCM, Part I, Section 5.1.1.c.1.
3-283.6.1ODCM Program DeviationsThe following are deviations from the program specified by the ODCM:1.1/14/13 Air Stations  R1 and R2 lost power for 6.2 hours. Air Stations  R3and R4 lost power for 2.1 hours.2.1/29/13 Sample Station R-5 lost power for approximately 7.5 hours.3.8/6/13 R-1 offsite environmental air sample station was found not runningby the Constellation technician during the weekly sample change out. Thevacuum pump was found to have failed and was replaced. The station wasreturned to service. From the flow rate data, the sample ran for about 2minutes before failing.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 44,336 hours out ofa possible 44,520 hours. The air sampling availability factor for the report period was 99.6%.
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 standard deviation, 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.
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 population 3-303.7.2ESTIMATION 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 a radionuclide 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 propagatederror 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 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.
3-313.7.3LOWER 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 theLLD 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 mass 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 Y  = 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.
3-323.8COMPLIANCE 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.3.8.1The R-1 station air sample for the period of 7/30/13 through 8/6/13 was found to have runfor approximately two minutes. The collected sample was analyzed for radioactivity. No plant related isotopes were found, but the required Lower Limit of Detection could not be met.3.8.2All remaining sample analyses performed in 2013 as required by the ODCM, achieved theLower Limit of Detection (LLD) as specified by ODCM, Part 1, Table 5.1-3. See report Table 3.8-1 for required LLD values.
3-33 TABLE 3.8-1REQUIRED DETECTION CAPABILITIES FORENVIRONMENTAL SAMPLE ANALYSISLOWER LIMIT OF DETECTION (LLD)Analysis Water(pCi/l)AirborneParticulateor 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 3,000pCi/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 from radiation 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 anyindividual 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 tounrestricted 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 particulateradionuclide's 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 uranium fuel cycle operations 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 - 1  4.0 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 2013*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGE NUMBER OFNON-ROUTINEREPORTSShoreline Sediment(pCi/kg-dry)Gamma-Spectrum AnalysisGSA (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
<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 2013*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGE NUMBER OFNON-ROUTINEREPORTSSurface Water(pCi/liter)H-3 (8):H-3GSA (24):Mn-54Fe-59Co-58Co-60Zn-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 2013*MEDIUM (UNITS)TYPE AND NUMBEROF ANALYSES*LLD(a)INDICATORLOCATIONS: MEAN(f) / RANGELOCATION (b) OF HIGHESTANNUAL MEAN: LOCATION &MEAN (f) / RANGECONTROL LOCATION:MEAN (f) / RANGE NUMBER OFNON-ROUTINEREPORTSTLD (mrem perstandard month)Gamma Dose (128)(d)    4.7  (116/116)  (i)      3.2 - 10.4TLD #85  (g):                9.9 (4/4)    0.2 miles at 292 o          9.3 - 10.43.9 (12/12)  (i)          3.2 - 4.9 0Air Particulates (pCi/m 3)Gross Beta (264):I-131 (264):GSA (20): Cs-134 Cs-137 0.01 0.07 0.05 0.060.016  (211/211)0.006 - 0.032<LLD<LLD
<LLDR-2                            0.016    (53/53)1.1 miles at 107 o0.007  -  0.032<LLD<LLD<LLD0.016  (53/53)0.006 - 0.031<LLD<LLD<LLD 1 0 0 0Milk(pCi/liter)GSA (36): (e) (h)
Cs-134 Cs-137Ba/La-140I-131 (36):
I-131 15 18 15 1<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD
<LLD<LLD 0 0 0 0Food Products(pCi/kg-wet)GSA (16): (h)
I-131 Cs-134 Cs-137 60 60 80<LLD<LLD
<LLD<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 was one optional location for 2012.(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 and 97. Control TLDs are TLDs located beyond the influence of the site (TLD #: 8, 14 and 49).
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 2013 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). Interms 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.DiscussionIn the United States, a person's average annual radiation dose is 620 mrem. About half thatamount comes from naturally occurring radionuclides. Radon and thoron gases account for two-thirds of this exposure, while cosmic, terrestrial, and internal radiation account for the remainder.The other half comes from manmade sources and is mostly from diagnostic medical procedures.The pie chart below shows a breakdown of radiation sources that contribute to the average annualU.S. radiation dose of 620 mrem. Nearly three-fourths of this dose is split between radon/thorongas (naturally occurring) and diagnostic medical procedures (manmade).Sources of Radiation Exposure in the United StatesSource: NCRP Report No. 160 (2009)Industrial &Occupational<0.1%Terrestrial (soil) 3%ConsumerProducts 2%Cosmic (space) 5%Internal 5%Nuclear Medicine12%Medical Procedures 36%Radon and Thoron37%        Natural Sources - 50%        ~310 millirem (0.31 rem)        Manmade Sources - 50%
        ~310 millirem (0.31 rem) 5 - 3There are three separate groups of radionuclides that were measured in the environment andanalyzed for the 2013 sampling program.1.The first of these groups consists of the radionuclides that are naturally occurring. Theenvironment contains a significant inventory of naturally occurring radioactive elements.
The components of natural or background radiation include the decay of radioactive elements in the earth's crust, a steady stream of high-energy particles from space called cosmic radiation and naturally-occurring radioactive isotopes in the human body like potassium-40.A number of naturally occurring radionuclides are present in the environment. These areexpected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radionuclides normally present include: Tritium, present as a result of the interaction of cosmic radiation with the upperatmosphere Beryllium-7, present as a result of the interaction of cosmic radiation with the upperatmospherePotassium-40 and Radium-226, naturally occurring radionuclides found in thehuman body and throughout the environmentBeryllium-7 and potassium-40 are especially common in REMP samples. Since they arenaturally occurring and are abundant, positive results for these radionuclides are reported in some cases in Section 6.0 of this report. Comparisons of program samples to naturally occurring radiation are made throughout this section to help put program results into perspective and to aid the reader in determining what, if any, significant impact is demonstrated by the REMP results.2.The second group consists of radionuclides that may be detected in the environment as aresult of the detonation of thermonuclear devices in the earth's atmosphere. Atmospheric nuclear testing during the early 1950's produced a measurable inventory of radionuclides presently found in the lower atmosphere, as well as in ecological systems. In 1963, an Atmospheric Test Ban Treaty was signed. Since the treaty, the global inventory of manmade radioactivity in the environment has been greatly reduced through the decay of short lived radionuclides and the removal of radionuclides from the food chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecological cycling. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China and underground weapons testing by India, Pakistan & North Korea. In some cases, the usual radionuclides associated with nuclear detonations were detected for several months following the test, and then after a peak detection period, diminished to a point where most could not be detected. Although reduced in frequency, atmospheric testing continued into the 1980's. The resulting fallout or deposition from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample media analyzed over the years.
Fallout radionuclides from nuclear weapons testing included Cesium-137 and Strontium-
: 90. The highest weapons testing concentrations were noted in samples collected for the1981 REMP. Cs-137 was the major byproduct of this testing and is still occasionallydetected in a few select number of environmental media.
5 - 43.The third group consists of radionuclides that may be detected in the environment arerelated to nuclear power technology. These radionuclides are the byproduct of theoperation of light water reactors. These byproduct radionuclides are the same as thoseproduced in atmospheric weapons testing, found in the Chernobyl and Fukushima Daiichi Nuclear Power Station fallout. This commonality makes a determination of the source ofthese radionuclides that may be detected in environmental samples difficult to determine.During 2013, there were no plant-related radionuclides detected in the REMP sampling.A number of factors must be considered in performing radiological sample data evaluationand interpretation. The evaluation is made using several approaches including trendanalysis and dose to man. An attempt has been made not only to report the data collectedduring 2013, but also to assess the significance of the radionuclides detected in the environment as compared to naturally occurring and manmade radiation sources. It isimportant to note that detected concentrations of radionuclides in the local environment asa result of man's technology are very small and are of no or little significance from anenvironmental or dose to man perspective.The 2009 per capita average dose was determined to be 620 mrem per year from all sources, asnoted in National Council on Radiation Protection and Measurement (NCRP) Report No. 160.This average dose includes such exposure sources as industrial & occupational, consumer products, terrestrial, cosmic, internal, nuclear medicine, medical procedures, radon and thoron.The 2009 per capita dose rate due to naturally occurring sources was 310 mrem per year. The percapita radiation dose from nuclear power production nationwide is less than one mrem per year.The naturally occurring gamma radiation in the environs of the Nine Mile Point site, resultingfrom radionuclides in the atmosphere and in the ground, accounts for approximately 48 mrem peryear. This dose is a result of radionuclides of cosmic origin (for example, Be-7) and of primordialorigin (Ra-226, K-40, and Th-232). A dose of 48 mrem per year, as a background dose, is significantly greater than any possible doses as a result of routine operations at the site during 2013.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 relevantfindings with a dose to man estimate where appropriate, and an analysis of possible long-term andshort-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 ODCM* Provide more comprehensive monitoring than is currently required* Monitor the secondary dose to man pathways* Maintain the analytical data base established when the plants began commercial operation 5 - 5The 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 that are 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 2013 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 - 65.1AQUATIC 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 2013sampling period.5.1.1SHORELINE SEDIMENT RESULTSA.Results SummaryShoreline sediment samples were obtained in April and September of 2013 at oneoffsite control location (Lang's Beach located near Oswego Harbor) and at one indicator location (Sunset Bay) which is an area east of the site considered to haverecreational value.A total of four sediment samples were collected for the 2013sample program, twoindicator and two control. These results continue to show a downward trend over the last 20 years. Cs-137 was not detected in samples collected from the Sunset Bayindicator location and the  Lang's Beach control location during 2013. No plant-related radionuclides were detected in the 2013shoreline sediment samples.The following is a graph of the average Cs-137 concentration in shoreline sedimentsamples over 20 years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1994.
5 - 7B.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 (Lang's Beach). Samples were collected from both theindicator and control locations in April and September 2013. The results of thesesample collections are presented in Section 6.0, Table 6-1, "Concentrations ofGamma Emitters in Shoreline Sediment Samples - 2013". Potassium-40 (K-40) and Ra-226, both naturally occurring isotopes, were the only radionuclides detected inthe 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 critical pathway 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 hours per year at the beach area or on the shoreline,The sediment has a mass of 40 kg/m 2(dry) to a depth of 2.5 cm,The shoreline width factor is 0.3, andThe maximum 2013 LLD concentration of <0.086 pCi/g (dry).Using these conservative parameters, the potential dose to the maximum exposedindividual (teenager) would be 0.00029 mrem/year to the whole body and 0.00034mrem/year to the skin. This calculated dose is very small and is insignificant whencompared to the natural background annual exposure of approximately 48 mrem asmeasured by control TLDs in the vicinity of the site.
5 - 8D.Data TrendsCs-137 was not detected at the indicator and control sample locations from 2008through 2013.The previous five years of data show that Cs-137 was not detected at the indicatorlocation. Cesium-137 was not detected in the control location samples over this same five year period.The general absence of Cs-137 in the indicator and control samples can be attributedto changing lake levels and shoreline erosion. Recent soil samples, from locationsbeyond any expected influence from the site, have contained levels of Cs-137 equalto or greater than the concentrations found in shoreline samples collected in the past.Cs-137 is commonly found in soil samples and is attributed to weapons testingfallout.The previous ten year data trend for indicator shoreline samples showed an overalldownward trend in concentration measured at the indicator sample locations. Over the previous ten year period of 2004 through 2013, mean concentrations at theindicator location ranged from a maximum of 0.08 pCi/g (dry) in 2005 to a minimumof 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cs-137 was not detected atthe indicator location for 2008 through 2013. This continues to support the long termdecreasing trend in Cs-137 concentration in shoreline sediment samples. Cs-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 - 95.1.2FISH SAMPLE RESULTSA.Results SummaryA total of 18 fish samples were collected for the 2013 sample program. Speciescollected were: Brown Trout, Lake Trout, Chinook Salmon, Smallmouth Bass andWalleye. The analytical results for the 2013 fish samples showed no detectableconcentration of radionuclide that would be attributable to plant operations at the siteor 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 acombination of both the indicator and/or control locations. (Refer to Tables 7-3 and7-4). These low levels of Cs-137 represented no significant dose to man or impact on the environment.The 2013 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 2013 results are consistent with previous year's results in that they continue to support the general long-term downward trend in fish Cs-137concentrations over the last 25 years. Cs-137 was not detected in fish samplescollected from 2003 to 2013 at indicator locations. The period of 2000 through 2013 as 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 lakedischarges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samples served 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 2013 in units of pCi/g (wet).The spring fish collection was made up of 9 individual samples representing threeseparate species
.Brown Trout, Lake Trout, and Walleye were collected.The total fall fish collection was comprised of 9 individual samples representingthree individual species. Walleye, Chinook Salmon, and Smallmouth Bass werecollected.Cs-137 was not detected in any of the fish species collected for the 2013 sampleprogram.
5 - 10C.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 of detectable concentrations of plant-related radionuclides in the 2013 fish samplesdemonstrates that there is no attributable dose to man from operations at the sitethrough 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 (2009 through 2013)show that the number of positive detections has decreased over this period relative tohistorical 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 2013 andthe previous fourteen years.The data trend shows a consistent level of Cs-137 measured in fish between 1997 and1998. After 1998, the number of positive detections drops off as noted in the fiveyear trend. The 1995 through 2013 results, as a group, are the lowest Cs-137concentrations 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 toion exchange with soils and sediments and radiological decay. The concentrations ofCs-137 detected in fish since 1976 are considered to be the result of weapons testing fallout. The general downward trend in concentrations will continue as a function ofadditional ecological cycling and radiological decay.
5 - 11Section 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 waterlocations are sampled and analyzed. These additional locations are the Oswego CityWater Intake, the NMP1 Intake and the NMP2 Intake. Gamma spectral analysis wasperformed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples collected from the additional sample locations. The resultsof the gamma spectral analyses showed that only naturally-occurring radionuclideswere detected in the 60 samples from the five locations collected for the 2013 Sampling Program. The two naturally-occurring radionuclide detected were K-40 and Ra-226and were not related to plant operations. Monthly composite samples showed nopresence of plant-related gamma emitting isotopes in the waters of Lake Ontario as aresult 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 2013REMP program. The results for the 2013 samples showed no positive detection of tritium.
5 - 12B.Data Evaluation and DiscussionGamma spectral analysis was performed on monthly composite samples from five LakeOntario sampling locations. No plant-related radionuclides were detected in 2013samples. This is consistent with historical data, which has not shown the presence of plant-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 2013 sample programwere 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 2013 results had LLD values that ranged from <366 pCi/l to <389 pCi/l. The ODCM Control location (Oswego Steam Station inlet canal) results showed no positivedetections and the sample results had LLD values in the range of <366 pCi/l to <389pCi/l.Tritium was not detected in any of the twelve optional Lake Ontario samples collectedin the 2013 program.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 current patterns in the lake.The following is a summary of LLD results for the 2013 sample program:SampleLocationTritium Concentration pCi/literMinimumMaximumMean (Annual)JAFInlet (Indicator)*
<366<389<377Oswego Steam Inlet (Control)*<366<389<377NMP #1 Inlet<366<389<377NMP #2 Inlet<366<389<377Oswego City Water Suppl y<366<389<377*  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.C.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 and maximum organ using the maximum LLD value and Regulatory Guide 1.109 methodology. Based on a water ingestion rate of 510 liters/yr and a maximum LLDconcentration of 389 pCi/l, the calculated dose would be less than 0.041 mrem to thechild whole body and less than 0.040 mrem to the child liver (critical age group/organ).
5 - 13D.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 2013lake water samples were consistent with results from theprevious five years for both the indicator and control locations. The mean 2013 tritiumconcentrations were <377 pCi/l for the control and <377 pCi/l for the indicator location.For the previous five years, there were no positive detections for the indicator and control locations. This previous five year data set is consistent with long term tritiumresults measured at the site. The indicator data from the previous ten year period, 2003through 2012, are representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured. The 1999 mean controlvalue of 365pCi/l is the highest concentration measured since 1987 and is within thevariability of results measured over the life of the program. The ten year historicalresults are consistent between the control and indicator locations with no large variationin 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, the Oswego City Water Supply results were used as control location data as this locationclosely approximates the Oswego Steam Station, the current control location. There isno existing preoperational data for comparison to recent data.Historical data for Surface Water Tritium is presented in Section 7.0, Tables 7-7 and 7-
: 8.
5 - 145.2TERRESTRIAL PROGRAMThe terrestrial program consists of samples collected from four environmentalpathways. These pathways are:Airborne particulate and radioiodine,Direct Radiation,Milk, andFood ProductsSection 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrialsamples collected for the 2013 reporting period.5.2.1AIR PARTICULATE GROSS BETAA.Results SummaryWeekly air samples were collected  and analyzed for particulate gross beta activity. Forthe 2013program, a total of 53 samples were collected from control location R-5 and211 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 maintainedand are discussed in Section 5.2.1.B below. The mean gross beta concentration forsamples collected from the control location (R-5) in 2013 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 2013 was 0.016 pCi/m
: 3. The consistency between the indicatorand control mean values, demonstrates that there are no increased airborne radioactivitylevels in the general vicinity of the site from plant effluents.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 of795 samples were collected and analyzed as part of the 2013 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 air sample locations are maintained from which weekly samples are collected. Theoptional offsite locations are designated as D-2, E, F and G. The optional onsitelocations are designated as D-1, G, H, I, J and K.
5 - 15Gross beta analysis requires that the samples be counted no sooner than 24 hours aftercollection. This allows for the decay of short half-life naturally-occurringradionuclides, thereby increasing the sensitivity of the analysis for plant-relatedradionuclides.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/m
: 3. The offsite ODCM control station (R-5)annual mean gross beta concentration was 0.016 pCi/m
: 3. The minimum, maximum andaverage gross beta results for sample locations required by the ODCM were as follows:LocationConcentration pCi/m 3MinimumMaximumMeanR-10.0060.0280.016R-20.0070.0320.016R-30.0080.0300.016 R-40.0070.0290.016 R-5 (control)0.0060.0310.016 5 - 16The mean weekly gross beta concentrations measured in 2013 are illustrated in thefollowing graphs:The fluctuations observed in the gross beta activity over the year can be attributed tochanges in the environment, especially seasonal changes. The concentrations of naturally-occurring radionuclides in the lower levels of the atmosphere directly abovethe land are affected by time-related processes such as wind direction, precipitation,snow cover, soil temperature and soil moisture content.C.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 the associated dose factor. See Section 5.2.2.C for dose calculations from airconcentrations. The dose received by man from air gross beta concentration is acomponent of the natural background.
5 - 17D.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 whichwas carried out in 1980.The mean gross beta concentration measured in 1969 to 2013 are illustrated in thefollowing graph:The 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 of2004 through 2013 is very small. This is illustrated by the following graph.
5 - 18The mean annual gross beta concentration at the control station (R-5) has remainedsteady with a narrow range of 0.014 pCi/m 3to 0.019 pCi/m
: 3. The mean annualconcentrations for the indicator stations for this same time period were similar to thecontrol and ranged from a minimum of 0.015 pCi/m 3 to a maximum mean of 0.019pCi/m 3 in 2005.Historical data of air particulate gross beta activity are presented in Section 7.0, Tables7-9 and 7-10.5.2.2QUARTERLY 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 nearthe site boundary and offsite as a control location. Ten additional air sampling stations are also maintained as part of the sampling program. Together, these fifteen continuousair sampling stations make up a comprehensive environmental monitoring network formeasuring radioactive air particulate concentrations in the environs of the site.
Annually, the air monitoring stations provide 795 individual air particulate sampleswhich 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 2013.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 naturallyoccurring.
5 - 19B.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 the fifteen monitoring stations are required by the ODCM and the remaining ten areoptional to provide an effective monitoring network. Composite air filter samples areassembled 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 notrequired by the ODCM, for which analytical results have been provided, include sixonsite locations and four offsite locations. The analytical results for the 60 air particulate filter composites in 2013 showed no detectable activity of plant relatedradionuclides.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 2013. The monthly air particulate samplingprogram demonstrated no offsite dose to man from this pathway as a result ofoperations of the plants located at the Nine Mile Point Site (NMP).D.Data TrendsNo plant related radionuclides were detected during 2013 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 the atmosphere 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 of1980 when Co-60 was not detected at the control location. The presence of Co-60 inthe 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 only positive detection of Co-60 since 1984. The detection of Co-60 in the one 2000 samplewas an isolated event associated with effluents from the NMP1 facility. There havebeen no subsequent measurable concentrations of Co-60 in the environment surrounding the NMP site.
5 - 20Historical 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 year's 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 was not detected in any of the 795 samples analyzed for the 2013program.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 those required 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 usingactivated 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 in plant effluents is not evaluated due to the factthat no I-131 was detected in 2013. The I-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located atNine Mile Point.
5 - 21D.Data TrendsThere was no I-131 detected in any of the samples, collected from the 15 samplestations, for 2012 or 2013.In 2011, I-131 was detected at all 15 sampling locations over a three week period. Thepositive detections were the result of the Fukushima event. Prior to then, there had been no positive detection of I-131 in air samples collected from 2002 to 2010.I-131 has previously been detected in samples collected in 1986 and 1987. The 1986detection of I-131 was the result of the Chernobyl accident and the 1987 detection wasthe 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.Historical data for I-131 are presented in Section 7.0, Tables 7-13 and 7-14.
5 - 225.2.4DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)A.Results SummaryThermoluminescent dosimeters (TLDs) are used to measure direct radiation (gammadose) in the environment. As part of the 2013 environmental monitoring program,TLDs were placed at a total of 72different environmental TLD locations (32 requiredby the ODCM and 40 optional locations). These TLDs were placed, collected and readeach quarter of 2013. 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.The 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)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 thedesignation of specific TLD locations that make up each category is presented in Section 3.1.5, TLD (Direct Radiation) of this report.A summary of the 2013 dose rates for each of the five geographical locations is asfollows:Geographic CategoryDose in mrem per standard monthMinMaxMeanOnsite (Optional)3.312.24.9Site Boundary (Inner Ring) *3.54.73.9Offsite Sectors (Outer Ring) *3.24.53.8Special Interest *3.24.53.8Control *3.24.94.0* Geographical locations required by the ODCM 5 - 23Comparison of annual mean dose rates associated with each geographical locationindicate that there is no statistical difference in annual dose as a function of distancefrom the site boundary. The measured annual dose rate at the nearest resident to the site was 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) werewell within expected normal variation when compared to the Control TLD results.The results for the 2013 environmental TLD monitoring program indicate that therewas no significant increase in dose rates as a result of operations at the site. TheHydrogen Water Chemistry system and the Independent Spent Fuel Storage Installation(ISFSI) in use at the Fitzpatrick plant and NMPNS did not measurably increase the ambient radiation exposure rate beyond the site boundary.B.Data Evaluation and DiscussionDirect Radiation (Gamma Dose) measurements were taken at 72 differentenvironmental locations during 2013,  32 of which are required by the ODCM. Theselocations are grouped into five geographical location categories for evaluation ofresults. The five categories include: Onsite, Site Boundary, Offsite Sector, Special Interest and Control locations. All categories are required by the ODCM with theexception of the Onsite TLDs. Onsite TLDs are placed at various locations within thesite boundary to provide additional information on direct radiation levels at and aroundthe NMP1, NMP2 and JAFNPP facilities.Onsite TLD results ranged from 3.3 to 12.2 mrem per standard month resulting in anaverage dose rate of 4.9 mrem per standard month in 2013
.Site Boundary TLD results ranged from 3.5 to 4.7 mrem per standard month resultingin an average dose of 3.9 mrem per standard month in 2013. This range included allTLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location required by the ODCM was10.4 mrem per standard month. This TLD, (TLD 85) represents the site boundarymaximum dose and is located in the WNW sector along the lakeshore in closeproximity to the Nine Mile Point 1 plant. The TLD locations along the lakeshore closeto the plants (TLD #s 23, 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities. These locations are not accessible tomembers of the public and the TLD results for these areas are not representative of doserates measured at the remaining site boundary locations.
5 - 24Offsite Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in eachof the 8 land based meteorological sectors ranged from 3.2 to 4.5 mrem per standardmonth with an average dose rate of 3.8 mrem per standard month.Special Interest TLDs from all locations ranged from 3.2 to 4.5 mrem per standardmonth with a 2013 annual average dose rate of 3.8 mrem per standard month.The Control TLD group required by the ODCM utilizes locations positioned wellbeyond the site. 2013 Control TLD results ranged from 3.2 to 4.9 mrem per standardmonth with an annual average dose rate of 4.0 mrem per standard month.TLD analysis results are presented in Section 6.0, Table 6-10.C.Dose Evaluation2013annual 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: 3.8 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)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 of4.0 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 the levels 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 ineach of the 16 meteorological sectors, TLDs located offsite in each land based sector ata distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs located at control locations. Site Boundary, Offsite Sector and Special Interest TLDlocations became effective in 1985; therefore, trends for these results can only beevaluated from 1985 to the present.
5 - 25The following graph illustrates TLD results for the Control, Site Boundary, OffsiteSectors and Special Interest groups from 1999 through 2013:TLDs located at the site boundary averaged 3.9 mrem per standard month during 2013(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 4.0 mrem per standard month.Offsite Sector TLDs averaged 3.8 mrem per standard month during 2013. This result isalso consistent with the previous five year average of 3.9 mrem per standard month foroffsite sectors.Special Interest TLD locations averaged 3.8 mrem per standard month during 2013which is consistent with the previous five year average of 3.9 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. 2013 control results fromall Control TLDs averaged 4.0 mrem per standard month, consistent with the previousfive year average of 4.1 mrem per standard month. The 2013 TLD program results, when compared to the previous ten years, showed no significant trends relative toincreased dose rates in the environment.Historical data for the various TLD groupings are presented in Section 7.0, Tables 7-15through 7-20.
5 - 265.2.5MILKA.Results SummaryA total of 36 milk samples were collected during the 2013program and analyzed forgamma emitting radionuclides using gamma spectroscopy. In addition, each sampleundergoes 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 36 milk samples collected in2013 from the two 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 2013.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 2013 results demonstrate that routine operations of the Nine Mile Point Siteresulted in no measurable contribution to the dose to the public from the cow/milk pathway.B.Sampling OverviewMilk samples were collected from one indicator location and one control location. TheODCM requires that three sample locations be within five miles of the site. Based onthe milk animal census, there were no adequate milk sample locations within five miles of the site in 2013. Samples were collected from two farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway. Theindicator location was located 8.8 miles from the site. The control samples were collected from a farm located 16.0 miles from the site and in a low frequency windsector (upwind). The geographic location of each sample location is listed below:Location No.Direction From SiteDistance (Miles)55E8.877 (Control)SSW16.0Indicator location #55 and Control location #77 were sampled from April throughDecember. Sampling occurs during the first and second half of each month. Samples were not required to be collected during January through March of 2013 as a result ofI-131 not having been detected in samples collected during November and December of2012, as stipulated in the ODCM.
5 - 27C.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 each sample. I-131 and gamma analysis results for milk samples collected during 2013areprovided in Section 6.0, Table 6-11.Iodine-131 was not detected in any indicator or control milk samples analyzed during2013. All I-131 milk results were reported as Lower Limits of Detection (LLD). No plant-related radionuclides were detected in any milk sample collected in 2013. K-40was 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 of the environmental media samples. Cs-137 was not detected in any indicator or controlmilk sample collected in 2013.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 beenmeasured in environmental samples. A 70 kilogram (154 pound) adult contains approximately 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 TrendsMan-made radionuclides are not routinely detected in milk samples. In the past thirtyyears, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicator activities 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 previous detection was in 1986 with a mean concentration of 13.6 pCi/liter. The 1986 activitywas a result of the Chernobyl accident.The comparison of 2013 data to historical results over the operating life of the plantsshows that Cs-137 and I-131 levels in milk 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 - 285.2.6FOOD PRODUCTS (VEGETATION)A.Results SummaryThere were no plant-related radionuclides detected in the 13 food product samplescollected and analyzed for the 2013 program.Detectable levels of naturally occurring K-40 were measured in the control and most ofthe indicator samples collected for the 2013 program. Be-7 a naturally-occurringradionuclide, was also detected intermittently in samples collected in 2013. Theseresults are consistent with the levels measured in 2012and previous years.The results of the 2013 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 four indicator locations and one controllocation. The indicator locations are represented by nearby gardens in areas of highestD/Q (deposition factor) values based on historical meteorology and an annual garden census. The control location was a garden 15 miles away in a predominately upwind direction.Food product samples collected during 2013included the edible vegetables, cabbageand tomatoes. Non-edible vegetation consisting of corn leaves, grape leaves,horseradish leaves, rhubarb leaves, and squash leaves were also collected for the 2013program. The leaves of these plants were sampled as representative of broadleaf vegetation which is a measurement of radionuclide deposition. Samples were collectedduring the late summer/fall harvest season. Each sample was analyzed for gammaemitters using gamma spectroscopy
.The analysis of food product samples collected during 2013 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.Naturally-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.
5 - 29C.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 program demonstrated 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 foodproducts 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 0.004pCi/g (wet) in 1980. The trend for Cs-137 is a general reduction in concentration tonon detectable levels in samples collected during the 2000 through 2013 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 planteffluents. In 2013 a milk animal census, a nearest resident census and a garden surveywere performed.The results of the closest residence census conducted in 2013 required no change to Fitzpatrick ODCM's closest resident location.A garden census, not required by the ODCM, is performed to identify appropriategarden sampling locations and dose calculation receptors. Garden samples werecollected from a number of locations identified in the census as active for 2013. SeeTable 3.3-1 for 2013 sampling locations.
5 - 30B.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 ofsurveys. A milk animal census is conducted to identify all milk animals within adistance of 10 miles from the site. The census, covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the ODCM. A resident census isconducted and is designed to identify the nearest resident in each meteorological sectorout 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 isconducted during the first half of the grazing season by sending questionnaires toprevious milk animal owners and also by road surveys to locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted bytelephone or in person. The local county agricultural extension service is also contactedas 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 238 cows and no goats based on the 2013 land use census. Thenumber of cows has decreased by 40 when compared to the 2012 census. The results of the 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 anddirection and distance of each of the nearest residence, are found in Section 6.0, Table6-14. There were no changes identified in the 2013 census for the closest resident inthe land based meteorological sectors. The nearest resident locations are illustrated inSection 3.3, Figure 3.3-5.
5 - 315.2.8DIRECT 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 in place around the perimeter of the ISFSI pad. TLDs were placed at these locations priorto 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 in this series was placed in the storage facility on November 12, 2005 bringing the totalnumber of casks in storage to nine. During the Fall of 2010, 6 casks were placed on thestorage pad bringing the total number of casks in storage to fifteen. The tenth cask was moved to the storage facility on July 14, 2010 and the fifteenth cask was moved to thestorage facility on October 5, 2010. During 2013 six aditional casks were placed instorage, bringing the total to twenty one casks in the storage facility.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 radiationmeasurements, presented in Section 5.2.4 of this report, concludes that there is no significant 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 thedose rates measured at the site boundary and the offsite control locations. The results for the Site Boundary, Offsite Sectors, and Special Interest (offsite) were well withinexpected normal variation when compared to the Control TLD results. The results forthe 2013 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) at the 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 siteboundary is consistent with design calculations performed to evaluate compliance with 10 CFR72.104(a).The measured results of the 2013 TLD monitoring program demonstrate compliancewith the offsite dose limits to members of the public specified in 40CFR190 and10CFR72.104(a).
5 - 32B.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 facilityperimeter. 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 36.2 mrem per standard month above the baseline dose ratewas measured at the north perimeter fence. The lowest measured dose rate of 2013 was7.8 mrem per standard month above the baseline dose rate and was measured at the eastperimeter fence.An evaluation of Site Boundary TLDs and Control TLDs results for 2013 shows thatthere is no increase in dose rate at or beyond the site boundary. A detailed discussion of this evaluation is found in Section 5.2.4. The Environmental TLD results for thisperiod show no significant difference in control and site boundary dose rates comparedto 2012.2013 DOSE IN MREM PER STANDARD MONTHMinimumMaximumMeanSite Boundary3.54.73.9Control3.24.94.0 5 - 3
 
==35.3CONCLUSION==
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 radiological environment 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 a comprehensive sampling program. Results of all samples are reviewed closely to determine any possible impact to the environment or to man. In addition, program results are evaluated forpossible short-term 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 is set 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 the REMP, 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, is determined to be a fraction of limits set forth by the NRC and EPA.The REMP continues to demonstrate that the effluents from the site to the environment contributeno significant or even measurable radiation exposures to the general public as confirmed by the sampling and analysis of environmental media from recognized environmental 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 and ISFSI programs. Environmental radiation levelsmeasured at the nearest residence are at the background level based on 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 1980's, the 1986 accident at the Chernobyl Nuclear Power Plant, and the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Station.The REMP did not detect any plant-related radionuclide in the sample media collected during2013. Dose from man-made sources in the environment is very small when compared to the dose originating from naturally-occurring sources of radioactivity.Radiation 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 thepublic, 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 in Oswego County due to natural sources is approximately 48 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 2013 Radiological Environmental Monitoring Program, itcan be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that effluents from the site to the environment contribute no significant or even measurable radiation exposures to the general public.
5 - 3
 
==45.4REFERENCES==
1.U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses toMan 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 Doses toMan from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliancewith 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, Rockville, 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, 1987.15.National Council on Radiation Protection and Measurements (NCRP), Ionizing RadiationExposure of the Population of the United States, NCRP Report No. 160, 2009.16.Institute of Nuclear Power Operations, Special Report on the Nuclear Accident at theFukushima Daiichi Nuclear Power Station, INPO 11-005, November 2011.
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 f04/29/1321060 +/- 696< 52.3< 51.3< 50.0< 80.4< LLD09/25/1320880 +/- 1101< 91.1< 64.2< 83.0< 181.8< LLD04/29/1312330 +/- 511< 27.2< 25.0< 36.7< 53.5< LLD09/25/1310810 +/- 770< 61.6< 70.4< 52.0< 173.4< LLDTABLE 6-1CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2013Results in Units of pCi/kg (dry)  +/-  1 SigmaCs-137Zn-65GAMMA EMITTERS
* Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5    f Plant related radionuclidesCollection DateSample Location ***K-40Lang's Beach(06, Control)Sunset Bay (05) *Co-60Cs-134 6 - 3Others f5/8/2013BROWN TROUT3708 +/- 341 < 40 < 39 < 117 < 39 < 42 < 41 < 93< LLD5/8/2013LAKE TROUT4493 +/- 362 < 43 < 36 < 113 < 40 < 40 < 43 < 100< LLD5/8/2013WALLEYE3968 +/- 350 < 52 < 44 < 85 < 42 < 52 < 47 < 110< LLD8/20/2013CHINNOOKSALMON6012 +/- 434 < 39 < 45 < 148 < 36 < 45 < 47 < 105< LLD8/20/2013WALLEYE5006 +/- 395 < 39 < 37 < 111 < 42 < 46 < 37 < 98< LLD8/20/2013SMALLMOUTH4468 +/- 378 < 44 < 39 < 115 < 46 < 31 < 40 < 118< LLDDateDescriptionCo-58Mn-54TABLE 6-2CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES -
2013Results in Units of pCi/kg (wet)  +/-  1 SigmaFITZPATRICK * (03)***
* Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5    f Plant related radionuclidesK-40Fe-59Co-60Cs-137Cs-134Zn-65GAMMA EMITTERS 6 - 4Others f5/8/2013BROWN TROUT3991 +/- 391 < 37 < 31 < 133 < 38 < 41 < 41 < 125< LLD5/8/2013LAKE TROUT4158 +/- 345 < 43 < 41 < 66 < 39 < 47 < 43 < 98< LLD5/8/2013WALLEYE4221 +/- 369 < 53 < 33 < 104 < 53 < 59 < 45 < 113< LLD8/20/2013CHINOOKSALMON4649 +/- 363 < 37 < 33 < 80 < 42 < 44 < 36 < 101< LLD8/20/2013SMALLMOUTH4222 +/- 338 < 36 < 35 < 129 < 35 < 39 < 40 < 87< LLD8/20/2013WALLEYE4860 +/- 371 < 41 < 42 < 109 < 43 < 42 < 44 < 128< LLDCONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES -
2013K-40Mn-54GAMMA EMITTERSFe-59DateZn-65
* Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5    f Plant related radionuclidesCo-58Results in Units of pCi/kg (wet)  +/-  1 SigmaTABLE 6-2 (Continued)NINE MILE POINT *  (02)***DescriptionCs-137Cs-134Co-60 6 - 5Others f5/8/2013LAKE TROUT4799 +/- 436 < 59 < 49 < 139 < 52 < 53 < 46 < 133< LLD5/9/2013BROWN TROUT4635 +/- 404 < 38 < 34 < 126 < 55 < 39 < 35 < 104< LLD5/9/2013WALLEYE5304 +/- 400 < 48 < 24 < 110 < 35 < 44 < 30 < 112< LLD8/20/2013SMALLMOUTH5745 +/- 416 < 57 < 44 < 123 < 55 < 44 < 38 < 128< LLD8/21/2013CHINOOKSALMON5508 +/- 410 < 36 < 40 < 153 < 35 < 41 < 34 < 99< LLD8/22/2013WALLEYE5330 +/- 380 < 37 < 40 < 112 < 44 < 46 < 41 < 103< LLDCONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2013
* Sample required by the ODCM*** Corresponds to sample location noted on Figure 3.3-5    f Plant related radionuclidesTABLE 6-2 (Continued)K-40DescriptionCs-137Co-60Cs-134GAMMA EMITTERSOSWEGO HARBOR (CONTROL) *  (00)***DateResults in Units of pCi/kg (wet)  +/-  1 SigmaMn-54Zn-65Co-58Fe-59 6 - 6STATION CODEPERIODTRITIUMFirst Quarter01/02/1303/28/13< 389FITZPATRICK*Second Quarter03/28/1306/27/13< 372(03, INLET)***Third Quarter06/27/1309/30/13< 366Fourth Quarter09/30/1312/30/13< 380First Quarter01/04/1303/28/13< 389OSWEGO STEAM STATION*Second Quarter03/28/1306/28/13< 372(08, CONTROL)***Third Quarter06/28/1309/26/13< 366Fourth Quarter09/26/1301/03/14< 379First Quarter01/04/1303/28/13< 389NINE MILE POINT UNIT 1**Second Quarter03/28/1306/28/13< 372(09, INLET)***Third Quarter06/28/1309/26/13< 366Fourth Quarter09/26/1301/03/14< 379First Quarter01/04/1303/28/13< 389NINE MILE POINT UNIT 2**Second Quarter03/28/1306/28/13< 372(11, INLET)***Third Quarter06/28/1309/26/13< 366Fourth Quarter09/26/1301/03/14< 379First Quarter01/04/1303/28/13< 389OSWEGO CITY WATER**Second Quarter03/28/1306/28/13< 372(10)***Third Quarter06/28/1309/26/13< 366Fourth Quarter09/26/1301/03/14< 379
* 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 - 2013(QUARTERLY COMPOSITE SAMPLES)Results in Units of pCi/l  +/-  1 Sigma 6 - 7DateNUCLIDEI-131< 0.99< 0.77< 0.98< 0.87< 0.91< 0.77Cs-134< 1.86< 2.40< 4.86< 3.46< 2.52< 1.82Cs-137< 2.70< 3.64< 4.05< 2.65< 3.53< 2.47Zr-95< 5.15< 7.40< 6.46< 5.28< 8.19< 4.58Nb-95< 3.53< 5.28< 4.88< 3.36< 5.29< 2.88Co-58< 2.80< 4.50< 4.89< 3.28< 4.45< 2.96Mn-54< 2.66< 3.62< 3.34< 2.62< 3.53< 2.58Fe-59< 8.06< 12.7< 10.9< 9.06< 13.0< 8.46Zn-65< 5.85< 8.84< 9.36< 6.41< 9.81< 3.41Co-60< 2.25< 3.96< 4.03< 2.75< 4.52< 2.07K-40197.8 +/- 14.3262.7 +/- 23.4282 +/- 22.7121.6 +/- 14.5283.9 +/- 24.5182.8 +/- 14.96Ba/La-140< 6.65< 12.9< 13.2< 8.16< 13.6< 6.79DateNUCLIDEI-131< 0.81< 0.95< 0.99< 0.65< 0.86< 0.78Cs-134< 1.79< 3.14< 1.38< 2.31< 2.46< 1.71Cs-137< 2.64< 2.90< 1.94< 2.80< 3.21< 2.39Zr-95< 4.45< 5.07< 3.78< 6.80< 6.89< 4.91Nb-95< 3.47< 3.70< 2.77< 4.88< 4.64< 3.28Co-58< 3.19< 3.54< 2.32< 3.32< 3.82< 2.47Mn-54< 2.83< 2.83< 1.76< 3.20< 3.76< 2.34Fe-59< 8.26< 9.00< 7.21< 11.1< 11.5< 7.83Zn-65< 3.63< 6.79< 2.83< 8.40< 9.08< 5.11Co-60< 2.44< 2.33< 1.95< 3.82< 4.88< 2.24K-40193.0 +/- 15.2149.1 +/- 15.4109.8 +/- 9.3< 41.1< 41.636.3 +/- 9.2Ba/La-140< 6.65< 7.91< 6.79< 11.4< 12.5< 7.78
* Sample Location required by ODCM*** Corresponds to sample location noted on Figure 3.3-411/29/20131/3/20142/1/20133/1/20138/2/20138/30/20139/26/201311/1/20133/28/20134/26/20135/31/20136/28/2013CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2013Results in Units of pCi/liter  +/-  1 SigmaOSWEGO STEAM STATION * (08, CONTROL)***TABLE 6-4 6 - 8DateNUCLIDEI-131< 14.8< 11.0< 9.85< 9.69< 13.2< 12.7Cs-134< 1.80< 3.01< 3.01< 1.69< 2.03< 2.16Cs-137< 2.23< 2.66< 2.69< 2.54< 2.61< 2.54Zr-95< 4.81< 5.05< 4.60< 5.18< 5.13< 5.02Nb-95< 3.46< 3.52< 3.02< 3.43< 3.58< 2.96Co-58< 2.90< 3.11< 2.92< 3.08< 2.99< 3.46Mn-54< 2.50< 2.48< 2.56< 2.53< 2.66< 2.65Fe-59< 7.41< 8.93< 8.29< 8.64< 8.62< 8.49Zn-65< 5.63< 6.27< 6.09< 3.91< 7.05< 6.11Co-60< 2.51< 2.28< 2.67< 2.47< 2.44< 2.92K-4037.3 +/- 8.9159.3 +/- 14.5188.8 +/- 15.0164.9 +/- 14.5180.8 +/- 14.695.2 +/- 13.2Ba/La-140< 7.74< 9.04< 7.02< 7.04< 8.14< 9.13DateNUCLIDEI-131< 14.4< 12.8< 12.3< 14.2< 12.1< 12.5Cs-134< 2.15< 1.44< 1.22< 1.86< 1.91< 2.08 Cs-137< 2.54< 1.93< 1.58< 2.69< 2.60< 2.63Zr-95< 5.75< 4.13< 3.49< 5.98< 4.92< 6.23Nb-95< 3.97< 2.64< 2.51< 4.16< 3.47< 4.26Co-58< 3.40< 2.53< 1.79< 3.26< 2.63< 3.79Mn-54< 2.92< 1.94< 1.66< 2.49< 2.36< 3.45Fe-59< 9.30< 5.57< 5.60< 7.24< 7.87< 12.1 Zn-65< 6.54< 4.83< 2.26< 6.26< 3.01< 6.41Co-60< 2.71< 1.89< 1.74< 2.67< 2.17< 3.56K-40161.0 +/- 15.5168.1 +/- 10.9< 14.0124.7 +/- 14.8< 19.2< 34.5Ba/La-140< 7.94< 7.36< 6.92< 8.47< 6.33< 11.6    ** Optional Sample Location
*** Corresponds to sample location noted on Figure 3.3-411/29/20131/3/20142/1/20133/1/20138/2/20138/30/20139/26/201311/1/20133/28/20134/26/20135/31/20136/28/2013CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES -
2013Results in Units of pCi/liter  +/-  1 SigmaOSWEGO CITY WATER** (10)***TABLE 6-4 (continued) 6 - 9DateNUCLIDEI-131< 0.51< 0.57< 0.66< 0.62< 0.55< 0.60Cs-134< 6.07< 2.06< 3.67< 2.72< 2.18< 2.45Cs-137< 4.47< 2.70< 2.44< 3.35< 3.02< 3.27Zr-95< 9.49< 4.69< 4.94< 7.82< 5.62< 5.40Nb-95< 6.93< 3.59< 3.01< 4.60< 3.62< 3.37Co-58< 5.07< 3.36< 3.41< 3.27< 3.26< 3.34Mn-54< 4.21< 3.20< 2.69< 3.79< 2.83< 3.30Fe-59< 15.6< 6.32< 9.09< 14.0< 8.05< 9.14Zn-65< 12.0< 6.98< 5.62< 9.37< 7.14< 7.97Co-60< 4.66< 3.18< 3.01< 4.52< 3.38< 3.10K-40244.5 +/- 28.4< 32.4< 35.2< 43.7< 29.9164.8 +/- 17.3Ba/La-140< 11.4< 6.14< 7.11< 11.6< 6.57< 6.41DateNUCLIDEI-131< 0.60< 0.58< 0.61< 0.58< 0.48< 0.78Cs-134< 2.58< 2.21< 3.98< 1.72< 4.69< 2.51Cs-137< 3.18< 2.66< 3.80< 2.90< 3.56< 3.61Zr-95< 7.21< 5.75< 8.14< 5.21< 6.84< 6.33Nb-95< 4.64< 4.03< 4.66< 3.39< 3.93< 3.76Co-58< 4.18< 3.41< 4.12< 3.19< 3.70< 3.09Mn-54< 3.87< 2.59< 4.05< 2.70< 3.16< 2.83Fe-59< 10.2< 9.09< 13.0< 8.81< 9.49< 7.22Zn-65< 7.74< 4.07< 12.1< 5.78< 7.33< 3.67Co-60< 3.34< 3.08< 4.99< 2.76< 3.50< 2.91K-40148.8 +/- 18.249.6 +/- 12.5< 45.026.5 +/- 10.4153.9 +/- 18.334.0 +/- 10.9Ba/La-140< 8.78< 5.94< 11.4< 7.00< 8.82< 6.42
* Sample Location required by ODCM*** Corresponds to sample location noted on Figure 3.3-46/27/201312/2/201312/30/20131/31/20132/27/20137/31/20138/29/20139/30/201311/4/20133/28/20134/30/2013CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2013Results in Units of pCi/liter  +/-  1 SigmaFITZPATRICK* (03, INLET)***TABLE 6-4 (continued)5/29/2013 6 - 10DateNUCLIDEI-131< 10.1< 9.57< 9.54< 11.4< 11.0< 8.57Cs-134< 1.57< 1.60< 1.71< 2.01< 1.61< 1.82Cs-137< 2.16< 2.38< 2.26< 2.54< 2.42< 2.15Zr-95< 4.35< 4.76< 4.87< 5.04< 4.96< 4.34Nb-95< 3.23< 3.17< 2.95< 3.32< 3.54< 3.24Co-58< 2.53< 2.71< 2.53< 3.19< 2.78< 2.93Mn-54< 2.32< 2.30< 2.63< 2.65< 2.29< 2.38Fe-59< 6.62< 6.70< 6.57< 8.42< 6.48< 6.43Zn-65< 5.42< 5.53< 5.20< 6.41< 2.54< 2.95Co-60< 2.45< 2.35< 2.23< 2.62< 2.13< 2.53K-4036.8 +/- 9.237.8 +/- 8.3< 23.2115.9 +/- 13.728.0 +/- 8.528.5 +/- 8.5Ba/La-140< 6.17< 7.97< 5.86< 7.59< 8.18< 6.37DateNUCLIDEI-131< 12.1< 11.7< 9.1< 9.9< 14.0< 12.6Cs-134< 3.26< 2.14< 1.42< 1.71< 5.03< 2.09 Cs-137< 2.63< 2.77< 1.75< 2.37< 4.12< 2.94Zr-95< 4.76< 6.19< 3.94< 4.72< 8.77< 5.59Nb-95< 3.85< 3.86< 2.79< 3.47< 5.98< 3.71Co-58< 3.05< 3.30< 2.19< 2.77< 4.84< 3.23Mn-54< 3.12< 3.19< 1.80< 2.25< 3.60< 3.04Fe-59< 10.3< 10.6< 5.72< 7.56< 18.1< 8.97 Zn-65< 6.56< 6.95< 2.41< 2.93< 9.84< 6.63Co-60< 3.02< 3.33< 1.78< 2.30< 4.88< 2.23K-40< 33.8< 33.830.4 +/- 7.1< 22.7< 44.0125.0 +/- 14.2Ba/La-140< 8.63< 8.65< 5.64< 6.8< 14.2< 7.6  ** Optional Sample Location
*** Corresponds to sample location noted on Figure 3.3-46/28/201311/29/20131/3/20142/1/20133/1/20138/2/20138/30/20139/26/201311/1/20133/28/20134/26/2013CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES -
2013Results in Units of pCi/liter  +/-  1 SigmaNINE MILE POINT UNIT 1 ** (09, INLET)***TABLE 6-4 (Continued)5/31/2013 6 - 11DateNUCLIDEI-131< 12.2< 11.1< 12.2< 12.0< 12.5< 12.7Cs-134< 3.10< 3.27< 2.17< 3.15< 3.36< 3.84Cs-137< 2.37< 2.62< 3.02< 2.44< 2.70< 2.57Zr-95< 5.26< 5.12< 5.41< 6.09< 4.95< 5.29Nb-95< 3.46< 3.60< 3.79< 4.30< 3.45< 4.03Co-58< 3.38< 3.29< 3.31< 3.37< 3.32< 3.46Mn-54< 2.68< 2.73< 2.80< 2.80< 3.07< 3.30Fe-59< 9.59< 10.4< 8.33< 12.8< 8.70< 10.9Zn-65< 6.26< 6.34< 4.05< 8.23< 6.39< 7.16Co-60< 2.71< 2.71< 2.91< 3.74< 2.58< 3.18K-40105.9 +/- 13.7140.1 +/- 14.7120.0 +/- 14.3< 30.094.1 +/- 13.2< 35.2Ba/La-140< 8.42< 8.37< 8.58< 9.32< 6.43< 10.7DateNUCLIDEI-131< 11.5< 14.9< 10.0< 14.4< 14.9< 12.5Cs-134< 2.13< 1.84< 1.56< 2.34< 2.79< 2.15 Cs-137< 2.57< 2.28< 2.27< 2.80< 3.74< 2.96Zr-95< 5.22< 4.49< 3.93< 6.43< 7.15< 6.60Nb-95< 3.65< 3.58< 2.10< 4.11< 3.86< 4.37Co-58< 2.90< 2.43< 2.47< 3.62< 4.19< 3.09Mn-54< 2.49< 2.48< 2.15< 3.01< 3.43< 3.33Fe-59< 8.17< 7.70< 6.80< 12.7< 10.7< 8.48 Zn-65< 3.91< 5.55< 2.99< 8.22< 10.4< 8.29Co-60< 2.28< 2.38< 2.02< 3.65< 3.73< 3.56K-40155.6 +/- 14.0166.4 +/- 12.9128.7 +/- 11.5< 39.6113.8 +/- 18.2< 44.0Ba/La-140< 9.05< 8.20< 7.06< 13.2< 9.44< 12.8  ** Optional Sample Location
*** Corresponds to sample location noted on Figure 3.3-46/28/201311/29/20131/3/20142/1/20133/1/20138/2/20138/30/20139/26/201311/1/20133/28/20134/26/2013CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES -
2013Results in Units of pCi/liter  +/-  1 SigmaNINE MILE POINT UNIT 2 ** (11, INLET)***TABLE 6-4 (Continued)5/31/2013 6 - 12Week EndDate01/02/130.019+/-0.0010.021+/-0.0010.018+/-0.0010.021+/-0.0010.021+/-0.0010.020+/-0.0010.020+/-0.0010.021+/-0.0010.020+/-0.00101/08/130.026+/-0.0020.032+/-0.0020.030+/-0.0020.029+/-0.0020.031+/-0.0020.029+/-0.0020.028+/-0.0020.031+/-0.0020.031+/-0.002 01/15/130.028+/-0.0020.025+/-0.0020.024+/-0.0020.023+/-0.0020.025+/-0.0020.022+/-0.0010.022+/-0.0010.027+/-0.0020.024+/-0.00201/22/130.015+/-0.0010.014+/-0.0010.019+/-0.0010.016+/-0.0010.017+/-0.0010.015+/-0.0010.015+/-0.0010.017+/-0.0010.015+/-0.00101/29/130.017+/-0.0010.017+/-0.0010.017+/-0.0010.017+/-0.0010.014+/-0.0010.014+/-0.0010.013+/-0.0010.016+/-0.0010.017+/-0.00102/05/130.020+/-0.0010.019+/-0.0010.020+/-0.0020.017+/-0.0010.018+/-0.0010.021+/-0.0010.018+/-0.0010.021+/-0.0020.021+/-0.00202/12/130.020+/-0.0010.023+/-0.0020.021+/-0.0010.025+/-0.0020.025+/-0.0020.023+/-0.0020.017+/-0.0010.022+/-0.0020.023+/-0.00202/19/130.016+/-0.0010.016+/-0.0010.018+/-0.0010.014+/-0.0010.016+/-0.0010.016+/-0.0010.017+/-0.0010.019+/-0.0010.018+/-0.001 02/26/130.012+/-0.0010.010+/-0.0010.011+/-0.0010.008+/-0.0010.011+/-0.0010.010+/-0.0010.009+/-0.0010.011+/-0.0010.012+/-0.00103/05/130.015+/-0.0010.012+/-0.0010.013+/-0.0010.011+/-0.0010.014+/-0.0010.011+/-0.0010.013+/-0.0010.014+/-0.0010.012+/-0.00103/12/130.009+/-0.0010.012+/-0.0010.009+/-0.0010.010+/-0.0010.010+/-0.0010.012+/-0.0010.010+/-0.0010.011+/-0.0010.012+/-0.00103/19/130.017+/-0.0010.017+/-0.0010.015+/-0.0010.014+/-0.0010.015+/-0.0010.018+/-0.0010.015+/-0.0010.015+/-0.0010.016+/-0.001 03/26/130.011+/-0.0010.011+/-0.0010.012+/-0.0010.010+/-0.0010.010+/-0.0010.009+/-0.0010.010+/-0.0010.009+/-0.0010.012+/-0.001 04/02/130.010+/-0.0010.011+/-0.0010.012+/-0.0010.012+/-0.0010.010+/-0.0010.009+/-0.0010.011+/-0.0010.011+/-0.0010.010+/-0.00104/09/130.016+/-0.0010.018+/-0.0010.020+/-0.0020.022+/-0.0020.017+/-0.0010.017+/-0.0010.018+/-0.0010.016+/-0.0010.016+/-0.00104/16/130.008+/-0.0010.010+/-0.0010.009+/-0.0010.010+/-0.0010.009+/-0.0010.007+/-0.0010.012+/-0.0010.011+/-0.0010.010+/-0.001 04/23/130.016+/-0.0010.018+/-0.0010.015+/-0.0010.015+/-0.0010.013+/-0.0010.018+/-0.0010.014+/-0.0010.013+/-0.0010.016+/-0.001 04/30/130.021+/-0.0010.019+/-0.0010.019+/-0.0010.019+/-0.0020.019+/-0.0010.021+/-0.0010.020+/-0.0010.018+/-0.0010.022+/-0.00205/07/130.015+/-0.0010.018+/-0.0010.016+/-0.0010.016+/-0.0010.014+/-0.0010.015+/-0.0010.017+/-0.0010.014+/-0.0010.018+/-0.00105/14/130.008+/-0.0010.008+/-0.0010.009+/-0.0010.008+/-0.0010.009+/-0.0010.009+/-0.0010.011+/-0.0010.009+/-0.0010.010+/-0.001 05/21/130.012+/-0.0010.013+/-0.0010.010+/-0.0010.013+/-0.0010.012+/-0.0010.012+/-0.0010.015+/-0.0010.013+/-0.0010.013+/-0.001 05/29/130.013+/-0.0010.013+/-0.0010.013+/-0.0010.012+/-0.0010.012+/-0.0010.013+/-0.0010.015+/-0.0010.013+/-0.0010.015+/-0.00106/04/130.013+/-0.0010.015+/-0.0010.015+/-0.0010.014+/-0.0010.013+/-0.0010.014+/-0.0010.014+/-0.0010.013+/-0.0010.015+/-0.00106/11/130.010+/-0.0010.010+/-0.0010.011+/-0.0010.011+/-0.0010.008+/-0.0010.008+/-0.0010.009+/-0.0010.009+/-0.0010.012+/-0.001 06/18/130.013+/-0.0010.013+/-0.0010.012+/-0.0010.013+/-0.0010.010+/-0.0010.012+/-0.0010.015+/-0.0010.013+/-0.0010.015+/-0.00106/25/130.019+/-0.0010.023+/-0.0020.020+/-0.0010.020+/-0.0010.020+/-0.0010.020+/-0.0010.021+/-0.0010.017+/-0.0010.020+/-0.001
* Sample location required by ODCM ** Optional sample locationE **F **TABLE 6-5ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS -
2013GROSS BETA ACTIVITY pCi/ m 3+/-  1 SigmaR-1 *R-2 *R-3 *R-4
* G **R-5 *D-2 **
6 - 13Week End Date07/02/130.012+/-0.0010.011+/-0.0010.012+/-0.0010.012+/-0.0010.012+/-0.0010.010+/-0.0010.011+/-0.0010.009+/-0.0010.012+/-0.00107/09/130.014+/-0.0010.016+/-0.0010.017+/-0.0010.014+/-0.0010.014+/-0.0010.013+/-0.0010.016+/-0.0010.015+/-0.0010.016+/-0.00107/16/130.014+/-0.0010.014+/-0.0010.014+/-0.0010.015+/-0.0010.016+/-0.0010.012+/-0.0010.012+/-0.0010.011+/-0.0010.018+/-0.001 07/23/130.020+/-0.0010.019+/-0.0010.016+/-0.0010.017+/-0.0010.016+/-0.0010.015+/-0.0010.018+/-0.0010.016+/-0.0010.020+/-0.00207/30/130.010+/-0.0010.010+/-0.0010.010+/-0.0010.009+/-0.0010.010+/-0.0010.008+/-0.0010.012+/-0.0010.011+/-0.0010.010+/-0.00108/06/130.013+/-0.0010.010+/-0.0010.011+/-0.0010.010+/-0.0010.012+/-0.0010.010+/-0.0010.011+/-0.0010.012+/-0.00108/13/130.010+/-0.0010.013+/-0.0010.011+/-0.0010.014+/-0.0010.015+/-0.0010.014+/-0.0010.014+/-0.0010.013+/-0.0010.016+/-0.001 08/20/130.018+/-0.0010.015+/-0.0010.016+/-0.0010.014+/-0.0010.015+/-0.0010.014+/-0.0010.014+/-0.0010.014+/-0.0010.018+/-0.001 08/27/130.028+/-0.0020.025+/-0.0020.029+/-0.0020.025+/-0.0020.025+/-0.0020.026+/-0.0020.025+/-0.0020.025+/-0.0020.029+/-0.00209/04/130.024+/-0.0010.024+/-0.0010.020+/-0.0010.023+/-0.0010.020+/-0.0010.021+/-0.0010.020+/-0.0010.022+/-0.0010.022+/-0.00109/10/130.013+/-0.0010.012+/-0.0010.014+/-0.0010.013+/-0.0010.014+/-0.0010.013+/-0.0010.013+/-0.0010.014+/-0.0010.014+/-0.001 09/17/130.020+/-0.0010.021+/-0.0010.023+/-0.0020.022+/-0.0020.020+/-0.0010.018+/-0.0010.020+/-0.0010.019+/-0.0010.020+/-0.00109/24/130.015+/-0.0010.015+/-0.0010.015+/-0.0010.016+/-0.0010.014+/-0.0010.015+/-0.0010.016+/-0.0010.014+/-0.0010.016+/-0.00110/01/130.011+/-0.0010.012+/-0.0010.010+/-0.0010.011+/-0.0010.010+/-0.0010.011+/-0.0010.010+/-0.0010.010+/-0.0010.013+/-0.001 10/08/130.020+/-0.0010.019+/-0.0010.020+/-0.0010.019+/-0.0010.021+/-0.0020.020+/-0.0010.019+/-0.0010.021+/-0.0020.023+/-0.002 10/15/130.017+/-0.0010.018+/-0.0010.018+/-0.0010.019+/-0.0010.016+/-0.0010.017+/-0.0010.018+/-0.0010.015+/-0.0010.020+/-0.00110/22/130.020+/-0.0010.020+/-0.0010.020+/-0.0010.019+/-0.0010.019+/-0.0010.019+/-0.0010.020+/-0.0010.019+/-0.0010.018+/-0.00110/29/130.006+/-0.0010.007+/-0.0010.008+/-0.0010.007+/-0.0010.006+/-0.0010.007+/-0.0010.005+/-0.0010.006+/-0.0010.007+/-0.001 11/05/130.019+/-0.0010.017+/-0.0010.017+/-0.0010.016+/-0.0010.017+/-0.0010.015+/-0.0010.017+/-0.0010.018+/-0.0010.017+/-0.001 11/13/130.011+/-0.0010.012+/-0.0010.010+/-0.0010.012+/-0.0010.010+/-0.0010.012+/-0.0010.012+/-0.0010.013+/-0.0010.014+/-0.00111/19/130.018+/-0.0020.015+/-0.0010.018+/-0.0020.017+/-0.0020.018+/-0.0020.015+/-0.0010.013+/-0.0010.017+/-0.0010.017+/-0.00211/26/130.011+/-0.0010.013+/-0.0010.013+/-0.0010.012+/-0.0010.013+/-0.0010.011+/-0.0010.010+/-0.0010.012+/-0.0010.011+/-0.001 12/03/130.014+/-0.0010.017+/-0.0010.017+/-0.0010.015+/-0.0010.019+/-0.0020.018+/-0.0010.017+/-0.0010.017+/-0.0010.019+/-0.002 12/10/130.024+/-0.0020.023+/-0.0020.022+/-0.0010.023+/-0.0020.023+/-0.0020.021+/-0.0010.026+/-0.0020.024+/-0.0020.021+/-0.00112/17/130.022+/-0.0020.021+/-0.0010.022+/-0.0020.021+/-0.0010.025+/-0.0020.020+/-0.0010.021+/-0.0010.024+/-0.0020.022+/-0.00212/23/130.015+/-0.0010.018+/-0.0010.018+/-0.0010.016+/-0.0010.018+/-0.0020.016+/-0.0010.018+/-0.0010.015+/-0.0010.019+/-0.00212/31/130.026+/-0.0020.023+/-0.0010.023+/-0.0010.023+/-0.0010.027+/-0.0020.023+/-0.0010.022+/-0.0010.025+/-0.0020.023+/-0.001* ODCM required sample location
** Optional sample locationf Sample pump failure, No Sample AvailableR-4 *G **R-5 *D-2 **E **F **NSAfTABLE 6-5 (Continued)ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2013GROSS BETA ACTIVITY pCi/ m 3+/-  1 SigmaR-1 *R-2 *R-3
* 6 - 14Week EndDate12/31/120.014
+/-0.0010.015
+/-0.0010.017
+/-0.0010.020
+/-0.0010.013
+/-0.0010.012
+/-0.00101/07/130.031
+/-0.0020.034
+/-0.0020.033
+/-0.0020.036
+/-0.0030.029
+/-0.0020.035
+/-0.00201/14/130.027
+/-0.0020.029
+/-0.0020.029
+/-0.0020.031
+/-0.0020.030
+/-0.0020.029
+/-0.00201/21/130.017
+/-0.0010.018
+/-0.0010.019
+/-0.0010.016
+/-0.0010.016
+/-0.0010.018
+/-0.00101/28/130.019
+/-0.0010.015
+/-0.0010.017
+/-0.0010.014
+/-0.0010.016
+/-0.0010.016
+/-0.00102/04/130.021
+/-0.0020.018
+/-0.0010.021
+/-0.0020.017
+/-0.0010.020
+/-0.0010.021
+/-0.00102/11/130.025
+/-0.0020.024
+/-0.0020.022
+/-0.0010.023
+/-0.0020.021
+/-0.0010.024
+/-0.00202/18/130.020
+/-0.0010.016
+/-0.0010.018
+/-0.0010.016
+/-0.0010.018
+/-0.0010.019
+/-0.00102/25/130.011
+/-0.0010.012
+/-0.0010.013
+/-0.0010.011
+/-0.0010.010
+/-0.0010.013
+/-0.00103/04/130.013
+/-0.0010.012
+/-0.0010.011
+/-0.0010.011
+/-0.0010.012
+/-0.0010.011
+/-0.00103/11/130.014
+/-0.0010.014
+/-0.0010.012
+/-0.0010.012
+/-0.0010.013
+/-0.0010.011
+/-0.00103/18/130.017
+/-0.0010.017
+/-0.0010.016
+/-0.0010.018
+/-0.0010.018
+/-0.0010.016
+/-0.00103/25/130.015
+/-0.0010.013
+/-0.0010.014
+/-0.0010.014
+/-0.0010.010
+/-0.0010.011
+/-0.00104/01/130.011
+/-0.0010.008
+/-0.0010.008
+/-0.0010.008
+/-0.0010.007
+/-0.0010.010
+/-0.00104/08/130.014
+/-0.0010.016
+/-0.0010.018
+/-0.0010.018
+/-0.0010.018
+/-0.0010.021
+/-0.00104/15/130.009
+/-0.0010.009
+/-0.0010.012
+/-0.0010.009
+/-0.0010.009
+/-0.0010.009
+/-0.00104/22/130.017
+/-0.0010.017
+/-0.0010.015
+/-0.0010.019
+/-0.0010.013
+/-0.0010.015
+/-0.00104/29/130.023
+/-0.0020.017
+/-0.0010.019
+/-0.0010.021
+/-0.0010.022
+/-0.0010.020
+/-0.00105/06/130.017
+/-0.0010.012
+/-0.0010.017
+/-0.0010.016
+/-0.0010.016
+/-0.0010.014
+/-0.00105/13/130.008
+/-0.0010.007
+/-0.0010.010
+/-0.0010.009
+/-0.0010.010
+/-0.0010.010
+/-0.00105/20/130.015
+/-0.0010.013
+/-0.0010.013
+/-0.0010.012
+/-0.0010.012
+/-0.0010.012
+/-0.00105/28/130.014
+/-0.0010.010
+/-0.0010.013
+/-0.0010.011
+/-0.0010.013
+/-0.0010.013
+/-0.00106/03/130.014
+/-0.0010.018
+/-0.0010.016
+/-0.0010.018
+/-0.0020.019
+/-0.0020.017
+/-0.00106/10/130.010
+/-0.0010.011
+/-0.0010.008
+/-0.0010.010
+/-0.0010.010
+/-0.0010.009
+/-0.00106/17/130.011
+/-0.0010.010
+/-0.0010.013
+/-0.0010.012
+/-0.0010.013
+/-0.0010.012
+/-0.00106/24/130.017
+/-0.0010.014
+/-0.0010.017
+/-0.0010.018
+/-0.0010.016
+/-0.0010.016
+/-0.00107/01/130.015
+/-0.0010.016
+/-0.0010.015
+/-0.0010.015
+/-0.0010.015
+/-0.0010.015
+/-0.001 **  Optional sample locationD-1 **G **H **I **TABLE 6-6ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2013GROSS BETA ACTIVITY pCi/ m 3+/-  1 SigmaJ **K **
6 - 15Week EndDate07/08/130.015
+/-0.0010.013
+/-0.0010.016
+/-0.0010.016
+/-0.0010.015
+/-0.0010.015
+/-0.00107/15/130.017
+/-0.0010.013
+/-0.0010.017
+/-0.0010.015
+/-0.0010.013
+/-0.0010.014
+/-0.00107/22/130.019
+/-0.0010.018
+/-0.0010.019
+/-0.0010.019
+/-0.0010.017
+/-0.0010.016
+/-0.00107/29/130.011
+/-0.0010.010
+/-0.0010.012
+/-0.0010.010
+/-0.0010.011
+/-0.0010.009
+/-0.00108/05/130.012
+/-0.0010.012
+/-0.0010.012
+/-0.0010.010
+/-0.0010.011
+/-0.0010.012
+/-0.00108/12/130.013
+/-0.0010.012
+/-0.0010.013
+/-0.0010.011
+/-0.0010.014
+/-0.0010.014
+/-0.00108/19/130.017
+/-0.0010.011
+/-0.0010.015
+/-0.0010.015
+/-0.0010.014
+/-0.0010.014
+/-0.00108/26/130.028
+/-0.0020.025
+/-0.0020.030
+/-0.0020.025
+/-0.0020.028
+/-0.0020.029
+/-0.00209/03/130.024
+/-0.0010.025
+/-0.0020.023
+/-0.0010.022
+/-0.0010.026
+/-0.0020.024
+/-0.00109/09/130.015
+/-0.0010.010
+/-0.0010.013
+/-0.0010.010
+/-0.0010.011
+/-0.0010.013
+/-0.00109/16/130.023
+/-0.0020.021
+/-0.0010.023
+/-0.0020.024
+/-0.0020.021
+/-0.0010.024
+/-0.00209/23/130.014
+/-0.0010.014
+/-0.0010.014
+/-0.0010.012
+/-0.0010.012
+/-0.0010.015
+/-0.00109/30/130.010
+/-0.0010.008
+/-0.0010.007
+/-0.0010.006
+/-0.0010.008
+/-0.0010.008
+/-0.00110/07/130.027
+/-0.0020.025
+/-0.0020.027
+/-0.0020.022
+/-0.0020.021
+/-0.0020.019
+/-0.00210/14/130.021
+/-0.0020.016
+/-0.0010.016
+/-0.0010.017
+/-0.0010.018
+/-0.0010.016
+/-0.00110/21/130.018
+/-0.0010.017
+/-0.0010.019
+/-0.0010.011
+/-0.0010.020
+/-0.0020.019
+/-0.00110/28/130.010
+/-0.0010.007
+/-0.0010.009
+/-0.0010.008
+/-0.0010.009
+/-0.0010.009
+/-0.00111/04/130.017
+/-0.0010.016
+/-0.0010.013
+/-0.0010.011
+/-0.0010.015
+/-0.0010.018
+/-0.00111/12/130.013
+/-0.0010.012
+/-0.0010.012
+/-0.0010.008
+/-0.0010.013
+/-0.0010.012
+/-0.00111/18/130.017
+/-0.0020.016
+/-0.0010.017
+/-0.0020.011
+/-0.0010.018
+/-0.0020.015
+/-0.00111/25/130.009
+/-0.0010.009
+/-0.0010.010
+/-0.0010.007
+/-0.0010.009
+/-0.0010.009
+/-0.00112/02/130.014
+/-0.0010.014
+/-0.0010.014
+/-0.0010.009
+/-0.0010.015
+/-0.0010.015
+/-0.00112/09/130.026
+/-0.0020.026
+/-0.0020.028
+/-0.0020.017
+/-0.0010.026
+/-0.0020.027
+/-0.00212/16/130.022
+/-0.0020.027
+/-0.0020.023
+/-0.0010.018
+/-0.0010.024
+/-0.0020.022
+/-0.00112/22/130.022
+/-0.0020.019
+/-0.0020.021
+/-0.0020.013
+/-0.0010.020
+/-0.0020.022
+/-0.00212/30/130.027
+/-0.0020.023
+/-0.0010.025
+/-0.0020.015
+/-0.0010.027
+/-0.0020.025
+/-0.001 **  Optional sample locationTABLE 6-6 (Continued)ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS - 2013GROSS BETA ACTIVITY pCi/ m 3+/-  1 SigmaJ **K **D-1 **G **H **I **
6 - 16Week EndDate01/02/13 < 0.018 < 0.012 < 0.013 < 0.021 < 0.019 < 0.021 < 0.003 < 0.011 < 0.01801/08/13 < 0.004 < 0.016 < 0.016 < 0.014 < 0.024 < 0.020 < 0.021 < 0.020 < 0.025 01/15/13 < 0.023 < 0.016 < 0.018 < 0.025 < 0.016 < 0.021 < 0.015 < 0.015 < 0.01801/22/13 < 0.020 < 0.004 < 0.015 < 0.022 < 0.025 < 0.016 < 0.012 < 0.017 < 0.01701/29/13 < 0.023 < 0.021 < 0.015 < 0.017 < 0.020 < 0.016 < 0.015 < 0.015 < 0.020 02/05/13 < 0.021 < 0.018 < 0.018 < 0.024 < 0.017 < 0.020 < 0.019 < 0.013 < 0.02102/12/13 < 0.021 < 0.010 < 0.014 < 0.017 < 0.021 < 0.019 < 0.017 < 0.015 < 0.02002/19/13 < 0.017 < 0.021 < 0.022 < 0.020 < 0.020 < 0.013 < 0.018 < 0.020 < 0.017 02/26/13 < 0.019 < 0.013 < 0.018 < 0.020 < 0.018 < 0.022 < 0.015 < 0.016 < 0.023 03/05/13 < 0.017 < 0.017 < 0.018 < 0.020 < 0.017 < 0.025 < 0.016 < 0.015 < 0.02403/12/13 < 0.020 < 0.013 < 0.016 < 0.018 < 0.017 < 0.024 < 0.015 < 0.020 < 0.01303/19/13 < 0.021 < 0.024 < 0.018 < 0.021 < 0.019 < 0.025 < 0.019 < 0.018 < 0.017 03/26/13 < 0.021 < 0.013 < 0.022 < 0.023 < 0.018 < 0.014 < 0.018 < 0.022 < 0.022 04/02/13 < 0.017 < 0.017 < 0.025 < 0.014 < 0.018 < 0.021 < 0.010 < 0.020 < 0.01904/09/13 < 0.024 < 0.018 < 0.021 < 0.013 < 0.016 < 0.018 < 0.019 < 0.020 < 0.02104/16/13 < 0.022 < 0.014 < 0.024 < 0.022 < 0.013 < 0.017 < 0.016 < 0.013 < 0.026 04/23/13 < 0.022 < 0.017 < 0.019 < 0.012 < 0.016 < 0.016 < 0.015 < 0.018 < 0.01704/30/13 < 0.016 < 0.014 < 0.012 < 0.024 < 0.016 < 0.016 < 0.015 < 0.018 < 0.01805/07/13 < 0.018 < 0.023 < 0.016 < 0.025 < 0.021 < 0.016 < 0.018 < 0.015 < 0.023 05/14/13 < 0.026 < 0.014 < 0.012 < 0.028 < 0.026 < 0.018 < 0.014 < 0.017 < 0.022 05/21/13 < 0.021 < 0.021 < 0.021 < 0.019 < 0.014 < 0.018 < 0.019 < 0.018 < 0.02005/29/13 < 0.019 < 0.012 < 0.016 < 0.019 < 0.019 < 0.011 < 0.019 < 0.018 < 0.01506/04/13 < 0.025 < 0.025 < 0.020 < 0.023 < 0.015 < 0.027 < 0.020 < 0.021 < 0.027 06/11/13 < 0.024 < 0.015 < 0.021 < 0.016 < 0.017 < 0.017 < 0.017 < 0.015 < 0.02106/18/13 < 0.019 < 0.019 < 0.018 < 0.018 < 0.023 < 0.009 < 0.018 < 0.018 < 0.02106/25/13 < 0.017 < 0.022 < 0.020 < 0.011 < 0.021 < 0.019 < 0.024 < 0.014 < 0.018* Sample location required by ODCM** Optional sample locationR-1 *R-2 *R-3 *R-4 *R-5 *G **D-2 **F **
E **TABLE 6-7ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2013I-131 ACTIVITY pCi/ m3  +/-  1 Sigma 6 - 17Week EndDate07/02/13 < 0.017 < 0.024 < 0.020 < 0.012 < 0.023 < 0.019 < 0.016 < 0.016 < 0.02307/09/13 < 0.021 < 0.012 < 0.019 < 0.017 < 0.019 < 0.014 < 0.019 < 0.022 < 0.01907/16/13 < 0.010 < 0.015 < 0.012 < 0.025 < 0.019 < 0.017 < 0.019 < 0.022 < 0.01407/23/13 < 0.022 < 0.017 < 0.013 < 0.019 < 0.015 < 0.018 < 0.017 < 0.022 < 0.01707/30/13 < 0.021 < 0.015 < 0.021 < 0.016 < 0.019 < 0.020 < 0.015 < 0.019 < 0.01908/06/13 < 0.013 < 0.021 < 0.018 < 0.016 < 0.022 < 0.010 < 0.015 < 0.02008/13/13 < 0.017 < 0.019 < 0.019 < 0.020 < 0.025 < 0.017 < 0.022 < 0.017 < 0.02308/20/13 < 0.017 < 0.019 < 0.020 < 0.016 < 0.018 < 0.019 < 0.017 < 0.013 < 0.01408/27/13 < 0.018 < 0.014 < 0.020 < 0.021 < 0.017 < 0.021 < 0.022 < 0.020 < 0.02009/04/13 < 0.009 < 0.014 < 0.010 < 0.016 < 0.016 < 0.019 < 0.013 < 0.015 < 0.01409/10/13 < 0.016 < 0.010 < 0.014 < 0.023 < 0.018 < 0.019 < 0.021 < 0.016 < 0.02609/17/13 < 0.021 < 0.022 < 0.020 < 0.019 < 0.025 < 0.015 < 0.024 < 0.022 < 0.02409/24/13 < 0.023 < 0.020 < 0.017 < 0.017 < 0.017 < 0.021 < 0.022 < 0.010 < 0.02110/01/13 < 0.017 < 0.017 < 0.016 < 0.018 < 0.017 < 0.018 < 0.020 < 0.014 < 0.01910/08/13 < 0.021 < 0.014 < 0.019 < 0.022 < 0.016 < 0.024 < 0.016 < 0.023 < 0.01810/15/13 < 0.021 < 0.014 < 0.012 < 0.021 < 0.012 < 0.018 < 0.020 < 0.016 < 0.01510/22/13 < 0.024 < 0.026 < 0.016 < 0.023 < 0.012 < 0.018 < 0.015 < 0.021 < 0.01810/29/13 < 0.018 < 0.015 < 0.013 < 0.019 < 0.021 < 0.013 < 0.012 < 0.014 < 0.01611/05/13 < 0.019 < 0.012 < 0.020 < 0.023 < 0.017 < 0.019 < 0.013 < 0.018 < 0.01111/13/13 < 0.014 < 0.017 < 0.017 < 0.022 < 0.011 < 0.014 < 0.017 < 0.016 < 0.01811/19/13 < 0.018 < 0.020 < 0.021 < 0.025 < 0.017 < 0.028 < 0.019 < 0.024 < 0.02311/26/13 < 0.019 < 0.016 < 0.022 < 0.021 < 0.012 < 0.016 < 0.019 < 0.016 < 0.02012/03/13 < 0.025 < 0.021 < 0.020 < 0.022 < 0.023 < 0.019 < 0.014 < 0.019 < 0.01612/10/13 < 0.010 < 0.019 < 0.018 < 0.016 < 0.014 < 0.017 < 0.017 < 0.018 < 0.01812/17/13 < 0.023 < 0.013 < 0.020 < 0.017 < 0.020 < 0.020 < 0.019 < 0.013 < 0.02012/23/13 < 0.030 < 0.030 < 0.023 < 0.023 < 0.027 < 0.029 < 0.028 < 0.024 < 0.01912/31/13 < 0.019 < 0.015 < 0.018 < 0.019 < 0.022 < 0.016 < 0.019 < 0.017 < 0.019
* ODCM Required Sample Location ** Optional Sample Locationf Sample pump failure, No Sample AvailableNSAfR-1 *R-2 *R-3 *R-4 *R-5 *G **D-2 **F **
E **TABLE 6-7 (Continued)ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS - 2013I-131 ACTIVITY pCi/ m 3+/-  1 Sigma 6 - 18Week EndDate12/31/12 < 0.021 < 0.023 < 0.036 < 0.03401/07/13 < 0.010 < 0.024 < 0.033 < 0.031 < 0.016 < 0.02301/14/13 < 0.023 < 0.020 < 0.022 < 0.023 < 0.015 < 0.015 01/21/13 < 0.019 < 0.020 < 0.021 < 0.019 < 0.019 < 0.024 01/28/13 < 0.015 < 0.019 < 0.014 < 0.015 < 0.019 < 0.01302/04/13 < 0.018 < 0.014 < 0.021 < 0.020 < 0.020 < 0.01602/11/13 < 0.020 < 0.020 < 0.015 < 0.020 < 0.019 < 0.018 02/18/13 < 0.021 < 0.029 < 0.017 < 0.020 < 0.019 < 0.023 02/25/13 < 0.021 < 0.018 < 0.024 < 0.021 < 0.011 < 0.02103/04/13 < 0.025 < 0.017 < 0.018 < 0.022 < 0.018 < 0.02203/11/13 < 0.018 < 0.014 < 0.018 < 0.017 < 0.021 < 0.018 03/18/13 < 0.019 < 0.019 < 0.026 < 0.012 < 0.021 < 0.016 03/25/13 < 0.020 < 0.023 < 0.011 < 0.018 < 0.019 < 0.01704/01/13 < 0.018 < 0.014 < 0.021 < 0.016 < 0.017 < 0.02604/08/13 < 0.020 < 0.018 < 0.024 < 0.015 < 0.022 < 0.022 04/15/13 < 0.017 < 0.016 < 0.018 < 0.022 < 0.018 < 0.01704/22/13 < 0.015 < 0.018 < 0.011 < 0.024 < 0.020 < 0.02504/29/13 < 0.022 < 0.013 < 0.018 < 0.024 < 0.020 < 0.017 05/06/13 < 0.019 < 0.019 < 0.017 < 0.020 < 0.028 < 0.012 05/13/13 < 0.021 < 0.015 < 0.021 < 0.017 < 0.019 < 0.01805/20/13 < 0.020 < 0.018 < 0.020 < 0.013 < 0.017 < 0.02505/28/13 < 0.021 < 0.014 < 0.015 < 0.018 < 0.022 < 0.015 06/03/13 < 0.029 < 0.016 < 0.022 < 0.025 < 0.026 < 0.019 06/10/13 < 0.022 < 0.016 < 0.017 < 0.027 < 0.018 < 0.02406/17/13 < 0.020 < 0.022 < 0.015 < 0.012 < 0.014 < 0.02006/24/13 < 0.016 < 0.021 < 0.018 < 0.021 < 0.018 < 0.020 ** Optional Sample LocationJ **K **<  0.019<  0.016TABLE 6-8ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2012I-131 ACTIVITY pCi/ m 3+/-  1 SigmaD-1 **G **H **I **
6 - 19Week End Date07/01/13 < 0.018 < 0.013 < 0.015 < 0.018 < 0.026 < 0.01307/08/13 < 0.023 < 0.018 < 0.018 < 0.019 < 0.022 < 0.01407/15/13 < 0.012 < 0.015 < 0.018 < 0.022 < 0.010 < 0.01807/22/13 < 0.015 < 0.024 < 0.023 < 0.019 < 0.024 < 0.02407/29/13 < 0.022 < 0.019 < 0.014 < 0.017 < 0.017 < 0.01608/05/13 < 0.015 < 0.012 < 0.021 < 0.022 < 0.018 < 0.01808/12/13 < 0.010 < 0.018 < 0.016 < 0.018 < 0.010 < 0.02108/19/13 < 0.022 < 0.018 < 0.024 < 0.019 < 0.017 < 0.01208/26/13 < 0.016 < 0.019 < 0.022 < 0.018 < 0.020 < 0.02409/03/13 < 0.011 < 0.017 < 0.020 < 0.015 < 0.016 < 0.02209/09/13 < 0.020 < 0.022 < 0.024 < 0.023 < 0.020 < 0.02309/16/13 < 0.021 < 0.014 < 0.012 < 0.026 < 0.021 < 0.02409/23/13 < 0.016 < 0.019 < 0.020 < 0.014 < 0.020 < 0.01509/30/13 < 0.017 < 0.012 < 0.009 < 0.022 < 0.010 < 0.01710/07/13 < 0.016 < 0.018 < 0.017 < 0.015 < 0.014 < 0.01610/14/13 < 0.021 < 0.017 < 0.018 < 0.022 < 0.018 < 0.02210/21/13 < 0.018 < 0.014 < 0.019 < 0.013 < 0.020 < 0.00910/28/13 < 0.015 < 0.024 < 0.016 < 0.017 < 0.012 < 0.01611/04/13 < 0.009 < 0.014 < 0.018 < 0.022 < 0.014 < 0.01911/12/13 < 0.018 < 0.014 < 0.016 < 0.019 < 0.013 < 0.01511/18/13 < 0.023 < 0.025 < 0.022 < 0.023 < 0.016 < 0.02111/25/13 < 0.022 < 0.019 < 0.028 < 0.026 < 0.018 < 0.02412/02/13 < 0.028 < 0.018 < 0.020 < 0.021 < 0.021 < 0.02212/09/13 < 0.019 < 0.015 < 0.011 < 0.021 < 0.014 < 0.02112/16/13 < 0.018 < 0.029 < 0.011 < 0.021 < 0.021 < 0.01612/22/13 < 0.027 < 0.024 < 0.017 < 0.044 < 0.019 < 0.02412/30/13 < 0.014 < 0.016 < 0.016 < 0.019 < 0.019 < 0.014 **  Optional sample locationJ **K **D-1 **G **TABLE 6-8 (Continued)ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS - 2013I-131 ACTIVITY pCi/ m 3+/-  1 SigmaH **I **
6 - 20Be-762.8 +/-9.190.9 +/-11.292.2 +/-11.890.0 +/-11.775.7 +/-10.872.4 +/-10.692.3 +/-10.753.1 +/-10.275.3 +/-11.4Cs-134 <1.7 <1.7 <1.8 <1.9 <1.8 <1.7 <1.7 <2.3 <1.9Cs-137 <1.1 <1.1 <1.0 <1.5 <1.0 <0.7 <0.9 <1.3 <1.0Zr-95 <0.9 <2.6 <4.5 <4.1 <2.9 <4.0 <3.0 <3.5 <3.0Nb-95 <2.0 <2.2 <2.8 <2.2 <3.3 <2.0 <2.1 <2.2 <2.8Co-58 <1.4 <1.3 <2.0 <2.3 <2.3 <0.5 <1.5 <1.5 <1.8Mn-54 <0.4 <1.1 <1.6 <1.1 <1.1 <1.4 <1.1 <1.5 <1.7Zn-65 <3.9 <3.1 <6.0 <3.6 <3.6 <2.6 <2.4 <4.3 <4.0Co-60 <1.5 <1.2 <2.1 <1.7 <1.5 <1.5 <0.4 <1.6 <1.5K-40 <5.3 <18.2 <5.5 <17.9 <11.9 <18.6 <15.3 <16.821.2 +/-7.5Be-7117.4 +/-12.4124.2 +/-12.7117.6 +/-12.997.2 +/-11.2117.7 +/-12.7111.0 +/-12.3109.6 +/-12.2116.7 +/-12.1126.9 +/-13.0Cs-134 <1.9 <1.2 <1.8 <1.9 <1.7 <1.2 <1.6 <2.2 <1.8Cs-137 <1.2 <1.0 <1.1 <1.1 <1.4 <1.0 <1.1 <1.1 <1.2Zr-95 <4.0 <2.9 <4.1 <2.6 <3.7 <3.5 <3.4 <2.2 <3.5Nb-95 <4.0 <1.9 <3.9 <1.7 <2.7 <2.5 <3.8 <2.6 <2.5Co-58 <2.3 <1.3 <2.3 <2.4 <2.4 <2.0 <1.8 <2.2 <2.8Mn-54 <1.5 <0.9 <1.4 <0.9 <0.9 <0.4 <1.1 <1.7 <1.2Zn-65 <4.5 <2.6 <3.5 <3.6 <3.6 <1.0 <3.5 <3.9 <2.6Co-60 <0.4 <1.8 <1.1 <1.7 <1.2 <1.4 <1.4 <1.2 <1.8K-40 <21.4 <14.3 <15.0 <18.2 <17.4 <18.4 <17.5 <14.8 <18.5
* ODCM Required Sample Loction**  Optional Sample LocationOFFSITE SAMPLE LOCATIONS - 1ST QTR 2013OFFSITE SAMPLE LOCATIONS - 2ND QTR 2013E **F **G **E **F **G **TABLE 6-9CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2013Results in Units of 10E-3 pCi/ m 3+/-  1 SigmaD-2 **R-1 *R-2 *R-2 *R-3 *R-4 *R-5 *R-3 *R-4 *R-5 *D-2 **NuclideNuclideR-1
* 6 - 21Be-791.4 +/-13.3119.0 +/-12.1118.1 +/-13.0103.8 +/-12.2104.7 +/-12.5108.8 +/-12.583.6 +/-11.388.5 +/-11.9101.2 +/-11.8Cs-134 <1.5 <1.5 <2.1 <2.2 <1.9 <2.5 <1.7 <1.8 <2.3Cs-137 <1.0 <0.9 <1.2 <1.4 <1.3 <1.3 <1.3 <1.1 <1.7Zr-95 <2.6 <2.6 <3.1 <0.9 <3.7 <4.4 <2.4 <2.6 <4.8Nb-95 <2.7 <2.7 <1.8 <0.7 <3.0 <3.1 <3.3 <2.8 <3.1Co-58 <1.5 <2.0 <2.0 <1.4 <1.2 <2.5 <1.4 <2.2 <1.5Mn-54 <2.0 <1.4 <1.5 <1.0 <1.1 <1.7 <1.2 <0.9 <1.4Zn-65 <4.1 <3.5 <3.4 <3.8 <3.6 <4.1 <2.6 <4.7 <4.7Co-60 <1.6 <1.5 <1.5 <2.1 <1.7 <2.0 <1.5 <1.7 <1.7K-40 <15.8 <15.3 <12.3 <18.5 <12.3 <4.2 <14.7 <4.5 <12.2Be-791.5 +/-10.776.8 +/-9.881.3 +/-10.895.7 +/-11.177.3 +/-10.793.7 +/-10.772.3 +/-11.0100.7 +/-11.368.8 +/-10.0Cs-134 <2.2 <1.6 <2.0 <2.1 <1.4 <1.8 <1.7 <1.2 <1.3Cs-137 <1.6 <1.3 <1.1 <1.0 <0.9 <1.2 <1.2 <0.3 <1.3Zr-95 <3.2 <3.1 <2.5 <4.2 <3.7 <3.2 <3.9 <4.1 <3.3Nb-95 <3.3 <2.1 <2.5 <2.1 <2.7 <3.7 <3.1 <3.0 <3.0Co-58 <2.4 <1.3 <2.3 <2.2 <1.9 <2.4 <1.4 <1.3 <1.5Mn-54 <1.2 <1.1 <1.3 <1.2 <1.6 <1.5 <1.3 <1.6 <1.2Zn-65 <3.7 <2.6 <3.4 <3.1 <3.9 <3.8 <3.4 <3.8 <2.3Co-60 <1.1 <1.5 <1.1 <2.2 <0.5 <1.1 <1.8 <0.5 <0.4K-40 <14.2 <15.1 <4.3 <4.0 <22.8 <14.5 <14.1 <4.9 <11.6
* ODCM Required Sample Loction**  Optional Sample LocationTABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESE **F **G **E **F **G **OFFSITE SAMPLE LOCATIONS - 4TH QTR 2013NuclideR-1 *R-2 *R-5 *D-2 **OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2013Results in Units of 10E-3 pCi/ m 3+/-  1 SigmaOFFSITE SAMPLE LOCATIONS - 3RD QTR 2013NuclideR-1 *R-2 *R-3 *R-3 *R-4 *R-4 *R-5 *D-2 **
6 - 22Be-797.1 +/- 12.264.7 +/- 10.183.0 +/- 10.165.5 +/- 11.487.7 +/- 12.485.6 +/- 10.7Cs-134<2.1<1.9<1.6<2.1<1.7<2.0Cs-137<1.2<0.7<1.3<0.8<1.3<1.6Zr-95<4.2<3.1<4.9<4.6<2.7<4.1Nb-95<3.8<0.8<2.6<2.9<2.2<4.1Co-58<1.7<2.1<2.1<3.1<1.8<1.9Mn-54<2.0<1.5<1.7<1.7<1.8<1.1Zn-65<4.1<3.4<2.5<5.4<3.6<2.8Co-60<1.2<0.5<0.5<2.7<1.5<1.8K-40<4.4<5.3<16.1<17.1<15.3<15.1Be-7115.7 +/- 12.8107.7 +/- 11.9114.9 +/- 12.5129.8 +/- 13.5112.3 +/- 13.0114.9 +/- 11.8Cs-134<2.0<2.2<1.6<1.6<1.4<1.4Cs-137<0.7<1.8<0.9<1.2<1.1<1.2Zr-95<3.3<2.6<3.7<0.9<4.4<3.0Nb-95<1.9<3.0<3.9<3.0<3.2<2.1Co-58<1.9<2.3<1.9<2.3<2.4<1.2Mn-54<1.1<1.1<0.9<1.0<1.4<1.1Zn-65<2.2<2.4<3.3<3.9<3.9<2.4Co-60<0.4<1.4<1.5<0.5<1.7<1.2K-40<4.228.7 +/- 6.8<11.9<5.3<17.4<4.4**  Optional Sample LocationTABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2013Results in Units of 10E-3 pCi/ m 3+/-  1 SigmaONSITE SAMPLE LOCATIONS - 1ST QTR 2013D-1 **G **H **ONSITE SAMPLE LOCATIONS - 2ND QTR 2013I **J **K **NuclideNuclideD-1 **G **H **I **J **K **
6 - 23Be-7115.8 +/- 13.5129.7 +/- 12.8127.5 +/- 12.9121.6 +/- 12.9106.3 +/- 12.396.1 +/- 11.6Cs-134<2.2<1.1<2.3<1.7<2.2<2.5Cs-137<1.1<1.2<1.4<1.4<0.7<1.4Zr-95<4.2<4.0<5.1<3.6<0.8<3.1Nb-95<2.6<2.8<4.3<2.0<2.2<0.7Co-58<2.0<1.6<2.0<1.4<2.1<1.8Mn-54<1.7<1.4<1.5<1.2<1.3<1.5Zn-65<3.8<3.6<4.1<3.3<2.5<5.0Co-60<1.5<1.5<2.5<1.4<1.2<0.4K-40<18.2<15.5<15.7<5.2<23.7<4.1Be-784.4 +/- 11.082.9 +/- 11.079.2 +/- 10.469.8 +/- 9.673.6 +/- 9.8104.9 +/- 11.4Cs-134<1.2<1.6<1.5<1.5<1.7<2.4Cs-137<0.7<1.1<1.4<1.0<0.9<1.2Zr-95<2.0<2.6<2.9<3.6<3.7<3.2Nb-95<2.8<2.8<2.5<2.8<2.8<1.7Co-58<1.8<2.2<1.8<0.4<2.0<1.8Mn-54<1.5<1.4<1.3<1.1<0.8<1.2Zn-65<0.8<3.0<3.4<3.9<4.3<2.6Co-60<0.4<1.6<1.4<1.6<1.4<1.6K-40<14.6<14.724.8 +/- 6.7<11.7<11.8<14.0**  Optional Sample LocationTABLE 6-9 (Continued)CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITESOF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2013Results in Units of 10E-3 pCi/ m 3+/-  1 SigmaONSITE SAMPLE LOCATIONS - 3RD QTR 2013NuclideD-1 **G **H **I **J **K **ONSITE SAMPLE LOCATIONS - 4TH QTR 2013NuclideD-1 **G **H **I **J **K **
6 - 24LOCATIONNUMBER3D1 Onsite11.41+/-0.5211.69+/-0.5912.20+/-0.7212.11+/-0.5469&deg;at0.2 miles4D2 Onsite4.20+/-0.194.01+/-0.164.45+/-0.244.57+/-0.22140&deg;at0.4 miles5E Onsite4.10+/-0.234.04+/-0.174.44+/-0.204.66+/-0.19175&deg;at0.4 miles6F Onsite3.46+/-0.223.33+/-0.173.91+/-0.163.90+/-0.23210&deg;at0.5 miles7*G Onsite3.46+/-0.173.45+/-0.123.71+/-0.184.11+/-0.19245&deg;at0.7 miles8*R-5 Offsite Control4.52+/-0.274.20+/-0.174.89+/-0.194.93+/-0.2642&deg;at16.2 miles9D1 Offsite3.78+/-0.223.68+/-0.123.93+/-0.234.15+/-0.3080&deg;at11.4 miles10D2 Offsite3.60+/-0.303.51+/-0.153.79+/-0.164.11+/-0.22117&deg;at9.0 miles11E Offsite3.48+/-0.253.60+/-0.153.70+/-0.204.33+/-0.32160&deg;at7.2 miles12F- Offsite3.65+/-0.213.72+/-0.253.93+/-0.234.27+/-0.27190&deg;at7.7 miles13G Offsite3.86+/-0.173.66+/-0.234.06+/-0.234.21+/-0.31225&deg;at5.3 miles14*DeMass Rd SW Oswego - Control3.78+/-0.223.61+/-0.184.01+/-0.164.42+/-0.23227&deg;at12.5 miles15*Pole 66 W Boundary - Bible Camp3.54+/-0.183.34+/-0.173.61+/-0.143.95+/-0.18240&deg;at0.9 miles18*Energy Info Center - Lamp Post SW4.29+/-0.224.00+/-0.154.44+/-0.174.69+/-0.22268&deg;at0.4 miles19East Boundary - JAF Pole 94.20+/-0.233.84+/-0.174.30+/-0.204.59+/-0.2881&deg;at1.3 miles23*H Onsite4.50+/-0.214.55+/-0.184.91+/-0.175.32+/-0.2773&deg;at0.8 miles24I Onsite3.95+/-0.223.95+/-0.204.19+/-0.174.43+/-0.2598&deg;at0.8 miles25J Onsite3.93+/-0.183.71+/-0.274.05+/-0.214.51+/-0.30110&deg;at0.9 miles26K Onsite3.81+/-0.223.76+/-0.194.01+/-0.184.29+/-0.26132&deg;at0.5 miles27N Fence N of Switchyard JAF17.05+/-1.1017.42+/-0.8417.81+/-1.0820.37+/-0.8360&deg;at0.4 miles28N Light Pole N of Screenhouse JAF20.59+/-1.1724.47+/-2.1719.71+/-1.9423.97+/-1.5768&deg;at0.5 miles29N Fence N of W Side20.25+/-1.5522.79+/-0.8220.20+/-1.6021.55+/-1.4565&deg;at0.5 miles30N Fence (NW) JAF10.36+/-0.7011.27+/-0.6710.46+/-0.7611.88+/-0.5657&deg;at0.4 miles31N Fence (NW) NMP-17.10+/-0.366.92+/-0.236.88+/-0.317.12+/-0.41276&deg;at0.2 miles39N Fence Rad Waste-NMP-111.22+/-0.6311.84+/-0.4710.35+/-0.3910.37+/-0.57292&deg;at0.2 miles47N Fence (NE) JAF5.91+/-0.256.75+/-0.375.99+/-0.236.81+/-0.3869&deg;at0.6 miles49*Phoenix NY-Control3.24+/-0.233.56+/-0.193.62+/-0.183.78+/-0.26168&deg;at19.7 miles51Liberty & Bronson Sts E of OSS3.83+/-0.163.88+/-0.194.12+/-0.244.32+/-0.30233&deg;at7.4 miles52E 12th & Cayuga Sts Oswego School3.44+/-0.223.66+/-0.163.84+/-0.194.03+/-0.26227&deg;at5.8 miles53Broadwell & Chestnut Sts Fulton HS3.85+/-0.194.25+/-0.214.15+/-0.174.35+/-0.33183&deg;at13.7 miles54Liberty St & Co Rt 16 Mexico HS3.36+/-0.183.66+/-0.143.65+/-0.164.06+/-0.25115&deg;at9.3 miles55Gas Substation Co Rt 5-Pulaski3.53+/-0.213.83+/-0.183.67+/-0.194.09+/-0.2375&deg;at13.0 miles56*Rt 104-New Haven Sch (SE Corner)3.22+/-0.203.79+/-0.233.71+/-0.204.07+/-0.22124&deg;at5.2 miles58*Co Rt 1A-Alcan (E of E Entrance Rd)3.66+/-0.194.01+/-0.174.21+/-0.174.51+/-0.25222&deg;at3.0 miles75*Unit 2 N Fence N of Reactor Bldg7.18+/-0.367.83+/-0.367.29+/-0.427.46+/-0.36354&deg;at0.1 miles76*Unit 2 N Fence N of Change House5.67+/-0.465.73+/-0.195.64+/-0.256.04+/-0.2725&deg;at0.1 miles77*Unit 2 N Fence N of Pipe Bldg6.04+/-0.265.97+/-0.206.14+/-0.256.37+/-0.2636&deg;at0.2 milesTABLE 6-10DIRECT RADIATION MEASUREMENT RESULTS - 2013Results in Units of mrem/std. Month  +/-  1 SigmaFIRST QUARTERSECONDQUARTERTHIRD QUARTERFOURTHQUARTERDEGREES & DISTANCE (1)(1) Direction and distance based on NMP-2 reactor centerline.
* TLD required by ODCM 6 - 25LOCATIONNUMBER78*JAF E of E Old Lay Down Area3.85+/-0.194.15+/-0.154.48+/-0.254.61+/-0.2285&deg;at1.0 miles79*Co Rt 29 Pole #63 0.2 mi S of Lake Rd3.55+/-0.193.79+/-0.163.76+/-0.154.01+/-0.25120&deg;at1.2 miles80*Co Rt 29 Pole #54 0.7 mi S of Lake Rd3.69+/-0.183.97+/-0.153.79+/-0.214.23+/-0.28136&deg;at1.5 miles81*Miner Rd Pole #16 0.5 mi W of Rt 293.67+/-0.243.82+/-0.153.65+/-0.204.39+/-0.23160&deg;at1.6 miles82*Miner Rd Pole # 1-1/2 1.1 mi W of Rt 293.65+/-0.253.74+/-0.153.74+/-0.204.17+/-0.24180&deg;at1.6 miles83*Lakeview Rd Tree 0.45 mi N of Miner Rd3.46+/-0.173.63+/-0.243.78+/-0.174.00+/-0.22203&deg;at1.2 miles84*Lakeview Rd N Pole #6117 200ft N of Lake Rd3.66+/-0.203.82+/-0.163.81+/-0.164.25+/-0.22225&deg;at1.1 miles85*Unit 1 N Fence N of W Side of Screen House9.99+/-0.4910.39+/-0.479.32+/-0.479.75+/-0.46292&deg;at0.2 miles86*Unit 2 N Fence N of W Side of Screen House8.29+/-0.608.28+/-0.467.90+/-0.468.22+/-0.47311&deg;at0.1 miles87*Unit 2 N Fence N of E Side of Screen House8.21+/-0.388.49+/-0.458.04+/-0.418.23+/-0.45333&deg;at0.1 miles88*Hickory Grove Rd Pole #2 0.6 mi N of Rt 13.62+/-0.183.90+/-0.193.81+/-0.144.08+/-0.2097&deg;at4.5 miles89*Leavitt Rd Pole #16 0.4 mi S of Rt 13.78+/-0.214.19+/-0.204.04+/-0.194.48+/-0.25112&deg;at4.3 miles90*Rt 104 Pole #300 150 ft E of Keefe Rd3.54+/-0.183.96+/-0.163.75+/-0.144.13+/-0.26135&deg;at4.2 miles91*Rt 51A Pole #59 0.8 mi W of Rt 513.38+/-0.213.66+/-0.193.43+/-0.224.11+/-0.28157&deg;at4.9 miles92*Maiden Lane Rd Power Pole 0.6 mi S of Rt 1043.71+/-0.254.29+/-0.224.17+/-0.314.46+/-0.26183&deg;at4.4 miles93*Rt 53 Pole 1-1 120 ft S of Rt 1043.58+/-0.233.73+/-0.143.75+/-0.164.12+/-0.23206&deg;at4.4 miles94*Rt 1 Pole #82 250 ft E of Kocher Rd (Co Rt 63)3.24+/-0.223.52+/-0.113.49+/-0.143.87+/-0.32224&deg;at4.4 miles95*Alcan W access Rd Joe Fultz Blvd Pole #213.31+/-0.203.39+/-0.133.31+/-0.183.71+/-0.16239&deg;at3.7 miles96*Creamery Rd 0.3 mi S of Middle Rd Pole 1-1/23.44+/-0.153.65+/-0.223.66+/-0.193.96+/-0.24199&deg;at3.6 miles97*Rt 29 Pole #50 200ft N of Miner Rd3.36+/-0.273.90+/-0.143.68+/-0.194.07+/-0.20145&deg;at1.8 miles98Lake Rd Pole #145 0.15 mi E of Rt 293.72+/-0.204.01+/-0.133.86+/-0.214.23+/-0.22103&deg;at1.2 miles99NMP Rd 0.4 mi N of Lake Rd Env Station R13.75+/-0.234.23+/-0.184.03+/-0.194.37+/-0.1988&deg;at1.8 miles100Rt 29 & Lake Rd Env Station R23.82+/-0.214.17+/-0.213.85+/-0.214.42+/-0.22104&deg;at1.1 miles101Rt 29 0.7 mi S of Lake Rd Env Station R33.50+/-0.173.60+/-0.143.34+/-0.194.05+/-0.21132&deg;at1.5 miles102EOF/Env Lab Rt 176 E Driveway Lamp Post3.68+/-0.163.70+/-0.213.72+/-0.213.98+/-0.23175&deg;at11.9 miles103EIC East Garage Rd Lamp Post4.50+/-0.214.37+/-0.174.22+/-0.174.68+/-0.20267&deg;at0.4 miles104Parkhurst Rd Pole #23 0.1 mi S of Lake rd3.88+/-0.173.92+/-0.153.66+/-0.154.44+/-0.26102&deg;at1.4 miles105Lake view Rd Pole #36 0.5 mi S of Lake Rd3.94+/-0.194.02+/-0.213.91+/-0.224.11+/-0.26198&deg;at1.4 miles106Shoreline Cove W of NMP-1 Tree on W Edge5.00+/-0.274.94+/-0.225.06+/-0.245.10+/-0.24274&deg;at0.3 miles107Shoreline Cove W of NMP-1  30 ft SSW of #1064.86+/-0.254.89+/-0.224.85+/-0.214.95+/-0.30272&deg;at0.3 miles108Lake Rd Pole #142 300 ft E of Rt 29 S4.12+/-0.234.06+/-0.163.96+/-0.214.18+/-0.22104&deg;at1.1 miles109Tree North of Lake Rd 300 ft E of Rt 29 N4.18+/-0.314.07+/-0.154.11+/-0.244.25+/-0.34103&deg;at1.1 miles111State Route 38 Sterling NY - Control3.54+/-0.203.55+/-0.123.46+/-0.173.69+/-0.19166&deg;at26.4 miles112EOF/Env Lab Oswego County Airport3.80+/-0.223.73+/-0.203.76+/-0.203.77+/-0.18175&deg;at11.9 miles113Baldwinsville NY - Control3.78+/-0.223.78+/-0.193.44+/-0.203.84+/-0.23214&deg;at21.8 miles(1) Direction and distance based on NMP-2 reactor centerline.
* TLD required by ODCMResults in Units of mrem/std. Month  +/-  1 SigmaFIRST QUARTERSECONDQUARTERTHIRD QUARTERFOURTHQUARTERDEGREES & DISTANCE (1)TABLE 6-10 (Continued)DIRECT RADIATION MEASUREMENT RESULTS - 2013 6 - 26DateOthers f04/15/13< 0.591< 5.07< 6.491667 +/- 77.6< 5.96<LLD04/29/13< 0.721< 4.59< 5.771413 +/- 68.8< 4.56<LLD05/06/13< 0.742< 9.20< 6.651446 +/- 90.8< 10.4<LLD05/20/13< 0.684< 5.53< 6.771330 +/- 78.1< 4.86<LLD06/10/13< 0.656< 7.91< 7.641437 +/- 79.8< 6.83<LLD06/24/13< 0.763< 6.32< 6.841457 +/- 74.5< 5.97<LLD07/08/13< 0.733< 9.41< 6.651455 +/- 90.6< 6.78<LLD07/22/13< 0.802< 8.21< 6.951602 +/- 85.9< 6.92<LLD08/05/13< 0.631< 9.00< 7.841438 +/- 92.6< 7.94<LLD08/19/13< 0.701< 5.46< 7.271555 +/- 95.1< 5.32<LLD09/09/13< 0.744< 6.20< 6.371549 +/- 76.5< 6.74<LLD09/23/13< 0.697< 4.77< 6.501324 +/- 65.7< 6.72<LLD10/07/13< 0.769< 4.40< 6.121309 +/- 67.0< 7.60<LLD10/21/13< 0.676< 5.12< 7.301601 +/- 85.5< 5.64<LLD11/04/13< 0.471< 5.12< 6.111376 +/- 93.9< 10.8<LLD11/18/13< 0.717< 5.62< 8.371580 +/- 85.3< 9.27<LLD12/04/13< 0.585< 9.76< 8.031483 +/- 95.7< 12.2<LLD12/18/13< 0.383< 4.33< 5.651421 +/- 67.9< 4.89<LLD
* Sample Location is required by the ODCM.  ** Sample Location is Optional*** Corresponds to sample location noted on Figure 3.3-4 f Plant related radionuclidesI-131Cs-134Cs-137Ba/La-140K-40CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2013Results in Units of pCi/liter  +/-  1 SigmaSample Location ** No. 55 ***TABLE 6-11 6 - 27DateOthers f04/15/13< 0.734< 6.86< 7.521531 +/- 97.1< 11.96<LLD04/29/13< 0.651< 8.50< 6.771697 +/- 87.9< 3.84<LLD05/06/13< 0.679< 5.82< 7.641459 +/- 82.2< 6.89<LLD05/20/13< 0.868< 3.81< 5.671494 +/- 69.6< 4.98<LLD06/10/13< 0.746< 7.86< 7.271307 +/- 90.6< 6.77<LLD06/24/13< 0.665< 7.91< 6.951609 +/- 86.6< 6.31<LLD07/08/13< 0.646< 3.75< 6.141483 +/- 68.6< 4.56<LLD07/22/13< 0.743< 4.14< 5.161462 +/- 69.7< 5.41<LLD08/05/13< 0.717< 3.70< 4.771513 +/- 69.7< 7.29<LLD08/19/13< 0.625< 4.39< 5.261526 +/- 70.3< 5.21<LLD09/09/13< 0.639< 6.34< 8.841522 +/- 96.9< 9.73<LLD09/23/13< 0.579< 7.43< 7.961536 +/- 82.8< 9.14<LLD10/07/13< 0.706< 9.05< 7.801570 +/- 84.2< 6.87<LLD10/21/13< 0.803< 4.35< 5.621552 +/- 71.0< 7.28<LLD11/04/13< 0.597< 3.89< 7.401506 +/- 69.6< 6.80<LLD11/18/13< 0.641< 6.26< 8.231366 +/- 93.8< 9.74<LLD12/04/13< 0.688< 4.64< 5.651630 +/- 73.3< 7.77<LLD12/18/13< 0.301< 4.85< 8.231458 +/- 95.7< 7.46<LLD
* Sample Location is required by the ODCM.  ** Sample Location is Optional*** Corresponds to sample location noted on Figure 3.3-4 f Plant related radionuclidesBa/La-140K-40I-131Cs-134Cs-137CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2013Results in Units of pCi/liter  +/-  1 SigmaSample Location
* No. 77 (Control) ***TABLE 6-11(Continued) 6 - 28Location ***DateDescriptionOthers fC2*09/10/13SQUASH LEAVES2041.0 +/- 53.52935.0 +/- 85.9 < 12.1 < 5.7 < 6.3 < 11.4< LLD09/10/13RHUBARB LEAVES327.5 +/- 30.84357.0 +/- 116.3 < 11.1 < 6.5 < 7.8 < 12.8< LLD09/10/13HORSERADISH LEAVES971.4 +/- 63.24623.0 +/- 175.2 < 15.0 < 13.2 < 15.5 < 38.3< LLDLocation ***DateDescriptionOthers f133 *09/09/13CAULIFLOWER LEAVES192.0 +/- 50.13953.0 +/- 163.0 < 17.4 < 14.7 < 18.5 < 24.3< LLD09/09/13RHUBARB LEAVES487.9 +/- 46.72971.0 +/- 123.7 < 13.4 < 11.2 < 12.4 < 20.7< LLD09/09/13HORSERADISH LEAVES481.7 +/- 46.73878.0 +/- 149.4 < 21.4 < 15.6 < 12.9 < 35.5< LLDLocation ***DateDescriptionOthers f144**09/09/13HORSERADISH LEAVES477.7 +/- 52.34178.0 +/- 165.3 < 15.5 < 17.6 < 14.6 < 47.8< LLD09/09/13BEAN LEAVES2839.0 +/- 72.43723.0 +/- 119.5 < 11.0 < 7.8 < 9.7 < 16.1< LLD09/09/13CABBAGE525.4 +/- 51.73524.0 +/- 148.9 < 14.5 < 19.5 < 14.3 < 36.0< LLDLocation ***DateDescriptionOthers f484*09/09/13RHUBARB LEAVES563.7 +/- 56.23380.0 +/- 175.8 < 15.4 < 12.4 < 14.4 < 46.9< LLD09/09/13HORSERADISH LEAVES959.6 +/- 62.75200.0 +/- 186.5 < 13.8 < 15.9 < 13.3 < 24.3< LLD09/09/13CABBAGE433.7 +/- 61.44142.0 +/- 189.3 < 15.6 < 12.7 < 13.8 < 47.3< LLDLocation ***DateDescriptionOthers f48**09/09/13GRAPE LEAVES2175.0 +/- 96.03327.0 +/- 173.0 < 23.6 < 12.4 < 16.9 < 47.1< LLD
* Sample Location Required by the ODCM  ** Sample location is optional
*** Corresponds to Sample Location noted on Figure 3.3-5 f Plant Related RadionuclidesBe-7K-40I-131Cs-134Cs-137Zn-65Be-7K-40I-131Cs-134Cs-137Zn-65CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2013Zn-65I-131Be-7K-40I-131Cs-137Results in Units of pCi/kg (wet) +/- 1 sigmaBe-7Cs-134I-131Cs-137Be-7TABLE 6-12Cs-134K-40Cs-137Cs-134Zn-65 Zn-65K-40 6 - 29 TABLE 6-13MILK ANIMAL CENSUS 2013 Town orArea(a)LocationDesignation (1)Degrees (2)Distance (2)(Miles)Number ofMilk Animals (Cows)New Haven64108
&deg;7.835Mexico 14 55*72 125&deg;97&deg;100&deg;9.1 8.8 9.6 50 55 38 Granby(Control)77**190&deg;16.060 MILKING ANIMAL TOTALS:  238  (including control locations) MILKING ANIMAL TOTALS:  178  (excluding control locations)NOTES:* 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 - 30 TABLE 6-14RESIDENCE CENSUS 2013MeteorologicalSectorLocationMap Location (1)Direction (2)Distance (2)N*---NNE*---NE*---ENE*---E80 Sunset Bay RoadA83&deg;1.04 milesESE161 Lake RoadB116&deg;0.70 milesSE1216 County Route 29C143&deg;1.07 milesSSE1146 County Route 29D152&deg;1.29 milesS268 Miner RoadE173&deg;1.59 milesSSW210 Lakeview RoadF213&deg;1.65 milesSW319 Lakeview RoadG230&deg;1.45 milesWSWBayshore DriveH242&deg;1.81 milesW*---WNW*---NW*---NNW*---NOTES:
* This meteorological sector is over Lake Ontario. There is no residence within five miles(1)Corresponds to Figure 3.3-6(2)Direction and distance are based on JAF 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. Mean1969f******
************1974f******
************1975f******
************1986<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1987<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD <LLD <LLD 0.027 0.027 0.027<LLD<LLD<LLD1994<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2010<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2011<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2012<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2013<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.f 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.Mean1969f******
************1974f******
************1975f******
************1986<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1987<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD <LLD <LLD 0.25 0.32 0.29<LLD<LLD<LLD1990<LLD <LLD <LLD 0.28 0.30 0.29<LLD<LLD<LLD1991<LLD <LLD <LLD 0.12 0.14 0.13<LLD<LLD<LLD1992<LLD <LLD <LLD 0.12 0.14 0.13<LLD<LLD<LLD1993<LLD <LLD <LLD 0.18 0.46 0.32<LLD<LLD<LLD1994<LLD <LLD <LLD 0.06 0.37 0.22<LLD<LLD<LLD1995<LLD <LLD <LLD 0.14 0.15 0.15<LLD<LLD<LLD1996<LLD <LLD <LLD 0.15 0.17 0.16<LLD<LLD<LLD1997<LLD <LLD <LLD 0.11 0.17 0.14<LLD<LLD<LLD1998<LLD <LLD <LLD 0.06 0.06 0.06<LLD<LLD<LLD1999<LLD <LLD <LLD 0.06 0.10 0.08<LLD<LLD<LLD2000<LLD <LLD <LLD 0.06 0.07 0.06<LLD<LLD<LLD2001<LLD <LLD <LLD 0.06 0.07 0.07<LLD<LLD<LLD2002<LLD <LLD <LLD 0.05 0.05 0.05<LLD<LLD<LLD2003<LLD <LLD <LLD 0.04 0.05 0.05<LLD<LLD<LLD2004<LLD <LLD <LLD 0.04 0.04 0.04<LLD<LLD<LLD2005<LLD <LLD <LLD 0.06 0.09 0.08<LLD<LLD<LLD2006<LLD <LLD <LLD 0.06 0.06 0.06<LLD<LLD<LLD2007<LLD <LLD <LLD 0.04 0.04 0.04<LLD<LLD<LLD2008<LLD <LLD <LLD
<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2010<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2011<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2012<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD2013<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.
f 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. Mean1969fNo DataNo DataNo Data1974f0.940.940.941975f<MDL<MDL<MDL19860.0210.0320.02519870.0170.0400.03119880.0230.0530.03419890.0280.0430.03419900.0330.0790.04519910.0210.0340.02919920.0190.0260.02219930.0300.0360.03319940.0140.0310.02219950.0170.0230.01919960.0180.0220.02019970.0120.0300.02119980.0130.0130.0131999<LLD<LLD<LLD20000.0210.0210.0212001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<LLD<LLD<LLD* Control location was at an area beyond the influence of the site (westerly direction).f 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. Mean1969f0.010.130.061974f0.084.400.571975f1.101.701.3819860.0090.0510.02819870.0240.0630.03319880.0220.0540.03219890.0200.0440.03419900.0270.0930.04019910.0180.0450.02919920.0140.0300.02419930.0180.0350.02819940.0150.0230.01919950.0160.0220.01919960.0160.0250.02019970.0140.0230.01819980.0210.0210.02119990.0180.0210.0202000<LLD<LLD<LLD2001<LLD<LLD<LLD20020.0160.0160.0162003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<LLD<LLD<LLD* Indicator locations are in the general area of the NMP-1 and J.A. FitzPatrick cooling water discharge structures.f 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 DATASURFACE WATERResults in pCi/literLOCATION:  CONTROL fIsotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969ff******1974ff******1975ff******1986<LLD<LLD<LLD<LLD<LLD<LLD1987<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<LLD<LLD<LLD<LLD<LLD<LLD* No gamma analysis performed (not required).f Location was the City of Oswego Water Supply for 1969-1984 and the Oswego Steam Station inlet canal for 1985-Present.ff 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 DATASURFACE WATERResults in pCi/literLOCATION:  INDICATOR fIsotope Cs-137 Co-60 Year Min.Max.Mean Min.Max.Mean1969ff******1974ff******1975ff******1986<LLD<LLD<LLD<LLD<LLD<LLD1987<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<LLD<LLD<LLD<LLD<LLD<LLD* No gamma analysis performed (not required).f Indicator location was the NMP 1 Inlet Canal for the period 1969-1973, and the JAF Inlet Canal for 1974-Present.ff 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 DATASURFACE WATER TRITIUMResults in pCi/literLOCATION:  CONTROL *IsotopeTritium Year Min. Max. Mean1969fNo DataNo DataNo Data1974f<MDL<MDL<MDL1975f31141436219862505503731987140270210198824046032019891432171861990260320290199118020019019921903102431993160230188199425025025019952302302301996<LLD<LLD<LLD1997<LLD<LLD<LLD1998190190190199922051036520001962372122001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<LLD<LLD<LLD* Control location is the City of Oswego, drinking water for 1969-1984 and the Oswego Steam Station inlet canal for 1985-Presen t.f 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 DATASURFACE WATER TRITIUMResults in pCi/literLOCATION:  INDICATOR *IsotopeTritium Year Min. Max. Mean1969fNo DataNo DataNo Data1974f3805004401975f12448233519862605003801987160410322198843048046019891352882251990220290250199125039031019922403002731993200280242199418026022019953203203201996<LLD<LLD<LLD19971601601601998190190190199918027023320001611981852001<LLD<LLD<LLD20022972972972003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<LLD<LLD<LLD* Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the JAF Inlet Canal for 1974-Present.f 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 - 10TABLE 7-9HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR PARTICULATE GROSS BETAResults in pCi/m 3LOCATION:  CONTROL *IsotopeGross Beta Year Min. Max. Mean1969f0.1300.5400.3341974f0.0010.8080.1211975f0.0080.2940.08519860.0080.2720.03919870.0090.0370.02119880.0080.0390.01819890.0070.0390.01719900.0030.0270.01319910.0070.0280.01419920.0060.0200.01219930.0070.0220.01319940.0080.0250.01519950.0060.0230.01419960.0080.0230.01419970.0060.0250.01319980.0040.0340.01419990.0100.0320.01720000.0060.0270.01520010.0060.0340.01620020.0080.0270.01620030.0040.0320.01520040.0080.0320.01620050.0080.0340.01920060.0070.0330.01620070.0080.0280.01620080.0070.0310.01520090.0070.0300.01620100.0040.0260.01420110.0080.0340.01820120.0050.0250.01620130.0060.0310.016* Locations used for 1977-1984 were C offsite, D1 offsite, D2 offsite, E offsite, F offsite, and G offsite. Control location R-5 offsitewas used for 1986-Present (formerly C offsite location).f 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 - 11TABLE 7-10HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR PARTICULATE GROSS BETAResults in pCi/m 3LOCATION:  INDICATOR *Isoto p eGross Beta Yea r Min.Max.Mean1969f0.1300.5200.3201974f0.0030.8850.0581975f0.0010.4560.06719860.0070.2890.03919870.0090.0400.02119880.0070.0400.01819890.0070.0410.01719900.0060.0230.01419910.0060.0330.01519920.0050.0240.01319930.0050.0230.01419940.0060.0240.01519950.0040.0310.01419960.0060.0250.01319970.0010.0180.01019980.0020.0400.01519990.0090.0390.01720000.0050.0330.01520010.0040.0370.01620020.0060.0260.01620030.0050.0350.01520040.0030.0360.01620050.0070.0410.01920060.0050.0350.01520070.0070.0280.01620080.0040.0300.01620090.0060.0320.01620100.0050.0300.01520110.0070.0340.01820120.0040.0310.01620130.0070.0320.016* Locations used for 1969-1973 were D1 onsite, D2 onsite, E onsite, F onsite and G onsite. Locations used for 1974-1984 were D 1onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite and K onsite, as applicable. 1986 - Present: locationswere R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.f 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 - 12TABLE 7-11HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATESResults in pCi/m 3LOCATION:  CONTROL **Isoto p eCs-137Co-60 Yea r Min.Max.Mean Min.Max.Mean1969f******1974f******1975f******19860.00750.03110.0193<LLD<LLD<LLD1987<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<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 monitoringlocation for 1985-Present.f 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 - 13TABLE 7-12HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATESResults in pCi/m 3LOCATION:  INDICATOR **Isoto p eCs-137Co-60 Yea r Min.Max.Mean Min.Max.Mean1969f******1974f******1975f******19860.00690.03640.0183<LLD<LLD<LLD1987<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD0.00480.00480.00482001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<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-1 through R-4 a irmonitoring locations for 1985-Present.f 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 - 14TABLE 7-13HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR RADIOIODINEResults in pCi/m 3LOCATION:  CONTROL *Isotope Iodine-131 Year Min. Max. Mean1969f******1974f******1975f<MDL<MDL<MDL19860.0410.3320.1511987<LLD<LLD<LLD1988<LLD<LLD<LLD1989<LLD<LLD<LLD1990<LLD<LLD<LLD1991<LLD<LLD<LLD1992<LLD<LLD<LLD1993<LLD<LLD<LLD1994<LLD<LLD<LLD1995<LLD<LLD<LLD1996<LLD<LLD<LLD1997<LLD<LLD<LLD1998<LLD<LLD<LLD1999<LLD<LLD<LLD2000<LLD<LLD<LLD2001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD20110.0340.0930.0552012<LLD<LLD<LLD 2013<LLD<LLD<LLD* Locations D1 offsite, D2 offsite, E offsite, F offsite and G offsite used for 1976-1984. Location R-5 offsite used for 1985-Present.** No results - I-131 analysis not required.
f 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP. Iodine concentrations attributed to fallout from Fukushima accident.
7 - 15TABLE 7-14HISTORICAL ENVIRONMENTAL SAMPLE DATAAIR RADIOIODINEResults in pCi/m 3LOCATION:  INDICATOR *Isotope Iodine-131 Year Min. Max. Mean1969f******1974f******1975f0.250.300.2819860.0230.3600.11919870.0110.0180.0141988<LLD<LLD<LLD1989<LLD<LLD<LLD1990<LLD<LLD<LLD1991<LLD<LLD<LLD1992<LLD<LLD<LLD1993<LLD<LLD<LLD1994<LLD<LLD<LLD1995<LLD<LLD<LLD1996<LLD<LLD<LLD1997<LLD<LLD<LLD1998<LLD<LLD<LLD1999<LLD<LLD<LLD2000<LLD<LLD<LLD2001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD20110.0210.110.0552012<LLD<LLD<LLD 2013<LLD<LLD<LLD* 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.f 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP. Iodine concentrations attributed to fallout from Fukushima accident.
7 - 16TABLE 7-15HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem/standard monthLOCATION:  CONTROL **
Year Min. Max.MeanPreopf1974f 1975f1976 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 2010 2011 2012 2013 (1)2.7 4.8 3.2 4.0 3.3 3.3 3.8 3.5 3.8 4.9 4.7 5.3 (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)*
 
3.4 (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)*
 
3.4 (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)*
 
2.8 (2.8)*
 
2.6 (2.6)*
 
3.6 (3.6)*
 
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 8.2 7.5 (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)*
 
4.6 (4.6)*
 
5.5 (5.5)*
 
5.0 (5.0)*
 
4.9 (4.9)*
(1)5.6 5.5 5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.2 6.3 (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)*
 
3.9 (3.9)*
 
4.0 (4.1)*
 
4.0 (4.2)*
 
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.
f 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for JAFNP P.
7 - 17TABLE 7-16HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION:  SITE BOUNDARY **
Yea r Min.Max.MeanPreopf***1974f***1975f***19865.46.85.919874.75.95.319885.06.15.419894.55.24.819904.55.44.819914.35.54.819923.74.64.219933.84.84.319942.84.94.019953.55.14.419963.25.34.119973.55.94.619983.75.14.419993.37.54.720003.66.84.520013.65.34.520023.55.14.320033.24.94.320043.36.44.420053.44.84.220063.54.74.120073.25.44.320083.24.84.020093.14.53.920103.34.33.920113.15.34.120123.64.84.120133.54.73.9* 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 boundary is thelakeshore and is considered to be generally not accessible to the public. These locations are not used in the site boundary do sedetermination.f 1969 data is considered to be pre-operational for the site. 1974 and 1975 data is considered to be pre-operational for the JAFNPP.** TLD's used for statistics: 7, 18, 78, 79, 80, 81, 82, 83 & 84.
7 - 18TABLE 7-17HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION:  OFFSITE SECTORS **
Year Min. Max.MeanPreopf***1974f***1975f***19864.68.66.019874.36.05.219883.87.05.319892.56.84.919903.66.34.719913.65.84.719922.95.04.119933.46.34.519943.05.14.019953.25.24.319963.25.34.219973.55.84.419983.55.04.219993.65.64.420003.46.64.520013.65.44.420023.15.34.220033.44.84.120043.26.74.420053.24.74.020063.34.44.020073.15.14.220083.24.53.820093.34.53.920103.04.43.920113.05.34.020123.54.64.020133.24.53.8* Data not available (not required prior to 1985).** Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95.
f 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 - 19TABLE 7-18HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION:  SPECIAL INTEREST **
Year Min. Max.MeanPreopf***1974f***1975f***19864.88.26.119873.56.05.119883.96.65.319892.16.44.919903.26.34.819912.95.64.419923.04.84.119933.25.84.519942.94.84.119953.64.84.219963.25.14.219973.56.24.619983.75.64.419993.67.14.620003.67.34.720013.85.44.420023.55.54.220033.45.54.320043.05.94.220053.45.14.120063.55.34.120073.05.84.320083.15.14.020093.14.53.820103.24.73.920112.94.94.020123.44.74.020133.24.53.8* Data not available (not required prior to 1985).** Includes TLD numbers 15, 56, 58, 96, 97 and 98.
f 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 - 20TABLE 7-19HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION:  ONSITE INDICATOR **
Year Min. Max.MeanPreopf***1974f3.110.65.71975f4.616.07.319864.716.17.019874.011.45.819884.411.96.019892.713.16.019903.612.95.519913.211.65.419923.25.64.319933.113.65.219942.814.35.119953.528.66.219963.132.66.419973.528.88.119983.628.86.219993.328.46.620003.716.55.620013.814.55.620023.513.65.320033.212.95.320043.313.25.420053.414.15.420063.514.45.320073.214.85.620083.213.85.220093.113.64.920103.313.34.820113.113.05.120123.511.84.920133.312.25.0* 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)
.f 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 - 21TABLE 7-20HISTORICAL ENVIRONMENTAL SAMPLE DATAENVIRONMENTAL TLDResults in mrem per standard monthLOCATION:  OFFSITE INDICATOR **
Year Min. Max.MeanPreopf***1974f2.48.95.31975f4.57.15.519865.07.66.119874.46.65.219884.26.65.419892.86.44.619903.86.14.819913.45.84.519923.15.24.119933.25.75.019943.05.14.119953.95.74.419963.35.54.119973.76.24.719983.95.64.519993.87.14.620003.87.34.620013.75.94.620023.65.54.420033.15.54.420043.26.54.520053.65.14.220063.95.34.220073.44.94.320083.34.54.020093.34.13.820103.54.03.720113.24.84.020123.64.34.020133.54.33.9* No data available.** Includes TLD numbers 9, 10, 11, 12 and 13.f 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 - 22TABLE 7-21HISTORICAL ENVIRONMENTAL SAMPLE DATAMILKResults in pCi/literLOCATION:  CONTROL **Isotope Cs-137 I-131 Year Min.Max.Mean Min.Max.Mean1969f******1974f******1975f******19865.312.48.40.829.013.61987<LLD<LLD<LLD<LLD<LLD<LLD1988<LLD<LLD<LLD<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD<LLD<LLD<LLD1998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<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 from the site
.f 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 - 23TABLE 7-22HISTORICAL ENVIRONMENTAL SAMPLE DATAMILKResults in pCi/literLOCATION:  INDICATORIsotope Cs-137 I-131 Year Min.Max.Mean Min.Max.Mean1969f******1974f1.63910.50.702.001.231975f6.022160.012.990.3719866.111.18.60.330.05.219875.59.47.4<LLD<LLD<LLD198810.010.010.0<LLD<LLD<LLD1989<LLD<LLD<LLD<LLD<LLD<LLD1990<LLD<LLD<LLD<LLD<LLD<LLD1991<LLD<LLD<LLD<LLD<LLD<LLD1992<LLD<LLD<LLD<LLD<LLD<LLD1993<LLD<LLD<LLD<LLD<LLD<LLD1994<LLD<LLD<LLD<LLD<LLD<LLD1995<LLD<LLD<LLD<LLD<LLD<LLD1996<LLD<LLD<LLD<LLD<LLD<LLD1997<LLD<LLD<LLD0.250.440.351998<LLD<LLD<LLD<LLD<LLD<LLD1999<LLD<LLD<LLD<LLD<LLD<LLD2000<LLD<LLD<LLD<LLD<LLD<LLD2001<LLD<LLD<LLD<LLD<LLD<LLD2002<LLD<LLD<LLD<LLD<LLD<LLD2003<LLD<LLD<LLD<LLD<LLD<LLD2004<LLD<LLD<LLD<LLD<LLD<LLD2005<LLD<LLD<LLD<LLD<LLD<LLD2006<LLD<LLD<LLD<LLD<LLD<LLD2007<LLD<LLD<LLD<LLD<LLD<LLD2008<LLD<LLD<LLD<LLD<LLD<LLD2009<LLD<LLD<LLD<LLD<LLD<LLD2010<LLD<LLD<LLD<LLD<LLD<LLD2011<LLD<LLD<LLD<LLD<LLD<LLD2012<LLD<LLD<LLD<LLD<LLD<LLD2013<LLD<LLD<LLD<LLD<LLD<LLD* No data available (sample not required).f 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 - 24TABLE 7-23HISTORICAL ENVIRONMENTAL SAMPLE DATAFOOD PRODUCTSResults in pCi/g (wet)LOCATION:  CONTROL *Isotope Cs-137 Year Min. Max. Mean1969f******1974f******1975f******1986<LLD<LLD<LLD1987<LLD<LLD<LLD1988<LLD<LLD<LLD1989<LLD<LLD<LLD1990<LLD<LLD<LLD1991<LLD<LLD<LLD1992<LLD<LLD<LLD19930.0080.0080.0081994<LLD<LLD<LLD1995<LLD<LLD<LLD1996<LLD<LLD<LLD1997<LLD<LLD<LLD1998<LLD<LLD<LLD1999<LLD<LLD<LLD2000<LLD<LLD<LLD2001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<LLD<LLD<LLD* Locations was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.** No data available (control samples not required).f 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 - 25TABLE 7-24HISTORICAL ENVIRONMENTAL SAMPLE DATAFOOD PRODUCTSResults in pCi/g (wet)LOCATION:  INDICATOR *Isotope Cs-137 Year Min. Max. Mean1969f******1974f0.040.340.1421975f<MDL<MDL<MDL1986<LLD<LLD<LLD1987<LLD<LLD<LLD19880.0080.0080.00819890.0110.0110.0111990<LLD<LLD<LLD19910.0390.0390.0391992<LLD<LLD<LLD1993<LLD<LLD<LLD19940.0060.0120.01019950.0110.0120.0121996<LLD<LLD<LLD19970.0130.0130.0131998<LLD<LLD<LLD19990.0070.0070.0072000<LLD<LLD<LLD2001<LLD<LLD<LLD2002<LLD<LLD<LLD2003<LLD<LLD<LLD2004<LLD<LLD<LLD2005<LLD<LLD<LLD2006<LLD<LLD<LLD2007<LLD<LLD<LLD2008<LLD<LLD<LLD2009<LLD<LLD<LLD2010<LLD<LLD<LLD2011<LLD<LLD<LLD2012<LLD<LLD<LLD2013<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).f 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 James A.FitzPatrick Nuclear Power Plant (JAF) Environmental Laboratory has engaged the services of Eckert& Ziegler Analytics, Incorporated in Atlanta, Georgia.Eckert & Ziegler Analytics supplies sample media as blind sample spikes, which contain certifiedlevels of radioactivity unknown to the analysis laboratory. These samples are prepared andanalyzed by the JAF Environmental Laboratory using standard laboratory procedures. Eckert &
Ziegler Analytics issues a statistical summary report of the results. The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory'sperformance.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 SCHEDULETable 8-1SAMPLEMEDIALABORATORYANALYSISSAMPLE PROVIDERECKERT & ZIEGLERANALYTICSWaterGross Beta3WaterTritium3WaterI-1312WaterMixed Gamma2AirGross Beta2AirI-1312AirMixed Gamma2MilkI-1312MilkMixed Gamma2SoilMixed Gamma1VegetationMixed Gamma1TOTAL SAMPLE INVENTORY228.3ACCEPTANCE CRITERIAEach sample result is evaluated to determine the accuracy and precision of the laboratory's analysisresult. The sample evaluation method is discussed below.8.3.1SAMPLE RESULTS EVALUATIONSamples provided by Eckert & ZieglerAnalytics are evaluated using what is specified as theNRC 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 (referenceresult).
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 8-2ERROR 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 criteriaare contained in Procedure EN-CY-102, Laboratory Analytical Quality Control. 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 InterlaboratoryComparison Program. This method is used as the procedurally required assessment methodand requires the generation of a deviation from QA/QC program report when results are unacceptable.
8-48.4 PROGRAM RESULTS
 
==SUMMARY==
The Interlaboratory Comparison Program numerical results are provided on Table 8-3.8.4.1ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTSTwenty two QA blind spike samples were analyzed as part of Eckert & Ziegler Analytics2013Interlaboratory Comparison 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 86 individual analyses on the 22 QAsamples. Of the 86 analyses performed, 86 were in agreement using the NRC acceptancecriteria for a 100 % agreement ratio.
8-5TABLE 8-3INTERLABORATORY INTERCOMPARISON PROGRAMGross Beta Analysis of Air Particulate FilterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi +/-1 sigmaREFERENCELAB*pCi +/-1 sigmaRATIO (1)06/13/2013E10568FilterGROSSBETA98.9 +/- 1.094.6 +/- 1.581.05 A101.3 +/- 1.098.5 +/- 1.0Mean =99.6 +/- 0.612/05/2013 E10751AFilterGROSSBETA102.5 +/- 1.0 96+/-1.6 1.06 A102.2 +/- 1.0100.7 +/- 1.0Mean =101.8 +/- 0.6(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=AcceptableU=UnacceptableTABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMTritium Analysis of WaterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCELAB*pCi/liter +/-1 sigmaRATIO (1)3/14/2013E10490WaterH-34305 +/- 1584920 +/- 82.20.92 A4490 +/- 1564781 +/- 161Mean =4525 +/- 916/13/2013E10567WaterH-31106 +/- 124948 +/- 15.81.05 A919 +/- 122965 +/- 123Mean =997 +/- 719/12/2013E10614WaterH-3830 +/- 122965 +/- 16.10.88 A765 +/- 122700 +/- 120828 +/- 118871 +/- 119800 +/- 1181024 +/- 122908 +/- 120889 +/- 120Mean =846 +/- 40(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=AcceptableU=Unacceptable 8-6TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGross Beta Analysis of WaterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)03/14/2013E10493WaterGROSSBETA 276.5 +/- 2.6300.0 +/- 5.00.92 A 279.2 +/- 2.6 276.4 +/- 2.6Mean = 277.4 +/- 1.506/13/2013E10573WaterGROSSBETA 264.6 +/- 2.6294.0 +/- 4.90.90 A 265.3 +/- 2.6 266.0 +/- 2.6Mean = 265.3 +/- 1.509/12/2013E10619WaterGROSSBETA 244.4 +/- 2.3267.0 +/- 4.50.91 A 244.4 +/- 2.3 241.3 +/- 2.3Mean = 243.4 +/- 1.3(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=Acceptable U=UnacceptableINTERLABORATORY INTERCOMPARISON PROGRAMI-131 Gamma Analysis of Air CharcoalDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi +/-1 sigmaREFERENCE LAB*pCi +/-1 sigmaRATIO (1)6/13/2013E10571Air I-131 92.8 +/- 2.5789.5 +/- 1.491.04 A 96.8 +/- 3.1 89.5 +/- 3.02Mean = 93.0 +/- 1.689/12/2013E10618Air I-131 81.9 +/- 3.2179.8 +/- 1.330.99 A 78.1 +/- 2.99 77.8 +/- 3.03Mean = 79.3 +/- 1.78(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=Acceptable U=Unacceptable 8-7TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of WaterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)3/14/2013 E10491WaterCe-141 95 +/- 5.9497 +/- 1.621.02A102 +/- 7.24100 +/- 5.57Mean =99+/-3.63Cr-51260 +/- 26.30244 +/- 4.071.04A245 +/- 32.10254 +/- 25.50Mean = 253
+/-16.24 Cs-134107 +/- 7.58110.0 +/- 1.840.94A 95 +/- 10.80107 +/- 8.34Mean = 103
+/-5.20 Cs-137137 +/- 4.53137 +/- 2.290.97A129 +/- 5.88134 +/- 4.73Mean = 133
+/-2.93Co-58105 +/- 4.12107.0 +/- 1.791.03A113 +/- 5.74113 +/- 4.46Mean = 110.3 +/- 2.79Mn-54116 +/- 4.27107 +/- 1.791.03A105 +/- 5.76110 +/- 4.56Mean = 110.3 +/- 2.83Fe-59138 +/- 5.51130.0 +/- 2.171.09A141 +/- 7.36146 +/- 5.89Mean = 141.7 +/- 3.64Zn-65162 +/- 7.98155 +/- 2.591.08A165 +/- 10.60175 +/- 8.86Mean = 167.3 +/- 5.32Co-60207 +/- 4.12206 +/- 3.441.00A196 +/- 5.44212 +/- 4.47Mean = 205.0 +/- 2.72 I-131**60.3 +/- 1.0250.0 +/- 0.8351.20A58.2 +/- 1.10 61 +/- 1.02Mean = 59.8 +/- 0.60(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 8-8TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of WaterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)9/12/2013E10615WaterCr-51244+/-22.42.51E+02 +/- 4.18E+00 0.95A233+/-23.6267+/-22.2206+/-26.1 Mean =237.5+/-11.8 Cs-134133+/-7.21.56E+02 +/- 2.60E+00 0.92A147+/-6.8145+/-7.3151+/-5.7 Mean =144.0+/-3.4 Cs-137117+/-3.51.18E+02 +/- 1.97E+00 0.97A123+/-3.6111+/-3.6109+/-4.5 Mean =115.0+/-1.9Co-5898+/-3.59.73E+01 +/- 1.62E+00 1.01A98+/-3.2102+/-3.696+/-4.3 Mean =98.7+/-1.8Mn-54141+/-3.81.25E+02 +/- 2.09E+00 1.08A142+/-3.9131+/-3.9126+/-4.9 Mean =135.0+/-2.1Fe-59135+/-4.41.18E+02 +/- 1.97E+00 1.11A130+/-4.4127+/-4.7131+/-5.9 Mean =130.8+/-2.4Zn-65246+/-7.82.41E+02 +/- 4.02E+00 1.07A263+/-7.4269+/-8.2257+/-10.6 Mean =258.8+/-4.3Co-60186+/-3.21.77E+02 +/- 2.96E+00 1.04A180+/-3.2188+/-3.4179+/-4.3 Mean =183.3+/-1.8 I-131100+/-4.89.79E+01 +/- 1.63E+00 1.05A109+/-4.7100+/-4.3101+/-6.1 Mean =102.4+/-2.5 I-131**111+/-1.49.79E+01 +/- 1.63E+00 1.13 A109+/-1.6111+/-1.7 Mean =110.3+/-0.9(1) Ratio = Reported/Analytics.A=Acceptable* Sample provided by Analytics, Inc.U=Unacceptable** Result determined by Resin Extraction/Gamma Spectral Analysis.
8-9TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of MilkDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)6/13/2013 E10569MILKCe-141 88 +/- 5.490 +/- 1.510.97A 95 +/- 6.1 89 +/- 6.0 74 +/- 7.4 93 +/- 5.8Mean = 87.6 +/- 2.8Cr-51265 +/- 26.3250 +/- 4.181.05A260 +/- 27.4261 +/- 28.4267 +/- 34.0265 +/- 28.6Mean = 263.6 +/- 13.0 Cs-134121 +/- 8.7125 +/- 2.090.97A119 +/- 8.1123 +/- 8.4118 +/- 11.1127 +/- 8.4Mean = 121.6 +/- 4.0 Cs-137139 +/- 4.8151 +/- 2.520.95A147 +/- 4.7157 +/- 4.8137 +/- 6.0140 +/- 5.0Mean = 144.0 +/- 2.3Co-58 95 +/- 4.394 +/- 1.571.02A100 +/- 4.2101 +/- 4.1 88 +/- 5.5 94 +/- 4.4Mean = 95.7 +/- 2.0Mn-54175 +/- 5.4172 +/- 2.871.03A184 +/- 5.2177 +/- 5.2175 +/- 6.8171 +/- 5.4Mean = 176.4 +/- 2.5Fe-59126 +/- 5.8120 +/- 21.06A139 +/- 5.5122 +/- 5.3121 +/- 7.5129 +/- 5.9Mean = 127.4 +/- 2.7(Continued) 8-10TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of MilkDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/- 1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)6/13/2013E10569MIL KZN-65244 +/- 9.4 217+/-3.631.02A(Continued)228 +/- 9.4187 +/- 12.2218 +/- 10.3Mean = 221.8 +/- 4.6Co-60182 +/- 4.2175 +/- 2.931.02A182 +/- 3.9175 +/- 3.9168 +/- 5.2187 +/- 4.3Mean = 178.8 +/- 1.9 I-131 91 +/- 5.196 +/- 1.590.98A102 +/- 5.3 90 +/- 5.0 91 +/- 6.3 96 +/- 5.3Mean = 94.0 +/- 2.4 I-131**99 +/- 1.296 +/- 1.591.06A101 +/- 1.3104 +/- 1.4Mean = 101 +/- 0.8(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.A=Acceptable U=Unacceptable 8-11TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of MilkDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/liter +/-1 sigmaREFERENCE LAB*pCi/liter +/-1 sigmaRATIO (1)9/12/2013 E10617MILKCr-51253 +/- 36.60277 +/- 4.630.95A222 +/- 34.90313 +/- 31.50Mean = 262.7 +/- 19.86 Cs-134173 +/- 12.30172 +/- 2.880.98A171 +/- 12.20164 +/- 9.30Mean = 169.3 +/- 6.55 Cs-137131 +/- 5.97131 +/- 2.190.99A125 +/- 5.99135 +/- 4.70Mean = 130.3 +/- 3.23Co-58101 +/- 5.59108 +/- 1.81.00A113 +/- 6.11110 +/- 4.22Mean = 108.0 +/- 3.10Mn-54147 +/- 6.50139 +/- 2.321.08A164 +/- 6.59138 +/- 4.82Mean = 149.7 +/- 3.48Fe-59135 +/- 7.78130 +/- 2.181.11A152 +/- 7.96147 +/- 5.97Mean = 144.7 +/- 4.21Zn-65274 +/- 13.50266 +/- 4.451.04A244 +/- 13.60314 +/- 10.50Mean = 277.3 +/- 7.28Co-60200 +/- 5.64196 +/- 3.271.03A199 +/- 5.68204 +/- 4.15Mean = 201.0 +/- 3.01 I-131 99 +/- 7.1998.3 +/- 1.641.00A 94 +/- 7.49103 +/- 6.29Mean = 98.7 +/- 4.05 I-131**102 +/- 1.3898.3 +/- 1.641.05A103 +/- 1.79106 +/- 1.86Mean = 103.7 +/- 0.98(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.** Result determined by Resin Extraction/Gamma Spectral Analysis.
A=AcceptableU=Unacceptable 8-12TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Air Particulate FilterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi +/-1 sigmaREFERENCE LAB*pCi +/-1 sigmaRATIO (1)3/14/2013 E10492A FILTERCe-141118 +/- 3.62105 +/- 1.761.10A113 +/- 3.49115 +/- 3.41Mean = 115.3 +/- 2.03Cr-51296 +/- 20.00265 +/- 4.431.13A284 +/- 19.00319 +/- 21.00Mean = 299.7 +/- 11.56 Cs-134115 +/- 8.27120 +/- 2.010.93A105 +/- 8.12113 +/- 9.24Mean = 111.0 +/- 4.94 Cs-137155 +/- 4.36149 +/- 2.491.04A154 +/- 4.40155 +/- 4.84Mean = 154.7 +/- 2.62Co-58123 +/- 4.34117 +/- 1.951.07A121 +/- 4.27132 +/- 4.99Mean = 125.3 +/- 2.62Mn-54142 +/- 4.50117 +/- 1.951.19A135 +/- 4.40139 +/- 4.98Mean = 138.7 +/- 2.68Fe-59178 +/- 5.90142 +/- 2.371.21A170 +/- 5.85169 +/- 6.89Mean = 172.3 +/- 3.60Zn-65193 +/- 8.30169 +/- 2.821.17A194 +/- 8.78206 +/- 10.10Mean = 197.7 +/- 5.25Co-60237 +/- 4.39225.0 +/- 3.751.05A232 +/- 4.43240 +/- 5.09Mean = 236.3 +/- 2.68(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=AcceptableU=Unacceptable 8-13TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Air Particulate FilterDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi +/-1 sigmaREFERENCE LAB*pCi +/-1 sigmaRATIO (1)9/12/2013 E10616 FILTERCr-51274 +/- 18.00254 +/- 4.251.07A284 +/- 19.00252 +/- 18.90280 +/- 21.10Mean = 272.5 +/- 9.64 Cs-134147 +/- 8.41158 +/- 2.640.89A135 +/- 8.48141 +/- 9.24142 +/- 8.78Mean = 141.3 +/- 4.37 Cs-137122 +/- 4.00120 +/- 21.06A131 +/- 4.07129 +/- 4.21125 +/- 3.95Mean = 126.8 +/- 2.03Co-58109 +/- 3.8799 +/- 1.651.07A103 +/- 3.82109 +/- 4.22102 +/- 3.86Mean = 105.8 +/- 1.97Mn-54140 +/- 4.44127 +/- 2.131.11A137 +/- 4.48146 +/- 4.85143 +/- 4.50Mean = 141.5 +/- 2.29Fe-59153 +/- 5.73120 +/- 21.23A142 +/- 5.54148 +/- 6.28147 +/- 5.66Mean = 147.5 +/- 2.90Zn-65292 +/- 10.10244 +/- 4.081.20A291 +/- 10.20299 +/- 10.90294 +/- 10.10Mean = 294.0 +/- 5.17Co-60187 +/- 4.06180 +/- 31.07A192 +/- 4.09200 +/- 4.49194 +/- 4.02Mean = 193.3 +/- 2.08(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=AcceptableU=Unacceptable 8-14TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of SoilDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1)6/13/2013E10570SOILCe-1410.081+/-0.0180.098 +/- 0.0021.00A0.121+/-0.0200.097+/-0.0200.092+/-0.0210.082+/-0.025 Mean =0.098+/-0.009Cr-510.215+/-0.0820.271 +/- 0.0050.92A0.283+/-0.0830.297+/-0.0110.166+/-0.099 Mean =0.249+/-0.032 Cs-1340.132+/-0.0290.136 +/- 0.0021.11A0.155+/-0.0130.142+/-0.0150.135+/-0.0240.171+/-0.027 Mean =0.151+/-0.010 Cs-1370.218+/-0.0170.248 +/- 0.0050.92A0.242+/-0.0160.193+/-0.0160.242+/-0.0160.232+/-0.016 Mean =0.227+/-0.007Co-580.095+/-0.0130.102 +/- 0.0020.77A0.063+/-0.0120.074+/-0.0120.098+/-0.0130.079+/-0.013 Mean =0.078+/-0.006Mn-540.019+/-0.0160.186 +/- 0.0031.08A0.207+/-0.0150.178+/-0.0150.214+/-0.0160.204+/-0.015 Mean =0.201+/-0.007Fe-590.135+/-0.0180.130 +/- 0.0021.03A0.131+/-0.0180.115+/-0.0170.146+/-0.0180.141+/-0.020 Mean =0.133+/-0.008(Continued) 8-15TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of Soil (Continued)DATE SAMPLEID NO. MEDIUM ANALYSISJAF ELAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1)6/13/2013E10570SOILZn-650.221+/-0.0290.236 +/- 0.0041.06A(Continued)0.230+/-0.0240.284+/-0.0260.240+/-0.0240.243+/-0.026 Mean =0.249+/-0.012Co-600.172+/-0.0130.190 +/- 0.0030.93A0.175+/-0.0110.181+/-0.0110.163+/-0.0100.190+/-0.011 Mean =0.177+/-0.005(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=Acceptable U=Unacceptable 8-16TABLE 8-3 (Continued)INTERLABORATORY INTERCOMPARISON PROGRAMGamma Analysis of VegetationDATE SAMPLEID NO.MEDIUM ANALYSISJAF ELAB RESULTSpCi/g +/-1 sigmaREFERENCE LAB*pCi/g +/-1 sigmaRATIO (1)6/13/2013E10572VEGCe-1410.190+/-0.0130.215 +/- 0.0040.87A0.186+/-0.0150.197+/-0.0110.177+/-0.013 Mean =0.188+/-0.007Cr-510.583+/-0.0740.596 +/- 0.0100.87A0.569+/-0.0810.443+/-0.0620.482+/-0.071 Mean =0.519+/-0.036 Cs-1340.256+/-0.0290.298 +/- 0.0050.87A0.259+/-0.0250.260+/-0.0230.262+/-0.028Mean =0.259+/-0.013 Cs-1370.337+/-0.0150.259 +/- 0.0061.21A0.311+/-0.0140.318+/-0.0120.287+/-0.014 Mean =0.313+/-0.007Co-580.216+/-0.0140.224 +/- 0.0040.94A0.216+/-0.0120.199+/-0.0110.212+/-0.014 Mean =0.211+/-0.006Mn-540.429+/-0.0170.409 +/- 0.0070.95A0.374+/-0.0150.369+/-0.0140.387+/-0.017 Mean =0.390+/-0.008Fe-590.295+/-0.0190.285 +/- 0.0051.01A0.285+/-0.0180.297+/-0.0150.273+/-0.018 Mean =0.288+/-0.009Zn-650.494+/-0.0320.518 +/- 0.0090.97A0.495+/-0.0280.510+/-0.0270.509+/-0.031 Mean =0.502+/-0.015Co-600.373+/-0.0130.417 +/- 0.0070.92A0.402+/-0.0120.398+/-0.0110.361+/-0.013 Mean =0.384+/-0.006(1) Ratio = Reported/Analytics.* Sample provided by Analytics, Inc.A=AcceptableU=Unacceptable 8-1
 
==78.5 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., McGrawHill, 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 - 2.. . OJ16 0.05 0.0 4 0.03 5b ;;;:. u =-0.02 0.01 o --l-I-r l-I-l-I-l-I-e--L James A .. FitzPatrick N .P.P. r-Fish Cs-137 Figure 9.1 Q Q f1 f1 Q f1 o CONTR O L o IN DICA T OR l-* IN DICA T OR <L LD V A L UE t>CO NTR O L <L L D V A L UE Q Q Q Q Q Q Q Q Q f1 f1 f1 f1 f1 f1 f1 f1 f1 1992 1993 1994 1995 19% 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 9 - 3 400 350 300 250 ;;;; 200 'i. 150 100 50 o ,---f-f-r--f-l-I-f':.. James A. FitzPatrick N.P.P. l-f-Surface \Vaier -Tritium Figure 9.2 <j f':.. f':.. f':..
<j f':.. [J lN D I CA T OR o C O N TROL +lN D I C AT OR<L LD V A L U E c>C O NT R O L <L LD V A LUE <j <j <j <j <j <j <j f':.. f':.. f':.. f':.. f':.. f':.. f':.. f':..
1992 1 993 1 994 1995 1 996 1 997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 20ll 2012 2013 9 - 4<"" I: ;;;. u CI. 0.025 0.02 0.015 0.01 0.005 o , James A. FitzPatdck N.P.P. Ail" Particulate Filtel" -GI"OSS Beta FigUl"e 9.3 r--r---r--IJ INDICATOR IJ CONTRO L ,--r--I , 1987 1 988 1989 1 990 199 1 1997 1998 1 999 2000 200 1 2002 200 3 2004 2005 2006 200 7 2008 2009 2010 2011 2012 201 3 9 - 5;;;;. James A. FitzPatl'ick N.P.P. Ail' Pal'ticulate Filtel' -GI'OS S Beta FigUl'e 9.4 0.032 +1-------------------------
___1 I II . -II 0.022 I H '1 I R\ -+-lNDICA T OR CONTROL u 00 1 7 1 I lA' I I " 1/ Co .j ,\ ;r \'-Ii 0.0 1 2 I f c,<? If \\ /I {I '& \ C ( .. ; / .. Jr \' j I ,r ) \ / .. \ 7 I 0.002 1 2 3 4 5 6 7 8 9 to 11 12 1 3 1 4 1 5 16 17 18 19 20 21 22 23 2 4 25 26 Week No.
9 - 6 James A. FitzPatl"ick N.P.P. Ail' Particulate Filtel' -GI'OSS Beta FigUl"e 9.5 0.0 32 +I----------------------------l
-+-rNDlCATO R --{>-C ONTRO L 0.027 I" 9....... \ ( { I /I \1 r ""'\ I I 0.022 II \ , A "'5 ;;;. 0.0 17 r, # '1 I' \\ I \l I '\ 9 \ (]I OW: ()" U ---;Ir-' fl 0.012 +-t( '\ f A \" I' \\ n 0 {, j \, I C li , 0.00 7 1 --------'----------j 0.002 2 7 28 29 30 31 32 33 34 35 36 3 7 38 39 40 4 1 42 43 44 45 46 47 48 49 50 5 1 52 53 Week No.
9 - 7 0.006 0.005 0.004 ('"5 ;-.. o.ou' u . =.. fWO: 0.001 &deg; [J lND I CA TOR o CONT R O L -.lNDlCA T OR <LLD VALU E l>CONT R OL <LLD VALUE ! i i , i , ! t. t. t. t. t. t. t. , , , , , , James A.FitzPatrick N .P.P. Air Pal1iclliate Filter Composite Co-60 Figllre 9.6 t. t. t. t. t. t. , , , , , , , , t. t. t. t. t. t. t. t. , , , , , , , 1992 1993 1994 1995 1996 1997 1998 1 999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2000 2010 2011 2012 2013 9 - 8 , I I <><1 OJ <><1 T ::> f!5 .J ..: ..J T ;> ..: <><1 Cl ;> .J 0 ej ..J T 0< 0< ej <><1 0 .J 0 .J '"' '"' T ..: ..: <><1 Cl Cl I!i u "" u <><1 T [] 0 * <l -<><1 -<><1 -<><1 .,-<><1 .,-<><1 <><1 <><1 <><1 -<><1 -<><1 .,-<><1 i -', <><1 I <><1 T <><1 T <><1 f <><1 n 'n -;J"'j ---<:> 0 '"' 0 -r.j c; '" ci 0 ci ci clll/t)d 9 - 9'" I:: -;;0; U Q. 0.3 0) 0.1 o !;,. !;,. !;,. !;,. !;,. !;,. !;,. !;,.
James A. FitzPatrick N.P.P. !;,. Air Charcoal 1-131 Figure 9.8 !;,. !;,. !;,. !;,. o IN D I CA T OR D CONTROL .INDICAT O R <LLD V AL UE L;CONT R OL <L LD V A L UE F ukushima Accident / / !;,. !;,. !;,. !;,. !;,. !;,. !;,.
1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 1005 1006 2007 2008 2009 2010 20ll 2012 1013 9 - 10 ,c, g Ol N ::> 0 ..J ('-1 .: ..J :> .: 0 :> -'" ..J 0 t) ..J t) '" 0:: 0:: -0 ..J 0 ..J g '"' '"' .: .: 8 0 0 0 ;." u "" U ('-1 [] [] * <J '" 0 "-' N " '" '" c, 8 g .,-, '" 0 r-1 i '" n .:.: t-. 'c, '" "" 0 -.... g rh EQ f!:! E1 :::t ._ ..:.:d 01) 0 ;..= ('1 < '" '" "-' '" N IE 8 '" .., 0 N '" c,, '" (fJ 0, S: ,-C', '" '" '" C', -.,., "" '" .". 0, "" -g: 0, --00 '" .". (" C' -0 d d d II!:>d 9 - 11 0.4 iUS 0.3 0.25 '" U 0.2 0. 0.1 5 0.1 0.0 5 o --------t----------+---------+ .. _------+ .. James A. FitzPatrick N.P.P. Milk 1-131 Figure 9.10 [J IN DI C ATO R [J C ONTROL r-* IN DI C A TOR <L LD VALUE c.C O N TRPL <LLD V A LUE r-----t---------+---------+---------t---------f----------1;---------1---------+---------+---------+---------+----------4----------\--------"+--------+--------4---------1993 1994 1995 19% 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 9 - 12.James A. FitzPatrick N.P.P. TLD Data Figure 9.11 []COlltroi o Site Boundary 6.0 +1-------------------------------
-1 a Offsite
* Specials t " " " ii 2.0 1.0 0.0 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013}}

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