Text

Annual Radiological Environmental Operating Report
	ML061380740
Person / Time
Site:	FitzPatrick
Issue date:	05/10/2006
From:	; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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ML061380725	List: JAFP-06-0078, Annual Radiological Environmental Operating Report; ML061380731;
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1, 2005 - DECEMBER 31, 2005 FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT ENTERGY NUCLEAR FITZPATRICK, LLC (ENF)

ENTERGY NUCLEAR OPERATIONS, INC (ENO)

FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Program History 2-1 2.2 Site Description 2-2 2.3 Program Objectives 2-2 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection Methodology 3-6 3.2 Analyses Performed 3-11 3.3 Sample Locations 3-12 3.4 Land Use Census 3-25 3.5 Changes to the REMP Program 3-26 3.6 Deviation and Exceptions to the Program 3-26 3.7 Statistical Methodology 3-29 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-32 3.9 Regulatory Limits 3-34 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL 4-1 POSITION FORMAT 5.0 DATA EVALUATION AND DISCUSSION 5-1 5.1 Aquatic Program 5-6 5.2 Terrestrial Program 5-16 5.3 Conclusion 5-36 5.4 References 5-38 i

TABLE OF CONTENTS (Continued)

Page 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6-1 7.0 HISTORICAL DATA TABLES 7-1 8.0 QUALITY ASSURANCE/QUALITY CONTROL PROGRAM 8-1 9.0 GRAPHICAL PRESENTATIONS 9-1 ii

LIST OF TABLES Page Table 3.0-1 Required Sample Collection and Analysis 3-2 Table 3.3-1 Environmental Sample Locations 3-14 Table 3.8-1 Required Detection Capabilities For Environmental Sample Analysis, 3-33 Lower Limit of Detection (LLD)

Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary 4-2 Table 6-1 Concentration of Gamma Emitters in Shoreline Sediment Samples 6-2 Table 6-2 Concentration of Gamma Emitters in Fish Samples 6-3 Table 6-3 Concentration of Tritium Surface Water Samples 6-6 Table 6-4 Concentration of Gamma Emitters in Surface Water Samples 6-7 Table 6-5 Environmental Airborne Particulate Samples - Offsite Stations 6-12 Table 6-6 Environmental Airborne Particulate Samples - Onsite Stations 6-14 Table 6-7 Environmental Charcoal Cartridge Samples - Offsite Stations 6-16 Table 6-8 Environmental Charcoal Cartridge Samples - Onsite Stations 6-18 Table 6-9 Concentration of Gamma Emitters in Monthly Composites 6-20 Table 6-10 Direct Radiation Measurement Results 6-35 Table 6-11 Concentrations of Iodine-131 and Gamma Emitters in Milk 6-38 Table 6-12 Concentrations of Iodine-131 and Gamma Emitters in Food Products 6-40 Table 6-13 Milk Animal Census 6-41 Table 6-14 2005 Residence Census 6-42 Table 7-1,2 Historical Environmental Sample Data, Shoreline Sediment 7-2 Table 7-3,4 Historical Environmental Sample Data, Fish 7-4 Table 7-5,6 Historical Environmental Sample Data, Surface Water 7-6 Table 7-7,8 Historical Environmental Sample Data, Surface Water Tritium 7-8 Table 7-9,10 Historical Environmental Sample Data, Air Particulate Gross Beta 7-10 iii

LIST OF TABLES (Continued)

Page Table 7-11,12 Historical Environmental Sample Data, Air Radioiodine 7-12 Table 7-13,14 Historical Environmental Sample Data, Air Particulates 7-14 Table 7-15A,B Historical Environmental Sample Data, Environmental TLD 7-16 Table 7-16A-E Historical Environmental Sample Data, Environmental TLD 7-18 Table 7-17,18 Historical Environmental Sample Data, Milk 7-23 Table 7-19,20 Historical Environmental Sample Data, Food Products 7-25 Table 8-1 Interlaboratory Intercomparison Program Gross Beta, Tritium, Iodine & Gamma Analysis of Air, Water, Milk, Soil, Filter & Food Products 8-5 iv

LIST OF FIGURES Page Figure 3.3-1 New York State Map 3-19 Figure 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 Sediment 3-23 Sample Locations Map Figure 3.3-6 Nearest Residence Locations Map 3-24 Figure 9.1 Graph - Fish (Cs-137) 9-2 Figure 9.2 Graph - Surface Water Tritium 9-3 Figure 9.3 Graph - Airborne Particulate Gross Beta, Annual 9-4 Figure 9.4 Graph - Airborne Particulate Gross Beta, Weeks 1-26 (2004) 9-5 Figure 9.5 Graph - Airborne Particulate Gross Beta, Weeks 27-52 (2004) 9-6 Figure 9.6 Graph - Airborne Particulate Composite (Co-60) 9-7 Figure 9.7 Graph - Airborne Particulate Composite (Cs-137) 9-8 Figure 9.8 Graph - Airborne Radioiodine (I-131) 9-9 Figure 9.9 Graph - Milk (Cs-137) 9-10 Figure 9.10 Graph - Milk (I-131) 9-11 Figure 9.11 Graph - TLD Data 9-12 v

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published in accordance with the J.A. Fit zPatrick N.P.P. 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 15th of each year.

This report describes the Radiological Environmental Monitoring Program (REMP) program, the implementation of the program, and the results obtained as required by the Offsite Dose Calculation Manual (ODCM). The report also contains the analytical results tables, data evaluation, dose assessment, and data trends for each environmental sample media. Also included are results of the land use census, historical data and the Environmental Laboratorys performance in the Quality Assurance Intercomparison.

The REMP is a comprehensive surveillance program, which is implemented to assess the impact of 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 terrestrial pathways include airborne particulate and radioiodine, milk, food products and direct radiation.

During 2005 there were 2318 analyses performed on environmental media collected as part of the required monitoring program. These results demonstrated that there is no significant or measurable radiological impact from the operation of the FitzPatrick plant. Cesium-137 was detected in one aquatic pathway (shoreline sediment) at very low levels and was attributed to fallout from past weapons testing. The 2005 results for all pathways sampled are consistent with the previous five year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2005 Radiological Environmental Monitoring Program demonstrate that the routine operation at the James A. FitzPatrick site had no significant or measurable radiological impact on the environment. No elevated radiation levels were detected in the off-site environment as a result of the hydrogen injection program, the storage of radioactive waste, or the implementation of the Independent Spent Fuel Storage Installation. The results of the REMP continue to demonstrate that the operation of the plant did not result in a significant measurable dose to a member of the general population, or adversely impact the environment as a result of radiological effluents. The environmental program continues to demonstrate that the dose to a member of the public as a result of the operation of the James A. FitzPatrick Nuclear Power Plant remains significantly below the federally required dose limits specified in 10CFR20, 40CFR190 and 10CFR72.

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2.0 INTRODUCTION

The James A. FitzPatrick N.P.P. is owned and operated by Entergy Nuclear FitzPatrick, 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 2005.

2.1 PROGRAM HISTORY Environmental monitoring of the Nine Mile Point site has been on-going since 1964.

The program includes five years of pre-operational data, which was conducted prior to any reactor operations. In 1968, the Niagara Mohawk Power Company began the required preoperational environmental site testing program. This pre-operational data serves as a reference point to compare later data obtained during reactor operation. In 1969, the Nine Mile Point Unit 1 reactor, a 615 Megawatt Boiling Water Reactor (BWR) began full power operation. In 1975, the James A. FitzPatrick Nuclear Power Plant, owned and operated at that time by the New York Power Authority, began full power operation. The FitzPatrick Plant, an 881 Megawatt (Rated) BWR, occupies the east sector of the Nine Mile Point site, approximately 0.57 miles east of Nine Mile Point Unit 1. In 1988, The Nine Mile Point Unit 2 reactor, also owned and operated by Niagara Mohawk, began full power operation.

This 1207 Megawatt BWR is located between Unit 1 and FitzPatrick.

In 1985, the individual plant Effluent Technical Specifications were standardized to the generic Radiological 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 Program is shared, but each utility revi ews and publishes their own annual report. On November 21, 2000 the ownership and operation of the James A. FitzPatrick N.P.P.

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 07, 2001, the ownership of the Nine Mile Point Unit I and II facilities was transferred to Constellation Nuclear. These facilities are operated by Nine Mile Point Nuclear Station, LLC.

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In summary, three Boiling Water Reactors, which together generate 2703 Megawatts, have operated collectively at the Nine Mile site since 1988. A large database of environmental results from the exposure pathways have been collected and analyzed to evaluate the potential impact from reactor operations.

2.2 SITE DESCRIPTION The 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 J.A. FitzPatrick generating facility 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 18% of the land devoted to agriculture.

2.3 PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are to:

1. Measure and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.

2. Monitor natural radiation levels in the environs of the JAFNPP site.

3. Demonstrate compliance with the requirements of applicable federal regulatory agencies, including Technical Specifications and the Offsite Dose Calculation Manual.

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3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year. The James A FitzPatrick N.P.P. (JAFNPP) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

Shoreline Sediment

Fish

Surface Waters

Air

Milk

Food Products In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1. The JAF REMP sampling locations 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 (ICP). In addition to the participation in the ICP Program, sample splits are provided to the New York State Department of Health for cross checking purposes.

Sample collections for the radiological program are accomplished by a dedicated site environmental 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 contracted environmental engineering company, EA Engineering, Science and Technology, Inc. (EA).

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TABLE 3.0-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Sampling and Exposure Pathway Type and Frequency of Number of Samples (a) and Locations Collection Frequency and/or Sample (a) Analysis AIRBORNE Samples from 5 locations: Continuous sample Radioiodine Canisters:

Radioiodine operation with sample Analyze weekly for And Particulates

a. 3 Samples from off site locations in different sectors of the collection weekly or I-131.

highest calculated site average D/Q (based on all licensed site as required by dust reactors.). loading whichever is Particulate Samples:

more frequent. Gross beta radioactivity

b. 1 sample from the vicinity of a community having the highest following filter change (b) calculated site average D/Q (based on all licensed site reactors). composite (by location for gamma isotopic quarterly (as a

c. 1 sample from a control location 9 to 20 miles distant and in the minimum).

least prevalent wind direction(d) .

Direct Radiation(e) 32 stations with two or more dosimeters placed as follows: Quarterly Gamma dose monthly or quarterly

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 station in each of the land based sectors. There are 16 land based sectors in the inner ring, and 8 land based sectors in the outer ring.

c. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

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TABLE 3.0-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Sampling and Exposure Pathway Type and Frequency of Number of Samples (a) and Locations Collection Frequency and/or Sample (a) Analysis WATERBORNE

a. 1 sample upstream. (d) Composite sample Gamma isotopic analysis Surface(f) over a one month monthly. Composite for

b. 1 sample from the sites most downstream cooling water intake. period(g) . Tritium analysis quarterly(c).

1 sample from a downstream area with existing or potential Gamma isotopic analysis Sediment from recreational value. Twice per year semiannually(c).

Shoreline INGESTION

a. Samples from milk animals in 3 locations within 3.5 miles distant Twice per month, Gamma isotopic and I-131 Milk having the highest calculated site average D/Q. If there are none, April through analysis twice per month then 1 sample from milk animals in each of 3 areas 3.5 to 5.0 December (samples when milch animals are on miles distant having the highest calculated site average D/Q will be collected in pasture (April through (based on all licensed site reactors)(h). January through December); monthly (January March if I-131 is through March), if required(c).

b. 1 sample from milk animals at a control location (9 to 20 miles detected in November distant and in a less prevalent wind direction) (d) . and December of the preceding year).

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TABLE 3.0-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Sampling and Exposure Pathway (a) Type and Frequency of Number of Samples and Locations Collection Frequency and/or Sample (a) Analysis FISH

a. 1 sample of each of 2 commercially or recreationally important Twice per year. Gamma isotopic (c) analysis of species in the vicinity of a site discharge point. edible portions.

b. 1 sample of each of 2 species (same as in a. above or of a species with similar feeding habits) from an area at least 5 miles distant from the site(d) .

FOOD PRODUCTS

a. In lieu of the garden census as specified in Part 1, Section 5.2, Once during harvest Gamma isotopic(c) analysis of samples of at least 3 different kinds of broad leaf vegetation (such season. edible portions. (Isotopic to as vegetable) grown nearest each of two different off-site include I-131).

locations of highest predicted site average D/Q (based on all licensed site Reactors).

One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevalent wind direction sector(d) .

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NOTES 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 of choice at the most desired location or time. In these instances suitable alternative media and locations 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 historical data (specified in the ODCM) for all licensed site reactors.

(b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(c) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides 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 establish control locations in accordance with the distance and wind direction criteria, other sites, which provide valid background data, may be substituted.

(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.

(f) The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The "downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.

(g) Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure that a representative sample is obtained.

(h) A milk sampling location, as required in Table 3.0-1, is defined as a location having at least 10 milking cows present at a designated milk sample location. It has been found from past experience, 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 eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are 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.

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3.1 SAMPLE COLLECTION METHODOLOGY 3.1.1 SHORELINE SEDIMENTS One kilogram of shoreline sediment is collected at one area of existing or potential recreational value. One sample is also collected from a location beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately 1 inch. The samples are placed in plastic bags, sealed and shipped to the lab for analysis. Sediment samples are analyzed for gamma emitting radionuclides.

Shoreline sediment sample locations are shown in Section 3.3, Figure 3.3-5.

3.1.2 FISH Samples of available fish species that are commercially or recreationally important to Lake Ontario, such as Lake Trout, Salmon, Walleye and Smallmouth Bass, are collected twice per year, once in the spring and again in the fall.

Indicator samples are collected from a combination of the two on-site sample transects located off shore from the site. One set of control samples are collected at an off- site sample transect located off shore 8-10 miles west of the site.

Available species are selected using the following guidelines:

a. A minimum of two species that are commercially or recreationally important are to be collected from each sample location. Samples selected are limited to edible and/or sport species when available.

b. Samples are composed of 0.5 to 1 kilogram of the edible portion only.

Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis. Edible portions of each sample are analyzed for gamma emitting radionuclides. Fish collection locations are shown in Section 3.3, Figure 3.3-5.

3.1.3 SURFACE WATER Surface water samples are taken from the respective inlet canals of the James A.

Fitzpatrick Nuclear Power Plant (JAFNPP) and the NRCs Oswego Steam Station. The JAFNPP facility draws water from Lake Ontario on a continuous basis. This is used for the downstream or indicator sampling point for the Nine Mile Point site. The Oswego Steam 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 current patterns from the Oswego River located nearby.

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Samples from the JAFNPP facility are composited from automatic sampling equipment which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitters.

Samples from the Oswego Steam Station 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 emitting radionuclides.

A portion of the monthly sample from each of the locations is saved and composited to form quarterly composite samples, which are analyzed for tritium.

In addition to the sample results for the JAFNPP and Oswego Steam Station collection sites, data is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and from the City of Oswego drinking water supply.

The latter three locations are not required by the ODCM. These locations are optional sample points, which are collected 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.

3.1.4 AIR PARTICULATE / IODINE The air sampling stations required by the ODCM are located in the general area of the site boundary. The sampling stations are sited within a distance of 0.2 miles of the site boundary in sectors with the highest calculated deposition factor (D/Q) based on historical meteorological data. These stations (R-1, R-2, and R-3) are located in the E, ESE, and SE sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 Reactor Building. The ODCM also require that a fourth air sampling station be located in the vicinity of a year round community.

This station is located in the SE sector at a distance of 1.8 miles and is designated as Station R-4. A fifth station required by the ODCM is a control 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 On-Site 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 Off-Site in the southwest sector in the vicinity of the City of Oswego and is designated as Station G Off-Site. Three remaining 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 Off-Site Stations D2, E and F respectively.

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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. Sample volume 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 monthly by location and analyzed for gamma emitting radionuclides.

Air sampling station locations are shown in Section 3.3, Figures 3.3-2 and 3.3-3.

3.1.5 TLD (DIRECT RADIATION)

Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. Environmental TLDs are supplied and processed quarterly by the Areva/Framatome Environmental Laboratory. The laboratory utilizes a Panasonic based system using UD-814 dosimeters, which are constructed of rectangular teflon wafers impregnated with 25% CaSO4 :Dy phosphor. Each dosimeter contains three calcium sulfate elements and one lithium borate element.

A. Environmental TLDs Environmental TLDs are placed in five different geographical regions around site to evaluate 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 Geographical Description Category On-site TLDs placed at various locations within the Site Boundary, with three exceptions, are not required by the ODCM. (TLD locations comprising 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 Boundary An inner ring of TLDs placed in the general area of the Site Boundary in each of the sixteen meteorological sectors. This category is required by ODCM. (TLD locations comprising this group are: 7*, 18*, 23*, 75*, 76*, 77*, 78*, 79*, 80*, 81*, 82*,

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

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TLD Geographical Description Category Off-site Sector An outer ring of TLDs placed 4 to 5 miles from the site in each of the 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 Interest TLDs placed in Special Interest areas of high population density and use. These TLDs are located at or near large industrial sites, schools, or nearby towns or communities. This category is required by the ODCM. (TLD locations comprising this group are: 9, 10, 11, 12, 13, 15*, 19, 51, 52, 53, 54, 55, 56*, 58*, 96*,

97*, 98*, 99, 100, 101, 102, 108, and 109)

Control TLDs placed in areas beyond significant influence of the site and plant operations. These TLDs are located to the SW, S and NE of the site at distances of 12.6 to 24.7 miles. This category is also required by the ODCM. (TLD locations comprising this group are 8*, 14*, 49*, 111, 113)

TLD location required by the ODCM Although the ODCM require a total of 32 TLD stations, environmental TLDs are also placed at additional locations, not required by the ODCM, within the On-site, Special Interest and Control TLD categories to supplement the ODCM required direct radiation readings.

Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed in polyethylene packages to ensure dosimeter integrity and placed in open webbed plastic holders 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.

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B. 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) on site. 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 optional locations. Background data was collected starting in October 2000 at eight of the TLD locations 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 in polyethylene packages to ensure dosimeter integrity and placed in the field using a supporting structure such as a fence or other immovable object.

ISFSI TLD locations are shown in Section 3.3, Table 3.3.1.

3.1.6 MILK Milk samples are routinely collected from four farms during the sampling year.

These farms include three indicator locations and one control location. Samples are normally collected April through December of the sample year. If plant related radionuclides are detected in samples in November and December of the previous year, milk collections are continued into 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 until April of the sampling year. Milk samples were not collected in January through March of 2005 as there were no positive detections of plant related radionuclides in samples collected during November and December of 2004.

The ODCM also requires that a sample be collected from a control location nine to twenty miles from the site and in a less prevalent wind direction. This location is in the south sector 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 each sampled farm. Before the sample is drawn, the tank contents are agitated to assure a homogenous mixture of milk and butterfat. Two gallons are sampled from each indicator and control location at each collection. The samples are chilled, preserved and shipped fresh to the analytical laboratory within thirty-six hours of collection in insulated shipping 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 descriptio ns.)

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3.1.7 FOOD PRODUCTS (VEGETATION)

Food products are collected once per year during the late summer harvest season.

A minimum 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 also collected from available locations greater than 9.3 miles distant from the site in a less prevalent 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.

3.2 ANALYSES PERFORMED Environmental sample analyses are performed at the James A. FitzPatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory. The following samples are analyzed at the JAFNPP Environmental Lab:

Shoreline Sediment - gamma spectral analysis

Fish - gamma spectral analysis

Surface Water Monthly Composites - gamma spectral analysis, I-131

Surface Water Quarterly Composite - tritium

Air Particulate Filter - gross beta

Air Particulate Filter Composites - gamma spectral analysis

Airborne Radioiodine - gamma spectral analysis

Milk - gamma spectral analysis and I-131

Food Products (Vegetation) - gamma spectral analysis

Special Samples (soil, food products, bottom sediment, etc.) - gamma spectral analysis The analysis of Direct Radiation using Thermoluminescent Dosimeters (TLDs) is performed by a contractor laboratory - Areva/Framatome Environmental Laboratory.

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3.3 SAMPLE LOCATIONS Section 3.3 provides maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps.

This section also contains an environmental sample locatio n reference table (Table 3.3-1). This table contains the following information:

Sample Medium

Location designation, (this column contains the key for the sample location and is consistent with the designation on the sample location maps and on the sample results data tables).

Location description

Degrees and distance of the sample location from the site.

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3.3.1 LIST OF FIGURES Figure 3.3-1 New York State Map Figure 3.3-2 Off-Site Environmental Station and TLD Locations Map Figure 3.3-3 On-Site Environmental Station and TLD Locations Map Figure 3.3-4 Milk Sample and Surface Water Locations Map Figure 3.3-5 Nearest Residence (NMP), Food Product, Fish and Shoreline Sediment Sample Locations Map Figure 3.3-6 Nearest Residence (JAF) Locations Map 3-13

TABLE 3.3-1 2005 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE LOCATION DESCRIPTION DEGREES & DISTANCE (1)

MEDIUM DESIGNATION NUMBER Shoreline Sediment 05* Figure 3.3-5 Sunset Bay 82º at 1.4 miles 06 Figure 3.3-5 Langs Beach, Control 232° at 4.8 miles Fish 02* Figure 3.3-5 Nine Mile Point Transect 290° at 0.4 miles 03* Figure 3.3-5 FitzPatrick Transect 62° at 0.8 miles 00* Figure 3.3-5 Oswego Transect 236° at 5.9 miles Surface Water 03* Figure 3.3-4 FitzPatrick Inlet 54° at 0.6 miles 08* Figure 3.3-4 Oswego Steam Station Inlet 237° at 7.6 miles 09 Figure 3.3-4 NMP Unit 1 Inlet 319° at 0.3 miles 10 Figure 3.3-4 Oswego City Water 240° at 7.8 miles 11 Figure 3.3-4 NMP Unit 2 Inlet 336° at 0.3 miles Air Radioiodine and R-1* Figure 3.3-2 R-1 Station, Nine Mile Point Road 92° at 1.8 miles Particulates R-2* Figure 3.3-3 R-2 Station, Lake Road 107° at 1.1 miles R-3* Figure 3.3-3 R-3 Station, Co. Rt. 29 134° at 1.4 miles R-4* Figure 3.3-3 R-4 Station, Co. Rt. 29 145° at 1.8 miles R-5* Figure 3.3-2 R-5 Station, Montario Point 42° at 16.2 miles D-1 Figure 3.3-3 D1 On-Site Station 71° at 0.3 miles G Figure 3.3-3 G On-Site Station 245° at 0.7 miles H Figure 3.3-3 H On-Site Station 73° at 0.8 miles I Figure 3.3-3 I On-Site Station 95° at 0.8 miles J Figure 3.3-3 J On-Site Station 109° at 0.9 miles K Figure 3.3-3 K On-Site Station 132° at 0.5 miles G Figure 3.3-2 G Off-Site Station, Saint Paul Street 226° at 5.4 miles D-2 Figure 3.3-2 D2 Off-Site Station, Rt. 64 118° at 9.0 miles E Figure 3.3-2 E Off-Site Station, Rt. 4 162° at 7.1 miles F Figure 3.3-2 F Off-site Station, Dutch Ridge Road 192° 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.

Sample location required by ODCM 3 - 14

TABLE 3.3-1 (Continued) 2005 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE LOCATION DESCRIPTION DEGREES & DISTANCE (1)

MEDIUM DESIGNATION NUMBER Thermoluminescent 3 Figure 3.3-3 D1 Onsite 71° at 0.3 miles Dosimeters (TLD) 4 Figure 3.3-3 D2 Onsite 143° at 0.4 miles (Continued) 5 Figure 3.3-3 E Onsite 180° at 0.3 miles 6 Figure 3.3-3 F Onsite 213° at 0.5 miles 7* Figure 3.3-3 G Onsite 244° at 0.7 miles 8* Figure 3.3-2 R-5 Offsite Control 42° at 16.2 miles 9 Figure 3.3-2 D1 Offsite 80° at 11.4 miles 10 Figure 3.3-2 D2 Offsite 118° at 9.0 miles 11 Figure 3.3-2 E Offsite 162° at 7.1 miles 12 Figure 3.3-2 F- Offsite 192° at 7.7 miles 13 Figure 3.3-2 G Offsite 226° at 5.4 miles 14* Figure 3.3-2 DeMass Rd., SW Oswego - Control 227° at 12.5 miles 15* Figure 3.3-2 Pole 66, W. Boundary - Bible Camp 239° at 0.9 miles 18* Figure 3.3-3 Energy Info. Center - Lamp Post, SW 266° at 0.4 miles 19 Figure 3.3-2 East Boundary - JAF, Pole 9 83° at 1.4 miles 23* Figure 3.3-3 H Onsite 73° at 0.8 miles 24 Figure 3.3-3 I Onsite 95° at 0.8 miles 25 Figure 3.3-3 J Onsite 109° at 0.9 miles 26 Figure 3.3-3 K Onsite 132° at 0.5 miles 27 Figure 3.3-3 N. Fence, N. of Switchyard, JAF 60° at 0.4 miles 28 Figure 3.3-3 N. Light Pole,N. of Screenhouse, JAF 68° at 0.5 miles 29 Figure 3.3-3 N. Fence, N. of W. Side 65° at 0.5 miles 30 Figure 3.3-3 N. Fence, (NW) JAF 57° at 0.4 miles 31 Figure 3.3-3 N. Fence, (NW) NMP -1 279° at 0.2 miles 39 Figure 3.3-3 N. Fence, Rad. Waste-NMP-1 298° at 0.2 miles 47 Figure 3.3-3 N. Fence, (NE) JAF 69° at 0.6 miles 49* Figure 3.3-2 Phoenix, NY-Control 168° at 19.7 miles 51 Figure 3.3-2 Liberty & Bronson Sts., E of OSS 234° at 7.3 miles 52 Figure 3.3-2 E. 12th & Cayuga Sts., Oswego School 227° at 5.9 miles 53 Figure 3.3-2 Broadwell & Chestnut Sts. Fulton H.S. 183° at 13.7 miles (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.

Sample location required by ODCM 3 - 15

TABLE 3.3-1 (Continued) 2005 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE LOCATION DESCRIPTION DEGREES & DISTANCE (1)

MEDIUM DESIGNATION NUMBER Thermoluminescent 54 Figure 3.3-2 Gas Substation Co. Rt. 5-Pulaski 115° at 9.4 miles Dosimeters (TLD) 55 Figure 3.3-2 Rt. 104-New Haven Sch. (SE Corner) 75° at 13.0 miles (Continued) 56* Figure 3.3-2 Co Rt. 1A-Alcan (E. of E. Entrance Rd.) 124° at 5.2 miles 58* Figure 3.3-2 Unit 2, N. Fence, N. of Reactor Bldg. 222° at 3.0 miles 75* Figure 3.3-3 Unit 2, N. Fence, N. of Change House 356° at 0.1 miles 76* Figure 3.3-3 Unit 2, N. Fence, N. of Pipe Bldg. 28° at 0.1 miles 77* Figure 3.3-3 JAF. E. of E. Old Lay Down Area 39° at 0.2 miles 78* Figure 3.3-3 Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd. 86° at 1.0miles 79* Figure 3.3-3 Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd. 121° at 1.2 miles 80* Figure 3.3-3 Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29 137° at 1.5 miles 81* Figure 3.3-3 Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29 160° at 1.7 miles 82* Figure 3.3-3 Lakeview Rd., Tree 0.45 mi. N. of Miner Rd. 180° at 1.6 miles 83* Figure 3.3-3 Lakeview Rd., N., Pole #6117, 200ft. N. of Lake Rd. 203° at 1.2 miles 84* Figure 3.3-2 Unit 1, N. Fence, N. of W. Side of Screen House 225° at 1.1 miles 85* Figure 3.3-3 Unit 2, N. Fence, N of W. Side of Screen House 289° at 0.2 miles 86* Figure 3.3-3 Unit 2, N. Fence, N. of E. Side of Screen House 308° at 0.1 miles 87* Figure 3.3-3 Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 332° at 0.1 miles 88* Figure 3.3-2 Gas Substation Co. Rt. 5-Pulaski 97° at 4.5 miles 89* Figure 3.3-2 Leavitt Rd., Pole #16, 0.4 mi. S. of Rt.1 112° at 4.3 miles 90* Figure 3.3-2 Rt. 104, Pole #300, 150 ft. E. of Keefe Rd. 135° at 4.2 miles 91* Figure 3.3-2 Rt 51A, Pole #59, 0.8 mi. W. of Rt. 51 157° at 4.9 miles 92* Figure 3.3-2 Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104 183° at 4.5 miles 93* Figure 3.3-2 Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104 206° at 4.4 miles 94* Figure 3.3-2 Rt. 1, Pole #82, 250 ft. E. of Kocher Rd. (Co. Rt. 63) 224° at 4.4 miles 95* Figure 3.3-2 Alcan W access Rd., Joe Fultz Blvd, Pole #21 239° at 3.7 miles 96* Figure 3.3-2 Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2 199° at 3.7 miles 97* Figure 3.3-3 Rt. 29, Pole #50, 200ft. N. of Miner Rd. 145° at 1.8 miles 98* Figure 3.3-2 Lake Rd., Pole #145, 0.15 mi. E. of Rt 29 103° at 1.2 miles (1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline rounded to the nearest 1/10 of a mile.

Sample location required by ODCM 3 - 16

TABLE 3.3-1 (Continued) 2005 ENVIRONMENTAL SAMPLE LOCATIONS MAP FIGURE SAMPLE MEDIUM LOCATION DESCRIPTION DEGREES & DISTANCE (1)

DESIGNATION NUMBER Thermoluminescent 99 Figure 3.3-2 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R1 92° at 1.8 miles Dosimeters (TLD) 100 Figure 3.3-3 Rt. 29 & Lake Rd., Env. Station R2 106° at 1.1 miles (Continued) 101 Figure 3.3-3 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 133° at 1.4 miles 102 Figure 3.3-2 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 175° at 11.9 miles 103 Figure 3.3-3 EIC, East Garage Rd., Lamp Post 268° at 0.4 miles 104 Figure 3.3-2 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake rd. 102° at 1.4 miles 105 Figure 3.3-3 Lake view Rd. Pole #36, 0.5 mi. S. of Lake Rd. 199° at 1.4 miles 106 Figure 3.3-3 Shoreline Cove, W. of NMP -1, Tree on W. Edge 274° at 0.3 miles 107 Figure 3.3-3 Shoreline Cove, W. of NMP -1, 30 ft SSW of #106 273° at 0.3 miles 108 Figure 3.3-3 Lake Rd., Pole #142, 300 ft E. of Rt. 29 S. 105° at 1.1 miles 109 Figure 3.3-3 Tree North of Lake Rd., 300 ft E. of Rt. 29 N 104° at 1.1 miles 111 Figure 3.3-2 Control, State Route 38, Sterling NY 214° at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 175° at 11.9 miles 113 Figure 3.3-2 Control, Baldwinsville, NY 178° at 24.7miles Cows Milk 76 Figure 3.3-4 Indicator Location 120° at 6.3 miles 55 Figure 3.3-4 Indicator Location 97° at 8.7 miles 4 Figure 3.3-4 Indicator Location 115° at 7.6 miles 77* Figure 3.3-4 Control Location 190° at 16.0 miles Food Products 133* Figure 3.3-5 Indicator Location 83° at 1.6 miles 134* Figure 3.3-5 Indicator Location 83° at 1.5 miles 144* Figure 3.3-5 Indicator Location 140° at 1.6 miles 142** Figure 3.3-5 Indicator Location 143° at 1.8 miles C2 145* Figure 3.3-5 Control Location 222° at 15.4 miles Nearest Residence Based on NMP Unit 2 Centerline - Refer to Figure 3.3-5 (NMP)

Nearest Residence Based on JAF Centerline - Refer to Figure 3.3-6 (JAF)

(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline

Sample location required by ODCM

- Optional sample 3 - 17

TABLE 3.3-1 (Continued) 2005 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE LOCATION LOCATION DESCRIPTION MEDIUM DESIGNATION Thermoluminescent I-1* ISFSI West Fence, South End of Storage Pad Dosimeters TLD)

(Continued) 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 Pad I-13H ISFSI Building and Grounds Garage, East of Pad I-14H ISFSI Tree ~100 yards South of Pad I-15H ISFSI Transmission Line Tower South of Pad at East /West Access Road I-16H ISFSI Perimeter Fence ~100 yards West of Pad on Pad Centerline I-17H ISFSI North Fence of Main Switch Yard on Pad Centerline I-18H ISFSI North Inner Perimeter Fence at Lake Shore on Pad Centerline

Sample location required by ODCM H indicates Optional TLD location 3 - 18

3 - 19 3 - 20 3 - 21 3 - 22 3 - 23 3 - 24 3.4 LAND USE CENSUS The ODCM requires that a milch animal census and a residence census be conducted annually out to a distance of five miles. Milch animals are defined as any animal that is routinely used to provide milk for human consumption.

The milch animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. The census is done once per year in the summer. It is conducted by sending questionnaires to previous milch animal owners, and by road surveys to locate any possible new owners. In the event that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Cooperative Extension Service was also contacted to provide any additional information.

The residence census is conducted each year to identify the closest residence in each of the 22.5 degree 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 is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the ODCM if broadleaf vegetation sampling and analysis are performed.

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3.5 CHANGES TO THE REMP PROGRAM The following changes were implemented during the 2005 sampling program:

A. Food Product Sampling Program During the reporting period, no changes were made to the Environmental Monitoring locations samples to implement the requirements of the ODCM, Part I, Table 5.1-1.

Sample locations selected were based on the 2005 annual land use census. Based on the garden census, food product location 68 was added to the ODCM as a potential sampling location. This sample location was utilized to implement the 2005 food product sampling requirements.

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2005 sample program address only those samples or monitoring requirements which are required by the ODCM, Part I, Table 5.1-1. This section satisfies the reporting requirements of ODCM, Part I, Section 5.1.1.c.1.

A. ODCM Program Deviations The following are deviations from the program specified by the ODCM:

1. The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during the sample period of 2/1/05 through 2/8/05. The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to broken wires on the transmission line to the air station. No corrective action was implemented.

2. The air sampling pump at the R5 Environmental Sampling Station was inoperable for approximately 2.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during the sample period of 5/17/05 through 5/24/05. The air sample pump was running at the time of sample collection. The sample pump out of service time was determined based on the sample pump run time integrator. The inoperability of the pump was due to a short power outage as a downed tree interrupted power during the sample period. No corrective action was implemented.

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3. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 6/28/05 through 7/6/05.

The inoperability was caused by a power outage in the local electrical power distribution system. The el ngth of inoperability was approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

4. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 7/12/05 through 7/19/05.

The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

5. The air sampling pump at the R3 Environmental Sampling Station was temporarily inoperable during the sample period of 8/16/05 through 8/23/05.

The inoperability was caused by a power out age in the local electrical power distribution system. The length of inoperability was approximately 7.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

6. The air sampling pumps at the R3, R4, and R5 Environmental Sampling Stations were temporarily inoperable during the sample period of 7/26/05 through 8/2/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 2.8, 1.6, and 2.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , respectively. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

7. The air sampling pumps at the R3 and R4 Environmental Sampling Stations were temporarily inoperable during the sample period of 8/23/05 through 8/30/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 13 and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , respectively. Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

3 - 27

8. The air sampling pump at the R4 Environmental Sampling Station was temporarily inoperable during the sample period of 9/27/05 through 10/4/05.

The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 4.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

9. The air sampling pump at the R5 Environmental Sampling Station was temporarily inoperable during the sample period of 11/29/05 through 12/6/05.

The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

10. The air sampling pumps at the R1 and R2 Environmental Sampling Stations were temporarily inoperable during the sample period of 12/20/05 through 12/28/05. The inoperability was caused by a power outage in the local electrical power distribution system. The length of inoperability was approximately 1.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Operability was restored as power was restored to the electrical grid. No corrective action was implemented.

B. Air Sampling Station Operability Assessment The ODCM required air sampling program consists of 5 individual sampling locations. The collective operable time period for the air monitoring stations was 43,722 hours0.00836 days 0.201 hours 0.00119 weeks 2.74721e-4 months out of a possible 43,800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months . The air sampling availability factor for the report period was 99.82%.

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3.7 STATISTICAL METHODOLOGY There are a number of statistical calculation methodologies used in evaluating the data from the environmental monitoring program. These methodologies include determination of standard deviation, the mean and associated error for the mean and the lower limit of detection (LLD).

3.7.1 ESTIMATION OF THE MEAN AND STANDARD DEVIATION The mean, ( X ), and standard deviation, (s), were used in the reduction of the data generated by the sampling and analysis of the various media in the JAFNPP Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean ( X ) and the standard deviation(s):

A. Mean n

X = Xi i =1 N

Where, X = estimate of the mean.

i = individual sample, i.

N, n = total number of samples with positive indications.

Xi = value for sample i above the lower limit of detection.

B. Standard Deviation 1/ 2 n

s= (Xi X )2 i =1 (N 1)

Where, X = mean for the values of X s = standard deviation for the sample population.

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3.7.2 ESTIMATION OF THE MEAN & THE ESTIMATED ERROR FOR THE MEAN In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant related radionuclide(s). When a radio-nuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that mean. In cases where more than one positive sample result is available, the mean of the 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 associated propagated error.

A. Mean n

X = Xi i =1 N

Where, X = estimate of the mean.

i = individua l sample, i.

N,n = total number of samples with positive indications.

Xi = value for sample i above the lower limit of detection.

B. Error of the Mean (Reference 18) 1/2 n 2 ERROR MEAN = ( ERROR )

i =1 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 Standard Deviation.

Standard Deviation is a measure of dispersion from the arithmetic mean of a set of numbers.

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3.7.3 LOWER LIMIT OF DETECTION (LLD)

The LLD is the predetermined concentration or activity level used to establish a detection limit for the analytical procedures.

The LLDs are specified by the ODCM for radionuclides in specific media and are determined by taking into account the overall measurement methods. The equation used to calculate the LLD is:

4.66 S b LLD =

( E ) (V ) ( 2.22) (Y ) exp ( t )

Where:

LLD = the a priori lower limit of detection, as defined above (in picocuries per unit mass or volume);

sb = the standard deviation of the background counting rate or of the counting rate of a blank 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 radionuclide; t = the elapsed time between sample collection (or end of the sample collection period) and time of counting.

The ODCM LLD formula assumes that:

The counting times for the sample and background are equal.

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 detection capabilities 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 LLDs for specific media and radionuclides as specified by the NRC.

The LLDs actually achieved are routinely lower than those specified by the ODCM.

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3.8 COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)

ODCM, Part 1, Table 5.1-3 specify the detection capabilities for environmental sample analysis (see Report Table 3.8-1). ODCM, Part 1, Section 6.1 require that a discussion of all analyses for which the 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.

3.8.1 All sample analyses performed in 2005, as required by the ODCM, achieved the Lower Limit of Detection (LLD) as specified by ODCM, Part 1, Table 5.1-3. See report Table 3.8-1 for required LLD values.

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TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg, Analysis (pCi/l) (pCi/m3 ) wet) (pCi/l) wet) dry)

Gross Beta 4 0.01 H-3 3000 (a)

Mn-54 15 130 Fe-59 30 260 Co-58, Co-60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 I-131 15 (a) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 (a) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore an LLD value of 3000 pCi/liter is used for H-3 and an LLD value of 15 pCi/liter is used for I-131.

3 - 33

3.9 REGULATORY LIMITS Two federal agencies, the Nuclear Regulatory Commission and Environmental Protection Agency, have responsibility for regulations promulgated for protecting the public from radiation and radioactivity beyond the site boundary.

3.9.1 The Nuclear Regulatory Commission (NRC):

The NRC, in 10 CFR 20.1301 limits the levels of radiation in unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

less than or equal to 100 mrem per year to the total body.

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees. Conformance to these guidelines ensures that nuclear power reactor effluents 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 a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

less than or equal to 3 mrem per year to the total body and

less than or equal to 10 mrem per year to any organ.

The 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 and

less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-131, tritium, and all particulate radionuclides with half- lives greater than 8 days in gaseous effluents is limited to:

less than or equal to 15 mrem per year to any organ.

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The NRC, in 10CFR72.104(a), establishes criteria for radioactive materials in effluents and direct radiation from an Independent Spent Fuel Storage Installation (ISFSI).

During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the controlled area must not exceed:

25 mrem per year to the total body;

75 mrem per year to the thyroid and

25 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 environment.

2. Direct radiation from ISFSI.

3. Any other radiation from fuel cycle operation in the region.

3.9.2 Environmental Protection Agency (EPA).

The EPA, in 40CFR190.10 Subpart B, sets forth the environmental standards for the uranium fuel cycle. During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to:

less than or equal to 25 mrem per year to the total body,

less than or equal to 75 mrem per year to the thyroid and

less than or equal to 25 mrem per year to any other organ.

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4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMAT All sample data is summarized in table form. The tables are titled Radiological Environmental Monitoring Program Annual Summary and use the following format as specified in the NRC Branch Technical Position:

Column

1. Sample medium

2. Type and number of analyses performed

3. Required Lower Limits of Detection (LLD), see Section 3.8, Table 3.8-1. This wording indicates that inclusive data is based on 4.66 Sb (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 are keyed 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.

4-1

TABLE 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2005 INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER CONTROL LOCATION:

MEDIUM (UNITS) LLD(a) LOCATIONS: ANNUAL MEAN: NONROUTINE OF ANALYSES* MEAN (f) / RANGE MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS Shoreline Sediment GSA (4):

(pCi/kg-dry) Cs-134 150 <LLD <LLD <LLD 0 Cs-137 180 76 (2/2) No. 5: 76 (2/2) <LLD 0 63 - 90 1.4 miles @ 82o 63 - 90 Fish GSA (20): (h)

(pCi/kg-wet) Mn-54 130 <LLD <LLD <LLD 0 Fe-59 260 <LLD <LLD <LLD 0 Co-58 130 <LLD <LLD <LLD 0 Co-60 130 <LLD <LLD <LLD 0 Zn-65 260 <LLD <LLD <LLD 0 Cs-134 130 <LLD <LLD <LLD 0 Cs-137 150 <LLD <LLD <LLD 0 4-2

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2005 INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER CONTROL LOCATION:

MEDIUM (UNITS) LLD(a) LOCATIONS: ANNUAL MEAN: NONROUTINE OF ANALYSES* MEAN (f) / RANGE MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS Surface Water H-3 (8):

(pCi/liter)

H-3 3000(c) <LLD <LLD <LLD 0 GSA (24):

Mn-54 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0 Co-58 15 <LLD <LLD <LLD 0 Co-60 15 <LLD <LLD <LLD 0 Zn-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 <LLD <LLD <LLD 0 I-131 15(c) <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 4-3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2005 INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER CONTROL LOCATION:

MEDIUM (UNITS) LLD(a) LOCATIONS: ANNUAL MEAN: NONROUTINE OF A NALYSES* MEAN (f) / RANGE MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS TLD (mrem per Gamma Dose (128) (d) 4.8 (120/120) (i) TLD #85 (g): 8.8 (4/4) 4.3 (20/20) 0 standard month) 3.2 - 9.2 0.2 miles at 289o 8.6 - 9.2 3.4 - 5.1 Air Particulates Gross Beta (260): 0.01 0.019 (208/ 208) R-1 0.019 (52/52) 0.019 (52/ 52) 0 (pCi/m3 ) 0.007 - 0.041 1.8 miles @ 92o 0.009 - 0.036 0.008 - 0.034 I-131 (260): 0.07 <LLD <LLD <LLD 0 GSA (60):

Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0 Milk GSA (72): (e) (h)

(pCi/liter) Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0 I-131 (72):

I-131 1 <LLD <LLD <LLD 0 4-4

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2005 INDICATOR LOCATION (b) OF HIGHEST NUMBER OF TYPE AND NUMBER CONTROL LOCATION:

MEDIUM (UNITS) LLD(a) LOCATIONS: ANNUAL MEAN: NONROUTINE OF ANALYSES* MEAN (f) / RANGE MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS Food Products GSA (18): (h)

(pCi/kg-wet) I-131 60 <LLD <LLD <LLD 0 Cs-134 60 <LLD <LLD <LLD 0 Cs-137 80 <LLD <LLD <LLD 0 4-5

TABLE NOTES:

= Data for Table 4.0-1 is based on ODCM required samples unless otherwise indicated.

(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 nearest 1/10 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 and 3000 pCi/liter respectively.

(d) = The ODCM does not specify a particular LLD value for environmental TLDs.

(e) = The ODCMs criteria for indicator milk sample locations include locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site. Therefore, the only sample location required by the ODCM is the control location. There were three optional locations during 2005.

(f) = Fraction of number of detectable measurements to total number of measurements. Mean and range results are based on detectable 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 which is 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, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 94, 95, 96, 97, 98, 18, 56, and 58. Control TLDs are all TLDs located beyond the influence of the site (TLD #: 8, 14, 49, 111, and 113).

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5.0 DATA EVALUATION AND DISCUSSION A. Introduction Each year the results of the Annual Radiological Environmental Monitoring Program (REMP) are evaluated considering plant operations at the site, the natural processes in the environment and the archive 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 2005 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 impact of 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.

B. Units of Measure Some 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 atom decays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second.

Smaller units of the curie are used in this report. Two common units are the microcurie (uCi), one millionth (0.000001) of a curie, and the picocurie (pCi), one trillionth (0.000000000001) of a curie. The picocurie 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.

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C. Dose/Dose to Man The dose or dose equivalent, simply put, is the amount of ionizing energy deposited or absorbed in living 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 dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation.

The dose equivalent is measured in rem (roentgen equivalent man). In terms of environmental radiation, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One millirem is equal to 0.001 of a rem.

The term dose to man refers to the dose or dose equivalent that is received by members of the general public at or beyond the site boundary. The dose is calculated based on concentrations of radioactive material measured in the environment. The primary pathways that contribute to the dose to man are the inhalation pathway, the ingestion pathway, and direct radiation.

D. Discussion There are three separate groups of radionuclide that were measured in the environment in the media analyzed for the 2005 sampling program. The first of these groups consists of those radionuclides that are naturally occurring. The environment contains a significant inventory of naturally occurring radioactive elements. The components of natural or background radiation include the decay of radioactive elements in the earths crust, a steady stream of high-energy particles from space called cosmic radiation, naturally-occurring radioactive isotopes in the human body like potassium-40, medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in nature), and household items like televisions. In the United States, a persons average annual exposure from background radiation is 360 mrem, as illustrated on the following Background Radiation Chart.

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Background Radiation Radiation Exposure in the U.S.

(Percent of Total Effective Dose)

NCRP 93, 1987 A number of radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. These radionuclides are expected 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 upper atmosphere,

Beryllium - 7, present as a result of the interaction of cosmic radiation with the upper atmosphere,

Potassium -40 and radium-226, naturally occurring radionuclides found in the human body and throughout the environment, and

Fallout radionuclides from nuclear weapons testing, including cesium-137, and strontium-90.

Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally 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 natural background radiatio n 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.

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The second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earths atmosphere. Atmospheric nuclear testing during the early 1950s 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 man-made 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 Peoples Republic of China. In each case, the usual radionuclid es 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. The highest weapons testing concentrations were noted in samples collected for the 1981 REMP. Cs-137 was the major byproduct of this testing and is still occasionally detected in a few select number of environmental media.

The third group of radionuclides that may be detected in the environment are those that are related to nuclear power technology. These radionuclides are the byproduct of the operation of light water reactors. These byproduct radionuclides are the same as those produced in atmospheric weapons testing and found in the Chernobyl fallout. This commonality makes a determination of the source of these radionuclides that may be detected in environmental samples difficult to determine. During 2005, Cs-137 was the only potential plant-related radionuclide detected in the REMP samples.

A number of factors must be considered in performing radiological sample data evaluation and interpretation. The evaluation is made using several approaches including trend analysis and dose to man. An attempt has been made not only to report the data collected during 2005, but also to assess the significance of the radionuclides detected in the environment as compared to natural and other man- made radiation sources. It is important to note that detected concentrations of radionuclides in the local environment as a result of mans technology are very small and are of no or little significance from an environmental or dose to man perspective.

The 1987 per capita average dose was determined to be 360 mrem per year from all sources, as noted in NCRP Report No. 93 (Reference 13). This average dose includes such exposure sources as natural radiation, occupational exposure, weapons testing, consumer products and nuclear medicine. The 1987 per capita dose rate due to natural sources was 295 mrem per year. The per capita radiation dose from nuclear power production nationwide is less than one mrem per year.

5-4

The natural background gamma radiation in the environs of the Nine Mile Point site, resulting from radionuclides in the atmosphere and in the ground, accounts for approximately 60-65 mrem per year. This dose is a result of radionuclides of cosmic origin (for example, Be-7) and of primordial origin (Ra-226, K-40, and Th-232). A dose of 60 mrem per year, as a background dose, is significantly greater than any possible doses as a result of routine operations at the site during 2005.

The results of each sample medium are discussed in detail in Sections 5.1 and 5.2. This includes a summary of the results, the estimated environmental impact, a detailed review of any relevant detections with a dose to man estimate where appropriate, and an analysis of possible long term and short term trends.

During routine implementation of the REMP, additional or optional environmental pathway media are 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 main pathways, and

Maintain the analytical data base established when the plants began commercial operation.

The optional samples that are collected will vary from year to year. In addition to the optional sample media, additional locations are sampled and analyzed for those pathways required by the ODCM. These additional sample locations are obtained to ensure that a variety of environmental pathways 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 and evaluation. When additional locations are included, the use of this data is specifically noted in Sections 5.1 and 5.2.

Section 6.0 contains the analytical results for the sample media addressed in the report.

Tables are provided for each required sample medium analyzed during the 2005 program.

Section 7.0, titled Historical Data, contains statistics from previous years environmental sampling. The process of determining the impact of plant operation on the environment includes the 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 technological advances in laboratory procedures and analytical equipment.

5-5

5.1 AQUATIC PROGRAM The aquatic program consists of samples collected from three environmental pathways. These pathways are:

Shoreline Sediment

Fish

Surface Waters Section 6.0, Tables 6-1 through 6-4 present the analytical results for the aquatic samples collected for the 2005 sampling period.

5.1.1 SHORELINE SEDIMENT RESULTS A. Results Summary Shoreline sediment samples were obtained in April and October of 2005 at one offsite control location (Langs Beach located near Oswego Harbor) and at one indicator location (Sunset Bay) which is an area east of the site considered to have recreational value.

A total of four sediment samples were collected for the 2005 sample program, two indicator and two control. Cs-137 was detected in two of the samples collected from the Sunset Bay indicator location in 2005, measuring 0.090 and 0.063 pCi/g (dry). These results continue to show a downward trend over the last 10 years. Cs-137 was not detected in samples collected from the control location during 2005; however, Cs-137 has been detected in past control samples. Cs-137 was detected in control samples collected in 1993 at an average concentration of 0.027 pCi/g.

The general lack of Cs-137 at the control location is attributed to the differences in the sediment types between the two sample locations (See Data Evaluation and Discussion).

The source of the Cs-137 detected in the indicator shoreline sediment is considered to be the result of fallout from atmospheric nuclear weapons testing and not from operations at the site. The mean concentration of Cs-137 measured in the 2005 indicator sample is consistent with measured concentrations since shoreline sediment sampling began in 1985.

Historical mean concentrations measured at the indicator location ranged from a maximum of 0.33 pCi/g in 1993 to a minimum of 0.04 pCi/g (dry) in 2004. The results for the 2005 control location were less than the detection limit. No other plant-related radionuclides were detected in the 2005 shoreline sediment samples.

5-6

The calculated potential whole body and skin doses which may result from the measured Cs-137 concentrations are extremely small and are insignificant when compared to natural background doses.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous 12 years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1993.

pCi/gram Shoreline Sediment Cs-137 (dry) 0.35 0.3 CONTROL INDICATOR 0.25 Control< LLD Value 0.2 0.15 0.1 0.05 0

1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 B. Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Bay), and one control location (Langs Beach). Samples were collected from both the indicator and control locations in April and October 2005. The results of these sample collections are presented in Section 6.0, Table 6-1, Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2005. Cesium-137 (Cs-137) and Potassium-40 (K-40) were the primary radionuclides detected in the sediment samples.

Cs-137 was detected in the indicator samples collected in April and October for the 2005 program. The measured concentration for these samples were 0.090 and 0.063 pCi/g (dry).

The presence of Cs-137 in certain environmental sample media such as soil, shoreline sediment and fish is historically common. Cs-137 is a fission product that is produced in nuclear power reactors and during atmospheric weapons testing. In addition to the Cs-137 found in the environment as a result of past weapons testing, a significant inventory of Cs-137 was also introduced globally as a result of the Chernobyl accident in 1986. Because Cs-137 is found in environmental samples as a result of weapons testing and Chernobyl, it 5-7

is difficult to accurately determine the source of Cs-137 measured in the sediment sample.

It is highly probable that the source of the cesium is from sources other than the operation of plants at the Nine Mile Point Site. It is likely that any sediment sample containing Cs-137 which was the result of plant operation would also contain other plant related isotopes such as Co-60 and Cs-134. The absence of corroborating radionuclides would indicate that the source of Cs-137 in sediment samples is from the existing background Cs-137 which is attributed to weapons testing and the Chernobyl accident. This assessment is further substantiated by the fact that Cs-137 was detected in the 1993 sediment control sample.

Historically, Cs-137 has been routinely measured in the control samples of other environmental media such as fish and soil.

The general absence of Cs-137 in the control samples is attributed to the differences in the sediment types between the two sample locations. Few shoreline regions west of the site contain fine sediment and/or sand which would be representative of the indicator location.

It is difficult to obtain control samples that are comparable in physical and chemical characteristics to the indicator samples. Other factors, which include changing lake level and shoreline erosion, further complicate attempts at consistency in shoreline sediment sampling. Recent soil samples from locations beyond any expected influence from the site have contained levels of Cs-137 equal to or greater than the concentrations found in the 2005 shoreline sediment samples. The Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-137.

C. Dose Evaluation The radiological impact of Cs-137 measured in the shoreline sediment can be evaluated 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 parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated. The following regulatory guide values and the maximum 2005 shoreline sediment indicator Cs-137 concentration were used in calculating the dose to man:

A teenager spends 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at the beach area or on the shoreline,

The sediment has a mass of 40 kg/m2 (dry) to a depth of 2.5 cm,

The shoreline width factor is 0.3, and

The maximum measured Cs-137 concentration of 0.090 pCi/g (dry).

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.00030 mrem/year to the whole body and 0.00036 mrem/year to the skin. This calculated dose is very small and is insignificant when compared to the natural background annual exposure of approximately 60 mrem as measured by control TLDs in the vicinity of the site.

5-8

D. Data Trends The mean Cs-137 concentration for the shoreline sediment indicator sample for 2005 was 0.08 pCi/g (dry). This is consistent with mean concentration measured at the indicator location over the past ten years.

The previous five years of data show a stable mean concentration values measured at the indicator locations. Over the five year period, mean concentrations ranged from a high of 0.07 pCi/g (dry) in 2000 and 2001 to a low value of 0.04 pCi/g (dry) measured in 2004.

Cesium-137 was not detected in the control location samples over this same five year period.

The previous ten year data trend for indicator shoreline samples showed a overall downward trend in concentration measured at the indicator sample locations. Over the previous ten year period of 1995 through 2004, mean concentrations at the indicator location ranged from a maximum of 0.17 pCi/g (dry) in 1996 and 1997 to a minimum of 0.04 pCi/g (dry) measured in 2004. The mean indicator concentration measured in 2005 of 0.08 pCi/g (dry) continues to support the long term decreasing trend in Cs-137 concentration in shoreline sediment samples. Cesium-137 was not detected in the control samples collected over the previous ten years.

Shoreline sediment sampling at the indicator location commenced in 1985. Prior to 1985, no data was available for long term trend analysis.

Section 7.0, Tables 7-1 and 7-2 illustrate historical environmental data for shoreline sediment samples.

5-9

5.1.2 FISH SAMPLE RESULTS A. Results Summary A total of 20 fish samples were collected for the 2005 sample program. Species collected were: smallmouth bass, brown trout, walleye and Chinook salmon. The analytical results for the 2005 fish samples showed no detectable concentration of radionuclide that would be attributable to plant operations at the site or past atmospheric weapons testing. The absence of Cs-137 in the 2005 fish samples is significant in the fact that it continues to validate the absence of Cs-137 in fish samples observed in the previous two years. With the exception of 2001, 2003, 2004 and 2005, positive concentrations of Cs-137 have been measured in fish samples collected in the previous 20 years at a combination of both the indicator and/or control locations. (Refer to Tables 7-3 and 7-4). These low levels of Cs-137 represented no significant dose to man or impact on the environment.

The 2005 fish sample results demonstrate that plant operations at the Nine Mile Point Site have no measurable radiological environmental impact on the upper levels of the Lake Ontario food chain. The 2005 results are consistent with previous years results in that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last 24 years. Cs-137 was not detected in fish samples collected in 2000, 2001, 2003, 2004 and 2005 from indicator locations. The period of 2000 through 2005 as a group are the lowest results measured since the beginning of the Site Environmental Monitoring Program in 1969.

B. Data Evaluation and Discussion Fish collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area) and at two locations in the vicinity of the lake discharges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samples served as control samples while the NMPNS and JAFNPP samples served as indicator samples. All samples were analyzed for gamma emitters. Section 6.0, Table 6-2 shows individual results for all the samples collected in 2005 in units of pCi/g (wet).

The spring fish collection was made up of 9 individual samples representing three separate species. Walleye, smallmouth bass and brown trout were collected from all three locations.

The total fall fish collection was comprised of 11 individual samples representing four individual species. Brown trout, Chinook salmon and walleye were collected from all three sampling locations. Smallmouth bass were collected at the control and JAFNPP indicator locations.

Cs-137 was not detected in any of the fish species collected for the 2005 sample program 5 - 10

C. Dose Evaluation Fish represent the highest level in the aquatic food chain and have the potential to be a contributor to the dose to man from the operations at the site. The lack of detectable concentrations of plant-related radionuclides in the 2005 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway. Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish are an integral part of the human food chain.

D. Data Trends The Cs-137 data for fish samples over the previous five years (2000 through 2004) show that the number of positive detections has decreased over this period relative to historical data. With the exception of 2002 there was no positive detection of Cs-137 over the previous five year period at the indicator locations. There are no positive detections in 2001, 2003 or 2004 and only intermittent detections in the remaining years of this period.

The general lack of positive detections was continued in the 2005 sample year. The graph below illustrates the mean control and indicator Cs-137 concentrations for 2005 and the previous ten years.

ANNUAL MEAN CONCENTRATION FISH Cs-137 0.025 INDICATOR CONTROL INDICATOR <LLD VALUE 0.02 CONTROL <LLD VALUE pCi/gram (wet) 0.015 0.01 0.005 0

1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 5 - 11

The ten year data trend shows a cons istent level of Cs-137 measured in fish between 1994 and 2000. After 2000, the number of positive detections drops off as noted in the five year trend. The 1994 through 2004 results, as a group, are the lowest Cs-137 concentrations measured over the existence of the sample program.

The general long-term decreasing trend for Cs-137, illustrated in the graph below, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected in fish since 1976 are considered to be the result of weapons testing fallout. The general downward trend in concentrations will continue as a function of additional ecological cycling and radiological decay.

ANNUAL MEAN CONCENTRATION FISH Cs-137 1.5 1.25 INDICATOR CONTROL INDICATOR <LLD VALUE 1

CONTROL <LLD VALUE pCi/gram (wet) 0.75 0.5 0.25 0 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Section 7.0, Tables 7-3 and 7-4 show historical environmental sample data for fish.

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5.1.3 SURFACE WATER (LAKE)

A. Results Summary The ODCM requires that monthly surface water samples be taken from the respective inlet water supplies of the JAFNPP and NRG Energy's Oswego Steam Station. In conjunction with the required samples, three additional Lake Ontario surface water locations are sampled and analyzed. These additional locations are the Oswego City Water Intake, the NMP1 Intake and the NMP2 Intake. Gamma spectral analysis was performed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples collected from the additional sample locations. The results of the gamma spectral analyses showed that only naturally-occurring radionuclides were detected in the 60 samples from the five locations collected for the 2005 Sampling Program. The two naturally-occurring radionuclide detected were K-40 and Ra-226 and were not related to plant operations.

Monthly composite samp les showed no presence of plant-related gamma emitting isotopes in the waters of Lake Ontario as a result of plant operations.

The monthly surface water samples are composited on a quarterly basis and are analyzed for tritium. A total of 20 samples were analyzed for tritium as part of the 2005 REMP program.

The results for the 2005 samples showed no positive detections of tritium. All results for 2005 were below the established measurement sensitivity and are reported as less than the lower limit of detection (<LLD). There is no indication of a long-term buildup of tritium concentrations in the surface waters adjacent to the site.

B. Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. No plant-related radionuclides were detected in 2005 samples.

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 monthly samples for a given location. Tritium samples analyzed for the 2005 sample program were analyzed to an instrument detection level of 500 pCi/l.

The tritium results for the JAFNPP inlet canal samples contained no positive detections. The 2005 results had LLD values that ranged from <416 pCi/l to <498 pCi/ l. The ODCM Control location (Oswego Steam Station inlet canal) results showed no positive detections and the sample results had LLD values in the range of <413 pCi/l to <471 pCi/l.

5 - 13

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 2005 program. The Oswego City Water inlet is sampled to monitor drinking water quality and is representative 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 up-stream direction based on the current patterns in the lake.

No positive detections of tritium were identified in 2005. The following is a summary of LLD results for the 2005 sample program:

Tritium Concentration pCi/liter Sample Mean Location Minimum Maximum (Annual)

JAF Inlet (Indicator)* <416 <498 <440 Oswego Steam Inlet (Control)* <413 <471 <432 NMP #1 Inlet <413 <471 <432 NMP #2 Inlet <413 <471 <432 Oswego City Water Supply <413 <471 <432

Sample location required by ODCM The above LLD values are far below the ODCM required LLD value of 3000 pCi/l.

Analytical results for surface water samples are found in Section 6.0, Tables 6-3 through 6-4.

C. Dose Evaluation The radiological impact to members of the public from low levels of tritium in water is insignificant. 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 the maximum 2005 LLD concentration of <498 pCi/l, the calculated dose would be less than 0.052 mrem to the child whole body and less than 0.052 mrem to the child liver (critical age group/organ).

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D. Data Trends There are no data trends for gamma emitters such as Cs-137 and Co-60 as historically these radionuclides have not been detected in lake water samples.

Tritium results for the 2005 lake water samples were consistent with results from the previous five years for both the indicator and control locations. The mean measured tritium concentrations for the previous five year period of 2000 - 2004 ranged from <LLD pCi/l to 212 pCi/l for the control and 185 pCi/l to 297 pCi/l for the indicator location. By comparison, the mean 2005 tritium concentrations were <432 pCi/l and <440 pCi/l for the control and indicator locations respectively. The previous five year data indicates no significant trends in either the indicator or the control mean concentrations. This previous five year data set is consistent with long term tritium results measured at the site. The indicator data from the previous ten year period, 1995 through 2004, is representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured. The 1999 mean control value of 337 pCi/l is the highest concentration measured since 1989 and is within the variability of results measured over the life of the program. The ten year historical results are consistent between the control and indicator locations with no large variation in the measured results.

The following graph illustrates the concentrations of tritium measured in Lake Ontario over the past 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 location closely approximates the Oswego Steam Station, the current control location. There is no existing preoperational data for comparison to recent data.

Surface Water - Tritium 600 1975-1984: Oswego City Water Control Site 1985-2005: Oswego Steam Station Control Site INDICATOR 500 CONTROL INDICATOR <LLD VALUE CONTROL <LLD VALUE 400 pCi/l 300 200 100 0

1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 Historical data for Surface Water Tritium is presented in Section 7.0, Tables 7-7 and 7-8.

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5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples collected from four environmental pathways. These pathways are:

Airborne particulate and radioiodine,

Direct Radiation,

Milk, and

Food Products Section 6.0, Tables 6-5 through 6-12 present the analytical results for the terrestrial samples collected for the 2005 reporting period.

5.2.1 AIR PARTICULATE GROSS BETA A. Results Summary Weekly air samples were collected and analyzed for particulate gross beta particulate activity. For the 2005 program, a total of 52 samples were collected from control location R-5 and 208 samples were collected from indicator locations R-1, R-2, R-3, and R-4.

These five locations are required by the ODCM. Additional air sampling locations are maintained and are discussed in Section 5.2.1.B below. The mean gross beta concentration for samples collected from the control location (R-5) in 2005 was 0.019 pCi/ m3 . The mean gross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2005 was 0.019 pCi/m3 . The mean gross beta results for the indicator and the control stations were equivalent in 2005. The consistency between the indicator and control mean values, demonstrates that there are no increased airborne radioactivity levels in the general vicinity of the site. The indicator results are consistent with concentrations measured over the last fifteen years. This consistency demonstrates that the natural baseline gross beta activity has been reached. The man- made radionuclide contribution to the natural background from atmo spheric weapons testing and Chernobyl can no longer be detected above the background concentrations of naturally occurring beta emitting radionuclides.

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B. Data Evaluation and Discussion The air monitoring system consists of fifteen sample locations, six onsite and nine offsite.

Each location is sampled weekly for particulate gross beta activity. A total of 780 samples were collected and analyzed as part of the 2005 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 located beyond any local influence from the site. In addition, optional offsite and onsite air sample locations are maintained from which weekly samples are collected. The optional offsite locations are designated as D-2, E, F and G. The optional onsite locations are designated as D-1, G, H, I, J and K.

Gross beta analysis requires that the samples be counted no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after collection. This allows for the decay of short half- life naturally-occurring radionuclides, thereby increasing the sensitivity of the analysis for plant-related radionuclides.

Section 6.0, Tables 6-5 and 6-6 present the weekly gross beta activity results for samples collected from the offsite and onsite locations.

The average annual gross beta indicator concentrations for the ODCM indicator stations (R-1, R-2, R-3 and R-4) was 0.019 pCi/m3 . The offsite ODCM control station (R-5) annual mean gross beta concentration was also 0.019 pCi/m3 . The minimum, maximum and average gross beta results for sample locations required by the ODCM were as follows:

Concentration pCi/m3 Location Minimum Maximum Mean R-1 0.009 0.036 0.019 R-2 0.008 0.041 0.019 R-3 0.008 0.032 0.018 R-4 0.007 0.034 0.019 R-5 (control) 0.008 0.034 0.019 R1 - R4 Indicator Stations Min 0.007 Max 0.041 Mean 0.019 5 - 17

The mean weekly gross beta concentrations measured in 2005 are illustrated in the following graphs:

Air Particulate Filter - Gross Beta 2005 0.035 INDICATOR CONTROL 0.030 0.025 pCi/m3 0.020 0.015 0.010 0.005 1 3 5 7 9 11 13 15 17 19 21 23 25 WEEK #

Air Particulate Filter - Gross Beta 2005 0.035 INDICATOR CONTROL 0.030 0.025 pCi/m3 0.020 0.015 0.010 0.005 27 29 31 33 35 37 39 41 43 45 47 49 51 WEEK #

The fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, especially seasonal changes. The concentrations of naturally-occurring radionuclides in the lower levels of the atmosphere directly above the land are affected by time-related processes such as wind direction, precipitation, snow cover, soil temperature and soil moisture content.

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C. Dose Evaluation Dose calculations are not performed based on gross beta concentrations. Dose to man as 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 air concentrations. The dose received by man from air gross beta concentration is a component of the natural background.

D. Data Trends With the exception of the 1986 sample data, which was affected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1981, when the mean control value was 0.165 pCi/m3 . The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

The mean gross beta concentration measured in 1977 to 2005 are illustrated in the following graph:

Air Particulate Filter - Gross Beta 0.35 0.3 0.25 INDICATOR CONTROL 0.2 pCi/m3 0.15 0.1 Chernobyl Accident 0.05 0

1969 1977 1981 1985 1989 1993 1997 2001 2005 The trend for the previous five years represents a base line concentration or natural background level for gross beta concentrations. This trend is stable with minor fluctuations due to natural variations. The change in concentrations over the period of 1992 through 2005 is very small. This is illustrated by the following graph.

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Air Particulate Filter- Gross Beta 2005 0.02 0.018 INDICATOR CONTROL 0.016 0.014 0.012 pCi/m3 0.01 0.008 0.006 0.004 0.002 0

1992 1994 1996 1998 2000 2002 2004 For the previous ten year operational period of 1995 to 2005, the mean annual gross beta concentration at the control station (R-5) has remained steady with a narrow range of 0.013 pCi/m3 to 0.019 pCi/ m3 . The mean annual concentrations for the indicator stations for this same time period were similar to the control and ranged from a minimum of 0.010 pCi/m3 in 1997 to a maximum mean of 0.018 pCi/m3 in 2005.

Historical data of air particulate gross beta activity are presented in Section 7.0, Tables 7-9 and 7-10.

5.2.2 MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS)

A. Results Summary Fifteen air monitoring stations are maintained around the Nine Mile Point Site. Five of the 15 air monitoring stations are required by the ODCM and are located offsite near the site boundary and offsite as a control location. Ten additional air sampling stations are also maintained as part of the sampling program. Together, these fifteen continuous air sampling stations make up a comprehensive environmental monitoring network for measuring radioactive air particulate concentrations in the environs of the site. Annually, the air monitoring stations provide 780 individual air particulate samples which are assembled by location into 180 monthly composite samples. The monthly composites are analyzed using gamma spectroscopy.

No plant-related gamma emitting radionuclides were detected in any of the air particulate filter samples collected during 2005.

The gamma analysis results for the monthly composite samples routinely showed positive detections of Be-7, K-40, and Ra-226. Each of these radionuclides is naturally occurring.

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B. Data Evaluation Discus sion A total of fifteen air sampling stations are in continuous operation and located both onsite 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 are optional to provide an effective monitoring network. Composite air filter samples are assembled for each of the fifteen sampling locations. Each of the weekly air particulate filters collected for the month is assembled by location to form monthly composite samples. The monthly composite samples required by the ODCM are composite samples assembled for R-1, R-2, R-3, R-4 and R-5. Other sample locations not required by the ODCM, for which analytical results have been provided, include six onsite locations and four offsite locations. The analytical results for the 180 air particulate filter composites in 2005 showed no detectable activity of plant related radionuclides.

The results of the monthly composite samples are presented in Section 6.0, Table 6-9.

C. Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected in 2005. The monthly air particulate sampling program demonstrated no offsite dose to man from this pathway as a result of operations of the plants located at the Nine Mile Point Site.

D. Data Trends No plant related radionuclides were detected during 2005 at the offsite air monitoring locations.

The ten year database of air particulate composite analysis shows that there is no buildup 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 from 1977 through 1984 at both the indicator and control locations, with the exception of 1980 when Co-60 was not detected at the control location. The presence of Co-60 in the air samples collected during these years was the result of atmospheric weapons testing. 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 sample was an isolated event associated with effluents from the NMP1 facility. There have been no subsequent measurable concentrations of Co-60 in the environment surrounding the Nine Mile Point site.

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Historical data shows that Cs-137 is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years 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 the Chernobyl accident. Since 1986 there have been no detections of Cs-137 in the environment surrounding the Nine Mile Point site.

After 1986, no plant related or fallout radionuclides were detected in any of the offsite air particulate composite samples with the exception of the isolated detection of Co-60 in 2000 in a single sample. A review of the past five years data for air particulate filter composites indicates no plant related radiological impact on the environment from operations at the FitzPatrick plant. All previous historical positive detections of fission product radionuclides were associated with atmospheric weapons testing or the Chernobyl accident, with the exception of the 2000 detection noted above.

Historical data for air particulate results are presented in Section 7.0, Tables 7-13 and 7-14.

5.2.3 AIRBORNE RADIOIODINE (I-131)

A. Results Summary Iodine-131 (I-131) was not detected in any of the 780 samples analyzed for the 2005 program. No radioiodine has been measured offsite at the constant air monitoring stations since 1987.

B. Data Evaluation and Discussion Airborne radioiodine is monitored at the fifteen air sampling stations also used to 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 as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from 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 using activated charcoal cartridges. They are analyzed weekly for I-131. I-131 was not detected in any of the 2005 samples collected.

The analytical data for radioiodine are presented in Section 6.0, Tables 6-7 and 6-8.

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C. Dose Evaluation The calculated dose as a result of I-131 was not evaluated due to the fact I-131 was not detected during 2005. The I-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located at Nine Mile Point.

D. Data Trends No radioiodine has been detected in samples collected from the air sampling locations required by the ODCM since 1987.

There has been no positive detection of I-131 in air samples collected over the last ten years. This demonstrates that there is no measurable environmental impact or positive trend for iodine buildup due to plant operations during the period from 1996 through 2005.

I-131 has previously been detected in samples collected during the last twenty year period in 1986 and 1987. The 1986 detection of I-131 was the result of the Chernobyl accident and the 1987 detection was the result of plant operations.

Iodine-131 has been detected in the past at control locations. Control samples collected during 1976 had a mean I- 131 concentration of 0.60 pCi/m3 . During 1977 this mean decreased to 0.32 pCi/m3 , and further decreased by a factor of ten to 0.03 pCi/m3 in 1978.

I-131 was not detected in samples collected from the control location during 1979 - 1981 and 1983 to 1985. I-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m3 .

Iodine-131 has been detected in samples collected from the on-site indicator locations during 1980 to 1983 and 1986 to 1987. The mean concentrations ranged from 0.013 pCi/m3 in 1980 to a maximum of 0.119 pCi/m3 in 1986. The maximum mean indicator I-131 concentration of 0.119 pCi/m3 was the result of the Chernobyl accident. I-131 was detected in a total of 75 weekly samples collected during the 1986 sample program. The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m3 to a maximum of 0.36 pCi/m3 . Each positive detection of I-131 in samples collected in 1986 was the direct result of the Chernobyl Nuclear accident.

Historical data for I-131 are presented in Section 7.0, Tables 7-11 and 7-12.

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5.2.4 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD)

A. Results Summary Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. As part of the 2005 environmental monitoring program, TLDs were placed at a total of 72 different environmental TLD locations (33 required by the ODCM and 39 optional locations). These TLDs were placed, collected and read each quarter of 2005. 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 given location.

The 72 TLDs were placed in the following five geographical locations around the site boundary:

Onsite (areas within the site boundary),

Site Boundary (area of the site boundary in each of the 16 meteorological sectors),

Offsite Sector (area four to five miles from the site in each of the eight land based meteorological sectors),

Special Interest (areas of high population density and use), and

Control (areas beyond significant influence of the site).

All geographical locations are required by the ODCM with the exception of the Onsite area which was optional. Description of the five geograpical categories and the designation 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 2005 dose rates for each of the five geographical locations is as follows:

Dose in mrem per standard month Geographic Category Min Max Mean Onsite (Optional) 3.4 14.1 5.4 Site Boundary (Inner Ring) * (1) 3.4 4.8 4.2 Offsite Sectors (Outer Ring)

3.2 4.7 4.0 Special Interest * (2) 3.4 5.1 4.1 Control * (3) 3.4 5.1 4.3

Geographical locations required by the ODCM 1 Only includes TLD results that are not affected by radwaste direct shine (TLD #s. 78, 79, 80, 81, 82, 83, 84, 7, 18) 2 Only includes TLD results required by the ODCM (TLD #s. 15, 56, 58, 96, 97, 98) 3 Includes TLD results from locations #8, 14 & 49.

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Comparison of annual mean dose rates associated with each geographical location indicate that there is no statistical difference in annual dose as a function of distance from the site boundary. The measured annual dose rate at the nearest resident to the 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) were well within expected normal variation when compared to the Control TLD results.

The results for the 2005 environmental TLD monitoring program indicate that there was no significant increase in dose rates as a result of operations at the site. The Hydrogen Water Chemistry system and the Independent Spent Fuel Storage Installation (ISFSI) in use at the FitzPatrick plant did not measurably increase the ambient radiation exposure rate beyond the site boundary.

B. Data Evaluation and Discussion Direct Radiation (Gamma Dose) measurements were taken at 72 different environmental locations during 2005, 33 of which are required by the ODCM. These locations are grouped into five geographical location categories for evaluation of results. The five categories include: Onsite, Site Boundary, Offsite Sector, Special Interest and Control locations. All categories are required by the ODCM with the exception of the Onsite TLDs. Onsite TLDs are placed at various locations within the site boundary to provide additional information on direct radiation levels at and around the NMP1, NMP2 and JAFNPP facilities.

Onsite TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2005 direct radiation results for Onsite TLD locations were as follows:

1. Results for TLDs located near the NMP1, NMP2 and JAFNPP generating facilities and at previous or existing on-site air monitoring stations ranged from 3.4 to 14.1 mrem per standard month.

2. Results for TLDs located near the north shoreline of NMP1, NMP2 and Fitzpatrick facilities in close proximity to the Radwaste and Unit 1 Reactor Building ranged from 3.4 to 37.3 mrem per standard month.

3. Results for TLDs located onsite near the Energy Information Center and its associated shoreline ranged from 4.1 to 5.6 mrem per standard month.

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Site Boundary TLD results ranged from 3.4 to 9.2 mrem per standard month in 2005. This range included all TLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location required by the ODCM was 9.2 mrem per standard month. This TLD, (TLD 85) represents the site boundary maximum dose and is located in the WNW sector along the lake shore in close proximity to the NMP1 plant. The TLD locations along the lakeshore close to the plants (TLD #s 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities. These locations and are not accessible to members of the public and the TLD results for these areas are not representative of dose rates measured at the remaining site boundary locations. The remaining Site Boundary TLD locations, which are located away from the plant ranged from 3.4 to 4.8 mrem per standard month resulting in an average dose rate of 4.2 mrem per standard month.

Offsite Sector TLDs, required by the ODCM, located 4 to 5 miles from the site in each of the 8 land based meteorological sectors ranged from 3.2 to 4.7 mrem per standard month with an average dose rate of 4.0 mrem per standard month.

Special Interest TLDs from all locations ranged from 3.4 to 5.1 mrem per standard month with a 2005 annual average dose rate of 4.1 mrem per standard month.

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site. 2005 Control TLD results ranged from 3.4 to 5.1 mrem per standard month with an annual average dose rate of 4.3 mrem per standard month. These results include both the ODCM required control TLDs and the additional control TLDs.

TLD analysis results are presented in Section 6.0, Table 6-10.

C. Dose evaluation 2005 annual mean dose rates for each geographic location required by the ODCM are as follows:

Site Boundary: 4.2 mrem per standard month (TLD #s: 78, 79, 80, 81, 82, 83, 84, 7, 18)

Offsite Sectors: 4.0 mrem per standard month (TLD #s: 88, 89, 90, 91, 92, 93, 94, 95)

Special Interest: 4.1 mrem per standard month (TLD #s: 15, 56, 58, 96, 97, 98)

Control: 4.3 mrem per standard month (TLD #s 8, 14, 49) 5 - 26

The measured mean dose rate in the proximity of the closest resident was 4.2 mrem per standard month (TLD #s: 108, 109) which is consistent with the control measurements of 4.3 mrem per standard month.

The mean annual dose for each of the geographic location categories demonstrates that there 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 Trends A comparison of historical TLD results can be made using the different geographical categories of measurement locations. These include Site Boundary TLDs located in each of the 16 meteorological sectors, TLDs located offsite in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs located at control locations. Site Boundary, Offsite Sector and Special Interest TLD locations became effective in 1985; therefore, trends for these results can only be evaluated from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Offsite Sectors and Special Interest groups from 1992 through 2005:

TLD Data - Yearly Mean 6

Control Site Boundary Offsite Specials 5

4 mRem/Standard Month 3

2 1

0 1994 1996 1998 2000 2002 2004 5 - 27

TLDs located at the site boundary averaged 4.2 mrem per standard month during 2005 (Site Boundary average results do not include TLDs influenced by radwaste buildings and radwaste shipping activities). This result is consistent with the previous five year average of 4.4 mrem per standard month.

Offsite Sector TLDs averaged 4.0 mrem per standard month during 2005. This result is also consistent with the previous five year average of 4.3 mrem per standard month for offsite sectors.

Special Interest TLD locations averaged 3.9 mrem per standard month during 2005 which is consistent with the previous five year average of 4.4 mrem per standard month.

The last group of TLD locations required by the ODCM is the Control Group. This group utilized TLD locations positioned well beyond the site. 2005 control results from all Control TLDs averaged 4.3 mrem per standard month, consistent with the previous five year average of 4.4 mrem per standard month. The 2005 TLD program results, when compared to the previous twenty years, showed no significant trends relative to increased dose rates in the environment.

Section 7.0, Tables 7-15 through 7-20 show the historical environmental sample data for environmental TLDs.

5.2.5 MILK A. Results Summary A total of 72 milk samples were collected dur ing the 2005 program and analyzed for gamma emitting radionuclides using gamma spectroscopy. In addition, each sample undergoes an iodine extraction procedure to determine the presence of Iodine-131 (I-131).

I-131, a possible plant related radionuclide, is measured to evaluate the cow/milk dose pathway to man. I-131 was not detected in any of the 72 milk samples collected in 2005 from the four milk sample locations.

Gamma spectral analyses of the milk samples showed only naturally occurring radionuclides, such as K-40, were detected in milk samples collected during 2005. K-40 was detected in all indicator and control samples. K-40 is a naturally occurring radionuclide and is found in many environmental sample media.

The 2005 results demonstrate that routine operations of the Nine Mile Point Site resulted in no measurable contribution to the dose to the public from the cow/milk pathway.

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B. Sampling Overview Milk samples were collected from three indicator locations and one control location. The ODCM requires that three sample locations be within five miles of the site. Based on the milk animal census, there were no adequate milk sample locations within five miles of the site in 2005. Samples were collected from four farms located beyond the five- mile requirement to ensure the continued monitoring of this important pathway. The three indicator locations ranged from 6.3 to 8.7 miles from the site. The control samples were collected from a farm located 16.0 miles from the site and in a low frequency wind sector (upwind). The geographic location of each sample location is listed below:

Location No. Direction From Site Distance (Miles) 76 ESE 6.3 55 E 8.7 4 ESE 7.6 77 (Control) S 16.0 Samples were collected from Indicator locations #4, #55, # 76 and Control location #77 from April through December, during the first and second half of each month. Samples were not required to be collected during January through March of 2004 as a result of I-131 not having been detected in samples collected during November and December of 2004, as stipulated in the ODCM.

C. Data Evaluation and Discussion Each milk sample is analyzed for gamma emitters using gamma spectral analysis. The I-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 2005 are provided in Section 6.0, Table 6-11.

Iodine-131 was not detected in any indicator or control milk samples analyzed during 2005. All I-131 milk results were reported as Lower Limits of Detection (LLD). The LLD results for all samples ranged from < 0.34 to < 0.85 pCi/liter. No plant-related radionuclides were detected in any milk sample collected in 2005. K-40 was the most abundant radionuclide detected, and found in every indicator and control sample collected.

K-40 is a naturally-occurring radionuclide and is found in many of the environmental media samples. The K-40 concentration for all milk samples analyzed ranged from 1310 to 1930 pCi/ liter. Cs-137 was not detected in any indicator or control milk sample collected in 2005.

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D. Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected.

The dose to man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that the dose received due to exposure from plant effluents is negligible compared to the dose received from naturally occurring radionuclides. Significant levels of K-40 have been measured in environmental samples. A 70 kilogram (154 pound) adult contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalatio n, consumption, etc.).

The dose to bone tissue is about 20 mrem per year as a result of internal deposition of naturally-occurring K-40.

E. Data Trends Man- made radionuclides are not routinely detected in milk samples. In the past twenty years, Cs-137 was only detected in 1986, 1987, and 1988. The mean Cs-137 indicator activities for those years were 8.6, 6.8 and 10.0 pCi/liter, respectively. I-131 was measured in two milk samples collected in 1997 from a single sample location, having a mean concentration of 0.50 pCi/liter and was of undetermined origin. The previous detection was in 1986 with a mean concentration of 13.6 pCi/liter. The 1986 activity was a result of the Chernobyl accident.

The comparison of 2005 data to historical results over the operating life of the plants shows that Cs-137 and I-131 levels have decreased significantly since 1983.

Historical data of milk sample results for Cs-137 and I-131 are presented in Section 7.0, Tables 7-17 and 7-18.

5.2.6 FOOD PRODUCTS (VEGETATION)

A. Results Summary There were no plant-related radionuclides detected in the 16 food product samples collected and analyzed for the 2005 program.

Detectable levels of naturally occurring K-40 were measured in all control and indicator sample s collected for the 2005 program. Be-7 a naturally-occurring radionuclide, was also detected intermittently in samples collected in 2005. These results are consistent with the levels measured in 2004 and previous years.

The results of the 2005 sampling program demonstrate that there is no measurable impact on the dose to the public from the garden pathway as a result of plant operations.

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B. Data Analysis and Discussion Food product samples were collected from four indicator locations and one control location. The indicator locations are represented by nearby gardens in areas of highest D/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 2005 included one variety considered to be an edible broadleaf vegetable. Collards, an edible broadleaf vegetable, was collected from one indicator location. Collards was not available from the control location. The general lack of edible broadleaf vegetation samples was the result of grower preference and such varieties were not available in local gardens. Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Non-edible vegetation consisting of squash leaves, bean leaves, rhubarb, grape leaves, pumpkin leaves, squash leaves, and cucumber leaves were collected for the 2005 program. The leaves of these plants were sampled as representative of broadleaf vegetation which is a measurement of radionuclide deposition. In addition to the broadleaf vegetation, tomato samples were collected from three locations. Samples were collected during the late summer/fall harvest season. Each sample was analyzed for gamma emitters using gamma spectroscopy.

The analysis of food product samples collected during 2005 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 ga rden food products grown in areas close to the site.

Naturally occurring Be-7 and K-40 were detected in food product samples. The concentration of Be-7 in vegetation samples ranged from 0.28 to 1.02 pCi/g (wet). The concentration of K-40 in indicator and control samples ranged from 1.95 to 4.16 pCi/g (wet). The results for naturally-occurring radionuclides are consistent with the data of prior years.

Analytical results for food products are found in Section 6.0, Table 6-12.

C. Dose Evaluation The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant-related radionuclides were detected. The food product sampling program demonstrated no measurable offsite dose to man from this pathway as a result of operations of the plants located at Nine Mile Point.

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D. Data Trends Food product/vegetation sample results for the last five years demonstrate that there is no chronic deposition or buildup of plant-related radionuclides in the garden food products in the environs near the site.

The last positive indication was for Cs-137 which was detected at one indicator location in 1999 with a concentration of 0.007 pCi/g (wet).

Historically, Cs-137 had been detected in ten separate years since 1976 ranging from a maximum mean concentration of 0.047 pCi/g (wet) in 1985 to a minimum of 0.008 pCi/g (wet) in 1999. The trend for Cs-137 is a general reduction in concentration to non detectable levels in samples collected during the 2000 through 2005 sample programs.

Historical data of food product results are presented in Section 7.0, Tables 7-19 and 7-20.

5.2.7 LAND USE CENSUS RESULTS A. Results Summary The ODCM requires that an annual land use census be performed to identify potential new locations for milk sampling and for calculating the dose to man from plant effluents. In 2005, a milk animal census, a nearest resident census and a garden survey were performed.

The results of the closest residence census conducted in 2005 required no change to the James A. FitzPatrick Nuclear Power Plant Dose Calculation Manual (ODCM).

A garden census, not required by the ODCM, is performed to identify appropriate garden sampling locations and dose calculation receptors. Garden samples were collected from a number of locations listed in Appendix H of the ODCM and identified in the census as active for 2005. See Table 3.3-1 for 2005 sampling locations.

B. Data Evaluation and Discussion A land use census is conducted each year to determine the utilizatio n of land in the vicinity of the Nine Mile Point site. The land use census consists of two types of surveys. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. The census, covering areas out to a distance of 10 miles exceeds the 5 mile distance required by the ODCM. A resident census is conducted and is designed to identify the nearest resident in each meteorological sector out to a distance of 5 miles.

5 - 32

The milk animal census is an estimation of the number of cows and goats within an approximate 10 mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk animal owners and also by road surveys to locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted by telephone or in person.

The local county agricultural extension service is also contacted as an additional source of information concerning new milk animal locations in the vicinity of the site.

The number of milk animals located within an approximate 10 mile radius of the site was estimated to be 507 cows and 7 goats based on the 2005 land use census. The number of cows has increased by 7 and the number of goats has decreased by 3 when compared to the 2004 census. The goats identified during the census were not milking goats. 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 in order 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 residences are located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW.

The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-14. No changes were identified in the 2005 census for the closest resident in the land based meteorological sectors. The nearest resident locations are illustrated in Section 3.3, Figure 3.3-5.

5.2.8 DIRECT RADIATION, THERMOLUMINESCENT DOSIMETERS (TLD)

Independent Spent Fuel Storage Installation (ISFSI)

A. Results Summary Thermoluminescent Dosimeters (TLDs) are used top measure direct radiation (gamma dose) 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 prior to loading the first storage casks for baseline dose rate determination in the general area of the pad.

On April 25, 2002, the ISFSI facility was placed in service with the installation of the first storage cask on the pad. Two subsequent storage casks were moved to the storage facility on May 8, 2002 and May 21, 2002. A second series of six storage casks were added 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 total number of casks in 5 - 33

storage to nine. Dose rates measured around the perimeter of the storage facility during the first 3 quarters of 2005 were consistent with those measured in the previous year. The mean quarterly dose rates increased by a factor of 1.3 in the fourth quarter over a the mean of the previous three quarters. The maximaum dose rate measured in the first 3 quarters of 2005 was 29.7 mrem per standard month. The maximum dose rate in the fourth quarter of 2005 was 33.2 mrem per standard month total or 19.7 mrem per standard mo nth above the applicable baseline dose rate. The change in dose rate is the result of the six casks that were loaded on the pad starting in September of 2005. The nine casks are located on the northern end of the pad are in close proximity to the north ISFSI perimeter fence. In addition, the radiation exposure from hydrogen water chemistry also contribute to the higher dose rates measured at the north fe nceline of the ISFSI storage facility.

The increase in dose rate is limited to the general area of the storage facility. The implementation and loading of the ISFSI project has resulted in no increase in dose at the site boundary or to the public. The analysis of offsite doses from direct radiation measurements, presented in Section 5.2.4 of this report, concludes that there is no significant difference in annual dose to the public at or beyond the site boundary. The measured annual dose rate at the nearest residence to the site was consistent with the dose rates measured at the site boundary and the offsite control locations. The results for the Site Boundary, Offsite Sectors, and Special Interest (offsite) were well within expected normal variation whe n compared to the Control TLD results. The results for the 2005 environmental TLD monitoring program indicate that there is no significant increase in dose rates as a result of operations at the site. The use of hydrogen injection and the implementation of the Independent Spent Fuel Storate Installation (ISFSI) at the FitzPatrick plant did not measurably increase the ambient radiation exposure rate at or beyond the site boundary. The lack of a dose rate increase at or beyond the site boundary is consistent with design calculations performed to evaluate compliance with 10 CFR72.104(a).

The measured results of the 2005 TLD monitoring program demonstrate compliance with the offsite dose limits to members of the public specified in 40CFR190 and 10CFR72.104(a).

B. Program Design An array of eight TLD locations was established around the perimeter of the ISFSI pad 18 months prior to facility usage. Six months prior to the facility becoming operational, an additional 10 TLD locations were established at areas of interest on the facility perimeter.

These preoperational TLDs were used for baseline dose rate determination. The TLDs are placed, collected and read each quarter. Two dosimeters are placed at each location and 5 - 34

the average of the two dosimeters is reported. The quarterly results are 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 Evaluation The maximum dose rate of 19.7 mrem per standard month above the baseline dose rate was measured during the fourth quarter at the north perimeter fence. The lowest measured dose rate in the fourth quarter of 2005 was 5.6 mrem per standard month above the baseline dose rate and was measured at the southern perimeter fence due to the larger distance between the casks and the perimeter fence. The maximum dose at the southern perimeter fence was slightly higher at 8.6 mrem per standard month. The western perimeter fence had a maximum measured dose rate of 12.2 mrem above the baseline. The maximum measured dose rate on the eastern perimeter fence was 10.5 mrem per standard month above the baseline.

An evaluation of Site Boundary TLDs and Control TLDs results for 2005 shows that there 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 this period show no significant difference in control and site boundary dose rates for 2005.

2005 DOSE IN MREM PER STANDARD MONTH Minimum Maximum Mean Site Boundary 3.4 4.8 4.2 Control 3.4 5.1 4.3 5 - 35

5.3 CONCLUSION

The Radiological Environmental Monitoring Program (REMP) is an ongoing program implemented to measure and document the radiological impact of the James A. FitzPatrick operations on the local environment. 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 for possible short and long term historical trends.

The federal government has established dose limits to protect the public from radiation and radioactivity. 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 results of the 2005 Radiological Environmental Surveillance Program continue to clearly demonstrate that there is no significant short term or chronic long term radiological impact on the environment in the vicinity of the Nine Mile Point site. No unusual radiological characteristics were measured or observed in the local environment. The Environmental Monitoring Program continues to demonstrate that the effluents from the site to the environment contribute no 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 programs and the onsite Independent Spent Fuel Storage Installation (ISFSI) program. Environmental radiation levels measured 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 1980s and the 1986 accident at the Chernobyl Nuclear Power Plant. Both of these source terms have contributed to a measurable inventory of Cs-137 in the environment. The results for the 2005 sample program demonstrate that the concentrations of man- made radionuclides continue to decline. This reduction in environmental background concentrations will allow for the site environmental program to become mo re sensitive to the measurable impact of plant operations on the environment as time goes on.

5 - 36

The environmental monitoring program detected one potential plant-related radionuclide in the sample media collected during 2005. Cs-137 was detected in one shoreline sediment sample. The source of the Cs-137 measured in this sample is considered to be fallout from past atmospheric nuclear weapons testing. The measured concentration of Cs-137 in the sample was small and consistent with historical results for shoreline sediment. The impact of these Cs-137 concentrations are minimal in terms of dose to man. 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 vast majority of the total annual dose to members of the general public. The dose to members of the public, resulting from plant operations, is extremely small in comparison to the dose contribution from natural background levels and sources other than the plants. The whole body dose in Oswego County due to natural sources is approximately 50 - 60 mrem per individual per year as demonstrated by control environmental TLDs. The fraction of the annual dose to man, attributable to site operation, remains insignificant.

Based upon the overall results of the 2005 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of the site.

5 - 37

5.4 REFERENCES

1. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Ro utine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, March 1976.

2. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, October 1977 (Revision 1).

3. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, December, 1975.

4. U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

5. National Council on Radiation Protection and Measurements (NCRP), Environmental Radiation Measurements, NCRP Report No. 50, 1975.

6. National Council on Radiation Protection and Measurements (NCRP), Natural Background Radiation in the United States, NCRP Report No. 45, 1975.

7. National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.

8. National Council on Radiation Protection and Measurments (NCRP), Radiation Exposure from Consumer Products and Miscellaneous Sources, NCRP Report No. 56, 1977.

9. Interna tional Commission on Radiological Protection (ICRP), Radionuclide Release into the Environment: Assessment of Doses to Man, ICRP Publication 29, 1979.

10. Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill., 1980.

11. Schleien, Bernard. The Health Physics and Radiological Health Handbook. Scinta, Inc.,

Silver Spring, Maryland, 1992.

5 - 38

12. U.S. Department of Health and Human Services. Preparedness and Response in Radiation Accidents, National Center for Devices and Radiological Health, Rackville, Maryland 20857, August 1983.

13. National Council on Radiation Protection and Measurments (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 93, 1987.

14. National Council on Radiation Protection and Measurements (NCRP), Exposure of the Population in the United States and Canada from National Background Radiation, NCRP Report No. 94, 1987.

5 - 39

6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 6.1 Environmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year.

These values are comprised of both positive values and LLD values where applicable.

6.2 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal (see Section 3.7.3 for detailed explanation).

6.3 When the initial count of a sample indicates the presence of radioactivity, two recounts are normally performed. When a radionuclide is positively identified in two or more counts, the analytical results for that radionuclide is reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology).

6.4 Many of the tables are footnoted with the term "Plant Related Radionuclides".

Plant related radionuclides are radionuclides that are produced in the reactor as a result of plant operation either through the activation or fission process.

6-1

TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2005 Results in Units of pCi/g (dry) +/- 1 Sigma SAMPLE COLLECTION GAMMA EMITTERS LOCATION DATE K-40 Co-60 Cs-134 Cs-137 Zn-65 Others 04/19/05 19.2 +/- 1.01 <0.079 <0.077 0.090 +/- 0.031 <0.144 <LLD Sunset Bay (05)***

10/19/05 16.8 +/- 0.66 <0.060 <0.059 0.063 +/- 0.02 <0.081 <LLD 04/19/05 14.8 +/- 0.59 <0.042 <0.054 <0.046 <0.061 <LLD Lang's Beach (06, Control) 10/19/05 9.70 +/- 0.46 <0.045 <0.044 <0.042 <0.070 <LLD Plant related radionuclides

- - Corresponds to sample locations noted on Figure 3.3-5 6-2

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2005 Results in Units of pCi/g (wet) +/- 1 Sigma FITZPATRICK (03)***

DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Others 06/03/05 Brown Trout 5.44 +/- 0.39 <0.043 <0.052 <0.164 <0.056 <0.103 <0.054 <0.047 <LLD

<LLD 06/03/05 Walleye 4.66 +/- 0.42 <0.049 <0.053 <0.158 <0.057 <0.072 <0.048 <0.037 Smallmouth <LLD 06/07/05 3.79 +/- 0.37 <0.033 <0.040 <0.148 <0.048 <0.098 <0.044 <0.039 Bass

<LLD 09/07/05 Brown Trout 4.78 +/- 0.42 <0.048 <0.042 <0.128 <0.059 <0.099 <0.031 <0.039

<LLD 09/07/05 Chinook Salmon 4.14 +/- 0.72 <0.019 <0.117 <0.248 <0.029 <0.206 <0.083 <0.083

<LLD 09/07/05 Walleye 6.54 +/- 0.50 <0.044 <0.055 <0.140 <0.070 <0.133 <0.060 <0.039 Smallmouth <LLD 09/07/05 4.50 +/- 0.40 <0.038 <0.048 <0.119 <0.035 <0.112 <0.031 <0.042 Bass

- - Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6-3

TABLE 6-2 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2005 Results in Units of pCi/g (wet) +/- 1 Sigma NINE MILE POINT (02)***

DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Others 06/15/05 Brown Trout 5.12 +/- 0.45 <0.051 <0.037 <0.121 <0.063 <0.076 <0.049 <0.050 <LLD 06/15/05 Walleye 5.30 +/- 0.38 <0.045 <0.037 <0.128 <0.042 <0.107 <0.028 <0.045 <LLD Smallmouth 06/15/05 4.17 +/- 0.47 <0.046 <0.059 <0.084 <0.070 <0.131 <0.055 <0.054 <LLD Bass 09/07/05 Brown Trout 3.94 +/- 0.52 <0.054 <0.065 <0.221 <0.038 <0.146 <0.043 <0.046 <LLD 09/07/05 Chinook Salmon 4.78 +/- 0.46 <0.030 <0.041 <0.119 <0.043 <0.126 <0.044 <0.043 <LLD 09/07/05 Walleye 3.95 +/- 0.39 <0.051 <0.041 <0.132 <0.053 <0.092 <0.048 <0.046 <LLD

- - Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6-4

TABLE 6-2 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2005 Results in Units of pCi/g (wet) +/- 1 Sigma OSWEGO HARBOR (CONTROL) (00)***

DATE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Others 06/09/05 Brown Trout 6.71 +/- 0.50 <0.049 <0.056 <0.154 <0.046 <0.126 <0.052 <0.053 <LLD 06/09/05 Walleye 2.51 +/- 0.31 <0.039 <0.043 <0.118 <0.047 <0.082 <0.032 <0.040 <LLD Smallmouth 06/09/05 3.59 +/- 0.36 <0.036 <0.032 <0.142 <0.033 <0.097 <0.037 <0.039 <LLD Bass 09/08/05 Brown Trout 4.53 +/- 0.43 <0.045 <0.052 <0.142 <0.054 <0.104 <0.042 <0.027 <LLD 09/08/05 Chinook Salmon 5.10 +/- 0.44 <0.040 <0.051 <0.128 <0.064 <0.127 <0.047 <0.030 <LLD 09/13/05 Walleye 3.84 +/- 0.52 <0.046 <0.052 <0.172 <0.058 <0.091 <0.043 <0.048 <LLD Smallmouth 09/13/05 5.39 +/- 0.46 <0.050 <0.053 <0.160 <0.062 <0.126 <0.054 <0.045 <LLD Bass

- - Corresponds to sample location noted on Figure 3.3-5 Plant related radionuclides 6-5

TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2005 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma STATION CODE PERIOD DATE TRITIUM First Quarter 010/5/05 - 04/04/05 <416 FITZPATRICK* Second Quarter 04/04/05 - 07/01/05 <423 (03, INLET)*** Third Quarter 07/01/05 - 09/28/05 <422 Fourth Quarter 09/28/05 - 01/04/06 <498 First Quarter 12/29/05 - 04/01/05 <413 OSWEGO STEAM STATION* Second Quarter 04/01/05 - 06/30/05 <423 (08, CONTROL)*** Third Quarter 06/30/05 - 09/30/05 <421 Fourth Quarter 09/30/05 - 12/30/05 <471 First Quarter 12/29/05 - 04/01/05 <413 NINE MILE POINT UNIT 1** Second Quarter 04/01/05 - 06/30/05 <423 (09, INLET)*** Third Quarter 06/30/05 - 09/30/05 <421 Fourth Quarter 09/30/05 - 12/30/05 <471 First Quarter 12/29/05 - 04/01/05 <413 NINE MILE POINT UNIT 2** Second Quarter 04/01/05 - 06/30/05 <423 (11, INLET)*** Third Quarter 06/30/05 - 09/30/05 <421 Fourth Quarter 09/30/05 - 12/30/05 <471 First Quarter 12/29/05 - 04/01/05 <413 OSWEGO CITY WATER** Second Quarter 04/01/05 - 06/30/05 <423 (10)*** Third Quarter 06/30/05 - 09/30/05 <421 Fourth Quarter 09/30/05 - 12/30/05 <471

Sample location required by ODCM

- Optional sample location

- - Corresponds to sample location noted on Figure 3.3-4 6-6

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2005 Results in Units of pCi/liter +/- 1 Sigma OSWEGO STEAM STATION * (08, CONTROL)***

NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE I-131 <10.6 <8.35 <14.3 <8.1 <12.7 <14.7 Cs-134 <3.84 <1.58 <4.15 <1.64 <1.95 <4.98 Cs-137 <3.26 <2.29 <3.88 <2.13 <3.38 <4.35 Zr-95 <6.27 <4.32 <6.91 <4.67 <6.66 <11.9 Nb-95 <3.91 <2.94 <5.46 <2.98 <4.02 <5.89 Co-58 <3.92 <2.58 <4.11 <2.70 <3.93 <5.74 Mn-54 <3.3 <2.51 <3.8 <2.54 <3.22 <4.83 Fe-59 <11.6 <7.43 <12.9 <7.12 <10.5 <13.6 Zn-65 <7.55 <5.36 <9.41 <5.45 <7.61 <12.1 Co-60 <2.92 <2.38 <4.32 <2.19 <3.08 <5.21 K-40 353+/-23.1 244+/-13.3 152+/-21.1 277+/-13.9 260+/-19.1 202+/-27.7 Ba/La-140 <9.27 <6.22 <11.6 <5.59 <9.12 <13.6 NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER I-131 <8.51 <12.5 <12.7 <5.04 <7.5 <13.7 Cs-134 <2.77 <2.60 <3.92 <1.73 <1.6 <4.06 Cs-137 <2.60 <2.77 <3.78 <1.69 <2.77 <3.83 Zr-95 <4.74 <6.32 <8.43 <3.22 <5.05 <7.29 Nb-95 <3.55 <4.53 <5.76 <2.28 <3.40 <5.03 Co-58 <3.02 <3.67 <4.71 <1.83 <2.89 <4.54 Mn-54 <2.57 <2.87 <4.45 <1.92 <2.78 <4.22 Fe-59 <7.67 <10.2 <17.3 <5.54 <7.19 <13.1 Zn-65 <3.51 <7.22 <10.8 <4.22 <6.53 <9.45 Co-60 <2.51 <3.21 <4.24 <2.01 <2.85 <4.27 K-40 111+/-12.5 190+/-18.0 165+/-25.4 99.6+/-9.3 117+/-13.2 370+/-25.8 Ba/La-140 <6.9 <12.6 <14.6 <4.92 <7.14 <11.8

Sample location required by ODCM.

- - Corresponds to sample location noted on Figure 3.3-4 6-7

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2005 Results in Units of pCi/liter +/- 1 Sigma FITZPATRICK* (03, INLET)***

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE I-131 <7.21 <8.21 <9.26 <12.1 <11.7 <11.1 Cs-134 <1.52 <3.53 <3.05 <4.1 <3.84 <3.97 Cs-137 <2.08 <3.30 <2.57 <4.87 <3.46 <3.47 Zr-95 <4.72 <7.08 <6.23 <6.94 <7.06 <5.98 Nb-95 <3.08 <4.51 <3.95 <6.18 <5.17 <4.52 Co-58 <2.65 <3.73 <3.29 <4.46 <4.42 <3.68 Mn-54 <2.28 <3.27 <3.03 <3.65 <3.80 <3.68 Fe-59 <7.85 <11.6 <9.27 <12.9 <11.3 <10.5 Zn-65 <3.14 <6.80 <5.95 <8.09 <9.57 <7.17 Co-60 <2.22 <4.55 <2.99 <5.64 <4.29 <3.70 K-40 271+/-13.9 148+/-19.5 151+/-15.6 167+/-24.7 190+/-23.9 115+/-17.4 Ba/La-140 <5.27 <8.44 <7.76 <13.7 <8.15 <8.58 NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER I-131 <10.6 <9.17 <11.4 <9.98 <6.68 <12.3 Cs-134 <4.12 <3.29 <4.89 <3.73 <1.54 <4.12 Cs-137 <4.30 <3.43 <3.74 <3.48 <2.54 <3.88 Zr-95 <6.72 <6.53 <8.03 <5.97 <4.20 <7.79 Nb-95 <6.34 <4.86 <4.78 <3.14 <3.08 <5.16 Co-58 <5.14 <3.74 <4.91 <3.92 <2.83 <4.57 Mn-54 <3.87 <3.73 <4.62 <3.42 <2.86 <3.67 Fe-59 <13.1 <10.8 <13.1 <11.3 <8.44 <14.8 Zn-65 <6.26 <7.80 <9.93 <5.30 <6.42 <10.4 Co-60 <4.71 <4.43 <4.48 <3.47 <2.76 <4.42 K-40 108+/-20.2 209+/-20.6 196+/-22.9 136+/-17.7 79.1+/-12.2 187+/-23.0 Ba/La-140 <9.2 <8.86 <7.21 <8.59 <6.93 <12.3

Sample location required by ODCM.

- - Corresponds to sample location noted on Figure 3.3-4 6-8

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2005 Results in Units of pCi/liter +/- 1 Sigma NINE MILE POINT UNIT 1** (09, INLET)***

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE I-131 <10.6 <8.21 <10.8 <14.0 <12.3 <14.4 Cs-134 <3.82 <3.54 <2.65 <3.87 <3.73 <3.62 Cs-137 <3.17 <3.12 <2.28 <3.77 <3.77 <5.11 Zr-95 <6.74 <6.79 <5.50 <9.58 <7.05 <9.65 Nb-95 <4.45 <4.03 <3.04 <6.05 <5.30 <5.97 Co-58 <4.01 <3.43 <3.01 <5.43 <3.96 <5.52 Mn-54 <3.02 <3.69 <2.58 <4.39 <3.77 <5.33 Fe-59 <11.8 <11.3 <8.57 <16.6 <12.1 <15.7 Zn-65 <8.28 <7.89 <5.70 <10.8 <8.86 <11.9 Co-60 <4.11 <3.77 <2.74 <5.05 <3.62 <5.25 K-40 159+/-20.1 189+/-21.1 182+/-14.6 186+/-25.3 188+/-21.7 341+/-33.4 Ba/La-140 <11.1 <8.08 <7.95 <12.5 <11.6 <14.6 NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER I-131 <10.1 <13.9 <9.16 <9.21 <8.63 <11.7 Cs-134 <2.46 <3.33 <2.23 <2.70 <2.89 <3.44 Cs-137 <2.87 <3.36 <2.63 <2.30 <2.72 <3.39 Zr-95 <6.29 <7.03 <5.54 <4.82 <5.45 <6.27 Nb-95 <4.13 <4.49 <4.30 <3.32 <3.86 <4.64 Co-58 <3.54 <4.40 <3.35 <2.97 <3.24 <3.37 Mn-54 <3.03 <3.82 <2.66 <2.49 <2.80 <3.14 Fe-59 <10.6 <12.8 <10.4 <8.15 <9.74 <10.6 Zn-65 <8.12 <4.84 <7.45 <6.17 <7.16 <8.13 Co-60 <2.68 <3.78 <3.00 <2.83 <3.01 <3.24 K-40 385+/-23.3 180+/-21.0 131+/-15.1 197+/-14.8 196+/-16.6 143+/-17.3 Ba/La-140 <9.19 <9.26 <9.70 <7.62 <8.40 <10.2

- Optional sample location.

- - Corresponds to sample location noted on Figure 3.3-4 6-9

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2005 Results in Units of pCi/liter +/- 1 Sigma NINE MILE POINT UNIT 2** (11, INLET)***

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE I-131 <10.0 <7.46 <8.50 <8.56 <10.3 <14.1 Cs-134 <2.71 <2.31 <1.89 <2.58 <2.86 <1.85 Cs-137 <2.66 <2.67 <1.63 <2.43 <2.64 <2.47 Zr-95 <5.86 <5.76 <3.71 <5.07 <6.32 <6.66 Nb-95 <4.27 <3.45 <2.62 <3.68 <3.39 <3.89 Co-58 <3.28 <2.87 <2.05 <2.86 <3.18 <3.55 Mn-54 <3.01 <2.38 <1.96 <2.35 <3.18 <3.30 Fe-59 <11.1 <6.76 <6.34 <7.75 <8.60 <8.58 Zn-65 <3.76 <3.37 <3.91 <5.38 <5.95 <7.32 Co-60 <3.50 <3.03 <1.96 <2.62 <2.73 <3.65 K-40 157+/-16.4 144+/-14.5 90.8+/-9.37 87.9+/-13.0 159+/-16.3 168+/-17.4 Ba/La-140 <7.8 <6.37 <6.32 <8.12 <8.45 <11.4 NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER I-131 <9.73 <11.8 <12.7 <8.02 <12.5 <14.2 Cs-134 <3.28 <3.11 <4.34 <2.39 <3.27 <3.79 Cs-137 <2.65 <2.73 <4.14 <2.21 <2.70 <3.51 Zr-95 <5.93 <5.79 <7.56 <4.72 <6.15 <8.25 Nb-95 <3.79 <3.77 <5.12 <3.03 <3.99 <4.92 Co-58 <3.06 <2.92 <3.97 <2.55 <3.12 <4.78 Mn-54 <2.74 <2.75 <4.15 <2.41 <2.65 <3.92 Fe-59 <8.50 <8.40 <12.5 <7.86 <8.82 <13.7 Zn-65 <5.39 <5.99 <7.15 <3.07 <7.18 <9.25 Co-60 <2.85 <2.81 <4.29 <2.39 <3.06 <3.71 K-40 145+/-14.8 104+/-12.9 164+/-21.5 332+/-15.4 120+/-14.2 <153+/-21.9 Ba/La-140 <7.42 <8.79 <9.21 <7.45 <9.16 <11.5

- Optional sample location

- - Corresponds to sample location noted on Figure 3.3-4 6 - 10

TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2005 Results in Units of pCi/liter +/- 1 Sigma OSWEGO CITY WATER** (10)***

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE I-131 <10.7 <8.45 <14.8 <9.53 <10.6 <13.7 Cs-134 <2.03 <1.74 <3.31 <2.16 <2.03 <1.96 Cs-137 <3.13 <2.18 <3.56 <3.21 <2.97 <3.03 Zr-95 <5.50 <4.38 <8.75 <5.33 <5.87 <6.10 Nb-95 <3.53 <3.23 <5.22 <3.61 <3.86 <4.32 Co-58 <2.94 <2.56 <4.84 <2.73 <3.11 <3.43 Mn-54 <2.90 <2.52 <3.39 <2.76 <3.03 <2.80 Fe-59 <7.96 <7.48 <11.2 <8.44 <8.87 <9.86 Zn-65 <6.72 <5.39 <7.55 <3.65 <6.73 <7.07 Co-60 <3.00 <2.14 <4.28 <2.80 <2.94 <3.26 K-40 123+/-15.4 252+/-13.4 190+/-22.5 160+/-15.3 139+/-15.3 103+/-15.1 Ba/La-140 <9.13 <6.16 <15.0 <6.75 <8.35 <10.2 NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER I-131 <8.87 <9.81 <8.36 <9.68 <10.4 <13.5 Cs-134 <2.58 <2.40 <3.07 <1.86 <3.47 <3.94 Cs-137 <2.53 <1.80 <2.78 <2.82 <3.58 <3.28 Zr-95 <5.66 <4.11 <5.14 <5.54 <5.91 <6.42 Nb-95 <3.67 <2.84 <3.49 <4.04 <4.22 <4.61 Co-58 <3.23 <2.29 <3.55 <2.99 <3.84 <4.24 Mn-54 <2.86 <2.47 <2.77 <2.51 <3.37 <3.63 Fe-59 <8.84 <7.14 <9.49 <10.4 <12.2 <11.4 Zn-65 <5.77 <4.58 <6.41 <5.85 <7.89 <8.88 Co-60 <2.88 <2.06 <2.90 <2.80 <3.34 <3.45 K-40 155+/-15.2 88.9+/-10.1 105+/-13.7 150+/-14.5 390+/-23.4 141+/-18.4 Ba/La-140 <8.79 <7.68 <8.73 <8.54 <9.08 <11.6

- Optional Sample location

- - Corresponds to sample location noted on Figure 3.3-4 6 - 11

TABLE 6-5 NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE STATIONS - 2005 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS Week End R-1

R-2

R-3

R-4

R-5

D-2 ** E ** F ** G **

Date 1/11/2005 0.019 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 0.019 +/- 0.002 0.018 +/- 0.002 1/17/2005 0.020 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.002 0.021 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.021 +/- 0.002 1/25/2005 0.022 +/- 0.002 0.025 +/- 0.002 0.022 +/- 0.002 0.022 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 2/1/2005 0.019 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 2/8/2005 0.025 +/- 0.002 0.026 +/- 0.002 0.024 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.028 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 2/15/2005 0.021 +/- 0.002 0.018 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.019 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 2/23/2005 0.016 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 3/1/2005 0.019 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.002 0.022 +/- 0.002 0.017 +/- 0.002 0.019 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 3/8/2005 0.018 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.014 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.002 3/15/2005 0.017 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.017 +/- 0.001 0.022 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 3/22/2005 0.014 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.001 0.016 +/- 0.002 3/29/2005 0.016 +/- 0.001 0.015 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 4/5/2005 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.012 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 4/12/2005 0.021 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.002 0.022 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 4/19/2005 0.036 +/- 0.002 0.041 +/- 0.002 0.026 +/- 0.002 0.031 +/- 0.002 0.026 +/- 0.002 0.029 +/- 0.002 0.029 +/- 0.002 0.032 +/- 0.002 0.031 +/- 0.002 4/26/2005 0.015 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 5/3/2005 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.011 +/- 0.001 5/10/2005 0.022 +/- 0.002 0.026 +/- 0.002 0.020 +/- 0.001 0.022 +/- 0.002 0.020 +/- 0.001 0.018 +/- 0.001 0.023 +/- 0.002 0.018 +/- 0.001 0.016 +/- 0.001 5/17/2005 0.015 +/- 0.001 0.019 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.020 +/- 0.001 0.014 +/- 0.001 5/24/2005 0.014 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 6/1/2005 0.024 +/- 0.002 0.022 +/- 0.001 0.023 +/- 0.001 0.019 +/- 0.001 0.026 +/- 0.002 0.020 +/- 0.001 0.024 +/- 0.001 0.022 +/- 0.001 0.018 +/- 0.001 6/7/2005 0.028 +/- 0.002 0.026 +/- 0.002 0.019 +/- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.021 +/- 0.002 0.280 +/- 0.002 0.024 +/- 0.02 0.019 +/- 0.002 6/14/2005 0.240 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.024 +/- 0.002 0.024 +/- 0.002 0.023 +/- 0.002 0.022 +/- 0.001 0.021 +/- 0.001 0.025 +/- 0.002 6/21/2005 0.022 +/- 0.002 0.018 +/- 0.002 0.017 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.020 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 6/28/2005 0.029 +/- 0.002 0.027 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.022 +/- 0.002 0.024 +/- 0.002

Sample location required by ODCM

- Optional sample location 6 - 12

TABLE 6-5 (continued)

NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE STATIONS - 2005 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS Week End R-1

R-2

R-3

R-4

R-5

D-2 ** E ** F ** G **

Date 7/6/2005 0.020 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 0.022 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.001 7/12/2005 0.020 +/- 0.002 0.018 +/- 0.002 0.016 +/- 0.001 0.017 +/- 0.002 0.018 +/- 0.001 0.018 +/- 0.002 0.017 +/- 0.001 0.015 +/- 0.001 0.022 +/- 0.002 7/19/2005 0.021 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.001 0.024 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.001 7/26/2005 0.018 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 8/2/2005 0.015 +/- 0.001 0.017 +/- 0.001 0.010 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 8/9/2005 0.027 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.029 +/- 0.002 0.024 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 8/16/2005 0.025 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.002 0.024 +/- 0.002 0.024 +/- 0.002 8/23/2005 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 8/30/2005 0.016 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 9/7/2005 0.016 +/- 0.001 0.016 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 9/13/2005 0.024 +/- 0.002 0.028 +/- 0.002 0.024 +/- 0.002 0.029 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.022 +/- 0.002 0.027 +/- 0.002 9/20/2005 0.026 +/- 0.002 0.022 +/- 0.002 0.026 +/- 0.002 0.023 +/- 0.002 0.027 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.029 +/- 0.002 0.028 +/- 0.002 9/27/2005 0.022 +/- 0.001 0.020 +/- 0.001 0.021 +/- 0.002 0.018 +/- 0.001 0.024 +/- 0.002 0.020 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.001 0.021 +/- 0.001 10/4/2005 0.022 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.002 0.023 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.001 0.024 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 10/11/2005 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 10/18/2005 0.009 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 10/25/2005 0.010 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 11/1/2005 0.014 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 11/8/2005 0.023 +/- 0.002 0.024 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.002 0.025 +/- 0.002 11/15/2005 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 11/22/2005 0.022 +/- 0.002 0.017 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.022 +/- 0.002 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.021 +/- 0.002 11/29/2005 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 12/6/2005 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 12/13/2005 0.019 +/- 0.001 0.020 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.022 +/- 0.002 0.019 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 12/20/2005 0.015 +/- 0.001 0.021 +/- 0.002 0.015 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.021 +/- 0.002 12/28/2005 0.034 +/- 0.002 0.033 +/- 0.002 0.032 +/- 0.002 0.034 +/- 0.002 0.034 +/- 0.002 0.031 +/- 0.002 0.031 +/- 0.002 0.035 +/- 0.002 0.033 +/- 0.002 1/4/2006 0.013 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001

Sample location required by ODCM

- Optional sample location 6 - 13

TABLE 6-6 NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE STATIONS - 2005 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS Week End D1 ** G ** H ** I ** J ** K **

Date 1/10/2005 NA NA 0.017 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 1/17/2005 0.021 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.021 +/- 0.002 1/24/2005 0.022 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.025 +/- 0.002 1/31/2005 0.022 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.002 0.019 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.002 2/7/2005 0.021 +/- 0.002 0.021 +/- 0.002 0.029 +/- 0.002 0.024 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 2/14/2005 0.020 +/- 0.002 0.018 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 2/22/2005 0.016 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.001 0.015 +/- 0.001 2/28/2005 0.017 +/- 0.002 0.017 +/- 0.002 0.020 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.019 +/- 0.002 3/7/2005 0.016 +/- 0.002 0.017 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 0.016 +/- 0.002 3/14/2005 0.021 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.002 0.021 +/- 0.002 3/21/2005 0.018 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.001 0.016 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 3/28/2005 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 4/4/2005 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 4/11/2005 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 4/18/2005 0.023 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.001 0.020 +/- 0.001 0.021 +/- 0.002 0.020 +/- 0.001 4/25/2005 0.013 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 5/2/2005 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 5/9/2005 0.012 +/- 0.001 0.025 +/- 0.002 0.013 +/- 0.001 0.029 +/- 0.002 0.014 +/- 0.001 0.012 +/- 0.001 5/16/2005 0.011 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 5/23/2005 0.012 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 5/31/2005 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.010 +/- 0.001 6/6/2005 0.157 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 6/13/2005 0.018 +/- 0.001 0.022 +/- 0.001 0.021 +/- 0.001 0.022 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.001 6/20/2005 0.006 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 6/27/2005 0.014 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001

- Optional sample location NA = No Sample Available 6 - 14

TABLE 6-6 (continued)

NMPNS/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE STATIONS - 2005 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS Week End D1 ** G ** H ** I ** J ** K **

Date 7/5/2005 0.018 +/- 0.001 0.020 +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 7/11/2005 0.015 +/- 0.001 0.016 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.001 7/18/2005 0.022 +/- 0.002 0.019 +/- 0.001 0.022 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0.002 0.022 +/- 0.002 7/25/2005 0.015 +/- 0.001 0.021 +/- 0.002 0.015 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 8/1/2005 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 8/8/2005 0.026 +/- 0.002 0.028 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.028 +/- 0.002 0.029 +/- 0.002 8/15/2005 0.023 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 0.023 +/- 0.002 0.026 +/- 0.002 0.026 +/- 0.002 8/22/2005 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 8/29/2005 0.014 +/- 0.001 0.010 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 9/6/2005 0.017 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 9/12/2005 0.021 +/- 0.002 0.021 +/- 0.002 0.022 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.019 +/- 0.002 9/19/2005 0.028 +/- 0.002 0.030 +/- 0.002 0.028 +/- 0.002 0.033 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 9/26/2005 0.022 +/- 0.001 0.026 +/- 0.002 0.026 +/- 0.002 0.026 +/- 0.002 0.025 +/- 0.002 0.020 +/- 0.001 10/3/2005 0.021 +/- 0.002 0.019 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 10/10/2005 0.017 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 10/17/2005 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 10/24/2005 0.008 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 10/31/2005 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.008 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 11/7/2005 0.030 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.028 +/- 0.002 0.023 +/- 0.002 0.027 +/- 0.002 11/14/2005 0.014 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 11/21/2005 0.014 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.013 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 11/28/2005 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 12/5/2005 0.013 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 12/12/2005 0.021 +/- 0.002 0.018 +/- 0.001 0.021 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.001 12/19/2005 0.017 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 12/27/2005 0.034 +/- 0.002 0.036 +/- 0.002 0.034 +/- 0.002 0.032 +/- 0.002 0.030 +/- 0.002 0.034 +/- 0.002 1/4/2006 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001

- Optional sample location 6 - 15

TABLE 6-7 NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE STATIONS - 2005 I-131 ACTIVITY pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS Week End R-1

R-2

R-3

R-4

R-5

D-2 ** E ** F ** G **

Date 1/11/2005 <0.027 <0.021 <0.011 <0.020 <0.026 <0.023 <0.020 <0.017 <0.024 1/17/2005 <0.021 <0.024 <0.022 <0.025 <0.017 <0.024 <0.030 <0.025 <0.018 1/25/2005 <0.023 <0.018 <0.014 <0.014 <0.020 <0.016 <0.021 <0.016 <0.015 2/1/2005 <0.023 <0.018 <0.020 <0.017 <0.029 <0.013 <0.019 <0.017 <0.015 2/8/2005 <0.024 <0.018 <0.016 <0.020 <0.026 <0.017 <0.019 <0.017 <0.016 2/15/2005 <0.016 <0.017 <0.021 <0.024 <0.005 <0.028 <0.025 <0.013 <0.024 2/23/2005 <0.023 <0.021 <0.018 <0.012 <0.016 <0.013 <0.015 <0.009 <0.014 3/1/2005 <0.034 <0.020 <0.020 <0.028 <0.031 <0.017 <0.022 <0.019 <0.024 3/8/2005 <0.006 <0.017 <0.018 <0.021 <0.017 <0.023 <0.021 <0.010 <0.022 3/15/2005 <0.027 <0.019 <0.021 <0.012 <0.019 <0.026 <0.023 <0.019 <0.016 3/22/2005 <0.033 <0.026 <0.028 <0.024 <0.032 <0.029 <0.038 <0.028 <0.008 3/29/2005 <0.033 <0.029 <0.034 <0.017 <0.038 <0.024 <0.029 <0.006 <0.030 4/5/2005 <0.035 <0.021 <0.035 <0.037 <0.026 <0.038 <0.023 <0.022 <0.038 4/12/2005 <0.034 <0.007 <0.028 <0.028 <0.022 <0.030 <0.030 <0.018 <0.028 4/19/2005 <0.033 <0.026 <0.018 <0.037 <0.023 <0.019 <0.023 <0.028 <0.020 4/26/2005 <0.026 <0.025 <0.022 <0.030 <0.023 <0.027 <0.029 <0.025 <0.021 5/3/2005 <0.003 <0.025 <0.023 <0.033 <0.034 <0.030 <0.025 <0.022 <0.041 5/10/2005 <0.040 <0.030 <0.017 <0.041 <0.018 <0.029 <0.024 <0.009 <0.029 5/17/2005 <0.025 <0.030 <0.005 <0.023 <0.022 <0.032 <0.029 <0.019 <0.028 5/24/2005 <0.033 <0.036 <0.026 <0.035 <0.019 <0.027 <0.038 <0.020 <0.025 6/1/2005 <0.007 <0.016 <0.019 <0.032 <0.018 <0.020 <0.023 <0.022 <0.015 6/7/2005 <0.023 <0.023 <0.018 <0.023 <0.030 <0.022 <0.016 <0.022 <0.027 6/14/2005 <0.026 <0.025 <0.014 <0.023 <0.028 <0.026 <0.020 <0.020 <0.024 6/21/2005 <0.026 <0.029 <0.015 <0.036 <0.028 <0.008 <0.026 <0.017 <0.030 6/28/2005 <0.021 <0.021 <0.026 <0.031 <0.019 <0.026 <0.029 <0.026 <0.024

- Optional sample location 6 - 16

TABLE 6-7 (continued)

NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE STATIONS - 2005 I-131 ACTIVITY pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS Week End R-1

R-2

R-3

R-4

R-5

D-2 ** E ** F ** G **

Date 7/6/2005 <0.032 <0.020 <0.007 <0.023 <0.021 <0.022 <0.026 <0.026 <0.007 7/12/2005 <0.009 <0.036 <0.027 <0.027 <0.024 <0.030 <0.027 <0.006 <0.026 7/19/2005 <0.027 <0.031 <0.030 <0.023 <0.018 <0.033 <0.031 <0.023 <0.014 7/26/2005 <0.027 <0.025 <0.024 <0.030 <0.019 <0.019 <0.020 <0.003 <0.034 8/2/2005 <0.024 <0.038 <0.020 <0.024 <0.007 <0.015 <0.023 <0.008 <0.022 8/9/2005 <0.022 <0.19 <0.020 <0.016 <0.025 <0.012 <0.016 <0.022 <0.035 8/16/2005 <0.020 <0.015 <0.016 <0.016 <0.018 <0.017 <0.015 <0.015 <0.015 8/23/2005 <0.017 <0.011 <0.017 <0.025 <0.016 <0.018 <0.021 <0.019 <0.018 8/30/2005 <0.026 <0.016 <0.021 <0.028 <0.014 <0.016 <0.015 <0.017 <0.018 9/7/2005 <0.018 <0.016 <0.013 <0.013 <0.017 <0.020 <0.017 <0.020 <0.014 9/13/2005 <0.033 <0.027 <0.018 <0.010 <0.020 <0.024 <0.022 <0.029 <0.006 9/20/2005 <0.033 <0.027 <0.015 <0.036 <0.023 <0.033 <0.025 <0.031 <0.023 9/27/2005 <0.008 <0.035 <0.029 <0.031 <0.028 <0.028 <0.023 <0.032 <0.023 10/4/2005 <0.022 <0.026 <0.027 <0.024 <0.018 <0.025 <0.040 <0.013 <0.026 10/11/2005 <0.040 <0.027 <0.023 <0.021 <0.026 <0.026 <0.022 <0.033 <0.020 10/18/2005 <0.018 <0.025 <0.031 <0.015 <0.024 <0.025 <0.023 <0.029 <0.019 10/25/2005 <0.030 <0.006 <0.034 <0.024 <0.019 <0.033 <0.038 <0.018 <0.031 11/1/2005 <0.034 <0.027 <0.024 <0.024 <0.023 <0.022 <0.037 <0.021 <0.031 11/8/2005 <0.023 <0.025 <0.015 <0.008 <0.023 <0.027 <0.029 <0.018 <0.025 11/15/2005 <0.038 <0.022 <0.024 <0.030 <0.019 <0.022 <0.033 <0.023 <0.029 11/22/2005 <0.042 <0.026 <0.021 <0.031 <0.024 <0.024 <0.029 <0.023 <0.028 11/29/2005 <0.030 <0.032 <0.024 <0.031 <0.024 <0.022 <0.029 <0.026 <0.014 12/6/2005 <0.030 <0.027 <0.019 <0.030 <0.043 <0.019 <0.025 <0.027 <0.029 12/13/2005 <0.008 <0.033 <0.021 <0.024 <0.021 <0.023 <0.037 <0.020 <0.021 12/20/2005 <0.043 <0.006 <0.028 <0.030 <0.021 <0.030 <0.037 <0.020 <0.008 12/28/2005 <0.033 <0.025 <0.031 <0.021 <0.027 <0.025 <0.007 <0.027 <0.020 1/4/2006 <0.041 <0.022 <0.029 <0.031 <0.020 <0.025 <0.015 <0.017 <0.018

- Optional sample location 6 - 17

TABLE 6-8 NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE STATIONS - 2005 I-131 ACTIVITY pCi/m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS Week End Date D1 ** G ** H ** I ** J ** K **

1/10/2005 NA <0.016 <0.029 <0.011 <0.021 <0.021 1/17/2005 <0.018 <0.024 <0.015 <0.021 <0.010 <0.027 1/24/2005 <0.016 <0.025 <0.019 <0.028 <0.015 <0.020 1/31/2005 <0.017 <0.012 <0.020 <0.015 <0.023 <0.021 2/7/2005 <0.019 <0.018 <0.019 <0.019 <0.025 <0.019 2/14/2005 <0.020 <0.027 <0.026 <0.015 <0.024 <0.030 2/22/2005 <0.021 <0.023 <0.024 <0.028 <0.013 <0.019 2/28/2005 <0.022 <0.026 <0.028 <0.030 <0.019 <0.033 3/7/2005 <0.019 <0.020 <0.018 <0.027 <0.023 <0.019 3/14/2005 <0.024 <0.025 <0.016 <0.020 <0.015 <0.016 3/21/2005 <0.024 <0.004 <0.024 <0.020 <0.011 <0.022 3/28/2005 <0.010 <0.024 <0.023 <0.037 <0.028 <0.022 4/4/2005 <0.030 <0.020 <0.047 <0.024 <0.039 <0.032 4/11/2005 <0.033 <0.030 <0.020 <0.026 <0.027 <0.026 4/18/2005 <0.020 <0.033 <0.023 <0.008 <0.025 <0.024 4/25/2005 <0.024 <0.031 <0.018 <0.030 <0.029 <0.024 5/2/2005 <0.020 <0.025 <0.034 <0.025 <0.022 <0.022 5/9/2005 <0.007 <0.021 <0.023 <0.035 <0.023 <0.018 5/16/2005 <0.019 <0.027 <0.020 <0.036 <0.005 <0.015 5/23/2005 <0.021 <0.027 <0.023 <0.036 <0.005 <0.026 5/31/2005 <0.024 <0.015 <0.013 <0.028 <0.021 <0.025 6/6/2005 <0.023 <0.031 <0.012 <0.027 <0.024 <0.017 6/13/2005 <0.032 <0.020 <0.025 <0.027 <0.030 <0.020 6/20/2005 <0.007 <0.020 <0.023 <0.039 <0.025 <0.025 6/27/2005 <0.024 <0.023 <0.017 <0.030 <0.005 <0.030

Sample location required by ODCM

- Optional sample location NA = No Sample Available 6 - 18

TABLE 6-8 (continued)

NMPNS/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE STATIONS - 2005 I-131 ACTIVITY pCi/ m3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS Week End Date D1 ** G ** H ** I ** J ** K **

7/5/2005 <0.019 <0.014 <0.021 <0.033 <0.023 <0.024 7/11/2005 <0.024 <0.020 <0.020 <0.009 <0.039 <0.021 7/18/2005 <0.021 <0.029 <0.030 <0.041 <0.023 <0.024 7/25/2005 <0.033 <0.031 <0.021 <0.033 <0.029 <0.027 8/1/2005 <0.007 <0.007 <0.026 <0.006 <0.026 <0.029 8/8/2005 <0.031 <0.015 <0.026 <0.036 <0.019 <0.027 8/15/2005 <0.005 <0.013 <0.019 <0.022 <0.019 <0.020 8/22/2005 <0.023 <0.010 <0.019 <0.017 <0.017 <0.021 8/29/2005 <0.018 <0.022 <0.012 <0.015 <0.016 <0.024 9/6/2005 <0.019 <0.020 <0.015 <0.024 <0.019 <0.015 9/12/2005 <0.037 <0.006 <0.022 <0.033 <0.027 <0.024 9/19/2005 <0.008 <0.024 <0.022 <0.029 <0.020 <0.014 9/26/2005 <0.023 <0.018 <0.030 <0.030 <0.027 <0.032 10/3/2005 <0.008 <0.024 <0.034 <0.027 <0.007 <0.026 10/10/2005 <0.031 <0.029 <0.031 <0.028 <0.036 <0.035 10/17/2005 <0.031 <0.014 <0.023 <0.024 <0.022 <0.031 10/24/2005 <0.037 <0.022 <0.029 <0.022 <0.019 <0.037 10/31/2005 <0.031 <0.027 <0.028 <0.031 <0.024 <0.033 11/7/2005 <0.035 <0.017 <0.027 <0.044 <0.013 <0.022 11/14/2005 <0.035 <0.020 <0.026 <0.009 <0.024 <0.019 11/21/2005 <0.036 <0.021 <0.008 <0.020 <0.024 <0.028 11/28/2005 <0.024 <0.021 <0.005 <0.008 <0.021 <0.024 12/5/2005 <0.037 <0.031 <0.018 <0.035 <0.015 <0.015 12/12/2005 <0.025 <0.014 <0.021 <0.018 <0.038 <0.029 12/19/2005 <0.040 <0.021 <0.017 <0.021 <0.014 <0.037 12/27/2005 <0.026 <0.027 <0.021 <0.028 <0.018 <0.027 1/4/2006 <0.015 <0.034 <0.017 <0.024 <0.021 <0.025

Sample location required by ODCM

- Optional sample location 6 - 19

TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma R1 OFFSITE COMPOSITE*

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 116 +/- 22.3 99.4 +/- 22.0 119 +/- 19.4 107 +/- 14.8 122 +/- 22.4 94.9 +/- 20.6 Zn-65 <14.2 <3.77 <10.8 <7.38 <13.30 <3.89 Cs-134 <6.38 <5.45 <4.67 <2.29 <3.19 <5.05 Cs-137 <3.20 <3.20 <4.14 <1.61 <1.11 <3.30 Zr-95 <12.2 <7.41 <8.37 <1.36 <6.98 <7.65 Nb-95 <8.16 <4.94 <5.57 <0.90 <4.66 <6.45 Co-58 <4.36 <4.34 <4.21 <2.90 <5.15 <4.48 Mn-54 <5.59 <6.23 <3.71 <2.27 <3.59 <4.97 Co-60 <2.19 <2.19 <4.46 <3.5 <5.59 <2.25 K-40 <63.4 <22.3 <43.3 <29.60 <59.7 <65.4 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 103 +/- 18.4 113 +/- 20.0 106 +/- 15.8 75.3 +/- 16.5 89.1 +/- 16.4 <9.02 Zn-65 <2.22 <12.1 <8.34 <9.33 <7.22 <9.61 Cs-134 <4.72 <5.51 <4.65 <6.06 <4.40 <1.22 Cs-137 <3.62 <3.87 <3.13 <3.56 <2.94 <1.08 Zr-95 <6.46 <9.53 <7.11 <6.83 <8.96 <7.09 Nb-95 <5.54 <4.36 <4.76 <4.23 <5.42 <7.10 Co-58 <5.19 <5.48 <4.80 <1.39 <2.84 <4.38 Mn-54 <3.31 <3.32 <3.45 <3.24 <3.10 <1.31 Co-60 <1.25 <1.46 <3.61 <5.19 <4.77 <2.04 K-40 127 +/- 24.4 <61.80 <48.3 <19.5 <50.7 <75.0 Others <LLD <LLD <LLD <LLD <LLD <LLD

Sample location required by ODCM Plant related radionuclides 6 - 20

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma R2 OFFSITE COMPOSITE*

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 115 +/- 18.1 110 +/- 17.0 <37.1 107 +/- 16.8 65.6 +/- 15.7 86.3 +/- 18.3 Zn-65 <12.4 <8.97 <4.33 <9.38 <7.08 <11.0 Cs-134 <3.62 <5.16 <5.75 <4.53 <4.11 <3.37 Cs-137 <3.58 <3.28 <4.44 <3.72 <2.82 <3.47 Zr-95 <8.92 <11.4 <11.0 <6.16 <8.08 <8.58 Nb-95 <3.62 <4.65 <2.01 <4.56 <6.03 <5.73 Co-58 <4.00 <1.11 <6.51 <3.29 <3.1 <3.39 Mn-54 <0.96 <4.17 <4.08 <4.08 <2.81 <4.40 Co-60 <1.48 <5.46 <2.55 <3.50 <7.07 <4.55 K-40 <51.6 <61.2 <90.1 131+/- 25.1 <15.3 <16.2 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 124 +/- 22.6 82.6 +/- 18.3 118 +/- 24.1 78.3 +/- 14.6 99.8 +/- 21.6 40.0 +/- 13.8 Zn-65 <7.90 <11.9 <10.1 <9.12 <11.5 <8.40 Cs-134 <3.91 <5.72 <3.54 <4.22 <5.97 <4.02 Cs-137 <4.15 <5.02 <4.61 <2.57 <2.92 <0.73 Zr-95 <2.33 <2.72 <10.7 <6.89 <8.92 <8.32 Nb-95 <4.48 <8.34 <8.76 <5.17 <5.51 <3.44 Co-58 <3.68 <7.05 <7.51 <3.59 <6.14 <3.82 Mn-54 <1.13 <3.70 <6.58 <3.62 <3.27 <3.65 Co-60 <1.74 <5.71 <6.12 <3.31 <6.30 <1.33 K-40 <17.7 <60.9 <21.9 <34.9 <74.1 <59.8 Others <LLD <LLD <LLD <LLD <LLD <LLD

Sample location required by ODCM Plant related radionuclides 6 - 21

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma R3 OFFSITE COMPOSITE*

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 73.4 +/- 18.5 101 +/- 18.0 121 +/- 19.2 130 +/- 17.3 73.3 +/- 15.3 77.1 +/- 17.6 Zn-65 <9.93 <6.79 <6.56 <7.41 <6.50 <7.16 Cs-134 <2.54 <6.14 <4.53 <4.55 <4.03 <3.41 Cs-137 <0.78 <3.34 <0.77 <2.21 <3.58 <2.38 Zr-95 <1.82 <9.43 <6.46 <5.31 <9.74 <1.91 Nb-95 <4.46 <5.75 <6.11 <4.63 <4.93 <4.68 Co-58 <3.45 <4.43 <2.97 <4.32 <2.63 <4.20 Mn-54 <3.89 <2.42 <3.32 <3.56 <2.90 <4.11 Co-60 <5.21 <4.12 <3.63 <3.39 <1.38 <1.52 K-40 <65.2 <14.7 <48.6 93.5 +/- 19.5 <38.4 <53.3 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 127 +/- 18.3 47.4 +/- 16.0 58.8 +/- 15.9 75.0 +/- 16.3 88.1 +/- 20.8 49.4 +/- 12.8 Zn-65 <2.12 <12.9 <11.1 <13.3 <14.9 <7.62 Cs-134 <3.87 <3.22 <4.00 <5.41 <4.73 <3.59 Cs-137 <2.25 <2.85 <3.05 <4.46 <3.55 <2.43 Zr-95 <7.75 <7.30 <10.10 <8.85 <8.43 <7.23 Nb-95 <4.90 <7.71 <5.42 <6.79 <5.14 <4.32 Co-58 <2.72 <3.35 <2.93 <3.74 <4.45 <2.51 Mn-54 <0.79 <4.23 <3.94 <4.06 <1.50 <4.88 Co-60 <5.05 <4.34 <3.99 <6.24 <2.41 <3.27 K-40 <33.2 <42.1 <15.5 <50.1 <69.9 <12.2 Others <LLD <LLD <LLD <LLD <LLD <LLD

Sample location required by ODCM Plant related radionuclides 6 - 22

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma R4 OFFSITE COMPOSITE*

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 124 +/- 18.5 101 +/- 15.9 82.2 +/- 19.8 74.4 +/- 17.4 106 +/- 20.1 84.4 +/- 17.2 Zn-65 <6.30 <2.33 <12.1 <7.45 <11.4 <2.48 Cs-134 <4.04 <4.06 <4.43 <4.53 <4.59 <3.96 Cs-137 <0.74 <3.60 <3.01 <2.44 <4.11 <3.14 Zr-95 <8.14 <7.27 <6.13 <7.13 <12.0 <6.66 Nb-95 <4.88 <3.28 <5.25 <4.74 <5.40 <4.45 Co-58 <5.19 <3.65 <3.78 <4.84 <1.65 <3.89 Mn-54 <3.71 <3.73 <5.98 <4.26 <6.09 <5.23 Co-60 <1.33 <4.40 <4.03 <1.67 <6.42 <4.68 K-40 <36.9 <37.2 <54.0 <17.0 <24.3 <39.5 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 133 +/- 17.6 57.1 +/- 21.6 115 +/- 20.6 61.3 +/- 13.3 75.9 +/- 15.8 49.4 +/- 16.1 Zn-65 <9.89 <14.7 <11.4 <6.87 <9.51 <14.5 Cs-134 <3.71 <4.61 <5.10 <4.05 <4.94 <4.57 Cs-137 <2.30 <4.12 <4.56 <2.55 <2.60 <3.75 Zr-95 <5.73 <10.7 <9.90 <4.67 <8.60 <2.49 Nb-95 <4.05 <2.02 <5.07 <3.93 <5.33 <5.53 Co-58 <2.35 <4.94 <4.41 <2.27 <5.01 <3.77 Mn-54 <2.85 <4.78 <3.33 <3.17 <5.29 <4.99 Co-60 <3.31 <8.13 <6.15 <2.95 <4.92 <6.89 K-40 <32.1 <24.3 <111 +/- 24.8 <29.9 <40.9 <20.6 Others <LLD <LLD <LLD <LLD <LLD <LLD

Sample location required by ODCM Plant related radionuclides 6 - 23

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma R5 OFFSITE COMPOSITE*

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 89.9 +/- 18.9 97.4 +/- 20.5 91.4 +/- 17.3 72.5 +/- 18.1 91.8 +/- 15.9 96.7 +/- 19.8 Zn-65 <2.65 <12.6 <8.23 <14.0 <9.06 <11.5 Cs-134 <5.36 <4.61 <5.25 <4.95 <4.27 <4.69 Cs-137 <4.41 <4.08 <5.12 <2.72 <3.22 <2.51 Zr-95 <5.08 <6.40 <10.2 <6.73 <4.82 <9.15 Nb-95 <4.93 <5.49 <6.12 <8.09 <3.22 <4.36 Co-58 <1.14 <3.95 <4.66 <3.96 <0.98 <5.20 Mn-54 <4.84 <4.49 <4.97 <5.54 <3.22 <2.80 Co-60 <6.06 <6.84 <5.97 <5.36 <1.31 <8.17 K-40 <55.5 <15.7 117 +/- 24.0 <55.1 <45.8 <74.1 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 108 +/- 20.2 97.7 +/- 16.2 83.6 +/- 16.4 55.1 +/- 15.6 89.1 +/- 20.8 64.0 +/- 12.1 Zn-65 <3.43 <7.80 <9.96 <3.23 <10.9 <9.18 Cs-134 <4.49 <4.76 <5.00 <3.70 <3.78 <2.43 Cs-137 <4.47 <2.85 <2.14 <0.96 <3.36 <2.66 Zr-95 <10.8 <4.95 <7.87 <9.97 <10.0 <5.58 Nb-95 <6.57 <4.33 <5.61 <6.05 <5.36 <3.30 Co-58 <5.42 <1.00 <2.75 <4.46 <1.70 <2.80 Mn-54 <5.19 <3.12 <3.93 <3.20 <5.42 <2.54 Co-60 <1.99 <3.39 <3.73 <1.88 <8.37 <3.02 K-40 <55.4 <13.2 <47.9 <54.5 <23.7 <11.3 Others <LLD <LLD <LLD <LLD <LLD <LLD

Sample location required by ODCM Plant related radionuclides 6 - 24

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma D2 OFFSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 124 +/-19.9 87.8 +/- 17.5 128 +/- 23.0 106 +/- 15.0 132 +/- 21.4 111 +/- 21.0 Zn-65 <8.12 <10.3 <3.74 <8.32 <9.45 <12.6 Cs-134 <5.92 <4.96 <4.87 <2.99 <5.97 <5.63 Cs-137 <4.72 <4.36 <3.18 <2.65 <4.35 <3.31 Zr-95 <7.98 <6.78 <2.70 <5.03 <8.78 <9.67 Nb-95 <7.13 <6.32 <4.88 <3.89 <6.29 <5.12 Co-58 <4.23 <5.17 <1.58 <2.93 <4.99 <4.48 Mn-54 <4.35 <4.84 <4.78 <1.83 <5.14 <3.94 Co-60 <5.88 <6.14 <7.45 <2.82 <5.16 <2.26 K-40 115 +/- 23.7 116 +/- 25.0 <63.1 <29.9 <43.2 <23.0 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 111 +/- 16.1 114 +/- 21.4 79.8 +/- 18.0 66.1 +/- 15.2 68.4 +/- 18.7 54.2 +/- 11.5 Zn-65 <1.90 <9.55 <11.6 <10.1 <8.08 <12.0 Cs-134 <3.75 <4.52 <6.03 <4.49 <2.76 <5.01 Cs-137 <2.64 <3.99 <4.45 <2.95 <3.29 <2.71 Zr-95 <4.25 <7.52 <10.5 <5.02 <7.71 <9.00 Nb-95 <3.81 <4.49 <8.19 <5.90 <4.10 <5.38 Co-58 <3.13 <7.17 <1.69 <3.38 <4.61 <3.24 Mn-54 <2.05 <4.42 <3.84 <3.05 <2.76 <3.40 Co-60 <2.81 <1.51 <8.23 <3.12 <1.63 <3.48 K-40 <10.9 <54.8 <24.6 <11.2 <56.9 <12.5 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 25

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma E OFFSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 118 +/- 22.7 110 +/- 21.1 111 +/- 19.2 112 +/- 15.6 74 +/- 17.7 121 +/- 19.1 Zn-65 <16.0 <3.91 <10.7 <6.07 <11.6 <10.4 Cs-134 <5.55 <4.40 <4.65 <5.12 <5.03 <2.53 Cs-137 <3.26 <3.32 <0.85 <3.25 <3.20 <3.28 Zr-95 <2.79 <2.83 <5.65 <5.88 <8.32 <8.12 Nb-95 <5.09 <7.50 <5.55 <3.91 <6.86 <6.07 Co-58 <5.60 <6.58 <4.19 <3.14 <4.48 <4.75 Mn-54 <6.35 <5.79 <3.70 <3.57 <3.59 <2.82 Co-60 <2.22 <2.27 <1.56 <5.94 <4.69 <4.30 K-40 <64.5 <83.4 <15.9 <12.5 101 +/- 23.4 <15.4 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 87.6 +/- 18.4 89.2 +/- 16.2 88.8 +/- 16.1 77.0 +/-14.6 95.7 +/- 22.6 71.5 +/- 16.7 Zn-65 <12.4 <9.37 <8.17 <2.90 <4.47 <12.1 Cs-134 <4.17 <3.94 <3.87 <4.45 <5.95 <3.31 Cs-137 <0.71 <2.11 <4.03 <3.54 <1.34 <1.08 Zr-95 <7.30 <5.07 <5.42 <7.37 <11.6 <7.07 Nb-95 <3.20 <4.44 <4.20 <5.08 <5.58 <4.84 Co-58 <4.49 <4.29 <3.87 <4.59 <4.84 <4.37 Mn-54 <2.30 <2.27 <3.39 <5.11 <5.59 <3.75 Co-60 <4.36 <3.85 <5.18 <1.67 <2.62 <5.78 K-40 79.7 +/- 21.0 <37.4 <47.4 <48.4 <76.1 <20.7 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 26

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma F OFFSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 69.2 +/- 17.0 94.6 +/- 17.2 141 +/- 25.3 85.6 +/- 14.3 70.8 +/- 19.4 87.9 +/- 16.8 Zn-65 <13.2 <9.81 <11.6 <9.72 <14.2 <6.76 Cs-134 <4.35 <5.14 <4.67 <4.58 <4.91 <3.74 Cs-137 <2.17 <2.12 <3.32 <3.52 <1.06 <2.25 Zr-95 <5.33 <7.65 <8.21 <5.62 <2.46 <7.69 Nb-95 <6.46 <6.23 <5.46 <4.94 <1.64 <3.48 Co-58 <5.14 <1.05 <7.14 <4.54 <1.44 <5.17 Mn-54 <3.46 <0.92 <6.20 <2.56 <5.03 <3.88 Co-60 <4.16 <4.06 <6.54 <5.23 <6.76 <4.10 K-40 <59.1 <39.5 <24.7 93.7 +/- 19.9 <57.2 <14.7 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 99.2 +/- 18.8 91.5 +/- 17.8 65.6 +/- 18.9 69.6 +/- 13.9 96.1 +/- 15.5 47.6 +/- 15.6 Zn-65 <2.94 <9.84 <12.5 <7.01 <8.05 <2.33 Cs-134 <3.27 <3.68 <5.66 <3.29 <2.21 <4.03 Cs-137 <3.59 <4.82 <3.08 <3.18 <3.41 <3.13 Zr-95 <6.11 <9.01 <9.06 <5.50 <6.28 <5.05 Nb-95 <4.32 <4.90 <6.08 <4.01 <4.25 <5.11 Co-58 <1.31 <4.59 <4.45 <2.32 <2.52 <3.83 Mn-54 <3.75 <2.99 <3.90 <3.23 <2.30 <3.66 Co-60 <5.75 <4.01 <2.10 <3.01 <4.37 <1.33 K-40 <17.0 <38.9 <61.1 <11.2 <12.9 <36.7 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 27

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma G OFFSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 106 +/- 17.6 126 +/- 17.8 96.2 +/- 17.7 108 +/- 16.3 93.3 +/- 17.0 78.2 +/- 17.7 Zn-65 <6.95 <8.74 <8.33 <7.19 <11.3 <11.0 Cs-134 <5.06 <5.39 <3.88 <2.56 <4.01 <4.31 Cs-137 <3.41 <2.31 <3.75 <2.63 <3.56 <3.82 Zr-95 <5.37 <11.0 <6.50 <5.58 <6.78 <8.64 Nb-95 <3.60 <6.91 <3.40 <4.31 <5.26 <3.49 Co-58 <3.54 <3.51 <4.94 <3.26 <5.63 <3.88 Mn-54 <3.10 <3.09 <4.76 <3.34 <2.74 <3.96 Co-60 <4.21 <4.20 <1.40 <3.45 <6.16 <1.42 K-40 <40.9 <40.9 <14.2 <12.3 <40.6 <14.5 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 103 +/- 16.0 117 +/- 18.4 94.0 +/- 16.5 61.9+/-14.5 83.0 +/- 21.1 <21.3 Zn-65 <7.04 <8.48 <11.9 <9.42 <12.4 <6.62 Cs-134 <3.49 <4.49 <3.82 <4.38 <2.59 <3.53 Cs-137 <2.18 <2.20 <3.39 <3.60 <3.52 <2.11 Zr-95 <8.85 <6.92 <6.01 <6.90 <10.8 <1.75 Nb-95 4.75 <4.90 <4.66 <5.36 <6.80 <4.76 Co-58 <2.64 <2.85 <4.06 <4.56 <3.29 <1.02 Mn-54 <0.77 <2.99 <3.77 <4.13 <6.18 <4.23 Co-60 <4.21 <4.01 <3.81 <5.23 <1.60 <1.33 K-40 <40.6 <38.9 <40.4 <19.7 <16.3 <13.5 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 28

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma D1 ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 86.5 +/- 24.2 94.9 +/- 24.1 134 +/- 24.5 92.2 +/- 18.1 121 +/- 22.2 101 +/- 18.2 Zn-65 <12.5 <9.93 <3.74 <7.42 <13.1 <2.56 Cs-134 <5.43 <6.03 <5.88 <2.57 <3.13 <3.12 Cs-137 <4.10 <3.25 <4.64 <3.96 <1.09 <3.58 Zr-95 <9.65 <12.4 <10.8 <5.67 <6.92 <8.97 Nb-95 <6.53 <5.11 <4.95 <7.28 <4.66 <6.60 Co-58 <9.20 <4.44 <5.45 <4.18 <5.11 <4.02 Mn-54 <1.80 <3.88 <5.54 <2.90 <3.53 <4.57 Co-60 <7.61 <7.61 <7.42 <4.51 <5.49 <1.48 K-40 <28.5 <81.7 <62.8 <48.1 <58.6 <15.0 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 150 +/- 23.2 90.8 +/- 18.2 140 +/- 21.9 106 +/- 18.2 87.3 +/- 19.9 51.7 +/- 14.7 Zn-65 <9.61 <12.2 <11.9 <2.96 <9.74 <7.57 Cs-134 <5.39 <4.82 <5.83 <4.94 <4.26 <4.66 Cs-137 <3.41 <6.02 <3.80 <3.10 <1.10 <2.93 Zr-95 <2.45 <12.50 <2.00 <7.58 <12.7 <9.19 Nb-95 <2.45 <7.78 <6.55 <5.26 <6.16 <3.89 Co-58 <6.11 <6.51 <6.07 <4.71 <5.62 <4.42 Mn-54 <3.97 <3.78 <4.90 <4.00 <5.64 <1.03 Co-60 <1.96 <7.37 <6.40 <1.70 <2.07 <5.79 K-40 <54.7 <62.2 129 +/- 30.8 <49.3 <60.1 <16.3 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 29

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma G ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 83.0 +/- 18.8 82.1 +/- 18.0 133 +/- 19.9 101 +/- 16.8 63.5 +/- 15.2 77.7 +/- 16.1 Zn-65 <9.03 <8.92 <10.5 <5.75 <6.79 <6.56 Cs-134 <4.14 <3.67 <3.23 <3.91 <3.93 <4.20 Cs-137 <3.29 <2.81 <3.71 <2.65 <2.70 <0.77 Zr-95 <9.24 <5.49 <7.10 <5.67 <7.81 <6.54 Nb-95 <5.59 <6.67 <6.77 <4.42 <5.88 <6.26 Co-58 <4.82 <4.74 <4.14 <4.71 <3.08 <3.00 Mn-54 <3.60 <3.56 <3.63 <4.12 <2.69 <3.87 Co-60 <4.32 <4.27 <4.35 <4.40 <6.76 <3.62 K-40 <52.9 <60.6 96.3 +/- 25.4 <12.4 <14.6 <38.4 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 148 +/- 23.4 89.2 +/- 19.0 109 +/- 21.1 90.9 +/- 14.2 56.2 +/- 14.6 43.9 +/- 13.9 Zn-65 <13.7 <6.83 <12.0 <5.16 <8.74 <7.10 Cs-134 <4.99 <4.29 <5.46 <3.86 <4.80 <3.10 Cs-137 <4.07 <0.78 <5.69 <2.43 <2.80 <3.21 Zr-95 <6.27 <9.88 <8.82 <6.29 <7.71 <7.09 Nb-95 <6.54 <4.83 <5.96 <2.61 <1.23 <4.38 Co-58 <1.34 <3.18 <1.50 <3.89 <5.79 <3.94 Mn-54 <3.02 <0.94 <5.56 <3.02 <2.36 <2.40 Co-60 <1.70 <1.43 <2.03 <3.54 <5.85 <2.92 K-40 <17.3 <50.0 <58.8 <10.5 <38.3 <30.9 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 30

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma H ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 113 +/- 18.1 92.1 +/- 18.7 131 +/- 21.6 104 +/- 16.2 72.6 +/- 15.2 <46.1 Zn-65 <10.6 <7.12 <4.10 <7.82 <6.37 <12.2 Cs-134 <3.81 <5.84 <1.36 <3.61 <3.94 <5.88 Cs-137 <3.02 <3.91 <5.42 <3.21 <3.49 <4.00 Zr-95 <7.56 <8.15 <8.29 <6.84 <9.62 <13.2 Nb-95 <1.20 <4.71 <7.08 <3.52 <4.92 <6.31 Co-58 <1.03 <5.48 <8.06 <2.73 <2.60 <5.48 Mn-54 <3.83 <0.98 <3.85 <2.76 <2.84 <1.39 Co-60 <1.37 <4.31 <2.41 <5.33 <1.35 <5.88 K-40 <38.2 <41.9 <85.0 <31.4 <37.5 <22.0 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 102 +/- 16.6 106 +/- 21.7 97.0 +/- 16.8 71.4 +/- 17.9 119 +/- 14.8 58.6 +/- 12.2 Zn-65 <7.04 <11.9 <10.6 <11.6 <6.69 <6.74 Cs-134 <3.19 <4.08 <4.65 <5.16 <4.38 <3.17 Cs-137 <2.52 <3.07 <0.79 <0.95 <3.16 <2.15 Zr-95 <5.82 <7.47 <6.98 <8.54 <4.56 <3.67 Nb-95 <6.35 <5.20 <6.15 <4.20 <4.78 <3.89 Co-58 <3.37 <5.49 <4.07 <4.44 <3.51 <3.99 Mn-54 <3.25 <1.36 <5.23 <3.99 <0.88 <2.79 Co-60 <1.16 <2.10 <1.45 <5.05 <5.97 <3.65 K-40 <40.5 <21.4 <40.1 <19.0 <66.1 <42.9 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 31

TABLE 6-9 (cont inued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma I ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 118 +/- 20.5 85.9 +/- 16.9 140 +/- 18.5 95.6 +/- 14.8 108 +/- 17.8 77.2 +/- 17.7 Zn-65 <9.96 <2.50 <2.43 <8.56 <10.4 <13.6 Cs-134 <5.17 <4.99 <0.87 <4.26 <4.06 <3.01 Cs-137 <2.53 <2.16 <3.07 <2.44 <2.55 <3.38 Zr-95 <8.59 <6.77 <6.55 <4.10 <7.36 <8.06 Nb-95 <1.39 <3.58 <5.11 <4.96 <4.95 <5.43 Co-58 <4.76 <4.59 <3.82 <0.83 <4.80 <6.52 Mn-54 <4.13 <3.44 <3.89 <2.36 <3.30 <6.05 Co-60 <5.42 <5.45 <1.40 <3.63 <1.34 <4.52 K-40 148 +/- 29.7 <50.2 <48.8 <50.1 <37.1 <47.6 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 72.6 +/- 14.4 67.5 +/- 17.4 123 +/- 21.1 72.4 +/- 15.3 78.1 +/- 14.8 69.3 +/- 15.2 Zn-65 <7.16 <9.03 <16.0 <7.91 <12.7 <11.2 Cs-134 <3.46 <4.83 <4.48 <3.46 <3.09 <1.03 Cs-137 <4.26 <3.26 <4.21 <3.84 <2.32 <0.92 Zr-95 <5.90 <8.47 <5.53 <6.72 <8.23 <8.22 Nb-95 <6.87 <5.89 <6.10 <3.60 <3.42 <8.09 Co-58 <0.94 <5.50 <4.06 <3.50 <3.68 <3.41 Mn-54 <3.24 <3.59 <4.09 <2.70 <0.98 <3.86 Co-60 <1.18 <4.28 <1.56 <5.76 <4.28 <4.89 K-40 <32.7 <15.3 <56.9 113 +/- 23.3 <58.00 <52.10 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 32

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma J ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 87.2 +/- 19.0 99.8 +/- 20.8 83.3 +/- 20.0 107 +/- 17.9 86.6 +/- 19.5 109 +/- 18.9 Zn-65 <13.4 <15.3 <11.7 <11.7 <14.9 <7.59 Cs-134 <6.35 <5.21 <7.29 <4.61 <3.55 <4.40 Cs-137 <3.34 <3.77 <3.26 <4.08 <4.82 <3.49 Zr-95 <11.80 <8.60 <6.71 <5.49 <7.51 <5.91 Nb-95 <6.71 <6.30 <6.78 <5.15 <4.37 <5.06 Co-58 <5.44 <3.26 <1.20 <5.13 <4.63 <3.45 Mn-54 <3.76 <5.45 <6.78 <2.34 <5.29 <3.82 Co-60 <4.89 <6.33 <4.36 <3.56 <5.30 <1.61 K-40 101 +/- 24.9 128 +/- 32.2 <58.5 <13.3 106 +/- 30.0 <44.4 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 134 +/- 22.4 139 +/- 24.7 89.7 +/- 19.2 68.4 +/- 16.5 84.4 +/- 18.2 46.9 +/- 10.2 Zn-65 <16.4 <4.14 <10.0 <7.56 <12.4 <9.56 Cs-134 <5.08 <5.44 <5.49 <2.61 <4.47 <3.04 Cs-137 <1.02 <1.22 <3.18 <3.38 <3.58 <2.63 Zr-95 <12.4 <12.8 <9.30 <8.27 <9.26 <6.49 Nb-95 <6.78 <2.09 <5.49 <4.95 <5.19 <2.37 Co-58 <5.54 <1.76 <4.74 <3.49 <4.43 <2.50 Mn-54 <4.09 <3.89 <3.56 <2.96 <4.51 <2.60 Co-60 <5.47 <2.41 <1.60 <5.77 <4.14 <0.98 K-40 <20.6 <67.3 <44.3 <16.3 <43.6 <9.93 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 33

TABLE 6-9 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2005 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma K ONSITE COMPOSITE**

NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE Be-7 100 +/- 18.4 72.7 +/- 17.9 133 +/- 19.3 133 +/- 17.5 107 +/- 16.4 102 +/- 15.7 Zn-65 <11.3 <11.9 <8.09 <8.39 <10.8 <6.39 Cs-134 <3.81 <6.40 <5.71 <4.52 <5.10 <3.36 Cs-137 <2.29 <4.19 <4.86 <3.29 <2.86 <2.97 Zr-95 <7.94 <7.71 <7.95 <7.65 <8.73 <6.37 Nb-95 <5.37 <5.18 <6.46 <4.54 <5.51 <3.38 Co-58 <2.82 <4.89 <5.88 <2.99 <4.41 <2.92 Mn-54 <4.64 <4.88 <4.33 <3.43 <3.51 <3.24 Co-60 <1.46 <5.07 <4.13 <3.27 <3.10 <3.53 K-40 <40.5 91.9 +/- 28.7 105 +/- 23.8 97.0 +/- 19.9 69.2 +/- 21.8 <37.3 Others <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Be-7 129 +/- 17.7 75.9 +/- 15.3 87.0 +/- 20.0 71.8 +/- 13.9 61.4 +/- 19.5 <37.4 Zn-65 <6.62 <8.30 <4.24 <5.55 <12.3 <6.58 Cs-134 <2.72 <4.18 <6.25 <3.89 <4.25 <3.94 Cs-137 <2.06 <3.38 <3.63 <2.92 <4.38 <2.40 Zr-95 <1.51 <5.31 <15.6 <4.83 <9.00 <3.96 Nb-95 <3.09 <4.69 <7.43 <4.58 <6.14 <3.99 Co-58 <3.19 <3.08 <4.57 <3.83 <4.41 <2.90 Mn-54 <3.76 <4.32 <5.00 <1.99 <4.84 <0.72 Co-60 <2.84 <3.60 <6.76 <3.81 <7.46 <3.92 K-40 <30.0 <38.0 <25.5 <11.3 <21.0 <32.5 Others <LLD <LLD <LLD <LLD <LLD <LLD

- Optional sample location Plant related radionuclides 6 - 34

TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS - 2005 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION FIRST SECOND THIRD FOURTH DEGREES &

LOCATION NUMBER QUARTER QUARTER QUARTER QUARTER DISTANCE (1) 3 D1 Onsite 13.9 +/- 0.6 13.7 +/- 0.7 14.1 +/- 0.6 13.4 +/- 0.6 69° at 0.2 miles 4 D2 Onsite 4.6 +/- 0.6 4.6 +/- 0.3 4.5 +/- 0.2 4.3 +/- 0.2 140° at 0.4 miles 5 E Onsite 4.5 +/- 0.5 4.7 +/- 0.3 4.7 +/- 0.2 4.4 +/- 0.3 175° at 0.4 miles 6 F Onsite 3.9 +/- 0.4 4.0 +/- 0.2 4.0 +/- 0.2 3.6 +/- 0.2 210° at 0.5 miles 7* G Onsite 3.8 +/- 0.3 3.7 +/- 0.2 3.7 +/- 0.2 3.4 +/- 0.2 250° at 0.7 miles 8* R-5 Offsite Control 4.9 +/- 0.3 5.0 +/- 0.3 5.1 +/- 0.4 4.7 +/- 0.2 42° at 16.4 miles 9 D1 Offsite 4.0 +/- 0.2 4.1 +/- 0.2 4.2 +/- 0.3 3.7 +/- 0.2 80° at 11.4 miles 10 D2 Offsite 4.0 +/- 0.2 4.1 +/- 0.2 4.0 +/- 0.3 3.8 +/- 0.2 117° at 9.0 miles 11 E Offsite 3.7 +/- 0.3 4.1 +/- 0.2 4.0 +/- 0.2 3.6 +/- 0.2 160° at 7.2 miles 12 F- Offsite 4.2 +/- 0.3 4.3 +/- 0.3 4.1 +/- 0.3 3.8 +/- 0.2 190° at 7.7 miles 13 G Offsite 4.3 +/- 0.4 4.4 +/- 0.2 4.2 +/- 0.2 4.1 +/- 0.2 225° at 5.3 miles 14* DeMass Rd., SW Oswego - Control 4.2 +/- 0.3 4.5 +/- 0.3 4.5 +/- 0.3 4.2 +/- 0.3 226° at 12.6 miles 15* Pole 66, W. Boundary - Bible Camp 3.8 +/- 0.3 3.8 +/- 0.2 3.7 +/- 0.2 3.6 +/- 0.2 237° at 0.9 miles 18* Energy Info. Center - Lamp Post, SW 4.6 +/- 0.3 4.5 +/- 0.2 4.4 +/- 0.2 4.3 +/- 0.2 265° at 0.4 miles 19 East Boundary - JAF, Pole 9 4.4 +/- 0.3 4.4 +/- 0.2 4.6 +/- 0.4 4.4 +/- 0.3 81° at 1.3 miles 23* H Onsite 5.4 +/- 0.3 5.2 +/- 0.3 5.2 +/- 0.3 5.0 +/- 0.2 70° at 0.8 miles 24 I Onsite 4.3 +/- 0.3 4.8 +/- 0.6 4.7 +/- 0.2 4.3 +/- 0.3 98° at 0.8 miles 25 J Onsite 4.3 +/- 0.3 4.3 +/- 0.2 4.3 +/- 0.2 3.9 +/- 0.2 110° at 0.9 miles 26 K Onsite 4.2 +/- 0.3 4.5 +/- 0.2 4.3 +/- 0.2 4.3 +/- 0.5 132° at 0.5 miles 27 N. Fence, N. of Switchyard, JAF 24.1 +/- 1.2 20.2 +/- 1.2 22.0 +/- 1.8 21.4 +/- 1.7 60° at 0.4 miles 28 N. Light Pole, N. of Screenhouse, JAF 37.3 +/- 1.8 27.7 +/- 1.8 23.1 +/- 2.4 30.8 +/- 2.0 68° at 0.5 miles 29 N. Fence, N. of W. Side 29.7 +/- 1.7 24.5 +/- 1.6 24.4 +/- 1.9 28.5 +/- 1.7 65° at 0.5 miles 30 N. Fence, (NW) JAF 17.4 +/- 1.0 12.2 +/- 0.9 12.6 +/- 1.0 12.2 +/- 0.8 57° at 0.4 miles 31 N. Fence, (NW) NMP-1 7.2 +/- 0.5 7.5 +/- 0.5 7.7 +/- 0.3 6.8 +/- 0.3 276° at 0.2 miles 6 - 35

TABLE 6-10 (continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2005 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION FIRST SECOND THIRD FOURTH DEGREES &

NUMBER LOCATION QUARTER QUARTER QUARTER QUARTER DISTANCE (1) 39 N. Fence, Rad. Waste-NMP-1 10.4 +/- 0.6 12.0 +/- 0.8 10.8 +/- 0.6 10.2 +/- 0.5 292° at 0.2 miles 47 N. Fence, (NE) JAF 7.8 +/- 0.4 6.9 +/- 0.5 7.3 +/- 0.4 7.7 +/- 0.7 69° at 0.6 miles 49* Phoenix, NY-Control 3.5 +/- 0.3 3.6 +/- 0.3 4.0 +/- 0.2 3.4 +/- 0.2 163° at 19.8 miles 51 Liberty & Bronson Sts., E of OSS 4.1 +/- 0.2 4.2 +/- 0.3 4.2 +/- 0.3 3.9 +/- 0.2 233° at 7.4 miles 52 E. 12th & Cayuga Sts., Oswego School 4.1 +/- 0.3 3.8 +/- 0.2 3.9 +/- 0.3 3.8 +/- 0.2 227° at 5.8 miles 53 Broadwell & Chestnut Sts. Fulton H.S. 4.1 +/- 0.2 4.6 +/- 0.3 4.5 +/- 0.2 4.0 +/- 0.2 183° at 13.7 miles 54 Liberty St. & Co. Rt. 16 Mexico H.S. 3.9 +/- 0.3 4.0 +/- 0.3 4.1 +/- 0.2 3.8 +/- 0.2 115° at 9.3 miles 55 Gas Substation Co. Rt. 5-Pulaski 3.7 +/- 0.2 4.3 +/- 0.3 4.1 +/- 0.2 3.8 +/- 0.2 75° at 13.0 miles 56* Rt. 104-New Haven Sch. (SE Corner) 3.8 +/- 0.2 3.8 +/- 0.2 3.9 +/- 0.3 3.4 +/- 0.2 123° at 5.3 miles 58* Co Rt. 1A-Alcan (E. of E. Entrance Rd.) 4.7 +/- 0.3 4.6 +/- 0.3 4.5 +/- 0.3 4.3 +/- 0.3 220° at 3.1 miles 75* Unit 2, N. Fence, N. of Reactor Bldg. 8.1 +/- 0.4 7.9 +/- 0.5 8.2 +/- 0.4 8.0 +/- 0.3 356° at 0.1 miles 76* Unit 2, N. Fence, N. of Change House 6.1 +/- 0.3 5.7 +/- 0.3 5.9 +/- 0.4 5.7 +/- 0.3 28° at 0.1 miles 77* Unit 2, N. Fence, N. of Pipe Bldg. 6.6 +/- 0.4 6.3 +/- 0.3 6.7 +/- 0.3 6.6 +/- 0.3 39° at 0.2 miles 78* JAF. E. of E. Old Lay Down Area 4.4 +/- 0.2 4.5 +/- 0.3 4.8 +/- 0.2 4.2 +/- 0.2 86° at 0.9 miles 79* Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd. 3.8 +/- 0.3 4.0 +/- 0.3 4.2 +/- 0.3 3.9 +/- 0.2 121° at 1.2 miles 80* Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd. 4.0 +/- 0.3 4.3 +/- 0.3 4.5 +/- 0.4 4.0 +/- 0.2 137° at 1.5 miles 81* Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29 3.9 +/- 0.3 4.1 +/- 0.2 4.4 +/- 0.2 4.0 +/- 0.2 160° at 1.7 miles 82* Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29 4.0 +/- 0.2 4.3 +/- 0.2 4.4 +/- 0.3 3.9 +/- 0.2 180° at 1.6 miles 83* Lakeview Rd., Tree 0.45 mi. N. of Miner Rd. 4.1 +/- 0.3 4.3 +/- 0.2 4.6 +/- 0.2 4.0 +/- 0.2 203° at 1.2 miles 84* Lakeview Rd., N, Pole #6117, 200ft. N. of Lake Rd. 4.1 +/- 0.2 4.1 +/- 0.2 4.4 +/- 0.2 4.0 +/- 0.2 225° at 1.1 miles 85* Unit 1, N. Fence, N. of W. Side of Screen House 8.8 +/- 0.5 8.7 +/- 0.5 9.2 +/- 0.5 8.6 +/- 0.3 289° at 0.2 miles 86* Unit 2, N. Fence, N of W. Side of Screen House 8.4 +/- 0.6 8.1 +/- 0.5 8.7 +/- 0.5 8.2 +/- 0.8 308° at 0.1 miles 87* Unit 2, N. Fence, N. of E. Side of Screen House 8.7 +/- 0.4 8.0 +/- 0.5 8.6 +/- 0.4 8.3 +/- 0.5 332° at 0.1 miles 88* Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 4.1 +/- 0.3 3.9 +/- 0.2 4.3 +/- 0.3 4.0 +/- 0.5 97° at 4.5 miles 6 - 36

TABLE 6-10 (continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2005 Results in Units of mrem/std. Month +/- 1 Sigma LOCATION FIRST SECOND THIRD FOURTH DEGREES &

NUMBER LOCATION QUARTER QUARTER QUARTER QUARTER DISTANCE (1) 89* Leavitt Rd., Pole #16, 0.4 mi. S. of Rt.1 4.4 +/- 0.3 4.2 +/- 0.2 4.6 +/- 0.3 4.0 +/- 0.2 112° at 4.3 miles 90* Rt. 104, Pole #300, 150 ft. E. of Keefe Rd. 4.1 +/- 0.3 3.7 +/- 0.2 4.2 +/- 0.2 3.7 +/- 0.2 135° at 4.2 miles 91* Rt 51A, Pole #59, 0.8 mi. W. of Rt. 51 3.8 +/- 0.2 3.8 +/- 0.3 4.1 +/- 0.2 3.5 +/- 0.2 157° at 4.9 miles 92* Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104 4.3 +/- 0.3 4.6 +/- 0.2 4.7 +/- 0.2 4.2 +/- 0.2 183° at 4.5 miles 93* Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104 4.1 +/- 0.3 3.9 +/- 0.3 4.3 +/- 0.3 3.7 +/- 0.2 206° at 4.4 miles 94* Rt. 1, Pole #82, 250 ft. E. of Kocher Rd. (Co. Rt. 63) 3.6 +/- 0.2 4.0 +/- 0.4 4.1 +/- 0.3 3.6 +/- 0.2 224° at 4.4 miles 95* Alcan W access Rd., Joe Fultz Blvd, Pole #21 3.2 +/- 0.2 3.5 +/- 0.2 3.7 +/- 0.2 3.5 +/- 0.2 239° at 3.7 miles 96* Creamery Rd., 0.3 mi. S. of Middle Rd., Pole 1-1/2 3.7 +/- 0.3 3.8 +/- 0.2 4.0 +/- 0.2 3.8 +/- 0.2 199° at 3.6 miles 97* Rt. 29, Pole #50, 200ft. N. of Miner Rd. 3.6 +/- 0.2 4.0 +/- 0.3 4.1 +/- 0.2 3.6 +/- 0.2 145° at 1.8 miles 98* Lake Rd., Pole #145, 0.15 mi. E. of Rt 29 3.9 +/- 0.2 4.1 +/- 0.3 4.3 +/- 0.2 3.9 +/- 0.2 103° at 1.2 miles 99 NMP Rd., 0.4 mi. N. of Lake Rd., Env. Station R1 4.1 +/- 0.4 4.2 +/- 0.3 4.7 +/- 0.2 4.0 +/- 0.2 92° at 1.8 miles 100 Rt. 29 & Lake Rd., Env. Station R2 3.9 +/- 0.2 4.4 +/- 0.2 4.5 +/- 0.2 4.0 +/- 0.2 106° at 1.1 miles 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 3.5 +/- 0.3 4.6 +/- 0.9 4.1 +/- 0.2 3.5 +/- 0.2 134° at 1.4 miles 102 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 3.7 +/- 0.3 3.9 +/- 0.2 4.3 +/- 0.2 3.8 +/- 0.2 175° at 11.9 miles 103 EIC, East Garage Rd., Lamp Post 4.3 +/- 0.3 4.4 +/- 0.3 4.9 +/- 0.5 4.1 +/- 0.2 266° at 0.4 miles 104 Parkhurst Rd., Pole #23, 0.1 mi. S. of Lake rd. 3.7 +/- 0.3 4.1 +/- 0.2 4.5 +/- 0.3 3.8 +/- 0.2 103° at 1.4 miles 105 Lake view Rd. Pole #36, 0.5 mi. S. of Lake Rd. 3.9 +/- 0.2 4.1 +/- 0.2 4.5 +/- 0.2 3.8 +/- 0.3 198° at 1.4 miles 106 Shoreline Cove, W. of NMP-1, Tree on W. Edge 5.0 +/- 0.3 4.9 +/- 0.3 5.6 +/- 0.3 5.4 +/- 0.9 272° at 0.3 miles 107 Shoreline Cove, W. of NMP-1, 30 ft SSW of #106 4.9 +/- 0.3 5.0 +/- 0.3 5.6 +/- 0.3 5.2 +/- 0.3 271° at 0.3 miles 108 Lake Rd., Pole #142, 300 ft E. of Rt. 29 S. 4.1 +/- 0.3 3.9 +/- 0.2 4.3 +/- 0.2 4.2 +/- 0.2 105° at 1.1 miles 109 Tree North of Lake Rd., 300 ft E. of Rt. 29 N 4.1 +/- 0.3 4.0 +/- 0.3 4.5 +/- 0.2 4.2 +/- 0.2 104° at 1.1 miles 111 Control, State Route 38, Sterling NY 3.3 +/- 0.2 3.8 +/- 0.2 4.2 +/- 0.2 3.9 +/- 0.2 214° at 21.8 miles 112 EOF/Env. Lab, Oswego County Airport 4.1 +/- 0.3 3.7 +/- 0.2 4.1 +/- 0.2 4.4 +/- 0.2 175° at 11.9 miles 113 Control, Baldwinsville, NY 3.5 +/- 0.2 3.6 +/- 0.3 3.7 +/- 0.2 3.8 +/- 0.2 178° at 24.7 miles (1) Direction and distance based on NMP-2 reactor centerline and sixteen 22.5o sector grid

TLD required by ODCM 6 - 37

TABLE 6-11 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2005 Results in Units of pCi/liter +/- 1 Sigma SAMPLE LOCATION*** No.55**

Collection Date I-131 K-40 Cs-134 Cs-137 Ba/La Others 04/ 04/05 <0.736 1400 +/- 88 <7.75 <6.76 <8.36 < LLD 04/18/05 <0.720 1630 +/-68 <3.85 <5.26 <5.93 < LLD 05/09/05 <0.610 1440 +/- 84 <6.62 <6.52 <5.51 < LLD 05/23/05 <0.799 1370 +/- 85 <9.12 <8.01 <9.97 < LLD 06/06/05 <0.468 1530 +/- 82 <6.76 <7.50 <4.45 < LLD 06/20/05 <0.796 1310 +/- 79 <6.96 <6.70 <7.17 < LLD 07/11/05 <0.727 1480 +/- 92 <6.46 <9.88 <9.38 < LLD 07/25/05 <0.461 1440 +/- 63 <5.15 <4.93 <6.57 < LLD 08/08/05 <0.384 1570 +/- 95 <9.34 <7.25 <7.96 < LLD 08/22/05 <0.633 1450 +/- 87 <8.45 <8.01 <9.00 < LLD 09/12/05 <0.670 1510 +/- 88 <8.00 <5.33 <9.48 < LLD 09/26/05 <0.819 1460 +/- 92 <6.10 <8.17 <5.86 < LLD 10/11/05 <0.593 1480 +/- 87 <7.33 <8.56 <7.86 < LLD 10/24/05 <0.649 1320 +/- 85 <7.40 <7.93 <8.64 < LLD 11/07/05 <0.760 1550 +/- 89 <8.57 <7.83 <7.85 < LLD 11/21/05 <0.535 1730 +/-99 <8.98 <7.90 <8.30 < LLD 12/05/05 <0.705 1720 +/- 98 <8.85 <7.73 <6.35 < LLD 12/19/05 <0.549 1480 +/- 91 <8.28 <8.74 <7.86 < LLD SAMPLE LOCATION*** No.4**

Collection Date I-131 K-40 Cs-134 Cs-137 Ba/La Others 04/04/05 <0.526 1700 +/- 100 <9.49 <9.23 <9.78 < LLD 04/18/05 <0.654 1410 +/- 132 <12.2 <14.0 <14.9 < LLD 05/09/05 <0.643 1540 +/- 95 <11.3 <8.67 <10.5 < LLD 05/23/05 <0.835 1650 +/- 98 <9.90 <8.85 <9.87 < LLD 06/06/05 <0.454 1420 +/- 77 <5.69 <6.69 <7.60 < LLD 06/20/05 <0.788 1550 +/- 90 <7.79 <6.05 <7.30 < LLD 07/11/05 <0.633 1500 +/- 95 <7.32 <7.19 <10.1 < LLD 07/25/05 <0.578 1440 +/- 65 <5.54 <4.96 <4.98 < LLD 08/08/05 <0.498 1520 +/- 96 <7.52 <8.21 <8.09 < LLD 08/22/05 <0.527 1650 +/- 97 <6.12 <8.29 <7.49 < LLD 09/12/05 <0.666 1440 +/- 87 <7.47 <6.86 <5.63 < LLD 09/26/05 <0.794 1720 +/- 101 <8.30 <5.04 <11.2 < LLD 10/11/05 <0.575 1470 +/- 85 <7.17 <7.24 <4.36 < LLD 10/24/05 <0.808 1430 +/- 88 <8.13 <6.78 <10.0 < LLD 11/07/05 <0.766 1460 +/- 90 <4.45 <7.93 <8.02 < LLD 11/21/05 <0.656 1490 +/- 89 <5.22 <7.43 <7.87 < LLD 12/05/05 <0.593 1930 +/- 150 <11.6 <13.3 <10.3 < LLD 12/19/05 <0.454 1640 +/- 93 <8.09 <7.57 <9.69 < LLD Plant related radionuclides

- Optional sample location

- - Corresponds to sample location noted on Figure 3.3-4 6 - 38

TABLE 6-11 (continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2005 Results in Units of pCi/liter +/- 1 Sigma SAMPLE LOCATION No.*** 76**

Collection Date I-131 K-40 Cs-134 Cs-137 Ba/La Others 04/4/05 <0.816 1660+/- 36 <1.93 <2.80 <4.57 < LLD 04/18/05 <0.796 1490 +/- 85 <6.09 <5.53 <7.84 < LLD 05/09/05 <0.711 1420 +/- 84 <7.86 <5.33 <8.72 < LLD 05/23/05 <0.835 1620 +/- 68 <4.17 <6.45 <5.94 < LLD 06/06/05 <0.526 1460 +/- 80 <6.23 <6.05 <7.29 < LLD 06/20/05 <0.806 1480 +/- 88 <5.81 <8.37 <9.02 < LLD 07/11/05 <0.757 1610 +/- 94 <7.73 <5.66 <10.6 < LLD 07/25/05 <0.478 1860 +/- 76 <6.45 <6.60 <7.71 < LLD 08/08/05 <0.336 1450 +/- 92 <7.69 <8.24 <6.19 < LLD 08/22/05 <0.834 1420 +/- 95 <6.82 <8.16 <13.2 < LLD 09/12/05 <0.693 1760 +/- 101 <7.15 <7.68 <13.2 < LLD 09/26/05 <0.775 1640 +/- 101 <10.3 <9.84 <10.9 < LLD 10/11/05 <0.486 1690 +/- 94 <10.2 <7.78 <5.67 < LLD 10/24/05 <0.795 1700 +/- 98 <5.95 <7.99 <11.6 < LLD 11/07/05 <0.780 1610 +/- 96 <8.73 <9.19 <9.07 < LLD 11/21/05 <0.538 1590 +/- 117 <7.85 <10.1 <11.2 < LLD 12/05/05 <0.509 1540 +/- 90 <7.24 <8.44 <10.2 < LLD 12/19/05 <0.613 1730 +/- 99 <8.32 <8.08 <6.37 < LLD SAMPLE LOCATION No.77*** (Control)

Collection Date I-131 K-40 Cs-134 Cs-137 Ba/La Others 04/ 04/05 <0.628 1900 +/- 75 <4.06 <5.77 <6.05 < LLD 04/ 18/05 <0.761 1680 +/- 100 <10.5 <7.24 <10.6 < LLD 05/ 09/05 <0.525 1620 +/- 68 <4.02 <6.13 <7.21 < LLD 05/ 23/05 <0.826 1740 +/- 96 <7.79 <8.64 <9.62 < LLD 06/ 06/05 <0.533 1530 +/- 103 <9.34 <7.64 <13.1 < LLD 06/20/05 <0.837 1860 +/- 102 <6.45 <7.68 <9.17 < LLD 07/11/ 05 <0.808 1460 +/- 119 <10.5 <12.5 <10.9 < LLD 07/ 25/05 <0.540 1500 +/- 83.4 <6.92 <7.07 <9.19 < LLD 08/ 08/05 <0.398 1280 +/- 110 <10.2 <10.3 <14.2 < LLD 08/ 22/05 <0.564 1720 +/- 93 <9.22 <7.22 <5.65 < LLD 09/12/ 05 <0.771 1410 +/- 110 <9.18 <9.86 <12.8 < LLD 09/26/05 <0.781 1540 +/- 116 <10.5 <9.88 <14.2 < LLD 10/11/ 05 <0.767 1430 +/- 111 <10.6 <10.2 <11.9 < LLD 10/24/ 05 <0.838 1430 +/- 114 <10.8 <9.80 <12.8 < LLD 11/ 07/05 <0.844 1640 +/- 119 <11.4 <8.38 <13.9 < LLD 11/ 21/05 <0.588 1640 +/- 138 <9.73 <13.3 <13.1 < LLD 12/ 05/05 <0.663 1530 +/- 115 <9.95 <9.80 <12.2 < LLD 12/19/05 <0.510 1410 +/- 89.7 <8.27 <7.14 <6.56 < LLD Plant related radionuclides

Sample location required by ODCM

- Optional sample location

- - Corresponds to sample location noted on Figure 3.3-4 6 - 39

TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2005 Results in Units of pCi/g (wet) +/- 1 sigma COLLECTION SAMPLE DESCRIPTION Be-7 K-40 I-131 Cs-134 Cs-137 Zn-65 SITE DATE Tomatoes <0.159 2.82 +/- 0.26 <0.018 <0.032 <0.019 <0.053 Bean Leaves 0.814 +/- 0.10 2.81 +/- 0.25 <0.022 <0.028 <0.016 <0.053 133

09/14/05 Squash 1.02 +/- 0.14 3.57 +/- 0.37 <0.029 <0.030 <0.030 <0.090 Rhubarb Leaves <0.207 3.52 +/- 0.39 <0.028 <0.021 <0.037 <0.095 Collard Greens 0.304 +/- 0.12 4.05 +/- 0.42 <0.036 <0.034 <0.036 <0.086 134

09/14/05 Grape Leaves 0.718 +/- 0.12 1.95 +/- 0.27 <0.016 <0.029 <0.022 <0.086 Rhubarb Leaves 0.174 +/- 0.58 3.31 +/- 0.26 <0.017 <0.024 <0.018 <0.068 142 ** 09/14/05 Tomatoes <0.152 2.35 +/- 0.24 <0.021 <0.027 <0.017 <0.069 Grape Leaves 0.681 +/- 0.10 2.40 +/- 0.28 <0.026 <0.028 <0.029 <0.086 Horseradish Leaves <0.269 3.79 +/- 0.40 <0.025 <0.033 <0.0.27 <0.072 144

09/14/05 Tomatoes <0.179 3.11 +/- 0.28 <0.022 <0.032 <0.018 <0.068 Squash Leaves 0.88 +/- 0.10 2.47 +/- 0.24 <0.023 <0.028 <0.016 <0.053 Pumpkin Leaves <0.200 4.16 +/- 0.47 <0.028 <0.022 <0.037 <0.131 Rhubarb Leaves <0.150 3.87 +/- 0.30 <0.018 <0.028 <0.024 <0.058 Pumpkin Leaves <0.163 3.36 +/- 0.29 <0.026 <0.028 <0.029 <0.074 145

09/14/05 Horseradish Leaves 0.275 +/- 0.07 3.70 +/- 0.28 <0.021 <0.025 <0.023 <0.056 (Control) Cucumber Leaves 0.897 +/- 0.015 2.09+/- 0.35 <0.032 <0.030 <0.038 <0.125 Tomatoes <0.174 2.81 +/- 0.25 <0.021 <0.028 <0.027 <0.049

Sample Location required by ODCM

- Optional sample location Note: Other plant related radionuclides <LLD 6 - 40

TABLE 6-13 MILK ANIMAL CENSUS 2005 TOWN OR LOCATION DISTANCE (2) NUMBER OF MILK DEGREES (2)

AREA (a) DESIGNATION(1) (miles) ANIMALS Scriba 62 184o 6.6 5G(3) 75 145o 7.6 2G(3) 9 97o 4.8 40C New Haven 4* 113o 7.8 80C 64 107o 7.9 38C 14 123o 9.4 56C 60 91o 9.5 22C 76* 120o 6.3 25C Mexico 50 93o 8.7 NONE 55* 95o 9.0 57C 21 112o 10.3 71C 72 100o 9.6 39C Sterling 73 234o 13.1 NONE Richland 22 90o 9.7 4C 25 NONE Volney 66 22C Granby 77** 191o 13.9 53C (Control)

MILKING ANIMAL TOTALS: 507 Cows (including control locations) 7 Goats MILKING ANIMAL TOTALS: 454 Cows (excluding control locations) 7 Goats NOTES:

C = Cows G = Goats

= Milk sample location

- = Milk sample control location (1) = Reference Figure 3.3-4 (2) = Degrees and distance are based on NMP-2 reactor building centerline (3) = Goat is not currently producing milk or any milk produced is utilized by the owner NONE = No cows or goats at that location. Location was a previous location with cows and/or goats (a) = Census performed out to a distance of approximately 10 miles 6 - 41

TABLE 6-14 2005 RESIDENCE CENSUS MAP METEOROLOGICAL LOCATION DEGREES (2) DISTANCE (2)

LOCATION (1) SECTOR

N - -

NNE - -

NE - -

ENE - -

West Sunset Bay Road A E 82° 0.9 miles Lake Road B ESE 116° 0.7 miles County Route 29 C(3) SE 126° 1.6 miles County Route 29 D SSE 152° 1.3 miles Miner Road E S 187° 1.6 miles Lakeview Road F SSW 213° 1.7 miles Lakeview Road G SW 223° 1.5 miles Bible Camp Retreat H WSW 248° 1.3 miles

W - -

WNW - -

NW - -

NNW - -

NOTES:

This meteorological sector is over Lake Ontario. There is no residence within five miles (1) Corresponds to Figure 3.3-5 (2) Based on JAF reactor centerline GPS readings (3) In October 2004, a new home was built and occupied in the SE sector. The new home replaces location (Parkhurst Road, 127o @ 1.3 miles - Figure 3.3-5, Nearest Residence Location 1) as the nearest residence in that sector.

6 - 42

7.0 HISTORICAL DATA TABLES Sample Statistics from Previous Environmental Sampling The mean, minimum value and maximum value were calculated for selected sample mediums and isotopes.

Special Considerations:

1. Sample data listed as 1969 was taken from the NINE MILE POINT, PREOPERA-TION SURVEY, 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.

2. Sample results listed as 1974 and 1975 were taken from the respective Annual Radiological Environmental Operating Reports for Nine Mile Point Unit 1 Nuclear Station. Sample results listed as 1985 through the current year were taken from the respective James A. FitzPatrick Nuclear Power Plant Annual Radiological Environ-mental 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.

7-1

TABLE 7-1 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION: CONTROL

Isotope Cs-134 Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean Min. Max. Mean 1969 ** ** ** ** ** ** ** ** **

1974 ** ** ** ** ** ** ** ** **

1975 ** ** ** ** ** ** ** ** **

1985 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD 0.027 0.027 0.027 <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

Langs Beach - beyond influence of the site in a westerly direction.

- No data. Sample not required until new technical specifications implemented in 1985.

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

7-2

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT Results in pCi/g (dry)

LOCATION: INDICATOR

Isotope Cs-134 Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean Min. Max. Mean 1969 ** ** ** ** ** ** ** ** **

1974 ** ** ** ** ** ** ** ** **

1975 ** ** ** ** ** ** ** ** **

1985 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD 0.25 0.32 0.29 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 0.28 0.30 0.29 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 0.12 0.14 0.13 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 0.12 0.14 0.13 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 0.18 0.46 0.32 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 0.06 0.37 0.22 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 0.14 0.15 0.15 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 0.15 0.17 0.16 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 0.11 0.17 0.14 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 0.06 0.06 0.06 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 0.06 0.10 0.08 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 0.06 0.07 0.06 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 0.06 0.07 0.07 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 0.05 0.05 0.05 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 0.04 0.05 0.05 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 0.04 0.04 0.04 <LLD <LLD <LLD 2005 <LLD <LLD <LLD 0.06 0.09 0.08 <LLD <LLD <LLD

Sunset Beach - closest off-site location with recreational value.

- No data. Sample not required until new technical specifications implemented in 1985.

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

7-3

TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION: CONTROL

Isotope Cs-137 Year Min. Max. Mean 1969 No Data No Data No Data 1974 0.94 0.94 0.94 1975 <MDL <MDL <MDL 1985 0.026 0.047 0.034 1986 0.021 0.032 0.025 1987 0.017 0.040 0.031 1988 0.023 0.053 0.034 1989 0.028 0.043 0.034 1990 0.033 0.079 0.045 1991 0.021 0.034 0.029 1992 0.019 0.026 0.022 1993 0.030 0.036 0.033 1994 0.014 0.031 0.022 1995 0.017 0.023 0.019 1996 0.018 0.022 0.020 1997 0.012 0.030 0.021 1998 0.013 0.013 0.013 1999 <LLD <LLD <LLD 2000 0.021 0.021 0.021 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Control location was at an area beyond the influence of the site (westerly direction).

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

7-4

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet)

LOCATION: INDICATOR * (NMP/JAF)

Isotope Cs-137 Year Min. Max. Mean 1969 0.01 0.13 0.06 1974 0.08 4.40 0.57 1975 1.10 1.70 1.38 1985 0.018 0.045 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0.022 0.054 0.032 1989 0.020 0.044 0.034 1990 0.027 0.093 0.040 1991 0.018 0.045 0.029 1992 0.014 0.030 0.024 1993 0.018 0.035 0.028 1994 0.015 0.023 0.019 1995 0.016 0.022 0.019 1996 0.016 0.025 0.020 1997 0.014 0.023 0.018 1998 0.021 0.021 0.021 1999 0.018 0.021 0.020 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 0.016 0.016 0.016 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Indicator locations are in the general area of the NMP-1 and J.A. FitzPatrick cooling water discharge structures.

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

7-5

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/liter LOCATION: CONTROL Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 * * * * *

1975 * * * * *

1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

No gamma analysis performed (not required).

Location was the City of Oswego Water Supply for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 2005.

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

7-6

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER Results in pCi/liter LOCATION: INDICATOR Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 * * * * *

1975 * * * * *

1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

No gamma analysis performed (not required).

Indicator location was the NMP 1 Inlet Canal for the period 1969 - 1973, and the JAF Inlet Canal for 1974

- 2005.

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

7-7

TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/liter LOCATION: CONTROL

Isotope Tritium Year Min. Max. Mean 1969 No Data No Data No Data 1974 <MDL <MDL <MDL 1975 311 414 362 1985 230 430 288 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 143 217 186 1990 260 320 290 1991 180 200 190 1992 190 310 243 1993 160 230 188 1994 250 250 250 1995 230 230 230 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 190 190 190 1999 220 510 365 2000 196 237 212 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Control location is the City of Oswego, drinking water for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 2005.

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

7-8

TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/liter LOCATION: INDICATOR

Isotope Tritium Year Min. Max. Mean 1969 No Data No Data No Data 1974 380 500 440 1975 124 482 335 1985 250 1200** 530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 135 288 225 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 1994 180 260 220 1995 320 320 320 1996 <LLD <LLD <LLD 1997 160 160 160 1998 190 190 190 1999 180 270 233 2000 161 198 185 2001 <LLD <LLD <LLD 2002 297 297 297 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the JAF Inlet Canal for 1974-2005.

- Suspect sample contamination. Recollected samples showed normal levels of tritium.

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

7-9

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Results in pCi/m3 LOCATION: CONTROL

Isotope Gross Beta Year Min. Max. Mean 1969 0.130 0.540 0.334 1974 0.001 0.808 0.121 1975 0.008 0.294 0.085 1985 0.013 0.043 0.024 1986 0.008 0.272 0.039 1987 0.009 0.037 0.021 1988 0.008 0.039 0.018 1989 0.007 0.039 0.017 1990 0.003 0.027 0.013 1991 0.007 0.028 0.014 1992 0.006 0.020 0.012 1993 0.007 0.022 0.013 1994 0.008 0.025 0.015 1995 0.006 0.023 0.014 1996 0.008 0.023 0.014 1997 0.006 0.025 0.013 1998 0.004 0.034 0.014 1999 0.010 0.032 0.017 2000 0.006 0.027 0.015 2001 0.006 0.034 0.016 2002 0.008 0.027 0.016 2003 0.004 0.032 0.015 2004 0.008 0.032 0.016 2005 0.008 0.034 0.019

Locations used for 1977 - 1984 were C off-site, D1 off-site, D2 off-site, E off-site, F off-site, and G off-site.

Control location R-5 off-site was used for 1985-2005 (formerly C off-site location).

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

7 - 10

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA Results in pCi/m3 LOCATION: INDICATOR

Isotope Gross Beta Year Min. Max. Mean 1969 0.130 0.520 0.320 1974 0.003 0.885 0.058 1975 0.001 0.456 0.067 1985 0.001 0.044 0.021 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.006 0.023 0.014 1991 0.006 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.023 0.014 1994 0.006 0.024 0.015 1995 0.004 0.031 0.014 1996 0.006 0.025 0.013 1997 0.001 0.018 0.010 1998 0.002 0.040 0.015 1999 0.009 0.039 0.017 2000 0.005 0.033 0.015 2001 0.004 0.037 0.016 2002 0.006 0.026 0.016 2003 0.005 0.035 0.015 2004 0.003 0.036 0.016 2005 0.007 0.041 0.019

Locations used for 1969 - 1973 were D1 on-site, D2 on-site, E on-site, F on-site and G on-site. Locations used for 1974 - 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site and K on-site, as applicable. 1985 - 2005 locations were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

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

7 - 11

TABLE 7-11 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Results in pCi/m3 LOCATION: CONTROL

Isotope Iodine-131 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 <MDL <MDL <MDL 1985 <LLD <LLD <LLD 1986 0.041 0.332 0.151 1987 <LLD <LLD <LLD 1988 <LLD <LLD <LLD 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Locations D1 off-site, D2 off-site, E off-site, F off-site and G off-site used for 1976 - 1984. Location R-5 off-site used for 1985 - 2005.

- No results - I-131 analysis not required.

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

7 - 12

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE Results in pCi/m3 LOCATION: INDICATOR

Isotope Iodine-131 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 0.25 0.30 0.28 1985 <LLD <LLD <LLD 1986 0.023 0.360 0.119 1987 0.011 0.018 0.014 1988 <LLD <LLD <LLD 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Locations used for 1976 - 1984 were D1 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on-site and K on-site, as applicable. Locations used for 1985 - 2005 were R-1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.

- No results - I-131 analysis not required.

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

7 - 13

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m3 LOCATION: CONTROL **

Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 * * * * *

1975 * * * * *

1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 0.0075 0.0311 0.0193 <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

No data available (not required prior to 1977).

- Locations included composites of off-site air monitoring locations for 1977 - 1984. Sample location included only R-5 air monitoring location for 1985 - 2005.

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 - 14

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES Results in pCi/m3 LOCATION: INDICATOR **

Isotope Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 * * * * *

1975 * * * * *

1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 0.0069 0.0364 0.0183 <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD 0.0048 0.0048 0.0048 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

No data available (not required prior to 1977).

- Locations included composites of on-site air monitoring locations for 1977 - 1984. Sample locations included R-1 through R-4 air monitoring locations for 1985 - 2005.

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 - 15

TABLE 7-15A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem/standard month LOCATION: CONTROL **

Year Min. Max. Mean Preop * *

1974 2.7 8.9 5.6 1975 4.8 6.0 5.5 1985 4.5 7.6 5.6 1986 5.3 7.5 6.3 1987 4.6 6.6 5.4 1988 4.4 6.8 5.6 1989 2.9 6.4 4.7 1990 3.7 6.0 4.7 1991 3.8 5.8 4.7 1992 2.6 5.1 4.1 1993 3.4 5.7 4.4 1994 3.1 5.0 4.1 1995 3.4 5.7 4.4 1996 3.4 5.6 4.3 1997 3.7 6.2 4.7 1998 3.7 5.6 4.4 1999 3.6 7.1 4.6 2000 3.7 7.3 4.7 2001 3.6 5.4 4.4 2002 3.4 5.5 4.3 2003 3.4 5.5 4.2 2004 3.3 5.9 4.3 2005 3.3 5.1 4.1

Data not available.

- TLD #8 and 14 established 1974, TLD #49 established 1980, TLD #111 established 1988, TLD #113 established 1991.

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 - 16

TABLE 7-15B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: RETS CONTROL **

Year Min. Max. Mean Preop * *

1974 2.7 8.9 5.6 1975 4.8 6.0 5.5 1985 4.4 6.8 5.4 1986 5.5 7.2 6.3 1987 4.6 5.8 5.2 1988 4.8 6.8 5.4 1989 2.9 6.4 4.1 1990 3.7 6.0 4.8 1991 3.8 5.3 4.6 1992 2.6 4.7 3.9 1993 3.4 5.3 4.4 1994 3.1 4.6 3.9 1995 3.4 4.9 4.2 1996 3.4 5.6 4.2 1997 3.9 5.2 4.6 1998 3.7 4.8 4.2 1999 3.7 4.7 4.4 2000 3.7 5.5 4.3 2001 3.9 5.0 4.4 2002 3.4 5.2 4.1 2003 3.4 4.8 4.2 2004 3.3 5.9 4.6 2005 3.4 5.1 4.3

Data not available.

- TLD #s 8 & 14 established 1974, TLD #49 established 1980.

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 - 17

TABLE 7-16A HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SITE BOUNDARY **

Year Min. Max. Mean Preop * *

1974 * *

1975 * *

1985 4.9 5.9 5.3 1986 5.4 6.8 5.9 1987 4.7 5.9 5.3 1988 5.0 6.1 5.4 1989 4.5 5.2 4.8 1990 4.5 5.4 4.8 1991 4.3 5.5 4.8 1992 3.7 4.6 4.2 1993 3.8 4.8 4.3 1994 2.8 4.9 4.0 1995 3.5 5.1 4.4 1996 3.2 5.3 4.1 1997 3.5 5.9 4.6 1998 3.7 5.1 4.4 1999 3.3 7.5 4.7 2000 3.6 6.8 4.5 2001 3.6 5.3 4.5 2002 3.5 5.1 4.3 2003 3.2 4.9 4.3 2004 3.3 6.4 4.4 2005 3.4 4.8 4.2

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 the lakeshore and is considered to be generally not accessible to the public. These locations are not used in the site boundary dose determination.

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

- TLDs used for statistics: 7, 18, 78, 79, 80, 81, 82, 83 & 84.

7 - 18

TABLE 7-16B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: OFF-SITE SECTORS **

Year Min. Max. Mean Preop * *

1974 * *

1975 * *

1985 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 1988 3.8 7.0 5.3 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 1991 3.6 5.8 4.7 1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 1994 3.0 5.1 4.0 1995 3.2 5.2 4.3 1996 3.2 5.3 4.2 1997 3.5 5.8 4.4 1998 3.5 5.0 4.2 1999 3.6 5.6 4.4 2000 3.4 6.6 4.5 2001 3.6 5.4 4.4 2002 3.1 5.3 4.2 2003 3.4 4.8 4.1 2004 3.2 6.7 4.4 2005 3.2 4.7 4.0

Data not available (not required prior to 1985).

- TLD locations initiated in 1985 as required by the New Technical Specifications. Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95.

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

7 - 19

TABLE 7-16C HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: SPECIAL INTEREST **

Year Min. Max. Mean Preop * *

1974 * *

1975 * *

1985 3.9 6.8 5.3 1986 4.8 8.2 6.1 1987 3.5 6.0 5.1 1988 3.9 6.6 5.3 1989 2.1 6.4 4.9 1990 3.2 6.3 4.8 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 1994 2.9 4.8 4.1 1995 3.6 4.8 4.2 1996 3.2 5.1 4.2 1997 3.5 6.2 4.6 1998 3.7 5.6 4.4 1999 3.6 7.1 4.6 2000 3.6 7.3 4.7 2001 3.8 5.4 4.4 2002 3.5 5.5 4.2 2003 3.4 5.5 4.3 2004 3.0 5.9 4.2 2005 3.4 5.1 4.1

Data not available (not required prior to 1985).

- TLD locations initiated in 1985 as required by the New Technical Specifications. Includes TLD numbers 8, 15, 56, 58, 96, 97 and 98, which are located near critical residences and populated areas near the site.

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 - 20

TABLE 7-16D HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: ON-SITE INDICATOR **

Year Min. Max. Mean Preop * *

1974 3.1 10.6 5.7 1975 4.6 16.0 7.3 1985 4.7 15.9 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4.4 11.9 6.0 1989 2.7 13.1 6.0 1990 3.6 12.9 5.5 1991 3.2 11.6 5.4 1992 3.2 5.6 4.3 1993 3.1 13.6 5.2 1994 2.8 14.3 5.1 1995 3.5 28.6 6.2 1996 3.1 32.6 6.4 1997 3.5 28.8 8.1 1998 3.6 28.8 6.2 1999 3.3 28.4 6.6 2000 3.7 16.5 5.6 2001 3.8 14.5 5.6 2002 3.5 13.6 5.3 2003 3.2 12.9 5.3 2004 3.3 13.2 5.4 2005 3.4 14.1 5.4

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 - 2005). Locations are existing or previous on-site environmental air monitoring locations.

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 - 21

TABLE 7-16E HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month LOCATION: OFF-SITE INDICATOR **

Year Min. Max. Mean Preop * *

1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.1 4.8 1991 3.4 5.8 4.5 1992 3.1 5.2 4.1 1993 3.2 5.7 5.0 1994 3.0 5.1 4.1 1995 3.9 5.7 4.4 1996 3.3 5.5 4.1 1997 3.7 6.2 4.7 1998 3.9 5.6 4.5 1999 3.8 7.1 4.6 2000 3.8 7.3 4.6 2001 3.7 5.9 4.6 2002 3.6 5.5 4.4 2003 3.1 5.5 4.4 2004 3.2 6.5 4.5 2005 3.6 5.1 4.2

No data available.

- Includes TLD numbers 8, 9, 10, 11, 12 and 13 (off-site environmental air monitoring locations).

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 - 22

TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/liter LOCATION: CONTROL **

Isotope Cs-137 I-131 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 * * * * *

1975 * * * * *

1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD <LLD <LLD <LLD 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

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.

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 - 23

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/liter LOCATION: INDICATOR Isotope Cs-137 I-131 Year Min. Max. Mean Min. Max. Mean 1969 * * * * *

1974 1.6 39 10.5 0.70 2.00 1.23 1975 6.0 22 16 0.01 2.99 0.37 1985 <LLD <LLD <LLD <LLD <LLD <LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 9.4 7.4 <LLD <LLD <LLD 1988 10.0 10.0 10.0 <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD 1992 <LLD <LLD <LLD <LLD <LLD <LLD 1993 <LLD <LLD <LLD <LLD <LLD <LLD 1994 <LLD <LLD <LLD <LLD <LLD <LLD 1995 <LLD <LLD <LLD <LLD <LLD <LLD 1996 <LLD <LLD <LLD <LLD <LLD <LLD 1997 <LLD <LLD <LLD 0.25 .044 0.35 1998 <LLD <LLD <LLD <LLD <LLD <LLD 1999 <LLD <LLD <LLD <LLD <LLD <LLD 2000 <LLD <LLD <LLD <LLD <LLD <LLD 2001 <LLD <LLD <LLD <LLD <LLD <LLD 2002 <LLD <LLD <LLD <LLD <LLD <LLD 2003 <LLD <LLD <LLD <LLD <LLD <LLD 2004 <LLD <LLD <LLD <LLD <LLD <LLD 2005 <LLD <LLD <LLD <LLD <LLD <LLD

No data available (sample not required).

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

7 - 24

TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Results in pCi/g (wet)

LOCATION: CONTROL

Isotope Cs-137 Year Min. Max. Mean 1969 ** ** **

1974 ** ** **

1975 ** ** **

1985 <LLD <LLD <LLD 1986 <LLD <LLD <LLD 1987 <LLD <LLD <LLD 1988 <LLD <LLD <LLD 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 1992 <LLD <LLD <LLD 1993 0.008 0.008 0.008 1994 <LLD <LLD <LLD 1995 <LLD <LLD <LLD 1996 <LLD <LLD <LLD 1997 <LLD <LLD <LLD 1998 <LLD <LLD <LLD 1999 <LLD <LLD <LLD 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

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).

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

Data comprised of broadleaf and non-broadleaf vegetation (1980-1984). Data comprised of broadleaf vegetation only (1985-2005).

7 - 25

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS Results in pCi/g (wet)

LOCATION: INDICATOR

Isotope Cs-137 Year Min. Max. Mean 1969 ** ** **

1974 0.04 0.34 0.142 1975 <MDL <MDL <MDL 1985 0.047 0.047 0.047 1986 <LLD <LLD <LLD 1987 <LLD <LLD <LLD 1988 0.008 0.008 0.008 1989 0.011 0.011 0.011 1990 <LLD <LLD <LLD 1991 0.039 0.039 0.039 1992 <LLD <LLD <LLD 1993 <LLD <LLD <LLD 1994 0.006 0.012 0.010 1995 0.011 0.012 0.012 1996 <LLD <LLD <LLD 1997 0.013 0.013 0.013 1998 <LLD <LLD <LLD 1999 0.007 0.007 0.007 2000 <LLD <LLD <LLD 2001 <LLD <LLD <LLD 2002 <LLD <LLD <LLD 2003 <LLD <LLD <LLD 2004 <LLD <LLD <LLD 2005 <LLD <LLD <LLD

Indicator locations were available downwind locations within ten miles of the site and with high deposition potential.

- No data available (control samples not required).

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

Data comprised of broadleaf and non-broadleaf vegetation (1984). Data comprised of broadleaf vegetation only (1985-2005).

7 - 26

8.0 QA/QC PROGRAM 8.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that 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 JAF Environmental Laboratory has engaged the services of two independent laboratories to provide quality assurance comparison samples.

The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S.

Department of Commerces National Institute of Standards and Technology (NIST) in Gaithersburg, Maryla nd.

Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratorys performance for Analytic's sample results.

In addition to the Analytics Program, the JAF Environmental Laboratory participates in the NEI/NIST Measurement Assurance Program. In 1987, the nuclear industry established a Measurement Assurance Program at the National Bureau of Standards (now the National Institute of Standards and Technology) to provide sponsoring nuclear utilities an independent verification, traceable to NIST, of their capability to make accurate measurements of radioactivity, as described in NRC Regulatory Guide 4.15.

The program includes distribution to sponsoring utilities, approximately six times a year.

The samples are prepared by NIST to present specific challenges to participating laboratories. For 2005, the two mixed gamma samples analyzed tested the ability of the JAF Environmental Laboratory to accurately account for coincidence summing from Cs-134. NIST supplies sample media as blind sample spikes. These samples are prepared and analyzed by the JAF Environmental Laboratory and the results are submitted to the Entergy Nuclear Northeast representative, who uses predetermined acceptance criteria methodology for evaluating the laboratorys performance. The performance results along with the NIST Report of Test (Certifies what activities are present in the sample) are forwarded to the laboratory.

8-1

8.2 PROGRAM SCHEDULE SAMPLE LABORATORY SAMPLE PROVIDER MEDIA ANALYSIS ANALYTICS Water Gross Beta 1 Water Tritium 1 Water I-131 2 Water Mixed Gamma 3 Air Gross Beta 2 Air I-131 2 Air Mixed Gamma 3 Milk I-131 2 Milk Mixed Gamma 2 Soil Mixed Gamma 1 Vegetation Mixed Gamma 1 TOTAL SAMPLE INVENTORY 20 8.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratorys analysis result. The sample evaluation method is discussed below.

8.3.1 SAMPLE RESULTS EVALUATION Samples provided by Analytics and NIST are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

8-2

An 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 Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio = QC Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE 8.3.1 ERROR RESOLUTION RATIO OF AGREEMENT

<3 0.4-2.5 3.1 to 7.5 0.5-2.0 7.6 to 15.5 0.6-1.66 15.6 to 50.5 0.75-1.33 50.6 to 200 0.8-1.25

>200 0.85-1.18 This acceptance test is generally referred to as the NRC method. The acceptance criteria is contained in Procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Analytics and NIST.

Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a nonconformity report when results are unacceptable.

8-3

8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8-1.

8.4.1 ANALYTICS QA SAMPLES RESULTS Eighteen QA blind spike samples were analyzed as part of Analytics 2005 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: I-131

Air Particulate Filter: Mixed Gamma Emitters, Gross Beta

Water: I-131, Mixed Gamma Emitters, Tritium, Gross Beta

Soil: Mixed Gamma Emitters

Milk: I-131, Mixed Gamma Emitters

Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 79 individual analyses on the eighteen QA samples. Of the 79 analyses performed, 79 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2005 program.

8.4.2 NIST QA SAMPLES RESULTS In 2005, JAF Environmental Laboratory participated in the NEI/NIST Measurement Assurance Program. Two QA blind spike samples were analyzed. The following sample media were evaluated as part of the comparison program.

Air Particulate Filter: Mixed Gamma Emit ters

Water: Mixed Gamma Emitters The JAF Environmental Laboratory performed 10 individual analyses on the two QA samples. Of the 10 analyses performed, 10 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2005 program.

8.4.3 NUMERICAL RESULTS TABLES 8-4

TABLE 8 -1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCi/filter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 6/9/05 E-4583-05 AIR 142.4 +/- 1.8 pCi/filter GROSS 146.6 +/- 1.8 138.0 +/- 2.3 1.05 A BETA 145.2 +/- 1.8 Mean = 144.7 +/- 1.0 12/8/05 E-4824-05 AIR 202.8 +/- 3.0 pCi/filter GROSS 204.7 +/- 3.0 186.0 +/- 3.1 1.10 A BETA 206.5 +/- 3.0 Mean = 204.7 +/- 1.7 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-5

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Tritium Analysis Water (pCi/liter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 3/17/05 E-4487-05 WATER 6073 +/- 176 pCi/liter 5887 +/- 175 H-3 6040 +/- 200 0.99 A 5925 +/- 175 Mean = 5962 +/- 101 (1) Results reported as activity +/-1 sigma. Sample analyzed by JAF Environmental Laboratory (2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-6

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Iodine Analysis of Water, Air and Milk JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 3/17/05 E-4488-05 WATER 59.4 +/- 1.8 pCi/liter 63.3 +/- 2.4 I-131** 65.9 +/- 1.1 0.95 A 64.6 +/- 1.8 Mean = 62.4 +/- 1.1 6/9/05 E-4586-05 AIR 102.0 +/- 5.6 pCi/cc 98.7 +/- 4.8 I-131 92.5 +/- 1.5 1.04 A 88.1 +/- 4.4 Mean = 96.3 +/- 2.9 6/9/05 E-4584-05 MILK 80.4 +/- 2.2 pCi/liter 81.9 +/- 2.4 I-131** 86.9 +/- 1.5 0.93 A 81.3 +/- 2.7 Mean = 81.2 +/- 1.4 9/15/05 E-4716-05 AIR 65.2 +/- 4.0 pCi/cc 58.6 +/- 4.7 I-131 63.4 +/- 1.1 1.00 A 66.7 +/- 3.6 Mean = 63.5 +/- 2.4 9/15/05 E-4713-05 WATER 77.0 +/- 1.6 pCi/liter 78.0 +/- 2.0 I-131** 78.2 +/- 1.3 0.98 A 75.6 +/- 2.1 Mean = 76.9 +/- 1.1 9/15/05 E-4715-05 MILK 86.4 +/- 1.7 pCi/liter 90.6 +/- 1.9 I-131** 94.3 +/- 1.6 0.92 A 84.6 +/- 1.8 Mean = 87.2 +/- 1.0 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(**) Result determined by Resin Extraction/Gamma Spectral Analysis.

(A) Evaluation Results, Acceptable.

8-7

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (pCi/liter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 3/17/05 E-4488-05 WATER 222.0 +/- 11.4 pCi/liter 248.0 +/- 11.8 Ce-141 221 +/- 3.7 1.06 A 236.0 +/- 9.4 Mean = 235.3 +/- 6.3 278.0 +/- 53.9 295.0 +/- 48.7 Cr-51 322 +/- 5.4 0.86 A 262.0 +/- 38.5 Mean = 278.3 +/- 27.4 128.0 +/- 9.6 113.0 +/- 14.6 Cs-134 134 +/- 2.2 0.94 A 138.0 +/- 6.8 Mean = 126.3 +/- 6.2 112.0 +/- 8.0 121.0 +/- 7.9 Cs-137 125 +/- 2.1 0.97 A 130.0 +/- 6.3 Mean = 121.0 +/- 4.3 157.0 +/- 9.2 162.0 +/- 9.0 Mn-54 154 +/- 2.6 1.05 A 164.0 +/- 7.0 Mean = 161.0 +/- 4.9 106.0 +/- 10.0 114.0 +/- 9.6 Fe-59 107 +/- 1.8 1.07 A 122.0 +/- 7.1 Mean = 114.0 +/- 5.2 184.0 +/- 16.4 203.0 +/- 16.4 Zn-65 191 +/- 3.2 0.99 A 179.0 +/- 11.5 Mean = 188.7 +/- 8.6 136.0 +/- 6.6 131.0 +/- 6.3 Co-60 139 +/- 2.3 0.99 A 144.0 +/- 4.9 Mean = 137.0 +/- 3.5 117.0 +/- 8.2 120.0 +/- 8.0 Co-58 111 +/- 1.9 1.05 A 112.0 +/- 5.8 Mean = 116.3 +/- 4.3 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-8

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (pCi/liter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 9/15/05 E-4713 WATER 292.0 +/- 4.4 pCi/liter 284.0 +/- 9.0 Ce-141 282 +/- 4.7 1.03 A 296.0 +/- 4.1 Mean = 290.7 +/- 3.6 395.0 +/- 18.2 411.0 +/- 38.1 Cr-51 408 +/- 6.8 0.98 A 397.0 +/- 16.2 Mean = 401.0 +/- 15.1 152.0 +/- 3.3 152.0 +/- 6.3 Cs-134 148 +/- 2.5 1.03 A 153.0 +/- 2.9 Mean = 152.3 +/- 2.6 234.0 +/- 3.7 235.0 +/- 7.2 Cs-137 235 +/- 3.9 0.99 A 231.0 +/- 3.5 Mean = 233.3 +/- 2.9 119.0 +/- 2.8 118.0 +/- 5.5 Mn-54 111 +/- 1.9 1.07 A 118.0 +/- 2.7 Mean = 118.3 +/- 2.3 74.7 +/- 3.1 77.0 +/- 6.2 Fe-59 74 +/- 1.2 1.05 A 81.6 +/- 3.0 Mean = 77.8 +/- 2.5 158.0 +/- 5.3 160.0 +/- 11.0 Zn-65 149 +/- 2.5 1.08 A 163.0 +/- 5.2 Mean = 160.3 +/- 4.4 201.0 +/- 2.7 202.0 +/- 5.5 Co-60 202 +/- 3.4 0.99 A 198.0 +/- 2.6 Mean = 200.3 +/- 2.2 71.6 +/- 2.5 81.0 +/- 4.6 Co-58 77 +/- 1.3 1.00 A 79.2 +/- 2.5 Mean = 77.3 +/- 1.9 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-9

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 3/17/05 E-4489-05 FILTER 160.0 +/- 6.0 pCi/filter 151.0 +/- 5.4 Ce-141 155 +/- 2.6 1.01 A 160.0 +/- 4.8 Mean = 157.0 +/- 3.1 268.0 +/- 30.8 259.0 +/- 29.6 Cr-51 226 +/- 3.8 1.22 A 302.0 +/- 23.5 Mean = 276.3 +/- 16.3 107.0 +/- 7.0 94.5 +/- 7.1 Cs-134 93.9 +/- 1.6 1.08 A 102.0 +/- 5.4 Mean = 101.2 +/- 3.8 91.1 +/- 5.6 88.2 +/- 5.9 Cs-137 87.6 +/- 1.5 1.05 A 96.5 +/- 4.5 Mean = 91.9 +/- 3.1 115.0 +/- 6.6 116.0 +/- 7.1 Mn-54 108 +/- 1.8 1.10 A 126.0 +/- 5.5 Mean = 119.0 +/- 3.7 79.8 +/- 7.9 89.0 +/- 9.1 Fe-59 75.0 +/- 1.3 1.17 A 94.2 +/- 6.8 Mean = 87.7 +/- 4.6 150.0 +/- 12.5 162.0 +/- 14.1 Zn-65 134 +/- 2.2 1.15 A 151.0 +/- 10.0 Mean = 154.3 +/- 7.1 95.2 +/- 5.0 106.0 +/- 5.6 Co-60 97.1 +/- 1.6 1.02 A 96.6 +/- 4.0 Mean = 99.3 +/- 2.8 73.2 +/- 5.8 82.6 +/- 6.6 Co-58 77.8 +/- 1.3 1.01 A 80.1 +/- 4.9 Mean = 78.6 +/- 3.4 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-10

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 9/15/05 E-4714-05 FILTER 174.0 +/- 4.8 pCi/filter 173.0 +/- 4.8 Ce-141 187.0 +/- 5.8 165 +/- 2.8 1.07 A 170.0 +/- 4.4 Mean = 176.0 +/- 2.5 239.0 +/- 22.1 246.0 +/- 22.3 Cr-51 230.0 +/- 24.5 239 +/- 4.0 0.99 A 232.0 +/- 20.7 Mean = 236.8 +/- 11.2 90.4 +/- 5.2 93.2 +/- 5.2 Cs-134 110.0 +/- 6.6 86.3 +/- 1.4 1.10 A 84.7 +/- 4.9 Mean = 94.6 +/- 2.8 143.0 +/- 5.7 144.0 +/- 5.5 Cs-137 139.0 +/- 6.6 138 +/- 2.3 1.04 A 150.0 +/- 5.3 Mean = 144.0 +/- 2.9 75.0 +/- 4.4 65.4 +/- 4.4 Mn-54 82.9 +/- 5.6 65.0 +/- 1.1 1.19 A 84.9 +/- 4.5 Mean = 77.1 +/- 2.4 50.6 +/- 5.2 45.2 +/- 4.9 Fe-59 53.4 +/- 5.8 43.0 +/- 0.7 1.17 A 51.2 +/- 4.9 Mean = 50.1 +/- 2.6 93.6 +/- 9.3 110.0 +/- 9.0 Zn-65 118.0 +/- 10.8 87.2 +/- 1.5 1.19 A 93.3 +/- 8.5 Mean = 103.7 +/- 4.7 119.0 +/- 4.5 113.0 +/- 4.5 Co-60 133.0 +/- 5.8 118 +/- 2.0 1.01 A 114.0 +/- 4.3 Mean = 119.8 +/- 2.4 47.8 +/- 3.9 44.3 +/- 3.9 Co-58 39.1 +/- 4.5 44.7 +/- 0.8 1.00 A 47.3 +/- 3.8 Mean = 44.6 +/- 2.0 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable 8-11

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Milk (pCi/liter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 6/9/05 E-4584-05 MILK 85.9 +/- 8.64 pCi/liter 112.0 +/- 10.6 Ce-141 92.4 +/- 1.5 1.09 A 105.0 +/- 7.9 Mean = 101.0 +/- 5.3 224.0 +/- 48.4 298.0 +/- 61.1 Cr-51 303 +/- 5.1 0.96 A 350.0 +/- 45.5 Mean = 290.7 +/- 30.1 83.0 +/- 6.9 91.5 +/- 9.8 Cs-134 95 +/- 1.6 0.95 A 97.5 +/- 7.3 Mean = 90.7 +/- 4.7 174.0 +/- 9.8 178.0 +/- 10.9 Cs-137 189 +/- 3.2 0.93 A 175.0 +/- 8.5 Mean = 175.7 +/- 5.7 128.0 +/- 8.5 101.0 +/- 9.8 Mn-54 125 +/- 2.1 0.94 A 124.0 +/- 7.8 Mean = 117.7 +/- 5.0 49.5 +/- 10.1 71.3 +/- 11.9 Fe-59 63.9 +/- 1.1 0.96 A 63.5 +/- 8.3 Mean = 61.4 +/- 5.9 121.0 +/- 16.6 170.0 +/- 20.7 Zn-65 155 +/- 2.6 1.01 A 179.0 +/- 15.6 Mean = 156.7 +/- 10.3 142.0 +/- 7.0 Co-60 128.0 +/- 8.3 145 +/- 2.4 0.92 A 130.0 +/- 6.4 Mean = 133.3 +/- 4.2 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc (A) Evaluation Results, Acceptable 8-12

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Milk (pCi/liter)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 9/15/05 E-4715-05 MILK 232.0 +/- 4.9 pCi/liter 241.0 +/- 8.1 Ce-141 233 +/- 3.9 1.02 A 237.0 +/- 7.6 Mean = 236.7 +/- 4.1 326.0 +/- 21.0 344.0 +/- 35.9 Cr-51 338 +/- 5.7 0.97 A 314.0 +/- 31.4 Mean = 328.0 +/- 17.4 130.0 +/- 3.7 126.0 +/- 5.7 Cs-134 122 +/- 2.0 1.03 A 120.0 +/- 5.6 Mean = 125.3 +/- 2.9 187.0 +/- 4.0 198.0 +/- 7.0 Cs-137 195 +/- 3.2 0.99 A 194.0 +/- 6.3 Mean = 193.0 +/- 3.4 97.2 +/- 3.3 102.0 +/- 5.6 Mn-54 92.0 +/- 1.5 1.09 A 102.0 +/- 5.1 Mean = 100.4 +/- 2.8 65.0 +/- 3.7 49.9 +/- 6.3 Fe-59 61.0 +/- 1.0 1.00 A 68.4 +/- 6.0 Mean = 61.1 +/- 3.1 124.0 +/- 6.3 147.0 +/- 12.3 Zn-65 123 +/- 2.1 1.07 A 121.0 +/- 9.6 Mean = 130.7 +/- 5.6 159.0 +/- 3.2 163.0 +/- 5.3 Co-60 167 +/- 2.8 0.98 A 169.0 +/- 5.0 Mean = 163.7 +/- 2.6 55.2 +/- 2.8 62.6 +/- 5.0 Co-58 63.4 +/- 1.1 0.94 A 61.8 +/- 4.5 Mean = 59.9 +/- 2.4 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-13

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Soil (pCi/gram)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 6/9/05 E-4585-05 SOIL 0.203 +/- 0.022 pCi/gram 0.157 +/- 0.022 Ce-141 0.190 +/- 0.024 0.182 +/- 0.003 0.95 A 0.171 +/- 0.037 Mean = 0.173 +/- 0.017 0.356 +/- 0.101 0.593 +/- 0.122 Cr-51 0.697 +/- 0.135 0.596 +/- 0.010 1.08 A 0.640 +/- 0.198 Mean = 0.643 +/- 0.090 0.160 +/- 0.015 0.204 +/- 0.016 Cs-134 0.193 +/- 0.018 0.187 +/- 0.003 1.03 A 0.182 +/- 0.008 Mean = 0.193 +/- 0.009 0.449 +/- 0.021 0.480 +/- 0.023 Cs-137 0.479 +/- 0.027 0.474 +/- 0.008 1.01 A 0.473 +/- 0.010 Mean = 0.477 +/- 0.012 0.256 +/- 0.018 0.255 +/- 0.018 Mn-54 0.223 +/- 0.021 0.246 +/- 0.004 0.98 A 0.244 +/- 0.009 Mean = 0.241 +/- 0.010 0.109 +/- 0.025 0.104 +/- 0.029 0.132 +/- 0.032 Fe-59 0.126 +/- 0.002 1.01 A 0.131 +/- 0.031 0.157 +/- 0.033 Mean = 0.127 +/- 0.013 0.320 +/- 0.034 0.360 +/- 0.033 Zn-65 0.374 +/- 0.040 0.305 +/- 0.005 1.15 A 0.320 +/- 0.017 Mean = 0.351 +/- 0.018 0.277 +/- 0.014 0.266 +/- 0.015 Co-60 0.279 +/- 00.017 0.285 +/- 0.005 0.96 A 0.274 +/- 0.007 Mean = 0.273 +/- 0.008 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-14

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Vegetation (pCi/gram)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 6/9/05 E-4587-05 VEGETATION 0.179 +/- 0.012 pCi/gram 0.160 +/- 0.012 Ce-141 0.193 +/- 0.012 0.174 +/- 0.003 1.02 A 0.180 +/- 0.015 Mean = 0.178 +/- 0.009 0.600 +/- 0.087 0.464 +/- 0.075 Cr-51 0.470 +/- 0.059 0.569 +/- 0.010 0.95 A 0.638 +/- 0.118 Mean = 0.543 +/- 0.058 0.232 +/- 0.013 0.213 +/- 0.013 Cs-134 0.197 +/- 0.010 0.179 +/- 0.003 1.17 A 0.195 +/- 0.006 Mean = 0.209 +/- 0.007 0.370 +/- 0.015 0.340 +/- 0.015 Cs-137 0.341 +/- 0.012 0.355 +/- 0.006 0.97 A 0.326 +/- 0.007 Mean = 0.344 +/- 0.008 0.243 +/- 0.014 0.227 +/- 0.014 Mn-54 0.238 +/- 0.011 0.235 +/- 0.004 1.00 A 0.235 +/- 0.006 Mean = 0.236 +/- 0.008 0.123 +/- 0.015 0.112 +/- 0.016 Fe-59 0.139 +/- 0.012 0.120 +/- 0.002 1.04 A 0.123 +/- 0.014 Mean = 0.124 +/- 0.009 0.275 +/- 0.023 0.280 +/- 0.029 Zn-65 0.301 +/- 0.019 0.292 +/- 0.005 1.00 A 0.317 +/- 0.013 Mean = 0.293 +/- 0.014 0.273 +/- 0.011 0.252 +/- 0.011 Co-60 0.267 +/- 0.009 0.272 +/- 0.005 0.98 A 0.271 +/- 0.005 Mean = 0.266 +/- 0.006 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/Analytics (See Section 8.3).

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-15

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Water (pCi/ml)

JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 11/11/05 A19773-05 WATER GROSS 1908 +/- 2 pCi/ml BETA 1687 +/- 2 1908 +/- 2 1830 +/- 46 0.98 A 1706 +/- 2 Mean = 1802 +/- 2 (1) Results reported as activity +/-1 sigma.

(2) Results reported as activity +/-1 sigma.

(3) Ratio = Reported/known

(*) Sample provided by Analytics, Inc.

(A) Evaluation Results, Acceptable.

8-16

TABLE 8 -1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of NIST Filter and water samples JAF ENV REFERENCE DATE ID NO. MEDIUM ANALYSIS JAF RESULT (1) LAB* (2) RATIO (3) 8/2005 1801-20 FILTER Ce-141 1.86E5 +/- 791 pCi/filter 1.85E5 +/- 887 1.96E5 +/- 2176 0.96 A 1.96E5 +/- 785 Mean = 1.89E5 +/- 475 Ba-133 5.25E4 +/- 277 5.36E4 +/- 300 5.95E4 +/- 619 0.89 A 5.21E4 +/- 262 Mean = 5.27E4 +/- 162 Cs-134 2.90E4 +/- 230 2.30E4 +/- 226 2.79E4 +/- 254 0.97 A 2.95E4 +/- 224 Mean = 2.72E4 +/- 131 Fe-59 1.99E5 +/- 1140 1.94E5 +/- 1460 1.87E5 +/- 1982 1.06 A 2.03E5 +/- 1110 Mean = 1.99E5 +/- 720 Zn-65 9.59E4 +/- 686 9.30E4 +/- 878 9.02E4 +/- 1344 1.06 A 9.76E4 +/- 664 Mean = 9.55E4 +/- 432 8/2005 1800-10 WATER Ce-141 1.48E5 +/- 752 pCi/g 1.46E5 +/- 686 1.48E5 +/- 1125 0.99 A 1.47E5 +/- 845 Mean = 1.47E5 +/- 441 Ba-133 4.17E4 +/- 193 4.22E4 +/- 188 4.41E4 +/- 291 0.96 A 4.27E4 +/- 237 Mean = 4.22E4 +/- 120 Cs-134 2.69E4 +/- 170 2.69E4 +/- 166 2.62E4 +/- 115 1.03 A 2.74E4 +/- 208 Mean = 2.71E4 +/- 105 Fe-59 1.21E5 +/- 685 1.22E5 +/- 687 1.18E5 +/- 814 1.03 A 1.22E5 +/- 871 Mean = 1.22E5 +/- 435 Zn-65 6.16E4 +/- 426 6.12E4 +/- 423 5.91E4 +/- 745 1.04 A 6.13E4 +/- 535 Mean = 6.14E4 +/- 268 (1) Results reported as activity +/-1 sigma.

(1) Results reported as activity +/-2 sigma (total propagated uncertainty).

(3) Ratio = Reported/NIST (see Section 8.3).

(*) Sample provided by NIST.

(A) Evaluation Results, Acceptable.

8-17

8.5 REFERENCES

8.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

8.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).3 8-18

9.0 GRAPHICAL PRESENTATIONS

1. DATA GRAPHS This section includes graphic representation of selected sample results.

For graphic representation, results reported as MDL or LLD were considered to be at the "zero" level of activity. MDL and LLD results were indicated where possible.

2. SAMPLE LOCATIONS Sample location results specified as "indicator" and "control" on the graphs can be referenced back to Section 3.3 for specific locations.

9-1

James A. FitzPatrick N.P.P.

Fish Cs-137 Figure 9.1 0.06 INDICATOR CONTROL 0.05 INDICATOR <LLD VALUE CONTROL <LLD VALUE 0.04 pCi/gram (wet) 0.03 0.02 0.01 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-2

James A. FitzPatrick N.P.P.

Surface Water - Tritium Figure 9.2 600 INDICATOR CONTROL 500 INDICATOR <LLD VALUE CONTROL <LLD VALUE 400 pCi/l 300 200 100 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-3

James A. FitzPatrick N.P.P.

Air Particulate Filter - Gross Beta Figure 9.3 0.045 INDICATOR 0.04 CONTROL 0.035 0.03 0.025 pCi/m 3 0.02 0.015 0.01 0.005 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-4

James A. FitzPatrick N.P.P.

Air Particulate Filter - Gross Beta Figure 9.4 0.035 INDICATOR (R1, R2, R3, R4)

CONTROL (R5) 0.030 0.025 pCi/m 3 0.020 0.015 0.010 0.005 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Week No.

9-5

James A. FitzPatrick N.P.P.

Air Particulate Filter - Gross Beta Figure 9.5 0.035 INDICATOR (R1, R2, R3, R4)

CONTROL (R5) 0.030 0.025 pCi/m3 0.020 0.015 0.010 0.005 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 Week No.

9-6

James A. FitzPatrick N.P.P.

Air Particulate Filter Composite Co-60 Figure 9.6 0.006 INDICATOR CONTROL 0.005 INDICATOR <LLD VALUE CONTROL <LLD VALUE 0.004 pCi/m3 0.003 0.002 0.001 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-7

James A. FitzPatrick N.P.P.

Air Particulate Filter Composite Cs-137 Figure 9.7 0.02 INDICATOR 0.019 CONTROL 0.018 INDICATOR <LLD VALUE CONTROL <LLD VALUE 0.017 Chernobyl Accident 0.016 pCi/m3 0.015 0.014 0.013 0.012 0.011 0.01 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-8

James A. FitzPatrick N.P.P.

Air Charcoal I-131 Figure 9.8 0.16 INDICATOR 0.14 CONTROL INDICATOR <LLD VALUE 0.12 CONTROL <LLD VALUE Chernobyl Accident 0.1 pCi/m3 0.08 0.06 0.04 0.02 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-9

James A. FitzPatrick N.P.P.

Milk Cs-137 Figure 9.9 12 Chernobyl Accident INDICATOR CONTROL 10 INDICATOR <LLD VALUE CONTROL <LLD VALUE 8

pCi/l 6 4

2 0

1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-10

James A. FitzPatrick N.P.P.

Milk I-131 Figure 9.10 16 INDICATOR 14 Chernobyl Accident CONTROL INDICATOR <LLD VALUE CONTROL <LLD VALUE 12 10 pCi/l 8 6

4 2

0 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-11

James A. FitzPatrick N.P.P.

TLD Data Figure 9.11 7

Control Site Boundary 6

Offsite Specials mRem/Standard Month 5

4 3

2 1

0 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 9-12

JAFP-06-0078, Annual Radiological Environmental Operating Report

Contents

Text

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

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JAFP-06-0078, Annual Radiological Environmental Operating Report

Text

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

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