Text

2008 Annual Radiological Environmental Operating Report
	ML091390825
Person / Time
Site:	Nine Mile Point
Issue date:	05/15/2009
From:	Syrell T; Constellation Energy Group, Nine Mile Point
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML091390825 (183)
	v • d • e

P.O. Box 63 Lycoming, NY 13093 0 Constellation Nine Mile Point Nuclear StationEnergy° May 15, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit Nos. 1 & 2; Docket Nos. 50-220 & 50-410 2008 Annual Radiological Environmental Operating Report In accordance with the Technical Specifications for Nine Mile Point Nuclear Station, Units 1 and 2, enclosed is the 2008 Annual Radiological Environmental Operating Report for the period January 1, 2008 through December 31, 2008.

This submittal does not contain any new regulatory commitments.

Should you have questions regarding the information in this submittal, please contact me at (315) 349-5219.

'Very truly yours, Licensing Director TFS/KES

Enclosure:

Nine Mile Point Nuclear Station, 2008 Annual Radiological Environmental Operating Report cc: S. J. Collins, NRC Region I Administrator R.V. Guzman, NRC Project Manager J. T. Furia, NRC Senior NRC Resident Inspector

-J

ENCLOSURE NINE MILE POINT NUCLEAR STATION 2008 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Nine Mile Point Nuclear Station, LLC May 15, 2009

Constellation Energy Nine Mile Point Nuclear Station NINE MILE POINT NUCLEAR STATION, LLC 2008 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC 2008 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2008 - December 31, 2008 For NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket No. 50-220 And NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket No. 50-410

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 3-13 3.2 Analyses Performed 3-18 3.3 Sample Locations 3-19 3.4 Land Use Census 3-30 3.5 Changes to the REMP Program 3-30 3.6 Deviation and Exceptions to the Program 3-31 3.7 Statistical Methodology 3-32 3.8 Compliance with Required Lower Limits of Detection (LLD) 3-35 3.9 Regulatory Dose Limits 3-37 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 5-34 5.4 References 5-36 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 8.1 Program Description 8-1 8.2 Program Schedule 8-2 8.3 Acceptance Criteria 8-2 8.4 Program Results Summary 8-4 8.5 References 8-4 ii

LIST OF TABLES Page Table 3.0-1 Required Sample Collection and Analysis, Nine Mile Point Unit 1 3-2 Table 3.0-2 Required Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 Environmental Sample Locations 3-20 Table 3.8-1 Required Detection Capabilities for Environmental Sample Analysis, 3-36 Lower Limit of Detection (LLD)

Table 4.0-1 Radiological Environmental Monitoring Program Annual Summary, 4-2 January - December 2008 Table 6-I Concentrations of Gamma Emitters in Shoreline Sediment Samples 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples 6-6 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples 6-7 Table 6-5 Concentration of Tritium, Strontium, and Gamma Emitters in 6-12 Groundwater Samples Table 6-6 Environmental Airborne Particulate Samples - Offsite, Sample 6-13 Locations, Gross Beta Activity Table 6-7 Environmental Airborne Particulate Samples - Onsite Sample 6-15 Locations, Gross Beta Activity Table 6-8 Environmental Charcoal Cartridge Samples - Offsite Sample 6-17 Locations, 1-131 Activity Table 6-9 Environmental Charcoal Cartridge Samples - Onsite Sample 6-19 Locations, 1-131 Activity Table 6-10 Concentrations of Gamma Emitters in Quarterly Composites - 6-21 Offsite Sample Locations Table 6-11 Concentrations of Gamma Emitters in Quarterly Composites - 6-23 OnsiteSample Locations Table 6-12 Direct Radiation Measurement Results 6-25 iii

LIST OF TABLES (continued)

Page Table 6-13 Concentrations of Iodine-131 and Gamma Emitters in Milk 6-29 Table 6-14 Concentrations of Gamma Emitters in Food Products 6-32 Table 6-15 Milk Animal Census 6-33 Table 6-16 Residence Census 6-34 Table 7-1 Historical Environmental Sample Data, Shoreline Sediment (Control) 7-1 Table 7-2 Historical Environmental Sample Data, Shoreline Sediment (Indicator) 7-2 Table 7-3 Historical Environmental Sample Data, Fish (Control) 7-3 Table 7-4 Historical Environmental Sample Data, Fish (Indicator) 7-4 Table 7-5 Historical Environmental Sample Data, Surface Water (Control) 7-5 Table 7-6 Historical Environmental Sample Data, Surface Water (Indicator) 7-6 Table 7-7 Historical Environmental Sample Data, Surface Water Tritium (Control) 7-7 Table 7-8 Historical Environmental Sample Data, Surface Water Tritium (Indicator) 7-8 Table 7-9 Historical Environmental Sample Data, Groundwater Tritium (Control) 7-9 Table 7-10 Historical Environmental Sample Data, Groundwater Tritium (Indicator) 7-10 Table 7-11 Historical Environmental Sample Data, Air Particulate Gross Beta (Control) 7-11 Table 7-12 Historical Environmental Sample Data, Air Particulate Gross Beta (Indicator) 7-12 Table 7-13 Historical Environmental Sample Data, Air Particulates (Control) 7-13 Table 7-14 Historical Environmental Sample Data, Air Particulates (Indicator) 7-14 Table 7-15 Historical Environmental Sample Data, Air Radioiodine (Control) 7-15 Table 7-16 Historical Environmental Sample Data, Air Radioiodine (Indicator) 7-16 Table 7-17 Historical Environmental Sample Data, Environmental TLD (Control) 7-17 Table 7-18 Historical Environmental Sample Data, Environmental TLD (Site Boundary) 7-18 iv

LIST OF TABLES (continued)

Page Table 7-19 Historical Environmental Sample Data, Environmental TLD (Offsite Sectors) 7-19 Table 7-20 Historical Environmental Sample Data, Environmental TLD (Special Interest) 7-20 Table 7-21 Historical Environmental Sample Data, Environmental TLD 7-21 (Onsite Indicator)

Table 7-22 Historical Environmental Sample Data, Environmental TLD 7-22 (Offsite Indicator)

Table 7-23 Historical Environmental Sample Data, Milk (Control) 7-23 Table 7-24 Historical Environmental Sample Data, Milk (Indicator) 7-24 Table 7-25 Historical Environmental Sample Data, Food Products (Control) 7-25 Table 7-26 Historical Environmental Sample Data, Food Products (Indicator) 7-26 Table 8.3-1 Error Resolution/Ratio of Agreement 8-3 Table 8.4-1 Interlaboratory Intercomparison Program 8-5 v

LIST OF FIGURES Page Figure 3.3-1 New York State Map 3-24 Figure 3.3-2 Off-site Environmental Station and TLD Locations 3-25 Figure 3.3-3 Onsite Environmental Station and TLD Locations 3-26 Figure 3.3-4 Milk and Surface Water Sample Locations 3-27 Figure 3.3-5 Nearest Residence, Food Product, Fish and Shoreline Sediment 3-28 Sample Locations Figure 3.3-6 NMPNS On-site Groundwater Monitoring Wells and Unit 2 Storm 3-29 Drain Outfall vi

SECTION 1.0 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

The Annual Radiological Environmental Operating Report is published pursuant to Section 6.6.2 of the Nine Mile Point Unit 1 (NMPI) Technical Specifications, Section 5.6.2 of the Nine Mile Point Unit 2 (NMP2) Technical Specifications and 10 CFR 50.4.

This report describes the Radiological Environmental Monitoring Program (REMP), the implementation, and the results obtained as required by Technical Specifications (TS) and the Offsite Dose Calculation Manuals (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 Laboratory's performance in the Interlaboratory Comparison Quality Assurance Program (ICQAP) required by the NMP1 and NMP2 ODCM.

The REMP is a comprehensive surveillance program, which is implemented to assess the impact of site operations on the environment and compliance with 10CFR20 and 40CFR190. 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 2008 there were 1895 analyses performed on environmental media collected as part of the REMP. These results demonstrated that there was no significant or measurable radiological impact from the operation of either the NMP1 or NMP2 facilities. The 2008 results for all pathways sampled were consistent with the previous five year historical results and exhibited no adverse trends.

In summary, the analytical results from the 2008 REMP demonstrate that the routine operation of both facilities at the Nine Mile Point Site had no significant or measurable radiological impact on the environment. The results of the REMP continued to demonstrate that the operation of the plants 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 continued to demonstrate that the dose to a member of the public as a result of the operation of NMP1 and NMP2 remained significantly below the federally required dose limits specified in 10CFR20 and 40CFR190.

1-1

SECTION

2.0 INTRODUCTION

Nine Mile PointUnits 1 and 2 are operated by Nine Mile Point Nuclear Station, LLC. This report is submitted in accordance with Appendix A (Technical Specifications) Section 6.6.2 to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit 1 and Appendix A (Technical Specifications) Section 5.6.2 to License NPF-69, Docket No. 50-410 for the Nine Mile Point Nuclear Station Unit 2, for the calendar year 2008.

Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) Radiological Environmental Monitoring Program (REMP) requirements reside within the NMPl Offsite Dose Calculation Manual (ODCM) and NMP2 ODCM, respectively. Throughout this report references will be made to the "ODCM". This refers to both the NMP1 ODCM and NMP2 ODCM.

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 pre-operational environmental site testing' program. This pre-operational data serves as a reference point to compare data obtained during reactor operation. In 1969, NMP1, a 1850 Megawatts - Thermal (MWt) Boiling Water Reactor (BWR) began full power operation. In 1975, the James A.

FitzPatrick Nuclear Power Plant (JAFNPP), a 2536 MWt BWR, currently owned and operated by Entergy, began full power operation. In 1988, the NMP2 reactor, a 3323 MWt BWR located between NMP1 and JAFNPP, began full power operation. In 1995, NMP2 was uprated to 3467 MWt.

In 1985, the individual station Effluent Technical Specifications were standardized to the generic Radiological Effluent Technical Specifications, much of which is common to both NMP1 and JAFNPP, and subsequently NMP2. Subsequent Technical Specification amendments relocated the REMP requirements to the ODCM for all three plants. Data generated by the REMP is shared, but each operating company reviews and publishes their own annual report.

In summary, three BWRs, which together generate approximately 7853 MWt, have operated collectively at the Nine Mile Point Site since 1988. A large database of environmental results for the exposure pathways has been collected and analyzed to determine the effect from reactor operations.

2-1

I 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, Syracuse, New York, is located approximately 36 miles south southeast of the site. The reactors and support buildings occupy a small shoreline portion of the 900 acre site. The land, soil of glacier deposits, rises gently from the lake in all directions. Oswego County is a rural environment, with about 15% of the land devoted to agriculture.

2.3 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 NMPNS site.

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

I I

I 2-2

Section 3.0 PROGRAM DESCRIPTION

3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.3, an extensive sampling and analysis program is conducted every year. The Nine Mile Point Nuclear Station (NMPNS) Radiological Environmental Monitoring Program (REMP) consists of sampling and analysis of various media that include:

" Air

Fish

Food Products

Milk

Shoreline Sediment

Surface Waters

Groundwater In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1 and Table 3.0-2. The NMPNS REMP sampling locations are selected and verified by an annual land use census. The accuracy and precision of the sample analysis program is assured by participation in an Interlaboratory Comparison Quality Assurance Program (ICQAP). In addition to the participation in the ICQAP, 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 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).

3-1

TABLE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples (a) and Locations and/or Sample Frequency (a) Frequency AIRBORNE

a. Radioiodine and Samples from five locations; Continuous sampler operation Radioiodine Canisters -

Particulates with sample collection weekly analyze once/week for Three samples from offsite locations in different sectors or as required by dust loading, 1-131.

of the highest calculated site average D/Q (based on all whichever is more frequent.

site licensed reactors). Particulate Samplers -

Gross beta radioactivity One sample from the vicinity of an established year following filter change (b) round community having:the highest calculated site Composite (by location) average D/Q (based on all site licensed reactors). for gamma isotopic analysis (c)once per 3 One sample from a control location 10-17 miles distant months, (as a minimum).

and in a least prevalent wind direction (d)

b. Direct Radiation (e) 32 stations with two or more dosimeters to be placed as Once per 3 months Gamma dose once per 3 follows: an inner ring of stations in the general area of months.

the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each land based sector. (1) The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools and in 2 or 3 areas to serve as control stations.

At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

3-2 M M M M M M M M M M M M M MM

TABLE 3.0-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples (a) and Locations and/or Sample Frequency (a) Frequency WATERBORNE

a. Surface (f) One sample upstream. Composite sample over 1 Gamma isotopic analysis (c) month period (g once/month. Composite One sample from the site's downstream cooling water for once per 3 months intake. tritium analysis.

b. Sediment from One sample from a downstream area with existing or Twice per year Gamma isotopic analysis (c)

Shoreline potential recreational value.

INGESTION

a. Milk Samples from milk sampling locations in three locations Twice per month, April - Gamma isotopic (c)and within 3.5 miles distance having the highest calculated December (samples will be 1-131 analysis twice per site average D/Q. If there are none, then one sample collected in January - March month when animals are on from milking animals in each of 3 areas 3.5 - 5.0 miles if 1-131 is detected in pasture (April -

distant having the highest calculated site average D/Q November and December of December); once/month at (based on all site licensed reactors). the preceding year). other times (January -

March) if required.

One sample from a milk sampling location at a control location (9-20 miles distant and in a least prevalent wind direction) (d) 3-3

TABLE 3.0-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 1 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples (a) and Locations and/or Sample Frequency (a) Frequency

b. Fish One sample each of two commercially or recreationally Twice per year Gamma isotopic analysis (c) important species in the vicinity of a plant discharge on edible portions twice area (h) per year.

One sample each of the same species from an area at least 5 miles distant from the site (d).

c. Food Products Samples of three different kinds of broad leaf vegetation Once per year during harvest Gamma isotopic (c)analysis (such as vegetables) grown nearest to each of two season of edible portions (Isotopic different off-site locations of highest calculated site to include 1-131 or a average D/Q (based on all licensed site reactors). separate 1-131 analysis may be performed) once One sample of each of the similar broad leaf vegetation during the harvest season.

grown at least 9.3 - 20 miles distant in a least prevalent wind direction.

3-4 M- - m M M M M M M M M M m M

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 and may be substituted. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Highest D/Q locations are based on historical meteorological data for all site licensed 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 the 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 facility.

(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, such as historical control locations 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 by considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.

(f) The "upstream sample" should be taken at a distance beyond significant influence of the discharge. The "downstream sample" should be taken in an area beyond but near the mixing zone, if possible.

(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 obtaining a representative sample.

(h) In the event commercial or recreational important species are not available as a result of three attempts, then other species may be utilized as available.

3-5

TABLE 3.0-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or Sample Frequency Frequency AIRBORNE

a. Direct Radiation 32 routine monitoring stations (b) either with 2 or more Once per 3 months Gamma dose once per 3 dosimeters or with 1 instrument for measuring and months recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the Site Boundary.

An outer ring of stations, one in each land base meteorological sector in the 4 to 5 mile (c)range from the site.

The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools, and in one of two areas to serve as control stations (d) 3-6

- m mm m m m m m m m m m m m M m m m

m M - M M -M M M m M - - m TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or Sample Frequency Frequency

b. Airborne Samples from five locations: Continuous sampler operation Radioiodine Canister Radioiodine and with sample collection 1-131 analysis weekly Particulates Three samples from offsite locations close to the site weekly, or more frequently if boundary (within one mile) in different sectors of the required by dust loading Particulate Sampler highest calculated annual site average ground-level D/Q Gross beta radioactivity (based on all site licensed reactors)(e). analysis > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change M*,

One sample from the vicinity of an established year- Gamma isotopic analysis round community having the highest calculated annual on each sample where site average ground-level D/Q (based on all site licensed gross beta activity is > 10 reactors)(e). times the previous yearly mean of control samples One sample from a control location at least 10 miles and gamma isotopic distant and in a least prevalent wind direction (d). analysis (g)of composite sample (by location) once per 3 months.

WATERBORNE

a. Surface One sample upstream (d)(h) Composite sample over 1- Gamma isotopic analysis (g) month period (i). once per month and tritium One sample from the site's downstream cooling water analysis once per 3 months.

intake (h) 3-7

TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a)

Freauencv and/or Sample Frequency

b. Ground Samples from one or two sources if likely to be Grab sample once per 3 Gamma isotopic (g)and affected 0) months. tritium analysis once per 3 months.

c. Drinking One sample each of one to three of the nearest water Composite sample over a 2- 1-131 analysis on each supplies that could be affected by its discharge .'1 week period') when 1-131 composite when the dose analysis is performed; calculated for the monthly composite otherwise. consumption of the water is greater than 1 mrem per year. () Composite for gross beta and gamma isotopic analyses Wg) monthly. Composite for tritium analysis once per 3 months.

d. Sediment from One sample from a downstream area with existing or Twice per year Gamma isotopic analysis(g)

Shoreline potential recreational value.

3-8

- - M Ml -M M M M M M M M M M M

- -M mm m M mM m m mm m m m TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or Sample Frequency Frequency INGESTION

a. Milk Samples from Milk Sampling Locations in three Twice per month, April - Gamma isotopic (g)and locations within 3.5 miles(e) distance having the highest December (samples will be 1-131 analysis twice/month calculated annual site average D/Q (based on all collected January - March if when animals are on licensed site reactors). If there are none, then 1 sample 1-131 is detected in November pasture (April -

from Milk Sampling Locations in each of three areas 3.5 and December of the December); once per

- 5.0 miles(e) distant having the highest calculated preceding year)(m). month at other times annual site average D/Q (based on all licensed site (January - March if reactors). required).

One sample from a Milk Sample Location at a control location 9 - 20 miles distant and in a least prevalent wind direction (d)

b. Fish One sample each of two commercially or recreationally Twice per year Gamma isotopic analysis (g) important species in the vicinity of a plant discharge on edible portions twice area (n) per year.

One sample of the same species in areas not influenced r (d) by station discharge.

3-9

TABLE 3.0-2 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRED SAMPLE COLLECTION AND ANALYSIS Nine Mile Point Unit 2 Exposure Pathway Sampling and Collection Type of Analysis and Number of Samples and Sample Locations (a) and/or Sample Frequency Frequency

c. Food Products One sample of each principal class of food products At time of harvest (p) Gamma isotopic (g)and from any area that is irrigated by water in which liquid 1-131 analysis of each plant wastes have been discharged (o) sample of edible portions.

Samples of three different kinds of broad leaf vegetation Once per year during the (such as vegetables) grown nearest to each of two harvest season.

different offsite locations of highest calculated annual site average D/Q (based on all licensed site reactors)(e).

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

3-10 M m - m mm mm m m m M m m m M m m M

NOTES FOR TABLE 3.0-2 (a) Specific parameters of distance and direction sector from the centerline of one reactor, and additional descriptions where pertinent, shall be provided for each and every sample location in Table 3.0-2. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable because of such circumstances as hazardous conditions, seasonal unavailability (which includes theft and uncooperative residents), or malfunction of automatic sampling equipment.

(b) 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. Each of the 32 routine monitoring stations shall be equipped with 2 or more dosimeters or with 1 instrument for measuring and recording dose rate continuously. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(c) At this distance, 8 wind rose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

(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) Having the highest calculated annual site average ground-level D/Q based on all site licensed reactors.

(f) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 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.

(g) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(h) 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.

(i) In this program, representative composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(k) Drinking water samples shall be taken only when drinking water is a dose pathway.

3-11

I U

(1) Analysis for 1-131 may be accomplished by Ge-Li analysis provided that the lower limit of detection (LLD) for 1-131 in water samples found on Table 3.8-1 can be met. Doses shall be calculated for the maximum organ and age group.

(m) Samples will be collected January through March if 1-131 is detected in November and December of the proceeding year.

(n) In the event two commercially or recreationally important species are not available after three attempts of collection, then two samples of one species or other species not necessarily commercially or recreationally important may be utilized.

(o) Applicable only to major irrigation projects within 9 miles of the site in the general down current I direction.

(p) If harvest occurs more than once/year, sampling shall be performed during each discrete harvest.

If harvest occurs continuously, sampling shall be taken monthly. Attention shall be paid to including samples of tuberous and root food products.

3 I

I I

I 3-12 I I

3.1 SAMPLE COLLECTION METHODOLOGY 3.1.1 SHORELINE SEDIMENTS 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 offshore from the site. One set of control samples are collected at an off-site sample transect located offshore, 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 the edible portion only.

Selected fish samples are frozen 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 JAFNPP and the NRG Oswego Generating 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 approximately7.6 miles west of the site. This "upstream" location is considered a control location 3 -13

I I

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.

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 thisý location are obtained weekly and are composited to form a monthly composite sample.

The monthly samples are analyzed for gamma emitting radionuclides.

I 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 (NMP1) and Nine Mile Point Unit 2 (NMP2) facility inlet canal samples and from the City of Oswego drinking water supply. These 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 3 three locations are analyzed for gamma emitting nuclides, and quarterly composite samples are analyzed for tritium.

Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMP2 ODCM,

was not required during 2008. There was no groundwater source in 2008 that was tapped for il drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties were suitable for contamination; therefore, drinking water was not a dose pathway during 2008.

Surface water sample locations are shown in Section 3.3 on Figure 3.3-4.

3.1.4 GROUNDWATER MONITORING PROGRAM "*

The Nuclear Energy Institute (NEI) Groundwater Protection Initiative (GPI) - Final Guidance i Document, August 2007, was established to determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids' Under

-the GPI, groundwater monitoring is accomplished through sampling of the water table around the plant and analyzing for tritium. NMPNS started monitoring groundwater wells in October 2005 and has been monitoring the plant dewatering systems' as part of the Generic Letter 80-10 for 3 "several years. Samples collected from these locations are analyzed for tritium, gamma emitters,

'and strontium:

3-14

'-' .' *,. "*T'* *i* '¸)"{

During the operating year 2008, there were no unplanned releases or spills of radioactive liquids on the NMPNS site.

Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2008. There were no groundwater sources in 2008 that were tapped for drinking or irrigation purposes in areas where the. hydraulic gradient or recharge properties were suitable for contamination; therefore, drinking water was not a dose pathway during 2008.

Groundwater samples are analyzed using liquid scintillation detection and gamma isotopic analysis.

Groundwater sample locations are shown in Section 3.3, Figure 3.3-6.

3.1.5 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 NMP2 Reactor Building. The ODCM also requires that a fourth air sampling station be located in the vicinity of a year round community. This station is located in the SE sector at a 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 16.4 miles from the site in the NE meteorological sector.

In addition to the five ODCM required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary and are designated as Onsite Stations D1, G, H, I, J, and K. These locations are within the site boundary of the NMIPNS and JAFNPP.

One air sampling station is located Offsite in the SW sector in the vicinity of the City of Oswego and is designated as Offsite Station G. Three remaining air sampling stations are located in the ESE, SSE, and SSW sectors and range in distance from 7.2 to 9.0 miles. These are designated as Offsite Stations D2, E and F, respectively.

Each station collects airborne particulates using glass fiber filters (47 millimeter diameter) and radioiodine using charcoal sample cartridges (2 x 1 inches). 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 quarterly by location and analyzed for gamma emitting radionuclides.

3-15

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

3.1.6 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 NP Environmental Laboratory. The laboratory utilizes a Panasonic based system using UD-814 dosimeters which are constructed of rectangular teflon wafers impregnated with 25% CaSO 4:Dy phosphor. Each dosimeter contains three calcium sulfate elements and one lithium borate element.

Environmental TLDs are placed in five different geographical regions around the 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 Category Description I Onsite TLDs placed at various locations within the Site Boundary and are not required by the ODCM, with the exception of TLD # 7, 18 and

23. (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 the ODCM. (TLD locations comprising I

this group are: 7*, 18*, 23*, 75*, 76*, 77*, 78*, 79*, 80*, 81*,

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

Offsite An outer ring of TLDs placed 4 to 5 miles from the site in each of i the eight 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*)

3 3-16

TLD Geographical Category Description 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 ODCM Although the ODCM require a total of 32 TLD stations; environmental TLDs arealso placed at additional locations not required by the ODCM, within the Onsite, Special Interest and Control TLD categories to supplement the ODCM required direct radiation data.

Two dosimeters are placed at each TLD monitoring location. The TLDs are sealed in polyethylene packages to ensure dosimeter integrity, 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.

3.1.7 MILK Milk samples are routinely collected from three farms during the sampling year. These farms include two indicator locations and one control location. Samples are normally collected April through December of the sample year. If plant related radionuclides are detected during 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 next sampling year.

Milk samples were not collected in January through March of 2008 as there were no positive detections of plant related radionuclides in samples collected during November and December 2007.

3-17

I I

The ODCM also requires that a sample be collected from a control location nine to twenty miles from the site and in a least 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 collected from each indicator and control location during the first half and second half of each month. 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.

3.1.8 FOOD PRODUCTS (VEGETATION) i Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broadleaf vegetation, edible or inedible, is collected from two different indicator garden locations. Sample locations are selected from 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 least 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 The following environmental sample analyses are performed by the JAFNPP Environmental Laboratory:

" Air Particulate Filter - Gross Beta

Air Particulate Filter Composites - Gamma Spectral Analysis

" Airborne Radioiodine - Gamma Spectral Analysis

Fish - Gamma Spectral Analysis

Food Products (Vegetation) - Gamma Spectral Analysis i

Milk - Gamma Spectral Analysis and 1-131

Shoreline Sediment- Gamma Spectral Analysis

Special Samples (soil, food products, bottom sediment, etc.) - Gamma Spectral Analysis 3-18 i

Surface Water Monthly Composites - Gamma Spectral Analysis, 1-131

" Surface Water Quarterly Composites - Tritium The analysis of Direct Radiation using Thermoluminescent (TLD's) and strontium analysis are performed by a contractor laboratory - Areva NP Environmental Laboratory.

3.3 SAMPLE LOCATIONS Figures 3.3-1 through 3.3-6 provide 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 location reference table (Table 3.3-1). This table contains the following information:

Sample medium

" Map 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).

" Figure number

" Location description

Degrees and distance of the sample location from the site.

3.3.1 LIST OF FIGURES

Figure 3.3-1 -New York State

Figure 3.3 Off-Site Environmental Station and TLD Locations

" Figure 3.3 On-Site Environmental Station and TLD Locations

" Figure 3.3 Milk and Surface Water Sample Locations

Figure 3.3 Nearest Residence, Food Product, Fish and Shoreline Sediment Sample Locations

Figure 3.3 NMPNS On-site Groundwater Monitoring Wells and Unit 2 Storm Drain Outfall 3-19

TABLE 3.3-1 2008 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE NUMBER LOCATION DESCRIPTION DEGREES&

MEDIUMDESIGNATION MEDIUM DESIGNATIDISTANCE (1 & 2)

Shoreline Sediment 5* Figure 3.3-5 Sunset Bay 840 at 1.2 miles 6 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 620 at 0.8 miles 00* Figure 3.3-5 Oswego Transect - Control 2370 at 5.9 miles Surface Water 03* Figure 3.3-4 FitzPatrick Inlet 710 at 0.5 miles 08* Figure 3.3-4 Oswego Steam Station Inlet - Control 2360 at 7.6 miles 09 Figure 3.3-4 NMP Unit 1 Inlet 3190 at 0.3 miles 10 Figure 3.3-4 Oswego City Water 2400 at 7.8 miles 11 Figure 3.3-4 NMP Unit 2 Inlet 3360 at 0.3 miles 3530 at 0.3 miles Air Radioiodine and R-l* Figure 3.3-2 R-1 Station, Nine Mile Point Road 920 at 1.8 miles Particulates R-2* Figure 3.3-3 R-2 Station, Lake Road 1060 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 1450 at 1.8 miles R-5* Figure 3.3-2 R-5 Station, Montario Point - Control 420 at 16.2 miles Dl Figure 3.3-3 DI On-Site Station 730 at 0.3 miles G Figure 3.3-3 G On-Site Station 244' at 0.7 miles H Figure 3.3-3 H On-Site Station 74' at 0.8 miles I Figure 3.3-3 I On-Site Station 960 at 0.8 miles J Figure 3.3-3 J On-Site Station 1100 at 0.9 miles K Figure 3.3-3 K On-Site Station 1330 at 0.5 miles G Figure 3.3-2 G Off-Site Station, Saint Paul Street 2260 at 5.4 miles D2 Figure 3.3-2 D2 Off-Site Station, Rt. 64 1180 at 9.0 miles E Figure 3.3-2 E Off-Site Station, Rt. 4 1620 at 7.1 miles F Figure 3.3-2 F Off-site Station, Dutch Ridge Road 1920 at 7.6 miles 3 - 20 M M--- M M M --M M M M M ý M

- - - m m m m m - -- nm m-m -- m-m TABLE 3.3-1 (Continued) 2008 ENVIRONMENTAL SAMPLE LOCATIONS SA E" DS AP N F UDEGREES &

SI NUMBER L IN DESCRIPTIONDISTANCE( 2 Thermoluminescent 3 Figure 3.3-3 DI On-Site Station 730 at 0.3 miles Dosimeters (TLD) 4 Figure 3.3-3 D2 On-Site Station 143' at 0.4 miles 5 Figure 3.3-3 E On-Site Station 1500 at 0.4 miles 6 Figure 3.3-3 F On-Site Station 213' at 0.5 miles 7* Figure 3.3-3 G On-Site Station 2440 at 0.7 miles 8 Figure 3.3-2 R-5 Off-Site Station 420 at 16.2 miles 9 Figure 3.3-2 State Route 3 800 at 11.4 miles 10 Figure 3.3-2 D2 Off-Site Station 1180 at 9.0 miles 11 Figure 3.3-2 E Off-Site Station 1620 at 7.1 miles 12 Figure 3.3-2 F Off-Site Station 1920 at 7.7 miles 13 Figure 3.3-2 G Off-Site Station 2260 at 5.4 miles 14* Figure 3.3-2 Southwest Oswego - Control 2270 at 12.5 miles 15* Figure 3.3-2 West Site Boundary 2390 at 0.9 miles 18* Figure 3.3-3 Energy Information Center 2660 at 0.5 miles 19 Figure 3.3-2 East Site Boundary 830 at 1.4 miles 23* Figure 3.3-3 H On-Site Station 740 at 0.8 miles 24 Figure 3.3-3 I On-Site Station 960 at 0.8 miles 25 Figure 3.3-3 J On-Site Station 1100 at 0.9 miles 26 Figure 3.3-3 K On-Site Station 1330 at 0.5 miles 27 Figure 3.3-3 North Fence, JAFNPP 600 at 0.4 miles 28 Figure 3.3-3 North Fence, JAFNPP 680 at 0.5 miles 29 Figure 3.3-3 North Fence JAFNPP 650 at 0.5 miles 30 Figure 3.3-3 North Fence JAFNPP 570 at 0.4 miles 31 Figure 3.3-3 North Fence NMP-1 2780 at 0.2 miles 39 Figure 3.3-3 North Fence NMP-1 2960 at 0.2 miles 47 Figure 3.3-3 North Fence JAFNPP 690 at 0.6 miles 49* Figure 3.3-2 Phoenix, NY- Control 168' at 19.7 miles 51 Figure 3.3-2 Oswego Steam Station, East 2340 at 7.3 miles 52 Figure 3.3-2 Fitzhugh Park Elementary School, East 227' at 5.9 miles 53 Figure 3.3-2 Fulton High School 1830 at 13.7 miles 54 Figure 3.3-2 Mexico High School 1150 at 9.4 miles 55 Figure 3.3-2 Pulaski Gas Substation, Rt. 5 750 at 13.0 miles 3-21

TABLE 3.3-1 (Continued) 2008 ENVIRONMENTAL SAMPLE LOCATIONS

FIGUR NUMBER LOCATION DESCRIPTION.-ER S&

SAWLE SAMPI*E" MAP ~DEGREES1 &1 MEDIUM DESIGNATION .. L A DISTANCE1& 2(I Thermoluminescent 56* Figure 3.3-2 New Haven Elementary School 1240 at 5.2 miles Dosimeters (TLD) 58* Figure 3.3-2 County Route 1A and Alcan 222' at 3.0 miles (Continued) 75* Figure 3.3-3 North Fence, NMP-2 3540 at 0.1 miles 76* Figure 3.3-3 North Fence, NMP-2 270 at 0.1 miles 77* Figure 3.3-3 North Fence, NMP-2 370 at 0.2 miles 78* Figure 3.3-3 East Boundary, JAFNPP 860 at 1.0 miles 79* Figure 3.3-3 County Route 29 1210 at 1.2 miles 80* Figure 3.3-3 County Route 29 1360 at 1.5 miles 81* Figure 3.3-3 Miner Road 1600 at 1.7 miles 82* Figure 3.3-3 Miner Road 1800 at 1.6 miles 83* Figure 3.3-3 Lakeview Road 2030 at 1.2 miles 84* Figure 3.3-2 Lakeview Road 2250 at 1.1 miles 85* Figure 3.3-3 North Fence, NMP-1 290' at 0.2 miles 86* Figure 3.3-3 North Fence, NMP-1 3100 at 0.1 miles 87* Figure 3.3-3 North Fence, NMP-2 3320 at 0.1 miles 88* Figure 3.3-2 Hickory Grove Road 970 at 4.5 miles 89* Figure 3.3-2 Leavitt Road 112' at 4.3 miles 90* Figure 3.3-2 Route 104 and Keefe Road 1350 at 4.2 miles 91* Figure 3.3-2 County Route 51A 1570 at 4.9 miles 92* Figure 3.3-2 Maiden Lane Road 183' at 4.5 miles 93* Figure 3.3-2 County Route 53 2060 at 4.4 miles 94* Figure 3.3-2 Country Route I and Kocher Road 224' at 4.4 miles 95* Figure 3.3-2 Lakeshore Camp Site 2390 at 3.7 miles 96* Figure 3.3-2 Creamery Road 1990 at 3.7 miles 97* Figure 3.3 -3 County Route 29 1450 at 1.8 miles 98* Figure 3.3-2 Lake Road 1030 at 1.2 miles 99 Figure 3.3-2 Nine Mile Point Road 920 at 1.8 miles 100 Figure 3.3-3 Country Route 29 and Lake Road 1060 at 1.1 miles 101 Figure 3.3-3 County Route 29 1340 at 1.4 miles 102 Figure 3.3-2 Oswego County Airport 1750 at 11.9 miles 103 Figure 3.3-3 Energy Center, East 2680 at 0.4 miles 104 Figure 3.3-2 Parkhurst Road 1020 at 1.4 miles 3 - 22 M- M M M iM M M M- M M MM

m-m--m m - m m - m m m m m - m -

TABLE 3.3-1 (Continued) 2008 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE.NUMBER LOCATION DESCRIPTION DEGREES &

MEDIUM DESIGNATION DISTANCE(1 & 2)

Thermoluminescent 105 Figure 3.3-3 Lakeview Road 1990 at 1.4 miles Dosimeters (TLD) 106 Figure 3.3-3 Shoreline Cove, West of NMP-1 2720 at 0.3 miles (Continued) 107 Figure 3.3-3 Shoreline Cove, West of NMP-1 271' at 0.3 miles 108 Figure 3.3-3 Lake Road 105' at 1.1 miles 109 Figure 3.3-3 Lake Road 1040 at 1.1 miles 11 Figure 3.3-2 Sterling, NY- Control 2140 at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 1750 at 11.9 miles 113 Figure 3.3-2 Baldwinsville, NY - Control 1780 at 24.7 miles Cows Milk 76 Figure 3.3-4 Indicator Location 1200 at 6.3 miles 55 Figure 3.3-4 Indicator Location 970 at 8.8 miles 4 Figure 3.3-4 Indicator Location 1150 at 7.6 miles 77* Figure 3.3-4 Control Location 1900 at 16.0 miles Food Products 133* Figure 3.3-5 Indicator Location 840 at 1.6 miles 134* Figure 3.3-5 Indicator Location 84' at 1.5 miles 142 Figure 3.3-5 Indicator Location 1450 at 1.7 miles 144* Figure 3.3-5 Indicator Location 1390 at 1.6 miles 145* Figure 3.3-5 Control Location 2220 at 15.4 miles 484 Figure 3.3-5 Indicator Location 1320 at 1.4 miles Groundwater MW 1-5 Figure 3.3-6 Down Gradient Wells - Indicator 42 0 to 51 0 at 0.1 miles GMXMW-1 Figure 3.3-6 Upland Well - Control 160 o at 0.3 miles GMXMW-2 Figure 3.3-6 Upland Well - Control 198 0 at 0.3 miles Outfall 001 Figure 3.3-6 NMP2 Dewatering System - Indicator 320 at 0.2 miles Table Notes:

(1) Degrees and distance based on Nine Mile Point Unit 2 Reactor Centerline (2) Degrees and Distances updated by Global Positioning System (GPS)

Sample location required by ODCM 3 - 23

FIGURE 3.3-1 NEW YORK STATE MAP CANADA VERMONT A

NEV YORK f/f

ýý-'SRCCHESTER RACUSE S(ncrKA f

'BUFFALO ALBA"Y*

PENWIYLVANI CONNECT1CUT NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit - 2 NEWJERSEY James A. FitzPatrick Nuclear Power Plant NEW YORK CITY 3-24 M M M M ý M m m mM M m m M ý -M M M M

FIGURE 3.3 - 2 OFF-SITE ENVIRONMENTAL STATION AND TLD LOCATIONS 3-25

m m m m m m m m- m m m m m m m m m m MAP OF OSWEGO COUNTY New York oImM w UIamS FIGURE 3.3-4 MILK AND SURFACE WATER SAMPLE LOCATIONS KEY:

MILK SAMPLE LOCATION SURFACE WATER LOCATION 3-27

I ENE3 El

~I!

ESE

ýl SE I3 s.

I, to nv, NI' 3-28

FIGURE 3.3-6 LAKE ONARIO NMPNS ON-SITE GROUNDWATER MW-5 MONITORING WELLS AND UNIT 2 Unit 2 Storm Drain Outfall 001 MW-4 STORM DRAIN OUTFALL ---- MW-3 MW-3 (i - Monitoring Well Location MW-2 NNE MW-i

- Storm Drain Outfall 001 38.75 11.25 5 25326.25 303.75 NNW rdo W SWE SLOGIO

\ Bu M

-52086 W 425(NE)E DITNEDIRECTION Parking (Based onMPNS-U2 Ro Bldg.)

MW - 1 208 J 51 (NE) Unit ~Uit 2 MW -2 215 J47 (NE)\

MW -3 220 44(NE)

UW -4 216 44 (NE)

MXO-MWT-1 571 M- 20 160 (SSE)

J4(N)GMX-MW-1 SSE 14 .

3-29

U 3.4 LAND USE CENSUS The ODCM require 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. This census is performed once per year in the summer 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 located 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 3

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 1 ODCM if broadleaf vegetation sampling and analysis is performed.

3.5 CHANGES TO THE REMP PROGRAM i The following changes were implemented during the 2008 sampling program: 3 A. Sediment Sampling Program 3 During the report period, one sample location for sediment from a shoreline area with existing or potential recreational value was changed. The ODCM required location was moved due to shoreline erosion. The new location is in the same geographical location and 3

meteorological sector. This location was used as the indicator location to implement the requirements of the NMP1 ODCM, Part I, Table D 3.6.20-1 and the NMP2 ODCM, Part I, Table D 3.5.1-1.

3 I

3 -30

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2008 sample program address only those samples or monitoring requirements which are required by the ODCM. This section satisfies the reporting requirements of Section D 6.9.1.d of the NMP1 ODCM and Section D 4.1.2 of theNMP2 ODCM.

A. ODCM PROGRAM DEVIATIONS The following are deviations from the program specified by the ODCM:

1. The air sampling pump at the R-5 Environmental Sampling Station was inoperable for approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months during the sample period of 8/19/08 through 8/26/08. 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 loss of power to the sampler. No corrective actions were required to restore unit to service.

2. The air sampling pump at the R-5 Environmental Sampling Station was inoperable for approximately 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months during the sample period of 8/26/08 through 9/3/08. 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 equipment failure. Air sample pump was replaced.

3. The air sampling pump at the R-5 Environmental Sampling Station was inoperable for approximately 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months during the sample period of 9/3/08 through 9/5/08. 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 loss of power to the sampler. No corrective actions were required to restore unit to service.

4. The air sampling pumps at the R-3 and R-4 Environmental Sampling Stations were inoperable for approximately 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months during the sample period of 9/9/08 through 9/16/08. 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 loss of power to the sampler. No corrective actions were required to restore unit to service.

5. The air sampling pump at the R-5 Environmental Sampling Station was inoperable for approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during the sample period of 10/28/08 through 11/4/08. The sample pump out of service time was determined based on the sample pump run time 3-31

I I

integrator. The inoperability of the pump was due to loss of power to the sampler. No corrective actions were required to restore unit to service.

6. The air sampling pumps at the R-3 and R-4 Environmental Sampling Stations were inoperable for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during the sample period of 11/25/08 through 12/2/08. 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 loss of power to the sampler. No corrective actions were required to restore unit to service.

B. AIR SAMPLING STATION OPERABILITY ASSESSMENT 3 The ODCM required air sampling program consists of 5 individual sampling locations.

The collective operable time period for the air monitoring stations was 43,785 hours0.00909 days 0.218 hours 0.0013 weeks 2.986925e-4 months out of a possible 43,920 hours0.0106 days 0.256 hours 0.00152 weeks 3.5006e-4 months . The air sampling availability factor for the report period was 99.69%.

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 NMPNS Radiological Environmental Monitoring Program (REMP). The following equations were utilized to compute the mean (X) and the standard deviation (s):

A. Mean i=1 N I 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.

3-32 i

B. Standard Deviation

- '1/2

!n S(N-I1 Where, X = mean for the values of X s = standard deviation for the sample population.

3.7.2 ESTIMATION OF THE MEAN AND 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 radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated 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 A.i n

X~iZ1xi 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.

3-33

I I

B. Error of the Mean (Reference 18)

I ERROR MEAN =

I Where, N I ERROR MEAN i

=

propagated error individual sample I

ERROR N, n

=

1 sigma* error of the individual analysis number of samples with positive indications I

Sigma (cT) I 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. I 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.

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

4.66 Sb Il LLD (E) (V) (2.22) (Y) exp (-XAt)

Where:

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

Sb = the standard deviation of the background counting rate or of the counting rate of a I

E =

blank sample, as appropriate (in counts per minute);

the counting efficiency (in counts per disintegration);

I 3 - 34

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; At 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.

3.8 COMPLIANCE WITH REQUIRED LOWER LIMITS OF DETECTION (LLD)

Tables D 4.6.20-1 and D 3.5.1-3 of the NMP1 ODCM and NMP2 ODCM, respectively, specify the detection capabilities for environmental sample analysis (See Table 3.8-1). The reporting requirements of NMP1 ODCM, Section D 6.9.1 .d and NMP2 ODCM, Section D 4.1.2 require that a discussion of all analyses for which the LLDs required by Tables D 4.6.20-1 and D 3.5.1-3 were not achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to this requirement.

All sample analyses performed in 2008, as required by the ODCM, achieved the Lower Limit of Detection (LLD) specified by ODCM Tables D 4.6.20-1 and D 3.5.1-3.

3 -35

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

Analysis Water Airborne Particulate or Fish Milk Food Products Sediment (pCi/I) Gases (pCi/m 3) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, 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 1-131 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 1-131.

3 -36 M MMMmMMmMM M MM MM MM MM MM

3.9 REGULATORY DOSE LIMITS Two federal agencies, the Nuclear Regulatory Commission and the 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 10CFR20.1301, 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 10CFR50, 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, or

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, or

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.

3 -37

I 3.9.2 Environmental Protection Agency (EPA)

I The EPA, in 40CFRI90.10 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 whole 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.

I I

3 -38i I

SECTION 4.0 SAMPLE

SUMMARY

TABLES IN BRANCH TECHNICAL POSITION FORMAT

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

JANUARY - DECEMBER 2008*

TYPE AND NUMBER INDICATOR LOCATION (b) OF HIGHEST CONTROL LOCATION: NUMBER OF MEDIUM (UNITS) OF ANALYSES* LLD(a) LOCATIONS: ANNUAL MEAN: MEAN (f) / RANGE NONROUTINE 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 <LLD <LLD <LLD 0 Fish GSA (18): (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

ý M M M M ý-- m M-m M m m m M m M M M M

m m m - m m m m m - m m - m m TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2008*

INDICATOR LOCATION (b) OF HIGHEST CONTROL LOCATION: NUMBER OF MEDIUM (UNITS) TYPE AND NUMBER LLD(a) LOCATIONS: ANNUAL MEAN: MEAN (R)/ RANGE NONROUTINE OF ANALYSES* 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 1-131 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

JANUARY - DECEMBER 2008*

TYPE AND NUMBER INDICATOR LOCATION (b) OF HIGHEST CONTROLLOCATION- NUMBER OF MEDIUM (UNITS) OF ANALYSES* LLD(a) LOCATIONS: ANNUAL MEAN: MEAN (f) / RANGE NONROUTINE MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS TLD (mrem per Gamma Dose (140) (d) 4.6 (120/120) (i) TLD #85 (g): 8.2(4/4) 4.1 (20/20) 0 standard month) 3.1-8.8 0.2 miles at 2900 7.5-8.7 3.3-5.1 Air Particulates Gross Beta (260): 0.01 0.016 (212/212) R-2 0.016 (53/53) 0.015 (53/53) 0 (pCi/m 3) 0.004-0.030 1.1 miles at 1060 0.006-0.030 0.007-0.031 1-131 (260): 0.07 <LLD <LLD <LLD 0 GSA (20):

Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0 Milk GSA (54): (e) (h)

(pCi/liter) Cs-134 15 <LLD <LLD <LLD 0 Cs-137 18 <LLD <LLD <LLD 0 BaiLa-140 15 <LLD <LLD <LLD 0 1-131 (54):

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

- M - M M - M m M m -M - -

m m m m m m m m m m m m m m m m m m m TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

JANUARY - DECEMBER 2008*

TYPE AND NUMBER INDICATOR LOCATION (b) OF HIGHEST CONTROL LOCATION: NUMBER OF MEDIUM (UNITS) TYPE ANALMER LLD(a) LOCATIONS: ANNUAL MEAN: CON L NONROUTINE O MEAN (f) / RANGE LOCATION & MEAN (f) / RANGE REPORTS Food Products GSA (27): (h)

(pCi/kg-wet) 1-131 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 Unit 1 and Unit 2 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 NMP2 reactor center-line. Units in this column are specified in medium column.

(c) = The ODCM specify an 1-131 and tritium LLD value for surface water analysis (non-drinking water) of 15 pCi/liter and 3000 pCi/liter respectively.

(d) = The ODCM do not specify a particular LLD value for environmental TLDs. The NMP1 and NMP2 ODCM containspecifications for environmental TLD sensitivities.

(e) = The ODCM 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 two optional locations during 2008.

(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).

4-6 m mmmM M m - - m - m -

SECTION 5.0 DATA EVALUATION AND DISCUSSION

5.0 DATA EVALUATION AND DISCUSSION A. Introduction Each year the results of the 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. This report not only presents the data collected during the 2008 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 radionuclide 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), which is one millionth (0.000001) of a curie, and the picocurie (pCi), which is 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.

5-1

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 I 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 (mrem) 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 I 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 i There are three separate groups of radionuclides that were measured in the environment in I the media analyzed for the 2008 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 earth's crust, a steady stream of high-energy particles from space called cosmic radiation, naturally- I 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 person's average annual exposure from background radiation is 360 mrem, as illustrated in the following Background Radiation chart.

I 5-2I

Background Radiation ALL SOURCES MAN-MADE RADIATION EXPOSURE SOURCES 360 mremlyr RADON 55% MEDICAL X-RAYS 11%

EMITTERS 11%

~INTEIRNAL TERRTIAL 8%

N% COSMIC 8% NUCLEAR MEDICINE4%

CONSUMER PRODUCTS 3%

OTHER<1%

MAN- Occupational 0.3%

MADE 18% Fallout <0.3%

Radiation Exposure In the U.S. Nuclear Power 0.1%

(Percent of Total Effective Dose) Miscellaneous 0.1%

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

" Falloutradionuclidesfrom 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 radiation are made throughout this section to help put program results into perspective and to aid the reader in determining what, if any, significant impact is demonstrated by the REMP results.

5-3

The second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's 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 People's Republic of China and underground weapons testing by India, Pakistan & North Korea. In each case, the usual radionuclides associated with nuclear detonations were detected for several months following the test, and then after a peak detection period, diminished to a point where most could not be detected. Although reduced in frequency, atmospheric testing continued into the 1980's. The resulting fallout or deposition from these most recent tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample media analyzed over the years. 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 2008, there were no plant-related radionuclides 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 2008, 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 man's 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 5-4

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.

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 2008.

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 2008 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 5-5

developing. As state-of-the-art detection capabilities improve, data comparison is difficult I 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.

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

Shoreline Sediment i

Fish

Surface Waters 5

Groundwater Section 6.0, Tables 6-1 through 6-5 present the analytical results for the aquatic samples collected for the 2008 sampling period.

Sampling for groundwater, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2008. There was no groundwater source in 2008 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties were suitable for contamination; therefore, groundwater was not a dose pathway during 2008. m 5.1.1 SHORELINE SEDIMENT RESULTS A. Results Summary i Shoreline sediment samples were obtained in April and October of 2008 at one offsite control location (Lang's Beach located near Oswego Harbor) and at one indicator location i (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 2008 sample program, two indicator and two control. Cs-137 was not detected in samples collected from the control or indicator locations during 2008. m The concentration of Cs-137 measured in the 2008 indicator sample is consistent with measured concentrations since shoreline sediment sampling began in 1985. Historical mean concentrations measured at the Sunset Bay indicator location ranged from a maximum of 0.33 5-6

pCi/g in 1993 to a minimum of less than lower limit of detection (<LLD) in 2008. The results for the 2008 control location were less than the detection limit. The one naturally-occurring radionuclide detected was K-40 and was not related to plant operations. No other plant-related radionuclides were detected in the 2008 shoreline sediment samples.

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous ten years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1999.

Shoreline Sediment Cs-137 0.1 0.09

Control* 0 Indicator 0.08 0.07 0.06

0) 0.05 0.04

(~.

0.03 0.02 -

0.01 ¢

0 ,

1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year * < Lover Limit of Detection 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 (Lang's Beach). Samples were collected from both the indicator and control locations in April and October 2008. The results of these sample collections are presented in Section 6.0, Table 6-1, "Concentrations of Gamma Emitters in Shoreline Sediment Samples". Potassium-40 (K-40) was the only significant radionuclides detected in the sediment samples.

Analytical results for shoreline sediment samples are found in Section 6.0, Tables 6-1.

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 5-7

radiation to the whole body and skin. Using the parameters provided in Regulatory Guide i 1.109, the potential dose to man in mrem per year can be calculated. The following regulatory guide values and the maximum 2008 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, i

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 <0.078 pCi/g (dry).

Using these conservative parameters, the potential dose to the maximum exposed i individual (teenager) would be 0.00026 mrem/year to the whole body and 0.00031 mrem/year to the skin. This calculated dose is very small and is insignificant when m compared to the natural background annual exposure of approximately 50 mrem as measured by control TLDs in the vicinity of the site.

D. Data Trends Cs-137 was not detected at the indicator or the control samples locations in 2008. The Cs-137 concentration for the shoreline sediment indicator sample for 2008 was <0.078 pCi/g (dry). This is consistent with mean concentration measured at the indicator location over the past ten years. 1 The previous five years of data show a general decreasing mean concentration values measured at the indicator locations. Over the five year period, mean concentrations ranged i from a high of 0.08 pCi/g (dry) in 2005 to a low value of 0.04 pCi/g (dry) measured in 2004 and 2007. Cesium-137 was not detected in the control location samples over this same five year period.

The general absence of Cs-137 in the control samples is attributed to the differences in the 5 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 3 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 n shoreline sediment samples collected in the past. The Cs-137 is commonly found in soil I

5-8

samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-137.

The previous ten year data trend for indicator shoreline samples showed an overall downward trend in concentration measured at the indicator sample locations. Over the previous ten year period of 1999 through 2008, mean concentrations at the indicator location ranged from a maximum of 0.08 pCi/g (dry) in 1999 to a minimum of 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cs-137 was not detected at the indicator location for 2008. This 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.

5.1.2 FISH SAMPLE RESULTS A. Results Summary A total of 18 fish samples were collected for the 2008 sample program. Species collected were: smallmouth bass, brown trout, and walleye. The analytical results for the 2008 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 2008 fish samples is significant in the fact that it continues to validate the absence of Cs-137 in fish samples observed. Since 2003 no Cs-137 has been measured in fish samples. Over the previous 20 years prior to 2003, Cs-137 has been detected at a combination of both the indicator and/or control locations (Refer to Tables 7-3 and 7-4).

These low levels of Cs-137 represented no significant dose to man or impact on the environment.

The 2008 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 2008 results are consistent with previous year's results in that they continue to support the general long-term downward trend in fish Cs-137 concentrations over the last.,33 years. Cs-137 was not detected in fish samples collected in 2003 to 2008 from indicator locations. The period of 2000 through 2008 as a group are the 5-9

lowest results measured since the beginning of the Site Environmental Monitoring I Program in 1969.

B. Data Evaluation and Discussion i Fish collections were made utilizing gill nets at one location greater than five miles from I the site (Oswego Harbor area) and at two locations in the vicinity of the lake discharges for the Nine Mile Point Nuclear Station (NMPNS) and the James A. Fitzpatrick Nuclear Power Plant (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 2008 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. 5 The total fall fish collection was comprised of 9 individual samples representing three individual species. Walleye, smallmouth bass and brown trout were collected. m Cs-137 was not detected in any of the fish species collected for the 2008 sample program i Analytical results for fish samples are found in Section 6.0, Table 6-2.

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. Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. 1 Therefore, these fish are an integral part of the human food chain. The lack of detectable concentrations of plant-related radionuclides in the 2008 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic 3

pathway.

D. Data Trends 5

The Cs-137 data for fish samples over the previous five years (2004 through 2008) show that the number of positive detections has decreased over this period relative to historical data. There were no positive detections of Cs-137 over the previous 5 year period at the indicator locations. The graph below illustrates the mean control and indicator Cs-137 concentrations for 2008 and the previous ten years. 5 5-10 5

Annual Mean Fish Cs-137 Concentrations 0.025 N Control U Indicator 0.02 U = Lower Lirmt of Detection W0.015 Q 0.01 0.005 0

C M 'T W) 10 N 00 0'. 0 C C0 C0 C 0 0 0 Year The ten year data trend shows a consistent level of Cs-137 measured in fish between 1999 and 2000. After 2000, the number of positive detections drops off as noted in the ten year trend. The 1999 through 2008 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.

5-11

I

~Fish Cs-137 I

1.4 U Control U Indicator -

B 1.2 Note: Years with values of less than the lower limit of detection are presented as zero in the graph.

1 0.8

0.6 0.4 0.2 m Imm m m- - -- mm-_ .--

(I W. 00 CD CD CD 00 CP, (Ii -t ca 00 0 4 -d o PD PD o.

D 00 CD 00 0* CD Q) C" ( CD0 0 0 0 0.

Year Section 7.0, Tables 7-3 and 7-4 show historical environmental sample data for fish.

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 Nine Mile Point Unit I (NMP1) Intake and the Nine Mile Point Unit 2 (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 2008 Sampling Program.

The two naturally-occurring radionuclide detected were K-40 and Ra-226 and were not related to plant operations. Monthly composite samples showed no presence of plant-related gamma emitting isotopes in the waters of Lake Ontario as a result of plant operations.

The monthly surface water samples are composited on a quarterly basis and are analyzed for tritium. A total of 20 samples were analyzed for tritium as part of the 2008 REMP program.

The results for the 2008 samples showed no positive detections of tritium. All results for 2008 were below the established measurement sensitivity and are reported as less than the 5-12

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 2008 samples.

This is consistent with historical data, which has not shown the presence of plant-related radiofntclides 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 2008 sample program were analyzed to an instrument detection level of 500 pCi/l.

The ODCM required indicator location (JAFNPP inlet canal) showed no positive detections of tritium. The 2008 results had LLD values that ranged from <424 pCi/l to <450 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 <424 pCi/1 to <450 pCi/1.

'Tritium Was not detected in any of the twelve optional Lake Ontario samples collected in the 2008 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.

The followingtable provides the specific LLDs for the 2008 sample program:

SamleTritium Concentration pCi/liter Sample Mean

'Location Minimum Maximum (Annual)

JAFNPP Inlet (Indicator)* <424 <450 <435 Oswego Steam Inlet (Control)* <424 <450 <435 NMP l Inlet <424 <450 <435 NMP2 Inlet <424 <450 <435 Oswego City Water Supply <424 <450 <435

Sample location required by ODCM The LLD values are below are below the ODCM required LLD of 3000 pCi/1 for a non-drinking water pathway.

5-13

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

4. 1 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 2008 LLD concentration of <450 pCi/l, the calculated dose would be less than 0.047 mrem to the child whole body and less than 0.047 mrem to the child liver (critical age group/organ).

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 2008 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 2003 to 2007 was <LLD pCi/l for the control and the indicator location. The mean 2008 tritium concentrations were.<435 pCi/l for the control and indicator locations. 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, 1998 through 2007, is representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured. The 1999 mean control value of 337 pCi/i 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 previous 20 years at both an indicator and control location. Prior to 1985, the Oswego City Water Supply results were used as control location data as this location closely approximates the Oswego Steam Station, the current control location. m 5-14

Surface Water Tritium 500 450 T control U indicator Mt Note: Years with values of less than the lower linit 400 of detection are presented as zero in the graph.

350

. 300 250 200 150 100 50 0

a, 0= Cl NO 00 ON Co M .r) ~0 00 00 ON ON ON OT ON ON a, ON o C) C 0 0 0 0 a, ON ON ON ON " oCo 0q 0 ci 0

ci 0

ci Year Section 7.0, Tables 7-5 through 7-8 show historical environmental sample data for surface water tritium.

5.1.4 GROUNDWATER A. Results Summary A groundwater monitoring program is not required by the ODCM. The program is being implemented as the result of Nuclear Energy Institue (NEI) Ground Water Protection Initiative. Groundwater samples were collected from a number of locations shown in Section 3.3 Figure 3.3-6 and listed in Table 3.3-1.

A total of 15 samples were collected for the 2008 sample program using two indicator locations and two control locations. The results for the 2008 samples showed no positive detections of tritium. All results in 2008 were below the established measurement sensitivity and are reported as less than the lower limit of detection (<LLD).

B. Data Evaluation and Discussion Gamma and strontium analysis were also performed on samples from each location. No plant-related radionuclides were detected in the 2008 samples. This is consistent with historical data, which has not shown the presence of plant-related radionuclides in groundwater samples.

5-15

Tritium samples analyzed for the 2008 sample program were analysed to a instrument detection limit of 500 pCi/I. The tritium results for the control locations contained no positive detections and had LLD values that ranged from <426 pCi/l to <439 pCi/l. The 3 indicator locations results showed no positive detections and had LLD values that ranged from <415 pCi/l to <446 pCi/l.

Analytical results for groundwater samples are found in Section 6.0, Table 6-5.

C. Dose Evaluation Sampling for groundwater, as found in Section D 3.5.1 of the NMP2 ODCM, was not i required during 2008. There was no groundwater source in 2008 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties I were suitable for contamination; therefore, drinking water was not a dose pathway during 2008. 3 D. Data Trends There are no data trends for gamma emitters or strontium as these radionuclides have not been detected in groundwater samples.

Historical data for groundwater tritium is presented in Section 7.0, Tables 7-9 and 7-10.

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

" Airborne particulate and radioiodine,

Direct Radiation, 3

Milk, and

" Food Products. 3 Section 6.0, Tables 6-6 through 6-14 present the analytical results for the terrestrial samples collected for the 2008 reporting period.

5-16

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 2008 program, a total of 52 samples were collected from control location R-5 and 208 samples were collected from indicator locations R-l, 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 2008 was 0.0 15 pCi/m 3. The mean gross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2008 was 0.016 pCi/mi3 . 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 twenty one years. This consistency demonstrates that the natural baseline gross beta activity has been reached. The man-made radionuclide contribution to the natural background from atmospheric weapons testing and Chernobyl can no longer be detected above the background concentrations of naturally occurring beta emitting radionuclides.

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 795 samples were collected and analyzed as part of the 2008 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 6-6 and 6-7 present the weekly gross beta activity results for samples collected from the offsite and onsite locations.

5-17

The mean annual gross beta indicator concentrations for the ODCM indicator stations (R- 3 1, R-2, R-3 and R-4) was 0.016 pCi/mr3. The offsite ODCM control station (R-5) annual mean gross beta concentration was 0.015 pCi/m3 . The minimum, maximum and average 3 gross beta results for sample locations required by the ODCM were as follows:

I 3

Concentration pCi/mi Location Minimum Maximum Mean R-I 0.007 0.026 0.016 R-2 0.006 0.030 0.016 R-3 0.007 0.025 0.015 R-4 0.004 0.026 0.016 R-5 (Control) 0.007 0.031 0.015 The mean weekly gross beta concentrations measured in 2008 are illustrated in the I following graphs:

00300 --- Indicator Air Particulate Filter - Gross Beta (2008)

-a- Control 3 0 0250 0 0100 0 0050 1 0 0000 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 #

5-183

Air Particulate Filter - Gross Beta (2008)

.-- Indicator -a-- Control o o~ooo 27 28 29 30 SI 32 04 33 05 36 31 38 39 40 41 42 43 44 45 40 47 48 41 5o 51 02 53 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.

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

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/m 3. The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

5-19

I The mean gross beta concentrations measured in 1977 to 2008 are illustrated in the following graph:

I I

Air Particulate Filter - Gross Beta 0.18 0.16 1980: Atmospheric U Control U Indicator I 0.14 I

Nuclear Tests 0.12 S 0.1 0.08 0.06 0.04 L

1986 Chernobyl Accident I

0.02 0

- - - - : -- :. : 71 V. . 7 4. . :. . : 9 V 2 z. : 0 z :

I Year I

The trend for the previous five years represents a base line concentration or natural I

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 I

1999 through 2008 is very small. This is illustrated by the following graph:

I 0.02 I Air Particulate Filter- Gross Beta I

I I n * , * -~ ..

0.018 0.016 0.014 I

I 0.012 0.01 Coto - M Iniao 0.008 0.006 0.004 0.002 I

0 0 0 0D a

0 CM 03 10 Year 0*

0o 0*

Q 10 Q

0 Q C5 I

I For the previous 10 years, the mean annual gross beta concentration at the control station (R-5) has remained steady with a narrow range of 0.015 pCi/m 3 to 0.019 pCi/m 3. The I

5 -20 I

mean annual concentrations for the indicator stations for this same time period were similar to the control and ranged from a minimum mean of 0.015 pCi/mi3 to a maximum mean of 0.019 pCi/mi3 in 2005.

Historical data of air particulate gross beta activity are presented in Section 7.0, Tables 7-11 and 7-12.

5.2.2 MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS)

A. Results Summary Fifteen air monitoring stations are maintained around the Nine Mile Pointý site. Five of the 15 air monitoring stations are required by the ODCM; four are located offsite near the site boundary and one is located 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 2008.

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.

B. Data Evaluation Discussion 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 2008 showed no detectable activity of plant related radionuclides.

5-21

I The results of the monthly composite samples are presented in Section 6.0, Table 6-8 and

9. 1 C. Dose Evaluation I The calculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected in 2008. 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 2008 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.

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 I

environment surrounding the Nine Mile Point site. I 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 I 2000 in a single sample. A review of the past five year's data for air particulate filter composites indicates no plant related radiological impact on the environment. All previous 5-22 3

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 (1-131)

A. Results Summary Iodine-131 (1-131) was not detected in any of the 795 samples analyzed for the 2008 program. No radioiodine has been measured offsite at the constant air monitoring stations since 1987.

B. Data Evaluation and Discussion Airborne radioiodine (1-131) 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 1-131. 1-131 was not detected in any of the 2008 samples collected.

The analytical data for radioiodine are presented in Section 6.0, Tables 6-10 and 6-11.

C. Dose Evaluation The calculated dose as a result of 1-131 was not evaluated due to the fact 1-131 was not detected during 2008. The 1-131 sampling program demonstrated no offsite dose to man from this pathway as a result of operation of the plants located at the Nine Mile Point site.

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

5 - 23

There has been no positive detection of 1-131 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 1999 through 2008.

1-131 has previously been detected in samples collected during the last twenty five year period in 1986 and 1987. The 1986 detection of 1-131 was the result of the Chernobyl accident, and the 1987 detection was the result of plant operations.

1-131 has been detected in the past at control locations. Control samples collected during 1976 had a mean 1-131 concentration of 0.60 pCi/mi3 . During 1977 this mean decreased to 0.32 pCi/m 3, and further decreased by.a factor of ten to 0.03 pCi/m 3 in 1978. 1-131 was not detected in samples collected from the control location during 1979 - 1981 and 1983 to 1 1985. 1-131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/rn 3. I Iodine-131 has been detected in samples collected from the on-site indicator locations during 1976 to 1978, 1980 to 1983 and 1986 to 1987. The mean concentrations ranged from 0.013 pCi/m 3 in 1980 to a maximum of 0.119 pCi/mi3 in 1986. The maximum mean indicator 1-131 concentration of 0.119 pCi/rn 3 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/rn 3 to a maximum of 0.36 pCi/m 3 . Each positive detection of 1-131 in samples collected in 1986 was the direct result of the Chernobyl accident.

Historical data for 1-131 are presented in Section 7.0, Tables 7-15 and 7-16.

5.2.4 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS (TLD) I A. Results Summary I Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. As part of the 2008 environmental monitoring program, TLDs were placed at a total of 72 different environmental TLD locations (32 required by the ODCM and 40 optional locations). These TLDs were placed, collected and read each quarter of I 2008. 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.

5-24

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

" Onsite (areas within the site boundary: TLDs 3, 4, 5, 6, 7, 23, 24, 25, and 26; TLDs 18, 27, 28, 29, 30, 30, 31, 39, 47; 103, 106, and 107 excluded),

" Site Boundary (area of the site boundary in each of the 16 meteorological sectors: Only includes TLD results that are not affected by radwaste direct shine, TLDs 7, 18, 78, 79, 80, 81, 82, 83, and 84; TLDs 23, 75, 76, 77, 85, 86, and 87 excluded),

" Offsite Sector (area four to five miles from the site in each of the eight land based meteorological sectors: TLDs 88, 89, 90, 91, 92, 93, 94, and 95),

Special Interest (areas of high population density and use: TLDs 15, 56, 58, 96, 97 and 98), and

Control (areas beyond significant influence of the site: TLDs 14 and 49).

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 2008 dose rates for each of the five geographical locations is as follows:

Dose in mrem per standard month Geographic Category Minimum Maximum Mean Onsite (Optional) 3.2 13.8 5.2 Site Boundary (Inner Ring) * (a) 3.2 4.8 4.0 Offsite Sectors (Outer Ring)

3.2 4.5 3.8 Special Interest * (2) 3.1 4.6 3.9 Control * (3) 3.3 4.8 4.0

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

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.

5 - 25

I The results for the 2008 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 systems used at NMPNS 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 2008, 32 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 Sectors, 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. i Onsite TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2008 direct radiation results for Onsite TLD locations were as follows:

1. Results for TLDs located near the NMP 1, NMP2 and JAFNPP generating facilities and at previous or existing on-site air monitoring stations ranged from 3.2 to 13.8 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 NMP1 Reactor Building ranged from 3.3 to 29.0 mrem per standard month.

I

3. Results for TLDs located onsite near the Energy Information Center and its associated shoreline ranged from 4.0 to 5.6 mrem per standard month.

Site Boundary TLD results ranged from 3.2 to 8.8 mrem per standard month in 2008. 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 8.8 mrem per standard month. This TLD, (TLD 87) represents the site boundary maximum dose and is located in the NNW sector along the lake shore in close proximity to the NMP1 plant. The TLD locations along the lakeshore close to the plants (TLDs 75, 76, 77, 85, 86 and 87) are influenced by radwaste buildings and radwaste shipping activities.

5-26

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 3.2 to 4.8 mrem per standard month resulting in an average dose rate of 4.0 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 4.5 mrem per standard month with an average dose rate of 4.2 mrem per standard month.

Special Interest TLDs from all locations ranged from 3.1 to 4.6 mrem per standard month with an annual average dose rate of 3.9 mrem per standard month.

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site. 2008 Control TLD results ranged from 3.3 to 5.1 mrem per standard month with an annual average dose rate of 4.1 mrem per standard month. These results include both the ODCM required control TLDs (#14 and 49) and the additional control TLDs (#8, 111 and 113).

TLD analysis results are presented in Section 6.0, Table 6-12.

C. Dose evaluation 2008 annual mean dose rates for each geographic location required by the ODCM are as follows:

Site Boundary: 4.0 mrem per standard month (TLDs: 78, 79, 80, 81, 82, 83, 84, 7, 18)

Offsite Sectors: 3.8 mrem per standard month (TLDs: 88, 89, 90, 91, 92, 93, 94, 95)

Special Interest: 3.9 mrem per standard month (TLDs: 15, 56, 58, 96, 97, 98)

Control: 4.0 mrem per standard month (TLDs 14, 49)

The measured mean dose rate in the proximity of the closest*resident was 4.1 mrem per standard month (TLD #s: 108, 109) which is consistent with the control measurements of 4.0 mrem per standard month.

5 - 27

I 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. I The TLD program verifies that operations at the site do not measurably contribute to the D.

levels of direct radiation present in the offsite environment.

Data Trends I

A comparison of historical TLD results can be made using the different geographical I

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 I 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 I

from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Offsite Sectors and Special Interest groups from 1999 through 2008:

TLD Data 6

0 Control M Site Boundary 0] fi 5

43 -

2 -

0 ON1 0 -q M0 "rr-ON 0c0 0 CD 00000 0C00, CD 0 C 00 C- N' el CN Nl ell C Year TLDs located at the site boundary averaged 4.0 mrem per standard month during 2008 (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 I

of 4.3 mrem per standard month. I 5 - 28

Offsite Sector TLDs averaged 3.8 mrem per standard month during 2008. This result is also consistent with the previous five year average of 4.1 mrem per standard month for offsite sectors.

Special Interest TLD locations averaged 3.9 mrem per standard month during 2008 which is consistent with the previous five year average of 4.1 mrem per standard month.

The last group of TLD locations required by the ODCM is the Control Group. This group utilized TLD locations positioned well beyond the site. 2008 control results from all Control TLDs averaged 4.0 mrem per standard month, consistent with the previous five year average of 4.2 mrem per standard month. The 2008 TLD program results, when compared to the previous ten years, showed no significant trends relative to increased dose rates in the environment.

Section 7.0, Tables 7-17 through 7-22 show the historical environmental sample data for environmental TLDs.

5.2.5 MILK A. Results Summary A total of 54 milk samples were collected during the 2008 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 (1-131).

1-131, a possible plant related radionuclide, is measured to evaluate the cow/milk dose pathway to man. 1-131 was not detected in any of the 54 milk samples collected in 2008 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 2008. 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 2008 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.

5 - 29

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 milch animal census, there were no adequate milk sample locations within five miles of the site in 2008. Samples were collected from three farms located beyond the five-mile requirement to ensure the continued monitoring of this important pathway. The two indicator locations ranged from 6 to 9 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 8.8 77 (Control) SSW 16.0 Samples were collected from Indicator locations #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 2008 as a result of 1-131 not having been detected in samples collected during November and December of 2007, 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. 1-131 and gamma analysis results for milk samples collected during 2008 are provided in Section 6.0, Table 6-13.

Iodine-131 was not detected in any indicator or control milk samples analyzed during 2008. All 1-131 milk results were reported as Lower Limits of Detection (LLD). The LLD results for all samples ranged from <0.43 to <0.97 pCi/liter. No plant-related radionuclides were detected in any milk sample collected in 2008. 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 1249 to 2530 pCi/liter. Cs-137 was not detected in any indicator or control milk sample collected in 2008.

The results of the milk samples are presented in Section 6.0, Table 6-13. I 5-30

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 (inhalation, 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 five 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. 1-131 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 2008 data to historical results over the operating life of the plants shows that Cs-137 and 1-13 1 levels have decreased significantly since the 1980's.

Historical data of milk sample results for Cs-137 and 1131 are presented in Section 7.0, Tables 7-23 and 7-24.

5.2.6 FOOD PRODUCTS (VEGETATION)

A. Results Summary There were no plant-related radionuclides detected in the 27 food product samples collected and analyzed for the 2008 program.

Detectable levels of naturally occurring K-40 were measured in all control and indicator samples collected for the 2008 program. Be-7 a naturally-occurring radionuclide, was also 5-31

detected intermittently in samples collected in 2008. These results are consistent with the i levels measured in previous years.

The results of the 2008 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.

B. Data Analysis and Discussion Food product samples were collected from five indicator locations and one control location. The indicator locations are represented by nearby gardens in areas of highest i 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 2008 did not included any varieties considered to I be an edible broadleaf vegetables. The general lack of edible broadleaf vegetation samples was the result of grower preference and such varieties were not available in local gardens. 3 Where broadleaf vegetables were not available, non-edible broadleaf vegetation were collected. Non-edible vegetation consisting of squash leaves, zucchini leaves, rhubarb leaves, grape leaves, corn leaves, horseradish leaves, green bean leaves, and pepper leaves were collected for the 2008 program. The leaves of these plants were sampled as representative of broadleaf vegetation which is a measurement of radionuclide deposition. i In addition to the broadleaf vegetation, tomato samples were collected from all 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 2008 did not detect any plant- i related radionuclides. Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

Naturally-occurring Be-7 and K-40 were detected in food product samples. The i concentration of Be-7 in vegetation samples ranged from <0.099 to 3.31 pCi/g (wet). The concentration of K-40 in indicator and control samples ranged from 1.93 to 8.61 pCi/g (wet). The results for naturally-occurring radionuclides are consistent with the data of prior years. I Analytical results for food products are found in Section 6.0, Table 6-14.

I 5 -32I

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 the Nine Mile Point site.

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 0.008 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 0.004 pCi/g (wet) in 1979. The trend for Cs-137. is a general reduction in concentration to non detectable levels in samples collected during the 2001 through 2008 sample programs.

Historical data of food product results are presented in Section 7.0, Tables 7-25 and 7-26.

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 2008, a milk animal census, a nearest resident census and a garden census were performed.

The results of the closest residence census conducted in 2008 required no change to either the NMP1 or NMP2 ODCMs' closest resident location.

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 Table 5-1 of the NMP1 and NMP2 ODCMs and identified in the census as active for 2008. See Table 3.3-1 for 2008 sampling locations.

5-33

B. Data Evaluation and Discussion A land use census is conducted each year to determine the utilization 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 I 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.

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 416 cows and 1 goats based on the 2008 land use census. The number of cows has increased by 35, when compared to the 2007 census. The census determined that the milk from goats identified was not shippped. The results of the milk animal census are found in Section 6.0, Table 6-15. I 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 I

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 6-16. There were I

no changes identified in the 2008 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.

5.3 CONCLUSION

I The Radiological Environmental Monitoring Program (REMP) is an ongoing program implemented to measure and document the radiological impact of NMPNS 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 5-34 i

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 2008 REMP 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 REMP 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.

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 2008 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 more sensitive to the measurable impact of plant operations on the environment as time goes on.'

The environmental monitoring program did not detect any plant-related radionuclide in the sample media collected during 2008. 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 5 -35

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 2008 Radiological Environmental Monitoring Program, it I 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.

5.4 REFERENCES

I

1. 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", 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 U Specifications for Nuclear Power Plants", December, 1975. I

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

5. National Council on Radiation Protection and Measurements (NCRP), Environmental I 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. 3

7. National Council on Radiation Protection and Measurements (NCRP), Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977. 3

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

I 5 -36 I

9. International 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.

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 - 37

SECTION 6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES

6.0 REPORT PERIOD ANALYTICAL RESULTS TABLES 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.

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).

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 are reported as the mean of the positive detections and the associated error for that mean (see Section 3.7.2 for methodology).

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 (pCi/kg (dry) +/- 1 Sigma)

Sample Location Collection I Gamma Emitters Date K-40 I Co-60 Cs-134 Cs-137 Zn-65 Others 04/17/08 21200 +/- 660 < 53.9 < 62.8 < 56.8 < 87.5 <LLD Sunset Bay (05)

10/17/08 19050 +/- 883 < 98.4 < 48.8 < 78.4 < 122.6 <LLD 04/17/08 8066 +/- 394 < 34.1 < 32.0 < 36.8 < 77.3 <LLD Lang's Beach (06, Control) 10/17/08 13520 +/- 600 < 56.7 < 57.6 < 51.1 < 83.2 <LLD

Sample required by the ODCM

- Corresponds to sample location noted on Figure 3.3-5

" Plant related radionuclides 6-2 M mM- ---- M M M - - -M M M- M- -M-

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES (pCi/kg (wet) +/- I Sigma)

FITZPATRICK * (03)**

Description Gamma Emitters Date I I K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others t 6/27/2008 Walleye 6050 +/- 415 < 44 < 48 < 131 < 57 < 42 < 50 < 142 <LLD 7/1/2008 Brown Trout 4355 +/- 417 < 53 < 45 < 124 < 45 < 44 < 39 < 112 <LLD 7/1/2008 Smallmouth Bass 4160 +/- 324 < 42 < 39 < 87 < 42 < 44 < 39 < 94 <LLD 9/19/2008 Walleye 5971 +/- 494 < 49 < 48 < 161 < 66 < 49 < 52 < 146 <LLD 9/19/2008 Smallmouth Bass 6647 +/- 450 < 56 < 42 < 150 < 54 < 37 < 57 < 146 <LLD 9/23/2008 Brown Trout 4424 +/- 432 < 56 < 35 < 125 < 78 < 45 < 45 < 144 <LLD

Sample required by the ODCM

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

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES (pCi/kg (wet) +/- 1 Sigma)

NINE MILE POINT * (02)**

Date I

Description 1 I K-40 Mn-54 Co-58 Gamma Emitters Fe-59 Co-60 I Cs-134 I Cs-137 Zn-65 I Others "

6/27/2008 Brown Trout 9042 +/- 695 < 62 < 71 < 231 < 48 < 41 < 71 < 197 <LLD 6/30/2008 SmallmouthBass 5574 +/- 420 < 36 < 38 < 113 < 35 < 42 < 38 < 77 <LLD 7/2/2008 Walleye 4164 +/- 415 < 40 < 45 < 63 < 48 < 49 < 43 < 106 <LLD 9/19/2008 Brown Trout 7386 +/- 666 < 68 < 76 < 201 < 82 < 64 < 57 < 195 <LLD 9/19/2008 Walleye 3580 +/- 359 < 44 < 29 < 143 < 54 < 42 < 42 < 126 <LLD 9/19/2008 SmallmouthBass 4173 +/- 363 < 42 < 43 < 132 < 42 < 41 < 34 < 112 <LLD

Sample required by the ODCM

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

-- ---- M---- M M - M M M - M

M M M M M m m M M M M M = M M m m M m TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES (pCi/kg (wet) +/- 1 Sigma)

OSWEGO HARBOR (CONTROL) * (00)**

Date Description Gamma Emitters I I K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 Others 6/28/2008 SmallmouthBass 4330 +/- 380 < 43 < 42 < 133 < 45 < 38 < 38 < 121 -<LLD 7/1/2008 Walleye 3792 +/- 364 < 39 < 39 < 140 < 48 < 39 <. 46 < 99 <LLD.

7/2/2008 Brown Trout 9027 +/- 709 < 81 < 63 < 193 < 62 < 58 < 61 < 195 <LLD 9/12/2008 Brown Trout 9268 +/- 771 < 68 < 66 < 244 < 84 < 36 < 81 < 209 <LLD 9/12/2008 Smallmouth Bass 3683 +/- 383 < 46 < 53 < 113 < 44 < 38 < 46 < 114 <LLD 9/19/2008 Walleye 3575 +/- 383 < 40 < 41 < 97 < 45 < 46 < 37 < 101 <LLD

Sample required by.the ODCM

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

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

(pCi/I +/- 1 Sigma)

Station Code Period Date Tritium First Quarter 01/02/08 03/31/08 <450 Fitzpatrick* Second Quarter 03/31/08 07/01/08 <439 (03, Inlet)*** Third Quarter 07/01/08 09/27/08 <427 Fourth Quarter 09/27/08 01/05/09 <424 First Quarter 12/28/07 03/28/08 <450 Oswego Steam Station* Second Quarter 03/28/08 06/27/08 <440 (08, Control)*** Third Quarter 06/27/08 09/25/08 <427 Fourth Quarter 09/25/08 12/26/08 <424 First Quarter 12/28/07 03/28/08 <450 Nine Mile Point Unit 1** Second Quarter 03/28/08 06/27/08 <440 (09, Inlet)*** Third Quarter 06/27/08 09/25/08 <427 Fourth Quarter 09/25/08 12/26/08 <424 First Quarter 12/28/07 03/28/08 <450 Nine Mile Point Unit 2** Second Quarter 03/28/08 06/27/08 <440 (11, Inlet)*** Third Quarter 06/27/08 09/25/08 <427 Fourth Quarter 09/25/08 12/26/08 <424 First Quarter 12/28/07 03/28/08 <450 Oswego City Water** Second Quarter 03/28/08 06/27/08 <440 (10)*** Third Quarter 06/27/08 09/25/08 <427 Fourth Quarter 09/25/08 12/26/08 <424

Sample location required by the ODCM

- - Optional sample location

** Corresponds to sample location noted on Figure 6-6

- /-- I-M - -M M M M M M -

m -- mm m- -m- - m-m mm-m- m m m TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES (pCi/liter +/- 1 Sigma)

OSWEGO CITY WATER* (10)**

Nulide January February March April May June

.1-131 < 14.3 < 14.9 < 14.4 < 13.7 < 11.4 < 9.53 Cs-134 < 4.16 < 5.09 < 4.47 < 2.27 < 3.70 < 1.67 Cs-137 < 3.80 < 5.08 < 3.12 < 3.12 < 3.45 < 2.49 Zr-95 < 8.33 < 9.22 < 7.18 < 5.18 < 6.57 < 4.92 Nb-95 < 5.08 < 6.61 < 4.82 < 3.84 < 4.41 < 3.18 Co-58 < 4.61 < 5.80 < 4.06 < 3.72 < 4.19 < 3.04 Mn-54 < 3.49 < 4.64 < 3.74 < 2.91 < 3.11 < 2.50 Fe-59 < 13.0 < 12.9 < 12.4 < 9.73 < 13.5 < 9.19 Zn-65 < 8.27 < 11.8 < 7.62 < 4.04 < 7.99 < 6.54 Co-60 < 3.13 < 5.96 < 3.50 < 2.64 < 3.16 < 3.09 K-40 337.3 +/- 25.6 321.6 +/- 30.4 109.2 +/- 16.9 326.0 +/- 19.2 186.8 +/- 18.9 < 24.8 Ba/La-140 < 11.2 < 12.7 < 8.65 < 8.87 < 10.7 < 7.27 Nuclide July August September October November December 1-131 < 13.9 < 14.9 < 12.5 < 12.7 -< 14.8 < 14.9 Cs-134 < 2.45 < 3.86 < 5.68 < 2.30 < 3.12 < 1.70 Cs-137 < 3.55 < 4.05 < 4.55 < 3.12 < 4.60 < 2.44 Zr-95 < 7.04 < 7.30 < 9.34 < 6.76 < 9.32 < 5.22 Nb-95 < 4.94 < 5.13 < 5.78 < 4.45 < 5.12 < 3.54 Co-58 < 4.36 < 4.32 < 4.81 < 3.88 < 5.37 < 2.89 Mn-54 < 3.46 < 3.78 < 3.89 < 3.04 < 4.45 < 2.48 Fe-59 < 11.1 < 11.6 < 14.5 < 10.4 < 17.8 < 8.19 Zn-65 < 4.70 < 10.1 < 12.5 < 4.52 < 11.9 < 6.05 Co-60 < 3.75 < 4.24 < 4.54 < 3.40 < 4.79 < 2.44 K-40 392.4 /- 23.3 162.9 +/- 21.7 415.6 +/- 32.7 382.7 +/- 21.8 168.6 +/- 26.4 140.0 +/- 12.9 Ba/La-140 < 11.2 < 12.0 < 9.25 < 9.85 < 13.8 < 10.5 Optional Sample Location

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

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES (pCi/liter +/- 1 Sigma)

NINE MILE POINT UNIT I * (09, INLET)**

Nuclide January February March J April 1 May 1 June 1-131 < 13.6 < 6.56 < 11.2 < 11.2 < 14.6 < 13.8 Cs-134 < 3.86 < 2.56 < 4.03 < 1.75 < 4.00 < 2.36 Cs-137 < 2.74 < 2.76 < 3.82 < 2.29 < 3.94 < 3.41 Zr-95 < 6.97 < 6.36 < 5.77 < 4.91 < 8.49 < 6.42 Nb-95 < 4.62 < 3.30 < 4.72 < 3.56 < 5.77 < 4.05 Co-58 < 3.65 < 2.72 < 4.91 < 2.74 < 4.11 < 3.66 Mn-54 < 3.33 < 2.54 < 3.78 < 2.20 < 4.25 < 3.20 Fe-59 < 10.6 < 7.41 < 11.0 < 7.93 < 13.9 < 9.73 Zn-65 < 5.21 < 6.33 < 7.92 < 5.85 < 6.60 < 8.51 Co-60 < 3.42 < 2.60 < 4.25 < 2.13 < 4.20 < 4.02 K-40 141.1 +/- 17.4 79.6 '+/- 12.8 < 37.3 37.3 +/- 8.47- 922.9 +/- 36.5 46.2 +/- 12.5 BaILa-140 < 11.7 < 6.04 < 11.9 < 6.53 < 11.7 < 10.3 Nuclide July August September October November December 1-131 < 12.7 < 10.9 < 14.9 < 9.99 < 12.7 < 11.3 Cs-134 < 2.26 < 2.03 < 4.87 < 2.49 < 2.64 < 1.41 Cs-137 < 3.68 < 2.71 < 6.12 < 2.16 < 3.73 < 1.89 Zr-95 < 6.83 < 5.76 < 10.6 < 4.22 < 6.89 < 4.02 Nb-95 < 4.20 < 2.89 < 7.16 < 3.21 < 5.01 < 2.76 Co-58 < 3.34 < 3.41 < 6.64 < 2.84 < 4.32 < 2.25 Mn-54 < 3.22 < 2.96 < 6.19 < 2.26 < 3.79 < 1.94 Fe-59 < 10.3 < 7.96 < 17.6 < 6.95 < 11.8 < 6.04 Zn-65 < 7.52 < 4.07 < 15.2 < 5.73 < 4.64 < 4.04 Co-60 < 3.42 < 2.73 < 6.06 < 2.48 < 3.66 < 1.87 K-40 165.7 +/- 17.8 51.4 +1- 10.6 850.1 +1- 50.1 97.0 +1- 11.2 < 44.7 72.4 +/- 8.65 BaILa-140 < 10.1 < 8.08 < 13.7 < 5.88 < 8.71 < 6.73

Optional Sample Location

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

M M M M M M M m M M M M TABLE 6-4 (continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES (pCi/liter +/- 1 Sigma)

FITZPATRICK* (03, INLET)**

Nuclide January February March April May June 1-131 < 0.55 < 0.53 < 0.42 < 0.82 < 0.72 < 0.42 Cs-134 < 3.01 < 4.79 < 6.70 < 2.22 < 3.74 < 1.78 Cs-137 < 3.97 < 5.28 < 6.13 < 2.37 < 5.94 < 2.27 Zr-95 < 7.42 < 8.33 < 14.3 < 5'53 < 9.40 < 4.13 Nb-95 < 5.21 < 7.03 < 10.5 < 3.19 < 7.46 < 3.17 Co-58 < 5.35 < 5.42 < 7.55 < 3.31I < 5.53 2.68 Mn-54 < 4.14 < 4.96 < 7.67 < 2.69 < 5.81 < 2.28 Fe-59 < 14.3 < 15.4 < 22.07 < 7.92 < 15.5 < 6.48 Zn-65 < 6.36 < 13.0 < 15.23 < 5.98 < 8.05 < 5.33

Co-60 < 4.01 < 4.01 < 8.18 < 2.93 < 6.67 < 2.29 K-40 139.8 +/- 22.8 < 53.3 908.0 +/- 57.0 72.6 +/- 13.2 . < 50.2 90.6 +/- 11.4 Ba/La-140 < 9.91 < 13.7 < 13.9 < 6.3-1 < 13.6 < 6.58 Nuclide July August September October November December 1-131 < 0.53 < 0.39 < 0.70 < 0.53 < 0.55 < 0.47 Cs-134 < 2.03 < 3.68 < 3.94 < 1.39 < 3.53 < 3.36 Cs-137 < 2.64 < 5.06 < 3.18 < 1.80 < 3.10 < 4.10 Zr-95 < 5.60 < 9.90 < 5.16 < 3.52 < *5.96 < 8.59 Nb-95 < 3.45 < 6.27 < 4.04 < 2.21 < 4.29 < 5.99 Co-58 < 3.45 < 5.31 < 3.49 K< 2.04 < 3.01 < 4.78 Mn,54 < 3.08 < 4.85 < 3.68 < 1.73 < 3.07 < 4.03 Fe-59 < 7.05 < 18.0 < 8.07 < 5.33 < 8.02 < 16.4 Zn-65 < 6.92 < 13.3 < 8.51 < 3.63 < 4.07 < 11.1 Co-60 < 3.1:1 < 5.64 < 3.41 < 1.90 < - 2.69 < 5.24 K-40 29.8 +/- 10.9 420.5 +/- 36.0 81.9 +/- 15.3 33.2 +/- 6.86 37.4 +/- 11.0 222.1 +/- 23.8 BaLa- 140 < 6.94 < 11.2 < 5.38 < 3.70 < 6.41 < 10.1

Sample Location required by ODCM

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

TABLE 6-4 (Continued)

CONCENTRATIONS.OF GAMMA EMITTERS IN SURFACE WATER SAMPLES (pCi/liter +/- 1 Sigma)

NINE MILE POINT UNIT 2 * (11, INLET) **

Nuclide January February March April May II June 1-131 < 12.3 < 10.30 < 14.7 < 10.8 < 10.1 < 11.7 Cs-134 < 3.45 < 3.82 < 4.85 < 4.11 < 2.12 < 3.79 Cs-137 < 3.38 < 3.27 < 4.30 < 3.55 < 2.75 < 3.50 Zr-95 < 6.87 < 6.55 < 8.50 < 6.28 < 5.47 < 7.05 Nb-95 < 4.49 < 4.69 < 5.49 < 4.54 < 3.41 < 4.52 Co-58 < 3.38 < 3.29 < 5.39 < 4.18 < 3.26 < 3.91 Mn-54 < 3.09 < 3.42 < 4.16 < 3.31 < 3.00 < 3.43 Fe-59 < 11.2 < 10.3 < 14.7 < 8.69 < 9.65 < 10.5 Zn-65 < 6.85 < 8.19 < 12.7 < 7.54 < 4.02 < 8.60 Co-60 < 2.94 < 3.01 < 5.51 < 3.98 < 3.34 < 3.77 K-40 288.3 +/- 19.0 100.4 +/- 15.4 329.2 +/- 29.8 90.0 +/- 17.6 90.4 +/- 13.8 166.9 +/- 19.5 Ba/La-140 < 9.75 < 10.9 < 11.7 < 9.70 < 6.11 < 11.5 Nuclide July August September October November December 1-131 < 13.4 < 14.6 < 8.80 < 12.8 < 12.0 < 13.4 Cs-134 < 2.15 < 4.34 < 2.31 < 3.86 < 4.24 < 1.67 Cs-137 < 2.69 < 3.94 < 3.11 < 3.28 < 4.31 < 2.05 Zr-95 < 6.27 < 8.48 < 7.28 < 6.91 < 9.16 < 5.28 Nb-95 < 4.43 < 4.26 < 3.66 < 4.83 < 5.30 < 3.23 Co-58 < 3.39 < 3.73 < 3.22 < 3.74 < 5.06 < 2.71 Mn-54 < 3.18 < 3.89 < 3.74 < 3.00 < 4.51 < 2.41 Fe-59 < 9.77 < 13.2 < 10.7 < 13.0 < 13.4 < 7.68 Zn-65 < 3.72 < 10.4 < 8.43 < 4.78 < 11.1 < 5.30 Co-60 < 2.85 < 4.71 < 3.23 < 3.81 < 5.18 < 2.45 K-40 38.6 +/- 11.5 171.6 +/- 20.0 109.7 +/- 16.1 420.7 +/- 23.3 < 38.4 104.0 +/- 11.3 Ba/La-140 < 9.23 < 13.2 < 7.26 < 9.92 < 14.0 < 8.98

Optional Sample Location

- Corresponds to sample location noted on Figure 3.3-4 6-10 SM Mm -mm- M m -M M m m M - M

mmmmmm m mm m m m mm m m m mm m TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES (pCi/liter +/- 1 Sigma)

OSWEGO STEAM STATION * (08, CONTROL) **

Nuclide January February March I April May June 1-131 < 0.68 < 0.49 < 0.75 < 0.55 < 0.73 < 0.69 Cs-134 < 5.61 < 4.98 < 5.21 < 3.91 < 3.61 < 1.80 Cs-137 < 5.19 < 3.60 < 6.09 < 4.94 < 4.76 < 2.43 Zr-95 < 10.2 < 8.19 < 7.96 < 9.66 < 8.30 < 4.19 Nb-95 < 7.04 < 6.14 < 7.56 < 5.15 < 5.70 < 3.12 Co-58 < 5.77 < 5.13 < 5.99 < 5.74 < 5.01 < 2.68 Mn-54 < 5.62 < 4.82 < 4.86 < 5.26 < 4.73 < 2.14 Fe-59 < 16.8 < 13.0 < 17.3 < 1417 < 16.3 < 7.02 Zn-65 < 12.9 < 10.15 < 12.3 < 12.9 < 10.6 < 2.86 Co-60 < 5.21 < 3.54 < 6.43 < 6.70 < 4.22 < 2.12 K-40 282.4 +/- 30.9 165.8 +/- 26.57 < 61.6 < 51.8 < 29.6 < 21.8 BaiLa-140 < 13.3 < 13.0 < 13.6 < 11.9 < 11.8 < 5.80 Nuclide July August September October November December 1-131 < 0.57 < 0.62 < 0.65 < 0.47 < 0.78 < 0.99 Cs-134 < 2.93 < 5.48 < 2.79 < 2.86 < 3.07 < 2.57 Cs-137 < 3.26 < 5.33 < 3.87 < 3.76 < 3.89 < 2.55 Zr-95 < 5.42 < 11.07 < 7.41 < 8.91 < 8.95 < 4.80 Nb-95 < 4.57 < 7.09 < 5.60 < 5.88 < 5.12 < 3.50 Co-58 < 4.23 < 6.50 < 4.88 < 4.96 < 4.10 < 2.82 Mn-54 < 3.19 < 5.21 < 3.97 < 4.00 < 3.44 < 2.45 Fe-59 < 9.75 < 17.1 < 13.0 < 15.2 < 12.4 < 8.45 Zn-65 < 8.98 < 14.6 < 9.99 <, 10.4 < 12.2 < 3.69 Co-60 < 4.05 < 6.35 < 4.89 < 4.49 < 4.93 < 2.39 K-40 79.6 +/- 15.6 790.6 +/- 45.4 118.5 +/- 21.8 446.5 +/- 29.2 68.3 +/- 17.1 392.6 +/- 17.4 Ba/La-140 < 10.6 < 13.5 < 11.8 < 15.0 < 13.0 < 8.84

Sample Location required by ODCM

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

TABLE 6- 5 CONCENTRATION OF TRITIUM, STRONTIUM AND GAMMA EMITTERS IN GROUNDWATER SAMPLES (pCi/l +/- 1 sigma)

Indicator Date Tritium Sr-90 GAMMA EMITTERS Location* D I K-40 Mn-54 Co-58 Fe-59 Co-60 Cs-134 I Cs-137 Zn-65 Other t-1/7/08 <439 280 +/-28 <4.30 <3.71 <9.05 <3.81 <5.22 <5.15 <6.12 <LLD NMP2 4/7/08 <446 <106 <7.55 <9.09 <16.7 <9.36 <4.99 <6.77 <14.0 <LLD Depression 5/12/08 <445 924+/-58 <6.73 <5.93 <17.6 <5.76 <4.42 <7.11 <8.69 <LLD Cone 7/7/08 <442 <48 <6.29 <5.20 <10.3 <5.20 <7.18 <5.13 <18.3 <LLD 8/11/08 <1.4 9/19/08 <420 -

9/24/08 <416 161 +/-42 <6.10 <6.35 <20.7 <8.58 <5.79 <5.69 <21.8 <LLD 10/6/08 <415 Indicator Date Tritium Sr-90 GAMMA EMITTERS Location* K-40 Mn-54 Co-58 Fe-59 I Co-60 I Cs-134 I Cs-137 Zn-65 Other "

MW-1 6/2/08 <439 93.4+/-18 <4.35 <4.17 <8.49 <3.64 <2.85 <2.25 <6.35 <LLD MW-5 6/2/08 <439 152 ÷/- 26 <6.01 <5.63 <13.2 <5.61 <5.72 <6.08 <6.57 <LLD MW-1 9/29/08 <427 <1.1 36.0 +/-21 <4.80 <4.23 <10.2 <4.23 <5.07 <4.57 <5.05 <LLD MW-5 9/29/08 <427 <1.7 113 +/-19 <4.64 <4.02 <9.36 <4.23 <3.29 <2.76 <5.93 <LLD Control Date Tritium Sr-90 GAMMA EMITTERS Location* K-40 Mn-54 Co-58 Fe-59 [ Co-60 I Cs-134 Cs-137 Zn-65 Other_

6/2/08 I<439 <5.3

<GMX-MWI <4.80 <5.33 <10.9 4.34 <3.60 <4.68 <5.98 <LLD GMX-MW2 9/30/08 <426 GMX-MW1 9/29/08 <427 <0.9 943 +/- 58 <7.06 <6.64 <18.4 <8.39 <7.06 <8.21 <10.5 <LLD

Corresponds to sample location noted on Figure 3.3-6

" Plant related radionuclides 6-12 m m- - m M m m -M M m m M m -M m m

TABLE 6-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS

________ ________GROSS BETA ACTIVITY (pCi! W3 +/- 1 Sigma) _______________

Week End R-1* R-2 * [ R-3~ R-4~ R-5~

7 D-2* E** ' F** I G**

'Date [I_ _

1/2/2008 0.023 +/- 0.002 0.021 +/- 0.001 0.022 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.002 0.019 +/- 0.001 0.018 +/- 0.001 0.022 +L 0.002 0.019 +/- 0.001 1/8/2008 0.021 +/- 0.002 0.020 +/- 0.002 0.018 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.002 0.014 +/-. 0.001 0.022 +/- 0.002 0.019 +/- 0.002 0.016 +/- 0.002 1/15/2008 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001- 0.015 +/- 0.001 0.015 :L 0.001 0.013 +/- 0.001 0.013 +/- 0.001 1/22/2008 .0.019 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001, 0.016 +/-L 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 1/29/2008 10.025 +/- 0.002 0.025 +/- 0.002 0.018 :L 0.001 0.026 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.021 +/- 0.002 2/6/2008 0.019 +/- 0.002 0.019 +/- 0.001 0.019 +/- 0.002 0.017 +/- 0.001 0.018 +/- 0.001 No Sample 0.017 +/- 0.001. 0.021 +/- 0.001 0.019 +/- 0.002 2/12/2008 0.019 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.002 0.018 +/-L 0.001 0.020 +/- 0.002 0.021 +/- 0.001 0.024 +/- 0.002 0.022 +/- 0.002 0.018 +/- 0.001 2/19/2008 0.019 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.002 0.022 +/-L 0.002 0.020 +/- 0.001 0.019 +/- 0.002 0.020 +/- 0.002 0.020 +/- 0.002 0.019 +L 0.001 2/26/2008 0.018 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.021 +/- 0.002 0.018 +/- 0.001 3/4/2008 0.015 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 3/11/2008 0.017 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.002 0.018 + 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.002 0.016 +/- 0.001 3/18/2008 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 3/25/2008 0.014 +/- 0.001. 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 4/1/2008 0.012 +/- 0.001 0.016 +/-L 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.017 .+0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.018 +/- 0.001 0.012 +/- 0.001 4/8/2008 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0.001 0.017 +0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 4/15/2008 0.008 +/- 0.001 0.010 +/- 0.001 0.007 1 0.001 0.009 +/- 0.001 0.008 +/-0.001 0.008 +/- 0.001 0.006 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 4/22/2008 0.026 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.026 +/- 0.002 0.026 +0.002 0.024 +/- 0.002 0.023 +/- 0.002 0.024 +/- 0.002 0.021 +/- 0.001 4/29/2008 0.018 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.018 :10.001 0.015 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 5/6/2008 0.019 +/- 0.001 0.016 +/- 0.001 0.021 +/- 0.002 0.016 +/- 0.001 0.017 +/-0.001- 0.013 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 5/13/2008 0.013 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 5/20/2008 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001. 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/-L 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 5/28/2008 0.007 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/-L 0.001 0.006 +/- 0.001 0.007 +/- 0.001 0.004 +/- 0.001 0.008 +/- 0.001 6/3/2008 0.015 +/- 0.001 0.013 +/- 0,001 0.011 +/- 0.001 0.016 +/- 0.001 0.012 +0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 6/10/2008 0.013 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001. 0.015 +/- 0.001 0.011 +/-0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 6/17/2008 0.017 +/- 0.001 0.014 .+/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/-0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 6/24/2008 10.010 +/- 0.001 10.008 +/- 0.001 10.009 +/- 0.001 10.010 +/- 0.001 10.009 +0.001 10.012 +/- 0.001 10.007 +/- 0.001 10.007 +/- 0.001 10.008 +/- 0.001

Sample location required by ODCM

- Optional sample location 6 -13

TABLE 6-6 (continue)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - OFFSITE SAMPLE LOCATIONS GROSS BETA ACTIVITY (pCi/ m 3 =l 1 Sigma)

[WeekDae Date End-J II1 R-1* R-2* R-3* R-4 j R-5 j

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

7/1/2008 0.016 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.011 +/- 0.001 0.013 + 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 7/8/2008 0.014 +/- 0.001 0.014 + 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 7/15/2008 0.010 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 7/22/2008 0.025 +/- 0.002 0.027 +/- 0.002 0.024 +/- 0.002 0.023 +/- 0.002 0.021 +/- 0.001 0.022 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.028 +/- 0.002 7/29/2008 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.001

.8/5/2008 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/-- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 8/12/2008 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 8/19/2008 0.017 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 8/26/2008 0.014 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 9/3/2008 0.014 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.002 0.013 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 9/9/2008 0.021 +/- 0.002 0.020 +/- 0.002 0.023 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 0.022 +/- 0.002 0.017 +/- 0.002 0.020 +/- 0.002 0.023 +/- 0.002 9/16/2008 0.011 +/- 0.001 0.013 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 9/23/2008 0.013 +/- 0.001 0.013 + 0.001 0.010 + 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.011 1 0.001 0.015 +/- 0.001 9/30/2008 0.018 +/- 0.002 0.013 +/- 0.001 0.016 +/- 0.002 0.017 +/- 0.002 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 10/7/2008 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 10/14/2008 0.025 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0.001 0.020 1 0.001 0.021 +/- 0.002 0.021 +/- 0.001 0.019 +/- 0.001 0.019 + 0.001 0.024 +/- 0.002 10/21/2008. 0.013 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 1 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 10/28/2008 0.010 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.004 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010. 0.001 0.012 +/- 0.001 11/4/2008 0.018 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 11/12/2008 0.023 +/- 0.001 0.021 +/- 0.001 0.021 +/- 0.001 0.023 +/- 0.001. 0.022 +/- 0.001 0.018 +/- 0.001 0.020 +/- 0.001 0.018 +/- 0.001 0.023 +/- 0.001 11/18/2008 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.008 +/- 0.001 11/25/2008 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 + 0.001 0.012 +/- 0.001 12/2/2008 0.015 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 12/9/2008 0.018 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 12/16/2008 0.019 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 12/23/2008 0.022 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.001 0.019 +/- 0.001 0.023 +/- 0.002 0.021 +/- 0.001 0.022 +/- 0.002, 0.020 +/- 0.001 0.023 +/- 0.002 12/30/2008 0.026 +/- 0.002 0.030 +/- 0.002 0.025 +/- 0.002 0.026 +/- 0.002 0.031 +/- 0.002 0.026 +/- 0.002 0.027 +/- 0.002 0.032 +/- 0.002 0.026 + 0.002

Sample location required by ODCM

- Optional sample location 6- 14 mim mmm mmm M M m mm M M M m M

- m -m---

m m m m - m m mn TABLE 6-7 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS GROSS BETA ACTIVITY (pCi/ m 3 +/- 1 Sigma)

Week End Date JH D G**

1/7/2008 0.019 - 0.002 0.020 +/- 0.002 0.022 - 0.002 0.022 + 0.002 0.017 + 0.001 0.020 +/- 0.002 1/14/2008 0.010 - 0.001 0.014 - 0.001 0.014 - 0.001 0.011 - 0.001 0.014 - 0.001 0.012 - 0.001 1/21/2008 0.018 - 0.001 0.016 - 0.001 0.019 - 0.002 0.019 - 0.002 0.016 - 0.001 0.018 - 0.001 1/28/2008 0.022 - 0.002 0.021 - 0.002 0.021 - 0.002 0.018 - 0.001 0.023 - 0.002 0.023 - 0.002 2/4/2008 0.024 - 0.002 0.022 +/- 0.002 0.026 - 0.002 0.0233 0.002 0.019 +/- 0.001 0.020 - 0.002 2/11/2008 0.017 - 0.001 0.016 - 0.001 0.021 - 0.001 0.014 - 0.001 0.016 - 0.001 0.019 - 0.001 2/18/2008 0.022 + 0.002 0.023 - 0.002 0.021 - 0.001 0.021 - 0.001 0.023 - 0.002 0.023 - 0.002 2/25/2008 0.019 - 0.001 0.018 - 0.001 0.019 - 0.001 0.014 - 0.001 0.020 - 0.001 0.018 - 0.001 3/3/2008 0.017 +/- 0.001 0.017 - 0.001 0.014 - 0.001 0.018 - 0.001 0.017 + 0.001 0.015 - 0.001 3/10/2008 0.016 + 0.001 0.017 - 0.001 0.018 - 0.001 0.017 - 0.001 0.020 - 0.001 0.018 - 0.001 3/17/2008 0.015 - 0.001 0.016 - 0.001 0.019 - 0.002 0.015 - 0.001 0.012 - 0.001 0.015 +/- 0.001 3/24/2008 0.015 - 0.001 0.014 - 0.001 0.013 - 0.001 0.017 - 0.001 0.019 + 0.001 0.014 - 0.001 3/31/2008 0.014 - 0.001 0.016 - 0.001 0.018 - 0.001 0.017 + 0.001 0.014 - 0.001 0.016 - 0.001 4/7/2008 0.015 - 0.001 0.013 - 0.001 0.013 - 0.001 0.014 - 0.001 0.014 - 0.001 0.016 +/- 0.001 4/14/2008 0.010 - 0.001 0.009 - 0.001 0.010 - 0.001 0.006 + 0.001 0.008 - 0.001 0.008 - 0.001 4/21/2008 0.021 - 0.002 0.018 - 0.001 0.016 - 0.001 0.021 - 0.002 0.022 - 0.002 0.021 - 0.002 4/28/2008 0.020 - 0.002 0.023 - 0.002 0.021 - 0.002 0.021 - 0.002 0.018 - 0.001 0.022 - 0.002 5/5/2008 0.014 - 0.001 0.014 - 0.001 0.015 - 0.001 0.015 - 0.001 0.014 - 0.001 0.016 - 0.001 5/12/2008 0.016 - 0.001 0.013 - 0.001 0.015 - 0.001 0.012 - 0.001 0.014 - 0.001 0.012 - 0.001 5/19/2008 0.012 - 0.001 0.011 - 0.001 0.011 - 0.001 0.012 - 0.001 0.011 - 0.001 0.009 - 0.001 5/27/2008 0.007 - 0.001 0.009 - 0.001 0.007 - 0.001 0.013 - 0.001 0.008 - 0.001 0.009 - 0.001 6/2/2008 0.011 - 0.001 0.011 +/-- 0.001 0.010 - 0.001 0.014 - 0.001 0.013 - 0.001 0.014 - 0.001 6/9/2008 0.015 +/-- 0.001 0.013 - 0.001 0.013 - 0.001 0.012 - 0.001 0.012 - 0.001 0.013 - 0.001 6/16/2008 0.014 - 0.001 0.012 - 0.001 0.016 - 0.001 0.011 + 0.001 0.012 - 0.001 0.014 - 0.001 6/23/2008 0.010 - 0.001 0.009 - 0.001 0.010 + 0.001 0.012 - 0.001 0.010 - 0.001 0.009 - 0.001 6/30/2008 0.018 - 0.001 0.016 - 0.001 0.014 +/- 0.001 0.014 - 0.001 0.017 - 0.001 0.015 - 0.001

- Optional sample location 6-15

TABLE 6-7 (Continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ONSITE SAMPLE LOCATIONS GROSS BETA ACTIVITY (pCi/ m 3 +/- 1 Sigma)

Week End -1 **

"DateI G** H** K**

D[

D-1**

7/7/2008 0.014 + 0.001 0.015 +/- 0.001 0.014 + 0.001 0.013 + 0.001 0.015 +/- 0.001 0.012 + 0.001 7/14/2008 0.014 +/- 0.001 0.014 + 0.001 0.016 + 0.001 0.018 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 7/21/2008 0.023 +/- 0.002 0.024 +/-- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.023 +/- 0.002 0.022 +/- 0.001 7/28/2008 0.017 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 8/4/2008 0.018 +/- 0.001 0.014 +/- 0.001 0.010 + 0.001 0.014 + 0.001 0.013 +/- 0.001 0.015 +/- 0.001 8/11/2008 0.008 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.011 - 0.001 0.012 +/- 0.001 0.013 +/- 0.001 8/18/2008 0.012 + 0.001 0.014 + 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.013 - 0.001 0.015 +/- 0.001 8/25/2008 0.015 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 9/2/2008 0.015 + 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.014 - 0.001 0.013 + 0.001 0.011 +/- 0.001 9/8/2008 0.022 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.002 9/15/2008 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.016 + 0.001 0.016 +/- 0.001 0.015 +/- 0.001 9/22/2008 0.016 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.002 0.015 +/- 0.002 0.010 +/- 0.001 0.012 +/- 0.001 9/29/2008 0.019 + 0.002 0.018 +/- 0.002 0.017 +/- 0.002 0.019 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 10/6/2008 0.010 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.008 + 0.001 0.009 +/- 0.001 0.010 +/- 0.001 10/13/2008 0.015 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 10/20/2008 0.021 +/- 0.001 0.017 +/- 0.001 0.018 + 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.001 10/27/2008 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.012 + 0.001 0.012 + 0.001 0.011 +/- 0.001 11/3/2008 0.014 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 11/10/2008 0.028 +/- 0.002 0.030 +/- 0.002 0.030 +/- 0.002 0.031 +/- 0.002 0.032 +/- 0.002 0.031 +/- 0.002 11/17/2008 0.008 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.007 + 0.001 0.010 +/- 0.001 0.008 +/- 0.001 11/24/2008 0.009 +/- 0.001 0.009 +/- 0.001 0.009 + 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.012 +/- 0.001 12/1/2008 0.017 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.016 + 0.001 0.017 +/- 0.001 0.015 +/- 0.001 12/8/2008 0.016 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 0.016 + 0.001 12/15/2008 0.017 +/- 0.001 0.016 +/- 0.001 0.021 +/- 0.001 0.018 +/- 0.001 0.018 +/- 0.001 0.022 +/- 0.002 12/22/2008 0.023. 0.002 0.021 +/- 0.001 0.022 +/- 0.002 0.021 +/- 0.001 0.021 +/- 0.002 0.0233 0.002 12/29/2008 0.025 +/- 0.002 0.025 +/- 0.002 0.025 +/- 0.002 0.029 +/- 0.002 0.028 +/- 0.002 0.026 +/- 0.002

- Optional sample location 6-16 m---- M - m m m Mm m m m m - m M

mmmm m m m mmmmimmmmm) mm m mn TABLE 8 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS 1-131 ACTIVITY (pCi/ m3+/- 1 Sigma)

Week End R1 R-2* R-3* R-4 R-5* D-22** E** F ** G**

Date 1 01/02/08 < 0.007 < 0.027 < 0.033 < 0.033 < 0.037 < 0.009 < 0.022 < 0.028 < 0.021 01/08/08 < 0.039 < 0.028 < 0.021 < 0.031 < 0.037 < 0.027 < 0.032 < 0.038 < 0.024 01/15/08 < 0.028 < 0.014 < 0.009 < 0.016 < 0.021 < 0.023 < 0.009 < 0.021 < 0.035 01/22/08 < 0.030 < 0.033 < 0.029 < 0.023 < 0.026 < 0.027 < 0.018 < 0.033 < 0.016 01/29/08 < 0.039 < 0.028 < 0.032 < 0.017 < 0.038 < 0.025 < 0.034 < 0.018 < 0.038 02/05/08 < 0.035 < 0.023 < 0.025 < 0.017 < 0.022 No Sample < 0.017 < 0.015 < 0.027 02/12/08 < 0.008 < 0.025 < 0.025 < 0.022 < 0.007 < 0.015 < 0.026- < 0.028 < 0.031 02/19/08 < 0.029 < 0.027 < 0.026 < 0.042 < 0.033 < 0.020 < 0.029 < 0.039 < 0.031 02/26/08 < 0.027 < 0.018 < 0.023 < 0.026 < 0.020 < 0.019 < 0.022 < 0.022 < 0.021.

03/04/08 < 0.050 < 0.026 < 0.031 < 0.033 < 0.019 < 0.013 < 0.020 < 0.008 < 0.018 03/11/08 < 0.038 < 0.022 < 0.021 < 0.023 < 0.030 < 0.026 < 0.017 < 0.020 < 0.018 03/18/08 < 0.039 < 0.018 < 0.020 < 0.023 < 0.034 < 0.020 < 0.032 < '0.027 < 0.042 03/25/08 < 0.018 < 0.031 < 0.037 < 0.020 < 0 .021 < 0.025 < 0.037 < 0.030 < 0.024 04/01/08 < 0.043 < 0.018 < 0.027 < 0.037 < 0.025 < 0.022 < 0.026 < 0.022 < 0.027 04/08/08 < 0.033 < 0.028 < 0.023 < 0.029 < 0.020 < 0.025 < 0.028 < 0.041 < 0.005 04/15/08 < 0.027 < 0.029 < 0.019 < 0.017 < 0.028 < 0.018 < 0.030 < 0.028 < 0.014 04/22/08 < 0.023 < 0.034 < 0.020 < 0.005 < 0.022 < 0.036 < 0.019 < 0.031 < 0.005 04/29/08 < 0.030 < .0.022 < 0.017 < 0.026 < 0.028 < 0.030 < 0.021 < 0.020 < 0.021 05/06/08 < 0.025 < 0.041 < 0.015 < 0.023 < 0.027 < 0.030 < 0.033 < 0.022 < 0.022 05/13/08 < 0.023 < 0.034 < 0.022 < 0.025 < 0.023- < 0.028 < 0.027 < 0.023 < 0.019 05/20/08 < 0.028 < '0.031 < 0.019 < 0.020 < 0.018 < 0.024 < 0.005 < 0.029 < 0.005 05/28/08 < 0.021 < 0.020 < 0.020 < 0.023 < 0.016 < 0.026 < 0.027 < 0.019 < 0.020 06/03/08 < 0'037 < 0.032 < 0.027 < 0.025 < 0.023 < 0.034 < 0.021 < 0.028 < 0.021 06/10/08 < 0.027 < 0.030 < 0.016 < 0.018 < 0.018 <. 0.028 < 0.006 < 0.025 < 0.028

06/i7/08 < 0.019 < .0.029 < 0.015 < 0.029 < 0.018 < 0.032 . < 0.021 - < 0.019 < 0.024 06/24/08 < 0.031 < 0.033 < 0.037 < 0.041 < 0.024 < 0.042 < 0.033 < 0.024 < 0.037

Sample location required by ODUM uptional sample location 6-17

TABLE 6-8 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - OFFSITE SAMPLE LOCATIONS -

1-131 ACTIVITY (pCi/ m3 1 Sigma) '

WeekEnd R-1

R-2

R-3

R-4

R-5

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

Date 07/01/08 < 0.031 < 0.015 < 0.016 < 0.035 < 0.023 < 0.034 < 0.023 < 0.026 < 0.028 07/08/08 < 0.020 < 0.013 < 0.018 < 0.018 < 0.019 < 0.031 < 0.015 < 0.017 < 0.018 07/15/08 < 0.024 < 0.028 < 0.019 < 0.025 < 0.025 < 0.024 < 0.022 < 0.019 < 0.027 07/22/08 < 0.024 < 0.023 < 0.027 < 0.005 < 0.021 < 0.023 < 0.018 < 0.023 < 0.022 07/29/08 < 0.022 < 0.022 < 0.013 < 0.017 < 0.020 < 0.027 < 0.026 < 0.026 < 0.01-3 08/05/08 < 0.035 < 0.015 < 0.026 < 0.033 <.0.014 < 0.029 < 0.020 < 0.023 < 0.020 08/i2/08 < 0.026 < 0.048 < 0.019 < 0.023 < 0.022 < 0.020 < 0.021 < 0.044 < 0.022 08/19/08 < 0.019 < 0.027 < 0.025 < 0.024 < 0.040 < 0.023 < 0.017 < 0.022 < 0.028 08/26/08 < 0.026 < 0.023 < 0.006 < 0.022 < 0.027 < 0.029 < 0.017 < 0.021 < 0.017 09/03/08 < 0.020 < 0.021 < 0.023 < 0.022 < 0.038 < 0.018 < 0.016 < 0.022 < 0.022 09/09/08 < 0.033 < 0.027 < 0.028 < 0.032 < 0.049 < 0.016 < 0.047 < 0.042 < 0.049 09/16/08 < 0.021 < 0.022 < 0.033 < 0.035 < 0.024 < 0.025 < 0.023 < 0.034 < 0.028 09/23/08 < 0.044 < 0.023 < 0.019 < 0.029 < 0.027 < 0.031 < 0.022 ,< 0.020 < 0.024 09/30/08 < 0.024 < 0.024 < 0.035 < 0.030 < 0.034 < 0.034 < 0.032 < 0.032 < 0.028 10/07/08 < 0.034 < 0.020 < 0.024 < 0.025 < 0.026 < 0.039 < 0.023 < 0.019 < 0.024 10/14/08 < 0.034 < 0.043 < 0.014 < 0.023 < 0.023 < 0.028 < 0.031 < 0.041 < 0.014 10/21/08 < 0.036 < 0.015 < 0.005 < 0.033 < 0.006 < 0.022 < 0.026 < 0.023 < 0.024 10/28/08 < 0.021 < 0.030 < 0.015 < 0.016 < 0.021 < 0.014 < 0.026 < 0.017 < 0.011 11/04/08 < 0.022 < 0.041 < 0.027 < 0.019 < 0.025 < 0.027 < 0.032 < 0.020 < 0.042 11/12/08 < 0.021 < 0.023 < 0.015 < 0.013 < 0.020 < 0.028 < 0.020 < 0.020 < 0.013 11/18/08 < 0.029 < 0.036 < 0.023 < 0.025 < 0.035 < 0.039 < 0.030 < 0.030 < 0.035 11/25/08 < 0.023 < 0.034 < 0.012 < 0.022 < 0.025 < 0.021 < 0.025 < 0.017 < 0.026 12/02/08 < 0.004 < 0.030 < 0.012 < 0.017 < 0.019 < 0.027 < 0,022 < 0.026 < 0.025

.12/09/08 < 0.017 < 0.033 < 0.020 < 0.009 < 0.015 < 0.020 < 0.021 < 0.018' < 0.028 12/16/08 < 0.020 < 0.018 < 0.014 < 0.016 < 0.018 < 0.023 < 0.024 < 0.028 < 0.016 12/23/08 < 0.015 < 0.021 < 0.012 < 0.015 < 0.018 < 0.021 < 0.020 < 0.012 < 0.025 12/29/09 < 0.019 < 0.019 < 0.013 < 0.015 < 0.027 < 0.015 < 0.018 < 0.024 < 0.025 Sample location required by OlNLIVl uptional sample location 6- 18 m m m- -m mmm mm mmmmmm m m m m

m----- m Mm m M m M M M M M MM TABLE 6-9 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS 1-131 ACTIVITY (pCi/ m3 1 Sigma)

Week End Date D-1 **G** H** I J** K**

01/07/08 < 0.023 < 0.020 < 0.019 < 0.021 < 0.027 < 0.025 01/14/08 < 0.008 < 0.023 < 0.027 < 0.021 < 0.023 < 0.024 01/21/08 < 0.030 < 0.021 < 0.017 < 0.034 < 0.022 < 0.025 01/28/08 < 0.023 < 0.026 < 0.024 < 0.020 < 0.026 < 0.024 02/04/08 < 0.029 < 0.020 < 0.028 < 0.020 < 0.021 < 0.023 02/11/08 < 0.029 < 0.026 < 0.028 < 0.027 < 0.024 < 0.013 02/18/08 < 0.036 < 0.033 < 0.035 < 0.022 < 0.018 < 0.022 02/25/08 < 0.021 < 0.021 < 0.033 < 0.016 < 0.005 < 0.026 03/03/08 < 0.017 < 0.027 < 0.048 < 0.005 < 0.019 < 0.038 03/10/08 < 0.034 < 0.014 < 0.025 < 0.015 < 0.041 < 0.020 03/17/08 < 0.048 < 0.020 < 0.019 < 0.025 < 0.040 < 0.027 03/24/08 < 0.055 < 0.035 < 0.016 < 0.030 < 0.055 < 0.018 03/31/08 < 0.047 < "-0.022 < 0.021 < 0.032 < 0.033 < 0.015 04/07/08 < 0.024 < -0.047 < 0.019 < 0.025 < 0.015 < 0.029 04/14/08 < 0.029 < 0.032 < 0.020 < 0.041 < 0.022 < 0.032 04/21/08 < 0.027 < 0.022 < 0.029 < 0.023 < 0.023 < 0.023 04/28/08 < 0.032 < 0.032 < 0.023 < 0.025 < 0.026 < 0.022 05/05/08 < 0.034 < 0.026 < 0.010 < 0.026 < 0.005 < 0.031 05/12/08 < 0.023 < 0.019 < 0.019 < 0.026 < 0.029 < 0.032 05/19/08 < 0.023 < 0.027 < 0.023 < 0.014 < 0.023 < 0.034 05/27/08 < 0.020 < 0.031 < 0.014 < 0.020 < 0.014 < 0.013 06/02/08 < 0.026 < 0.043 < 0.025 < 0.030 < 0.030 < 0.039 06/09/08 < 0.029 < 0.019 < 0.028 < 0.016 < 0.028 < 0.034 06/16/08 < 0.024 < 0.026 < 0.022 < 0.020 < 0.019 < 0.019 06/23/08 < 0.023 < 0.026 < 0.021 < 0.020 < 0.019 < 0.022 06/30/08 < 0.029 < 0.021 < 0.005 < 0.026 < 0.023 < 0.024

- Optional sample location 6-19

TABLE 6-9 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ONSITE SAMPLE LOCATIONS 1-131 ACTIVITY (pCi/ m3 1 Sigma)

Week End Date D-1 ** G** H** I** J** K**

07/07/08 < 0.027 < 0.035 < 0.015 < 0.014 < 0.022 < 0.021 07/14/08 < 0.032 < 0.022 < 0.017 < 0.034 < 0.030 < 0.026 07/21/08 < 0.021 < 0.033 < 0.021 < 0.020 < 0.025 < 0.032 07/28/08 < 0.018 < 0.031 < 0.018 < 0.020 < 0.021 < 0.017 08/04/08 < 0.026 < 0.022 < 0.027 < 0.029 < 0.022 < 0.024 08/11/08 < 0.021 < 0.036 < 0.006 < 0.024 < 0.035 < 0.030 08/18/08 < 0.016 < 0.035 < 0.015 < 0.017 < 0.030 < 0.022 08/25/08 < 0.026 < 0.026 < 0.017 < 0.026 < 0.014 < 0.023 09/02/08 < 0.018 < 0.017 < 0.020 < 0.016 < 0.031 < 0.016 09/08/08 < 0.040 < 0.031 < 0.030 < 0.024 < 0.034 < 0.023 09/15/08 < 0.035 < 0.019 < 0.023 < 0.019 < 0.036 < 0.025 09/22/08 < 0.034 < 0.005 < 0.030 < 0.062 < 0.030 < 0.032 09/29/08 < 0.032 < 0.029 < 0.028 < 0.029 < 0.031 < 0.037 10/06/08 < 0.018 < 0.027 < 0.047 < 0.025 < 0.018 < 0.024 10/13/08 < 0.023 < 0.033 < 0.020 < 0.018 < 0.030 < 0.036 10/20/08 < 0.031 < 0.034 < 0.026 < 0.029 < 0.029 < 0.022 10/27/08 < 0.025 < 0.021 < 0.017 < 0.019 < 0.023 < 0.024 11/03/08 < 0.017 < 0.037 < 0.021 < 0.026 < 0.030 < 0.019 11/10/08 < 0.022 < 0.034 < 0.021 < 0.017 < 0.025 < 0.018 11/17/08 < 0.019 < 0.034 < 0.032 < 0.033 < 0.032 < 0.028 11/24/08 < 0.021 < 0.040 < 0.027 < 0.020 < 0.020 < 0.032 12/01/08 < 0.023 < 0.015 < 0.029 < 0.017 < 0.035 < 0.023 12/08/08 < 0.028 < 0.016 < 0.034 < 0.018 < 0.023 < 0.024 12/15/08 < 0.019 < 0.021 < 0.016 < 0.016 < 0.023 < 0.023 12/22/08 < 0.018 < 0.022 < 0.014 < 0.016 < 0.024 < 0.024 12/29/08 < 0.019 < 0.036 < 0.021 < 0.015 < 0.019 < 0.023

- Optional sample location 6 - 20

- - - m

m- M M M M M M M M M M M

M M M M M M M M M M mM m M M M MM TABLE 6-10 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES (10E-3 pCi/ m3 +/- 1 Sigma)

OFFSITE SAMPLE LOCATIONS - 1ST QTR 2008 Nuclide R-1

R-2

R-3

R-4* R-55* D-22** E** F** G**

Be-7 115.4 +/- 14.0 106.6 +/- 12.8 124.3 +/- 14.3 122.6 +/- 13.7 128.9 +/- 13.9 115.1 +/- 17.0 95.8 +/- 12.9 120.6 +/- 12.9 158.8 +/- 15.4 Cs-134 < 2.0 < 1.4 < 1.6 < 1.8 < 1.7 < 2.1 < 1.4 < 2.2 < 2.1 Cs-137 < 1.7 < 1.5 < 1.8 < 1.5 < 1.2 < 1.8 < 0.3 < 1.8 < 0.9 Zr-95 < 3.3 < 3.7 < 3.6 < 5.1 < 2.4 < 5.6 < 2.6 < 4.3 < 5.7 Nb-95 < 2.7 < 2.7 < 2.3 < 2.8 < 2.4 < 1.2 < 2.1 < 3.5 < 4.0 Co-58 < 2.0 < 1.6 < 1.6 < 1.9 < 2.0 < 2.8 < 2.3 < 1.4 < 2.0 Mn-54 < 1.6 < 1.4 < 1.2 < 2.2 < 1.5 < 3.2 < 1.4 < 1.3 < 1.9 Zn-65 < 3.1 < 0.9 < 5.5 < 5.9 < 3.4 < 6.2 < 4.0 < 2.9 < 1.1 Co-60 < 0.6 < 1.3 < 2.5 < 1.7 < 1.3 < 3.5 < 1.6 < .1.4 < 1.7 K-40 < 5.9 < 13.5 51.7 +/- 10.8 48.7 +/- 9.4 < 16.8 75.1 +/- 15.3 < 5.9 < 14.3 < 22.1

" -OFFSITE SAMPLE LOCATIONS - 2ND QTR Nuclide R-1

R-2* R-3* R-4* R-55** D-2** E** F** G**

Be-7 116.0 +/- 12.1 84.4 +/- 14.1 104.3 +/- 11.8 116.9 +/- 12.1 121.4 +/- 13.3 108.5 +/- 13.3 125.4 +/- 13.1 120.2 +/- 17.2 115.5 +/- 12.2 Cs-134 < 1.6 < 1.9 < 2.2 < 1.6 < 1.8 < 2.3 < 1.9 < 2.0 <" 1.9, Cs-137 < 0.7 < 2.0 < 1.2 < 0.7 < 1.4 < 1.4 < 1.4 < 1.5 < 0.8 Zr-95 < 2.2 < 4.3 < 0.9 < 3.2 < 3.9 < 3.9 < 4.1 < 4.5 < 0.9" Nb-95 < 3.0 < 2.8 < 2.3 < 2.6 < 3.2 < 3.4 < 3.3 < 3.7 < 1.8

Co-58 < 2.1 < 3.8 < 1.4 < 1.2 < 1.7 < 2.7 < 1.3 < 3.0 < 1.7 Mn-54 < 1.5 < 2.1 < 1.2 < 1.3 < 1.2 < 1.7 < 1.5 < 2.1 < 1.2 Zn-65 < 4.3 < 5.6 < 4.1 < 4.1 < 3.3 < 4.2 < 4.0 < 7.7 < 1.0 Co-60. < 1.8 < 0.8 < 0.5 < 1.6 < 1.4 -* < 1.7 < 1.2 < 2.7. < 1.8 K-40 < 12.0 96.3 +/- .18.0 < 5.2 -< 15:7. < -15.1 . 34.8- +/- 8.0 < 20.0 96.5 +/-+- 19.3 < 17.7

Sample location required by ODCM

Optional sample location 6-21

TABLE 6-10 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES (10E-3 pCi/ m3 - 1 Sigma)

OFFSITE SAMPLE LOCATIONS - 3RD QTR Nuclide R-1* R-2 j R-3 j R-4 j R-5 j D-2** j E ** F ** G**

Be-7 94.5 +/- 14.5 115.0 +/- 12.2 140.4 +/- 12.9 104.7 +/- 12.2 97.0 +/- 12.5 102.2 +-/- 12.6 141.2 +/- 17.6 107.9 +/- 11.8 124.9 +/- 13.4 Cs-134 < 2.5 < 1.4 < 1.5 < 1.6 <. 1.7 < 1.9 < 1.9 < 1.7 <. 1.1 Cs-137 < 1.8 < 1.0 < 0.9 < 1.0 < 1.4 < 1.0 < 2.1 < 0.8 < 1.2 Zr-95 < 3.5 < 3.7 < 2.9 < 3.7 < 5.5 < 3.8 < 4.4 < 2.9 < 3.2 Nb-95 < .5.5 < 1.9 < 2.3 < 0.7 < 3.4 < 21.8 < 5.0 < 1.9 < 2.2 Co-58 < 2.9 < 2.4 < 1.9 < 2.3 < 1.4 < 2.1 < 3.2 < 1.4 < 1.8 Mn-54 < 1.8 < 1.2 < 0.9 < 1.0 < 1.8 < 1.9 < 2.1 < 1.0 < 11 Zn-65 < 7.0 < 2.8 < 4.2 < 3.5 < 2.9 < 4.7 < 6.9 < 3.5 < 4.0 Co-60 < 0.8 < 1.4 < 1.9 < 1.5 < 0.6 < 1.5 < 2.1 < 1.8 < 1.2 K-40 84.4 +/- 17.3 < 14.1 < 16.2 41.9 +/- 9.1 63.7 +/- 11.5 51.4 +/- 10.4 101.3 +/- 17.8 < 23.1 < 12.3 OFFSITE SAMPLE LOCATIONS - 4TH QTR Nuclide R-1* R-22* R-3 R-4* R-5* D-2** E** F **G Be-7 91.9 +/- 11.8 54.2 +/- 11.3 92.0 +/- 13.8 91.9 +/- 11.7 71.0 +/- 10.1 74.2 +/- 10.7 90.7 +/- 11.5 92.7 +/- 11.4 64.7 +/- 11.2 Cs-134 < 2.1 < 1.5 < 2.4 < 1.8 < 1.5 < 1.8 < 2.2 < 2.3 < 1.9 Cs-137 < 1.8 < 1.1 < 1.8 < 1.0 .< 1.0 < 0.8 < 1.9 < 1.4 < 1.3 Zr-95 2.9 < 3.7 < 5.6 < 2.3 < 2.8 < 4.0 < 5.5 < 4.7 < 2.1 Nb-95 < 4.8 < 3.5 < 4.1 < 3.3 < 2.7 < 2.9 < 3.7 < 4.0 < 3.6 Co-58 < 2.5 < 1.3 < 2.5 < 2.0 < 1.9 < 1.7 < 24 < 2.2 < 1.5 Mn-54 <. 1.3 < 1.3 < 2.5 < 1.2 < 1.3 < 2.0 < 1.7 < 1.9 < 1.6 Zn-65 < 4.1 < 4.7 < 5.6 < 5.3 < 4.1 < 3.8 < 4.3 < 4.1 < 4.2 Co-60 < 2.0 < 1.5 < 0.8 < 2.3,, < 1.6 < 1.8 < 2.4 < 1.2 < 1.9 K-40 55.1 +/- 10.1 < 12.0 72.8 +/- 14.3 < 13.9 < 12.6 < 5.1 141.5 .+/- 10.0 62.2 +/- 10.0 < 16.7

Sample location required by ODCM

Optional sample location 6 - 22 m m m- m M mm--m MM M M M M

m- - - -m- m -D m- m-n m m m m m-m m-m TABLE 6-11 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES (10E-3 pCi/ m 3 +/- 1 Sigma)

ONSITE SAMPLE LOCATIONS - 1ST OTR Nuclide D-1 G** H** I** J** K**

Be-7 113.1 +/- 13.6 107.0 +/- 12.6 110.4 +/- 13.7 123.7 +/- 14.1 95.4 +/- 11.6 124.1 +/- 16.6 Cs-134 < 1.1 < 1.8 < 1.7 < 1.4 < 1.4 < 2.3 Cs-137 < 1.2 < 1.2 < 0.3 < 1.2 < 1.2 < 1.6 Zr-95 < 4.2 < 0.9 < 3.6 < 6.6 < 2.3 < 4.0 Nb-95 < 0.8 < 2.0 < 3.8 < 2.8 < 3.1 < 4.8 Co-58 < 0.6 < 2.0 < 2.3 < 2.8 < 1.9 < 3.3 Mn-54 < 1.4 < 1.8 < 1.7 < 1.9 < 1.2 < 2.1 Zn-65 < 3.1 < 2.8 < 5.8 < 4.8 < 4.1 < 5.5 Co-60 < 1.6 < 1.3 < 2.1 < 2.5 < 0.5 < 3.6 K-40 < 15.8 < 5.1 < 5.9 54.7 +/- 11.9 < 16.3 56.8 +/- 13.4 ONSITE SAMPLE LOCATIONS - 2ND QTR Nuclide D-1 "* G** H** I I K Be-7. 107.3 +/- 12.5 116.1 +/- 13.6 127.6 +/- 13.7 128.3 +/- 12.8 110.1 +/- 12.3 88.9 +/- 13.5 Cs-134 < 1.6 < 1.9 < 1.7 < 1.4 < 1.7 < 2.5 Cs-137 < 1.0 < 1.5 < 1.2 < 1.3 < 1.2 < 1.5 Zr-95 < 3.4 < 5.3 < 4.3 < 3.4 < 2.5 < 4.5 Nb-95 < 2.8 < 3.7 < 3.5 < 3.6 < 0.8 < 4.0 Co-58 < 1.3 < 2.8 < 1.9 < 2.1 < 2.1 < 2.7 Mn-54 < 1.2 < 1.5 < 2.0 < 1.7 < 1.0 < 1.8 Zn-65 < 2.9 < 4.6 < 4.0 < 2.9 < 4.8 < 4.4 Co-60 < 1.6 < 2.5 < 1.2 < 1.6 < 2.2 < 1.5 K-40 < 12.3 < 16.0 49.9 +/- 11.2 < 18.1 < 15.6 52.7 +/- 10.6

Optional sample location 6 - 23

TABLE 6-11 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES (10E-3 pCi/ m3 +/- 1 Sigma)

ONSITE SAMPLE LOCATIONS - 3RD OTR Nuclide D-1** G** H** 1* j* K**

Be-7 111.3 +/- 16.0 92.4 +/- 12.1 93.0 +/- 12.1 94.4 +/- 12.8 110.5 +/- 13.0 111.3 +/- 12.8 Cs-134 < 2.5 < 1.2 < 1.6 < 1.6 < 1.9 < 1.7 Cs-137 < 1.8 < 0.8 < 1.3 < 1.2 < 0.9 < 1.6 Zr-95 < 6.1 < 3.4 < 3.3 < 4.1 < 2.7 < 3.5 Nb-95 < 5.0 < 1.9 < 3.3 < 2.1 < 2.2 < 3.5 Co-58 < 2.5 < 0.5 < 1.3 < 1.8 < 2.0 < 2.6 Mn-54 < 2.3 < 0.4 < 1.3 < 1.0 < 1.8 < 1.7 Zn-65 < 3.8 < 2.8 < 4.9 < 4.5 < 4.6 < 4.5 Co-60 < 3.0 < 0.5 < 2.1 < 0.5 < 2.0 < 1.4 K-40 69.3 +/- 16.1 < 21.0 < 12.8 < 23.3 < 16.1 67.6 +/- 11.6 ONSITE SAMPLE LOCATIONS - 4TH QTR Nuclide D-1** J* H***

H_**_I_**__**

Be-7 82.8 +/- 10.5 82.0 +/- 14.5 95.1 +/- 11.2 76.6 +/- 11.3 91.0 +/- 11.6 73.6 +/- 11.6 Cs-134 < 1.3 < 1.5 < 1.7 < 1.6 < 1.8 < 2.2 Cs-137 < 1.5 < 1.1 < 1.2 < 0.8 < 1.2 < 1.3 Zr-95 < 3.4 < 5.9 < 3.7 < 3.6 < 4.3 < 4.2 Nb-95 < 2.2 < 4.4 < 2.4 < 2.3 < 3.2 < 3.5 Co-58 < 1.7 < 2.1 < 1.4 < 1.8 < 2.2 < 1.9 Mn-54 < 1.3 < 1.4 < 1.4 < 1.3 < 1.5 < 1.3 Zn-65 .3.3 < 8.1 < 1.0 < 3.1 < 5.0 < 5.7 Co-60 < 2.1 < 2.1 < 1.4 < 1.2 < 1.5 < 0.6 K-40 < 16.3 66.6 +/- 13.9 < 20.3 < 12.2 < 20.5 < 15.1

- Optional sample location 6 - 24

--- M M -. M M -

M M M M M M

m mm m mmmB m m m - m - m -

TABLE 6-12 DIRECT RADIATION MEASUREMENT RESULTS (mrem/std. Month = 1 Sigma)

Location Location First Second Third Fourth Direction &

Number Quarter Quarter Quarter Quarter Distance (1) 3 DI Onsite 12.6 - 0.5 13.6 +/- 0.8 10.0 +/- 0.4 13.8 +/- 0.6 690 at 0.2 miles 4 D2 Onsite 4.0 +/- 0.2 4.6 + 0.2 4.2 +/- 0.2 4.8 +/- 0.2 1400 at 0.4 miles 5 E Onsite 4.2 + 0.2 5.0 +/- 0.3 4.4 + 0.2 4.9 +/- 0.2 1750 at 0.4 miles 6 F Onsite 3.4 + 0.1 4.0 +/- 0.2 3.9 +/- 0.2 4.1 +/- 0.2 2100 at 0.5 miles 7* G Onsite 3.2 +/- 0.1 4.1 +/- 0.3 3.6 + 0.2 3.9 +/- 0.2 2500 at 0.7 miles 8* R5 Offsite Control 4.5 +/- 0.2 5.1 +/- 0.4 4.8 + 0.2 5.1 +/- 0.2 420 at 16.4 miles 9 Dl Offsite 3.3 +/- 0.1 4.2 +/- 0.2 4.0 +/- 0.1 4.4 +/- 0.2 800 at 11.4 miles 10 D2 Offsite 3.4 +/- 0.2 4.2 +/- 0.2 3.8 +/- 0.1 4.1 +/- 0.2 1170 at 9.0 miles 11 E Offsite 3.4 + 0.2 4.1 +/- 0.2 3.8 +/- 0.2 4.2 +/- 0.2 160' at 7.2 miles 12 F-Offsite 3.4 +/- 0.2 4.2 +/- 0.4 3.9 +/- 0.2 4.2 +/- 0.2 190l at 7.7miles 13 G Offsite 3.9 +/- 0.2 4.5 +/- 0.2 4.0 +/- 0.2 4.4 +/- 0.2 2250 at 5.3 miles 14* Demass Road Southwest Oswego - Control 3.9 +/- 0.1 4.8 +/- 0.6 4.2 +/- 0.2 4.4 +/- 0.2 2260 at 12.6 miles 15* Pole 66 West Boundary - Bible Camp 3.5 +/- 0.1 4.0 +/- 0.2 3.7 +/- 0.2 4.0 +/- 0.2 2370 at 0.9miles 18* Energy Information Center - Lamp Post (Southwest) 4.0 +/- 0.2 4.8 +/- 0.3 4.3 +/- 0.3 4.8 +/- 0.2 2650 at 0.4 miles 19 East Boundary-JAFNPP Pole 9 3.8 +/- 0.2 4.6 +/- 0.4 4.3 +/- 0.2 4.7 +/- 0.3 81' at 1.3 miles 23* H Onsite 4.6 +/- 0.2 5.2 +/- 0.2 4.8 +/- 0.2 5.4 +/- 0.3 700 at 0.8 miles 24 I Onsite 3.8 +/- 0.1 4.7 +/- 0.5 4.3 +/- 0.2 4.6 +/- 0.2 980 at 0.8 miles 25 JOnsite 3.8 +/- 0.1 4.6 +/- 0.2 4.2 .+/- 0.2 4.5 +/- 0.2 110' at 0.9 miles 26 K Onsite 3.7 +/- 0.2 4.5 +/- 0.4 4.2 +/- 0.2 4.4 +/- 0.2 1320 at 0.5 miles 27 North Fence North of Switchyard JAFNPP 20.0 +/- 1.1 19.9 +/- 1.4 16.0 +/- 0.6 21.4 +/- 1.1 600 at 0.4miles 28 North Light Pole North of Screenhouse JAFNPP 26.5 +/- 1.0 25.8 +/- 1.8 21.1 +/- 1.7 29.0 +/- 1.1 68' at 0.5miles 29 North Fence North of West Side 24.1 +/- 1.4 23.0 +/- 0.9 17.9 +/- 1.3 23.9 +/- 1.3 650 at 0.5 miles (1) Direction and distance based on NMP2 reactor building centerline.

TLD required by ODCM 6-25

TABLE 6-12 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS (mrem/std. Month +/- 1 Sigma)

Location Location First Second Third Fourth Direction &

Number Quarter Quarter Quarter Quarter Distance (1) 30 North Fence (Northwest) JAFNPP 11.5 + 0.9 12.3 +/- 1.0 9.7 + 0.5 11.9 +. 0.8 570 at 0.4 miles 31 North Fence (Northwest)NMP1 6.8 +/- 0.3 7.6 + 0.4 6.9 +/- 0.3 7.8 + 0.3 2760 at 0.2miles 39 North Fence Rad. Waste-NMP1 8.8 + 0.4 9.8 + 0.6 9.0 +/- 0.3 9.9 +/- 0.6 2920 at 0.2 miles 47 North Fence (Northeast) JAFNPP 6.6 + 0.2 6.6 +/- 0.4 6.1 +/- 0.2 7.0 + 0.3 690 at 0.6 miles 49* Phoenix, NY-Control 3.3 + 0.1 3.7 +/- 0.2 3.6 +/- 0.2 3.7 + 0.2 1630 at 19.8 miles 51 Liberty & Bronson Sts East of Oswego Steam Station 3.8 +/- 0.2 3.9 +/- 0.2 4.0 +/- 0.2 4.3 +/- 0.3 2330 at 7.4 miles 52 East 12th & Cayuga Sts Oswego School 3.5 + 0.2 3.8 +/- 0.2 3.8 +/- 0.2 4.1 +/- 0.2 2270 at 5.8 miles 53 Broadwell & Chestnut Sts Fulton High School 3.6 +/- 0.1 4.3 +/- 0.3 4.2 +/- 0.2 4.6 + 0.2 1830 at 13.7 miles 54 Liberty St & Co Rt. 16 Mexico High School 3.5 +/- 0.1 3.7 + 0.2 3.7 +/- 0.2 4.1 +/- 0.2 115' at 9.3miles 55 Gas Substation Co Rt. 5-Pulaski 3.3 +/- 0.1 3.9 +/- 0.4 3.8 +/- 0.1 4.1 +/- 0.2 750 at 13.0 miles 56* Rt. 104-New Haven School (Southeast Comer) 3.1 +/- 0.2 3.8 +/- 0.3 3.6 +/- 0.1 3.8 +/- 0.2 1230 at 5.3 miles 58* CoRt. 1A-Alcan (East of East Entrance Road) 3.9 + 0.1 4.5 + 0.2 4.3 +/- 0.2 4.6 +/- 0.2 2200 at 3.1 miles 75* Unit 2 North Fence North of Reactor Building 6.7 +/- 0.2 7.0 +/- 0.4 7.0 +/- 0.2 7.9 +/- 0.4 50 at 0.1 miles 76* Unit 2 North Fence North of Change House 5.0 +/- 0.3 5.8 +/- 0.3 5.3 + 0.2 6.2 +/- 0.2 250 at 0.1 miles 77* Unit 2 North Fence North of Pipe Building 5.9 +/- 0.2 6.4 +/- 0.2 5.9 +/- 0.2 7.0 +/- 0.3 450 at 0.2 miles 78* JAFNPP East of East Old Lay Down Area 3.7 +/- 0.2 4.6 +/- 0.2 4.3 +/- 0.2 4.7 +/- 0.2 900 at 1.0miles 79* Co Rt. 29 Pole #63 0.2 Miles South of Lake Road 3.3 +/- 0.2 4.2 +/- 0.4 3.7 +/- 0.2 4.0 +/- 0.2 1150 at 1.1 miles 80* Co Rt. 29 Pole #54 0.7 Miles South of Lake Road 3.4 +/- 0.1 4.2 +/- 0.3 4.0 +/- 0.2 4.3 +/- 0.2 1330 at 1.4 miles 81* Miner Road Pole #16 0.5 Miles West ofRt. 29 3.6 + 0.2 4.1 +/- 0.2 3.9 +/- 0.2 4.2 +/- 0.3 1590 at 1.6miles (1) Direction and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6 - 26

- m - -

M -rI-I M M M r nm M M M M

TABLE 6-12 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS (mrem/std. Month +/- 1 Sigma)

Location First Second Third Fourth Direction &

Number Quarter Quarter Quarter Quarter Distance (1) 82* Miner Road Pole # 1-1/2 1.1 Miles West ofRt. 29 3.5 +/- 0.1 4.0 +/- 0.2 3.8 +/- 0.2 3.9 - 0.2 181' at 1.6 miles 83* Lakeview Road Tree 0.45 Miles North of Miner Road 3.3 +/- 0.1 3.9 + 0.2 3.7 + 0.2 4.0 +/- 0.2 2000 at 1.2 miles 84* Lakeview Road North Pole #6117 200 feet (ft) North of 3.6 + 0. 4.3 + 0.3 4.1 + 0.2 4.2 +/- 0.2 225° a 1.1miles Lake Road 85* Unit l North Fence North ofWest Side ofScreen House. 7.5 +/- 0.3 8.7 +/- 0.6 7.8 + 0.3 8.7 +/- 0.5' 294- at 0.2 miles 86* Unit2NorthFenceNorthofWestSideofScreenHouse 7.0 +/- 0.4 8.1 +/- 0.5 7.28 + 0.4 8.2 +/- 0.5 3150 at 0.1 miles 87* Unit2NorthFenceNorthofEastSideofScreenHouse, 7.1 +/- 0.3 8.2 + 0.2 7.3 +/- 0.4 8.8 +/- 0.4 341' at 0.1 miles 88* Hickory Grove Road Pole #2 0.6 Miles North ofRt. 1 3.4 + 0.1 4.1--+ 0.2 3.9 + 0.1 4.3 +/- 0.2 970 at 4.5miles

.89* Leavitt RoadPole #16 0.4 Miles South ofRt. 1 3.7 + 0.1 4.3 + 0.3 4.2 +/- 0.2 4.5 + 0.2 1110 at 4.1 miles 90* Rt. 104 Pole #300 150 Ft East of Keefe Road 3.2 + 0.1 3.9 +/- 0.3 3.5 + 0.2 4.2 +/- 0.2 1350 at 4.2 miles 91* Rt. 51A Pole #59 0.8 Miles West ofRt. 51 3.2 - 0.2 3.8 + 0.2 3.7 + 0.2 3.8 + 0.2 1560 at. 4.8 miles 92* Maiden Lane Road Power Pole 0.6 Miles South ofRt. 3.7 +/- 0.2 4.5 + 0.2 4.3 -E 0.2 4.5 + 0.2 1830 at 4.4 miles 104 93* Rt. 53 Pole 1-1 120 ft South ofRt. 104 . 3.6 - 0.1 4.1 + 0.2 3.8 + 0.2 4.3 + 0.2 2050 at 4.4 miles 94* Rt. 1 Pole #82 250 ft East of KocherRoad (Co Rt. 63) 3.4 +/- 0.1 3.8 +/- 0.2 3.5 + 0.2 4.1 + 0.2 223' at 4.7 miles 95* AlcanWestAccessRoadJoeFultzBlvdPole#21 3.2 + 0.1 3.5 +/- 0.2 3.4 + 0.2 3.8 + 0.2 2377 at 4.1 miles 96* Creamery Rd 0.3 Miles South of Middle Road Pole 1-1/2 3.4 + 0.2 4.0 + 0.2 3.9 + 0.2 4.2 +/- 0.2 199' at 3.6 miles 97* Rt. 29 Pole #50 200 ft North of Miner Road 3.2 + 0.2 3.9 +/- 0.2 4.0 + 0.2 4.1 +/- 0.2 1430 at 1.8 miles 98* Lake Road Pole#1450.15MilesEastofRt.29 3.5 +/- 0.2 4.1 +/- 0.3 4.0 +/- 0.2 4.5 +/- 0.2 101' at 1.2miles (1) Direction and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6-27

TABLE 6-12(Continued)

DIRECT RADIATION MEASUREMENT RESULTS (mrem/std. Month : 1 Sigma)

Location Location First Second Third Fourth Direction &

Number Quarter Quarter Quarter Quarter Distance (1) 99 Nine Mile Point Road 0.4 Miles North ofLakeRoad Air 3.6 +/- 0.1 4.3 +/- 0.2 4.2 +/- 0.3 4.6 +/- 0.2 88' at 1.8miles Station RI 100 Rt. 29 & Lake Road Air Station R2 3.5 +/- 0.2 4.1 +/- 0.4 4.2 +/- 0.2 4.5 +/- 0.2 1040 at 1.1 miles 101 Rt. 29 0.7 Miles South of Lake Road Air Station R3 3.3 +/- 0.2 3.9 +/- 0.4 3.7 +/- 0.2 3.8 + 0.2 132' at 1.5 miles 102 JAFNPPEnvironmentalLabRt. 176 E Driveway Lamp Post 3.4 +/- 0.1 4.0 +/- 0.2 3.9 +/- 0.1 4.1 +/- 0.2 1750 at ll.9miles 103 Energy Information Center East Garage Road Lamp Post 4.0 +/- 0.2 4.5 +/- 0.3 4.5 +/- 0.2 4.7 +/- 0.2 2670 at 0.4 miles 104 Parkhurst Road Pole #23 0.1Miles South ofLake Road 3.5 +/- 0.1 4.2 +/- 0.3 4.0 +/- 0.2 4.2 +/- 0.2 1020 at 1.4miles 105 Lake View Road Pole #36 0.5 Miles South ofLake Road 3.5 +/- 0.2 4.4 +/- 0.2 4.2 +/- 0.5 4.3 +/- 0.2 1980 at 1.4miles 106 Shoreline Cove West ofNMP1 Tree On West Edge 4.6 +/- 0.2 5.6 +/- 0.4 5.2 +/- 0.2 5.5 + 0.2 274' at 0.3 miles 107 Shoreline Cove West ofNMP1 30FtSouth-Southwest 4.4 +/- 0.2 5.3 +/- 0.3 5.0 +/- 0.2 5.3 +/- 0.2 2720 at 0.3 miles 1of #106 108 Lake Road Pole #142 300 ft East of Rt. 29 South 3.6 +/- 0.1 4.5 +/- 0.2 4.1 +/- 0.2 .4.3 + 0.2 104' at 1.1 miles 109 Tree North ofLake Road 300 ft East ofRt. 29 North 3.6 +/- 0.1 4.4 +/- 0.4 4.1 +/- 0.3 4.3 +/- 0.2 1030 at 1.1 miles 111 State Route 38 Sterling, NY - Control 3.4 +/- 0.2 4.1 +/- 0.3 3.7 +/- 0.2 4.1 +/- 0.2 1660 at 26.4 miles 112 JAFNPP Environmental Laboratory Oswego County 3.7 +/- 0.1 4.1 +/- 0.2 3.9 +/- 0.2 4.3 +/- 0.2 175' at 11.9 miles IAirport 113 1Baldwinsville, NY-Control 3.7 +/- 0.4 4.0 +/- 0.5 3.7 +/- .02 4.1 +/- 0.3 2140 at 21.8 miles (1) Direction and distance based on NMP-2 reactor centerline.

TLD required by ODCM 6-28

- m m - M M mm m m m M m m m m m M

TABLE 6-13 CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK (pCi/liter +/- 1 Sigma)

Sample Location ** No. 55 Date 1-131 Cs-134 Cs-137 K-40 BaILa-140 Others t 04/07/08 < 0.524 < 8.32 < 7.67 1425 +/- 90.7 < 5.10 <LLD 04/21/08 < 0.734 < 8.32 < 7.10 1752 +/- 88.4 < 7.30 <LLD 05/05/08 < 0.516 < 7.56 < 6.55 1500 +/- 82.8 < 7.28 <LLD 05/19/08 < 0.503 < 4.76 < 7.08 1526 +/- 82.9 < 8.97 <LLD 06/09/08 < 0.480 < 5.01 < 7.64 1533 +3- 79.4 < 9.00 <LLD 06/23/08 < 0.746 < 5.30 < 5.32 1539 +/- 82.4 < 8.18 <LLD 07/07/08 < 0.481 < 8.02 < 6.55 1568 +/- 84.2 < 8.61 <LLD 07/21/08 < 0.449 < 7.23 < 5.32 1594 +/- 85.2 < 6.76 <LLD 08/04/08 < 0.442 < 8.02 < 4.56 1570 +/- 84.3 < 6.78 <LLD 08/18/08 < 0.565 < 7.06 < 6.54 1405 +/- 9,1.3 < 8.35 <LLD 09/08/08 < 0.500 < 7.21 < 8.90 1885 +/- 107.7 < 10.34 <LLD 09/22/08 < 0.541 < 8.88 < 6.69 1605 +/- 84.4 < 6.77 <LLD 10/06/08 < 0.540 < 8.09 < 7.40 1408 +/- 90.1 < 11.69 <LLD 10/20/08 < 0.496 < 12.52 < 15.17 2530 +/- 156.8 < 13.41 <LLD

-.11/03/08 < ,0.569 < 10.36 < 8.45 1686 +/-/- 100.7 < 11.02 <LLD 11/17/08 < 0.486 < 6.14 < 9.66 1489 +/- 95.4 < 8.26 <LLD

.12/01/08 < 0.479 < 9.55 < 9.29 1652 +/- 102.6 < 13.50 <LLD 12/15/08 < 0.430 < 9.39 < 9.84 1629 +/- 99.0 < 12.28 <LLD

- Sample location is Optional

Corresponds to sample location noted on Figure 3.3-4

" Plant related radionuclides 6-29

TABLE 6-13 (Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK (pCi/liter +/- 1 Sigma)

Sample Location** No. 76 Date 1-131 Cs-134 Cs-137 K-40 BaJLa-140 Others t 04/07/08 < 0.537 < 6.70 < 7.44 1468 +/- 81.6 < 6.21 <LLD 04/21/08 < 0.967 < 4.15 *< 6.37 1642 +/- 78.4 < 4.02 <LLD 05/05/08 < 0.599 < 6.35 < 8.71 1490 +/- 96.7 < 8.25 <LLD 05/19/08 < 0.661 < 5.47 < 6.96 1668 +/- 78.4 < 6.88 <LLD 06/09/08 < 0.451 < 4.29 < 5.59 1719 +/- 65.1 - < 5.26 <LLD 06/23/08 < 0.433 < 5.41 < 6.24 1835 +/- 82.0 < 6.12 <LLD 07/07/08 < 0.535 < 11.34 < 8.50 1625 +/- 101.2 < 11.60 <LLD 07/21/08 < 0.526 < 5.01 < 8.91 1379 +/- 93.5 < 5.55 <LLD 08/04/08 < 0.434 < 5.34 < 7.10 1782 +/- 81.8 < 6.91 <LLD 08/18/08 < 0.599 < 4.76 < 7.68 1413 +/- 78.5 < 8.97 <LLD 09/08/08 < 0.553 < 6.14 < 6.31 1567 +/- 76.2 < 6.91 <LLD 09/22/08 < 0.678 < 8.91 < 9.48 1249 +/- 91.0 < 11.60 <LLD 10/06/08 < 0.533 < 8.02 < 6.69 1300 +/- 76.4 < 4.80 <LLD 10/20/08 < 0.665 < 9.59 < 5.52 1420 +/- 89.0 < 8.38 <LLD 11/03/08 < 0.613 < 4.51 < 7.72 1662 +/- 78.2 < 8.19 <LLD 11/17/08 < 0.568 < 5.47 < 9.33 1803 +/- 105.6 < 8.80 <LLD 12/01/08 < 0.541 < 7.21 < 9.74 1888 +/- 107.7 < 12.24 <LLD 12/15/08 < 0.499 < 9.00 < 8.21 1890 +/- 105.8 < 10.35 <LLD

- Sample location is Optional

Corresponds to sample location noted on Figure 3.3-4

" Plant related radionuclides 6-30

- - - 1 - M -M M M M M M M M M M M M

TABLE 6-13(Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK (pCi/liter +/- 1 Sigma)

Sample Location

No. 77 (Control)

Date 1-131 Cs-134 Cs-137 K-40 [ Ba/La-140 Others t 04/07/08 < 0.594 < 5.85 < 4.37 1450 +/- 68.1 < 4.97 <LLD 04/21/08 < 0.923 < 3.62 < 5.44 1371 +/- 67.8 < 5.69 <LLD 05/05/08 < 0.474 < 8.76 < 9.27 1546 +/- 95.0 < 10.49 <LLD 05/19/08 < 0.572 < 4.33 < 5.74 1460 +/- 67.7 < 4.52 <LLD 06/09/08 < 0.514 < 9.67 < 10.27 2280 +/- 118.7 < 10.81 <LLD 06/23/08 < 0.680 < 4.17 < 5.24 1397 +/- 66.9 < 6.30 <LLD 07/07/08 < 0.434 < 8.54 < 8.16 1487 +/- 94.1 < 9.15 <LLD 07/21/08 < 0.435 < 7.84 < 6.54 1303 +/- 85.8 < 6.43 <LLD 08/04/08 < 0.687 < 4.12 < 6.20 1473 +/- 68.2 < 5.34 <LLD 08/18/08 < 0.574 < 3.53 < 4.90 1535 +/- 65.7 < 5.63 <LLD 09/08/08 < 0.482 < 7.86 < 9.84 1519 +/- 95.7 < 8.27 <LLD 09/22/08 < 0.531 < 9.22 < 6.55 1632 +/- 97.4 < 12.98 <LLD 10/06/08 < 0.754 < 11.25 < 14.41 2474 +/- 153.1 < 13.47 <LLD 10/20/08 < 0.499 < 6.53 < 5.24 1507 +/-/- 68.4 < 4.71 <LLD 11/03/08 < 0.729 < 9.08 < 7.62 1541 +/-/- 100.4 < 12.28 <LLD 11/17/08 < 0.457 < 6.31 < 5.45 1375 +/- 65.7 < 3.88 <LLD 12/01/08 < 0.534 < 8.88 < 5.82 1531 +/- 83.5 < 6.77 <LLD 12/15/08 < 0.439 < 7.87 < 6.41 1497 +/- 82.6 < 6.77 <LLD

Sample location required by the ODCM

- - Corresponds to sample location noted on Figure.3.3-4 j" Plant related radionuclides 6-31

TABLE 6-14 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS (pCi/kg (wet) +/- 1 sigma)

Location ** Date Description Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 Others t 09/15/08 Tomatoes < 131 3666 +/- 244 < 20.7 < 25.0 < 18.3 < 54.7 < LLD Culeton 09/15/08 Rhubarb Leaves 109 +/- 52 2976 +/- 231 < 19.4 - < 27.3 < 18.2 < 60.7 < LLD 133* 09/15/08 Pepper Leaves 848 +/- 86 6142 +/- 291 < 21.8 < 21.7 < 16.3 < 55.0 <LLD 09/15/08 Bean Leaves 1369 +/- 99 2533 +/- 191 < 18.3 < 21.3 < 17.8 < 60.1 <LLD Kronenbitter 09/15/08 Grape Leaves 1507 +/- 130 3407 +/- 284 < 32.7 <. 40.8 < 32.8 < 44.1 < LLD 134* 09/15/08 Bean Leaves 1159 +/- 86 2595 +/- 190 < 16.3 < 22.3 < 16.6 < 39.8 < LLD 09/15/08 Tomatoes < 207 3383 +/- 263 < 24.4 < 23:9 < 29.8 < 84.1 < LLD 09/10/08 Tomatoes < 99 2122 +/- 141 < 12.1 < 16.9 < 12.1 < 31.5 < LLD 09/10/08 Horseradish Leaves 519 +/- 77 2686 +/- 207 < 23.7 < 30;8 < 22.9 < 65.8 < LLD O'Connor 484* 09/10/08 Rhubarb Leaves 141 +/- 51 3597 +/- 206- < 18.9 < 16.0 < 17.4 < 33.0 < LLD 09/10/08 Squash Leaves 1599 +/- 101 3070 +/- 197 < 19.0 < 15.5 < 20.6 < 64.9 <LLD 09/10/08 Zucchini Leaves 816 +/- 84 2264 +/- 171 < 21.1 < 11.3 < 17.4 < 47.7 < LLD 09/10/08 Squash Leaves - 1326 +/- 83 2417 +/- 157 < 18.2 < 13.5 < 15.2 _ < 23.2 <LLD Hall 142 ** 09/10/08 Tomatoes < 102 2566 +/- 130 < 11.7 < 12.2 < 9.1 < 33.0 <LLD 09/10/08 Grape Leaves 3308 +/- 173 2515 +/- 223 < 29.8 < 34.4 < 26.5 < 39.8 < LLD 09/10/08 Tomatoes < 137 3375 +/- 215 < 18.0 < 22.8 < 17.7 < 51.9 < LLD 09/10/08 Horseradish Leaves 303 +/- 84 3588 +/- 255 < 25.8 < 30.4 < 28.3 < 63.8 < LLD Whaley 09/10/08 Squash Leaves 2472 +/- 129 1826 +/- 173 < 19.2 < 13.7 < 17.0 < 45.6 <LLD 144

09/10/08 Corn Leaves 1791 +/- 120 5001 +/- 265 < 23.1 < 28.9 < 21.4 < 32.2 < LLD 09/10/08 Pepper Leaves 1120 +/- 140 8609 +/- 436 < 33.7 < 24.6 -< 33.4 < 99.0 < LLD 09/10/08 Zucchini Leaves 1805 +/- 109 3142 +/- 193 < 19.2 < 22.9 < 16.8 < 43.6 < LLD 09/16/08 Zucchini Leaves 575 +/- 72 3008 +/- 193 < 17.4 < 14.7 < 14.9 <. 46.5 < LLD 09/16/08 Horseradish Leaves 286 +/- 65 3074 +/- 242 < 18.4 < 16.0 < 23.7 < 67.9 < LLD Flack 09/16/08 Rhubarb Leaves < 190 2928 +/- 209 < 16.9 < 23.4 < 15.6 < 27.9 < LLD C2 (Control)

09/16/08 Corn Leaves 1349 +/- 132 4728 +/- 349 < 31.1 < 23.5 < 28.4 < 82.8 < LLD 09/16/08 Tomatoes < 149 4096 +/- 294 < 17.2 < 26.0 < 26.9 < 66.2 < LLD 09/16/08 Bean Leaves 945 +/- 110 3084 +/- 249 < 21.5 < 16.5 < 26.8 < 66.5 < LLD

Sample location required by the ODCM *** Corresponds to sample location noted on Figure 3.3-5

- Sample location is Optional t Plant related radionuclides 6 - 32 m - m-m m- m mm-m - m m - m - m m

m m m m - m m m m m m m m - m m m m TABLE 6-15 MILK ANIMAL CENSUS Town or Location Distance (2) Number of Area(a) Designation0'l Degrees(2) (Miles) Milk Animals 9 98' 4.8 40C IG New Haven 64 107' 7.9 40C 78 128' 8.0 6C 14 123' 9.14 56C 60- 91 9.5 20C 76* 120' 6.3 30C Mexico 55* 97' 8.8 55C 21 112* 10.3 70C 72 1000 9.6 36C 50 93 8.8 1C Granby 77** 190* 16.0 62C, (Control)

MILKING ANIMAL TOTALS: 416 Cows (including control locations) 1 Goats MILKING ANIMAL TOTALS: 354 Cows (excluding control locations) 1 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 (a) Census performed out to a distance of approximately 10 miles 6-33

TABLE 6-16 RESIDENCE CENSUS Meteorological Sector Location Map Location(1) Degrees (2) Distance(2)

N

NNE

NE

ENE

E West Sunset Bay, Lake A 1000 1.3 miles Road ESE Lake Road B 1040 1.1 miles SE County Route 29 C 1250 1.4 miles SSE Miner Road D 1580 1.7 miles S Miner Road E 1710 1.6 miles SSW Lakeview Road F 2080 1.2 miles SW Lakeview Road G 2170 1.1 miles WSW Bayshore Drive H 2370 1.4 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) Degrees and distance are based on NMP-2 Reactor Building centerline 6-34 m - M M- M M m MM - mm

SECTION 7.0 HISTORICAL DATA TABLES

7.0 HISTORICAL DATA TABLES 7-1

I I

TABLE 7-1 I HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (CONTROL) (")

I Cs-137 (pCi/g (ry)) ~ Co-60 (pCi/g (dry))

YEAR MIN. MAX. MEAN MIN. MAX. MEAN 1979 (2) 0.22 0.22 0.22 LLD LLD LLD 1980 0.07 0.09 0.08 LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD 1982 0.05 0.05 0.05 LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 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 0.03 0.03 0.03 LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD LLD LLD LLD 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD 2005 LLD LLD LLD LLD LLD LLD 2006 LLD LLD LLD LLD LLD LLD 2007 LLD LLD LLD LLD LLD LLD 2008 LLD LLD LLD LLD LLD LLD (1) Control location was at an area beyond the influence of the site (westerly direction).

(2) Sampling was initiated in 1979. Sampling was not required prior to 1979.

7-2 I I

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (INDICATOR)(1 CS-137 (pCi/g (ry)) ~ Co-60 (pCi/g (dry))~

YEAR MIN. MAX. MEAN MIN. MAX. MEAN 1985 (2) 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 0.25 0.34 0.30 LLD LLD LLD 1990 0.28 0.28 0.28 LLD LLD LLD 1991 0.11 0.16 0.14 LLD LLD LLD 1992 0.10 0.16 0.13 LLD LLD LLD 1993 0.17 0.49 0.33 LLD LLD LLD 1994 0.08 0.39 0.24 LLD LLD LLD 1995 0.16 0.17 0.16 LLD LLD LLD 1996 0.13 0.18 0.16 LLD LLD LLD 1997 0.13 0.18 0.16 LLD LLD LLD 1998 0.07 0.07 0.07 LLD LLD LLD 1999 0.06 0.09 0.08 LLD LLD LLD 2000 0.06 0.08 0.07 LLD LLD LLD 2001 0.06 0.07 0.07 LLD LLD LLD 2002 0.05 0.05 0.05 LLD LLD LLD 2003 0.04 0.05 0.05 LLD LLD LLD 2004 0.04 0.04 0.04 LLD LLD LLD 2005 0.06 0.09 0.08 LLD LLD LLD 2006 0.06 0.06 0.06 LLD LLD LLD 2007 0.04 0.04 0.04 LLD LLD LLD 2008 LLD LLD LLD LLD LLD LLD (1) Location was off-site at Sunset Beach (closest location with recreational value).

(2) Sampling initiated in 1985 as required by Technical Specifications requirements.

7-3

I TABLE 7-3 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL) ()

Cs-137 (pCi/g (wet))

YEAR [ MIN. I MAX. 1 MEAN 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 1980 0.03 0.11 0.06 1981 0.028 0.062 0.043 1982 0.027 0.055 0.046 1983 0.041 0.057 0.049 1984 0.015 0.038 0.032 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 0.033 1989 0.020 0.033 0.029 1990 0.025 0.079 0.043 1991 0.016 0.045 0.030 1992 0.019 0.024 0.022 1993 0.023 0.041 0.032 1994 0.012 0.035 0.024 1995 0.014 0.020 0.016 1996 0.014 0.018 0.016 1997 0.019 0.043 0.031 1998 0.013 0.013 0.013 1999 LLD LLD LLD 2000 0.02 0.02 0.02 2001 LLD LLD LLD 2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD 2005 LLD LLD LLD 2006 LLD LLD LLD 2007 LLD LLD LLD 2008 LLD LLD LLD (1) Control location was at an area beyond the influence of the site (westerly direction). I 7-4 I I

TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (INDICATOR) (1)

Cs-137 (pCi/g (wet))

YEAR MIN. MAX. MEAN 1976 0.5 3.9 1.4 1977 0.13 0.79 0.29 1978 0.03 0.10 0.08 1979 0.02 0.55 0.10 1980 0.03 0.10 0.06 1981 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 1986 0.009 0.051 0.028 1987 0.024 0.063 0.033 1988 0.020 0.074 0.034 1989 0.020 0.043 0.035 1990 0.024 0.115 0.044 1991 0.021 0.035 0.027 1992 0.013 0.034 0.026 1993 0.021 0.038 .0.030 1994 0.011 0.028 0.020 1995 0.016 0.019 0.018 1996 0.014 0.016 0.015 1997 0.015 0.017 0.016 1998 0.021 0.021 0.021 1999 0.016, 0.018 0.017 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 2006 LLD LLD LLD 2007 LLD, LLD LLD 2008 LLD LLD LLD (1) Indicator locations are in the general area of the NMP1 and J. A. FitzPatrick cooling water discharge structures.

7-5

I I

TABLE 7-5 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CONTROL) (3) I YEAR MIN.

Cs-137 (pCi/liter)

MAX. I MEAN MIN.

Co-60 (pCi/liter)

I MAX. I MEAN I

1976 1977 1978 (1)

(2)

(1)

(2)

(1)

(2)

(1)

(2)

(1)

(2)

(1)

(2) I LLD LLD LLD (2) (2) (2) 1979 1980 1981 2.5 LLD LLD 2.5 LLD LLD 2.5 LLD LLD LLD LLD 1.4 LLD LLD 1.4 LLD LLD 1.4 I

1982 1983 1984 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1985 1986 1987 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1988 1989 1990 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1991 LLD LLD LLD LLD LLD LLD 1992 1993 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1994 LLD LLD LLD LLD LLD LLD 1995 1996 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1997 LLD LLD LLD LLD LLD LLD 1998 1999 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2000 LLD LLD LLD LLD LLD LLD 2001 2002 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I 2003 LLD LLD LLD LLD LLD LLD 2004 2005 2006 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2007 2008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I (1) No gamma analyses performed (not required).

(2) Data showed instrument background results.

Location was the City of Oswego Water Supply for 1976 - 1984 and the Oswego Steam Station inlet canal for 1985 -

2007.

I 7-6 I I

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (INDICATOR) (")

Cs-137 (pCi/liter) Co-60 (pCi/liter)

(2) Data showed instrument background results.

(3) Location was the J. A. FitzPatrick inlet canal.

7-7

I U

TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (CONTROL)(1

_________________ _________________ TRITIUM (pCi/liter) ___________

YEAR MIN. I MAX. I MEAN 1976 440 929 652 1977 300 530 408

.1978 215 490 304 1979 174 308 259 1980 211 290 257 1981 211 328 276 1982 112 307 165 1983 230 280 250 1984 190 220 205 1985 230 370 278 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 180 660 373 1990 260 320 290 1991 180 190 1992 190 310 .242 1993 160 230 188 1994 250 250 1995 230 230 230 1.996 LLD LLD LLD 1997 LLD LLD LLD 1998 190 190 190 1999 220 510 337 2000 196 237 212 2001 LLD LLD LLD

'2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD 2005 LLD LLD LLD 2006 LLD LLD LLD 2007 LLD LLD LLD 2008 LLD LLD LLD

() Control location is the City of Oswego drinking water for 1976 canal for 1985 - 2008.

- 1984 and the Oswego Steam Station inlet I 7-8 I I

TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (INDICATOR) (1)

TRITIUM (pCi/liter)

YEAR MIN. MAX. MEAN 1976 365 889 627 1977 380 530 455 1978 377 560 476 1979 176 276 228 1980 150 306 227 1981 212 388 285 1982 194 311 266 1983 249 560 347 1984 110 370 280 1985 250 1200 (2) 530 1986 260 500 380 1987 160 410 322 1988 430 480 460 1989 210 350 280 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 2006 LLD LLD LLD 2007 LLD LLD LLD 2008 LLD LLD LLD (1) Indicator location is the FitzPatrick inlet canal.

(2) Suspect sample contamination. Recollected samples showed normal levels of tritium.

7-9

I U

TABLE 7-9 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA I GROUNDWATER TRITIUM (CONTROL) ()

TRITIUM (pCi/liter)

I YEAR 2005 MIN.

<854 MAX.

<854 MEAN

<854 I

2006(2) <447 <825 2007 2008

<442

<427

<445

<439

.<636

<444

<431 I

(1)

(2)

Control well locations (2) are upland wells located south of protected area.

Required LLD changed to 500 pCi/l from 1000 pCi/l I 7-10 I

I

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (INDICATOR) ()

TRITIUM (pCi/liter)

YEAR MIN. MAX. MEAN 2005 <854 <871 <863 2006(2) <462 <933 <823 2007 <440 <461 <445 2008 <427 <439 <433 (1) Indicator locations are down gradient wells located in the north-east corner of the protected area and samples

, collected from theNMP2 depression cone system.

(2) Required LLD changed to 500 pCi/I from 1000 pCi/I 7-11

I I

TABLE 7-11 I HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (CONTROL) (1) I GROSS BETA (pCi/mr3)

YEAR MIN. MAX. MEAN 1977 0.001 0.484 0.125 1978 0.01 0.66 0.16 1979 0.010 0.703 0.077 1980 0.009 0.291 0.056 1981 0.016 0.549 0.165 1982 0.011 0.078 0.033 1983 0.007 0.085 0.024 1984 0.013 0.051 0.026 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 0.006 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 2006 0.007 0.033 0.016 2007 0.008 0.028 0.016 2008 0.007 0.031 0.015 (1) Locations used for 1977 - 1984 were C offsite, DI offsite, D2 offsite, E offsite, F offsite, and G offsite. Control location R-5 offsite was used for 1985 - 2008 (formerly C offsite location).

I 7-12 I I

TABLE 7-12 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (INDICATOR) (1)

GROSS BETA (pCi/m3 )

YEAR MIN. MAX. MEAN 1977 0.002 0.326 0.166 1978 0.01 0.34 0.11 1979 0.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 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 0.005 0.023 0.014 1991 0.007 0.033 0.015 1992 0.005 0.024 0.013 1993 0.005 0.025 0.014 1994 0.006 0.025 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 0.037 0.016 2005 0.007 0.040 0.018 2006 0.005 0.035 0.015 2007 0.007 0.028 0.016 2008 0.004 0.030 0.016 (1) Locations used for 1977 - 1984 were DI onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite as applicable. 1985 - 2008 locations were R-1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-13

I I

TABLE 7-13 I HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (CONTROL) (1) I Cs-137 (pCi/m 3) Co-60 (pCi/m3) I YEAR MIN. MAX. MEAN MAX. MEAN I

MIN.

1977 0.0002 0.0112 0.0034 0.0034 0.0347 0.0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 1979 1980 0.0008 0.0015 0.0047 0.0018 0.0016 0.00'16 0.0005 LLD 0.0014 LLD 0.0009 LLD I 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 1983 1984 0.0002 0.0002 LLD 0.0009 0.0002 LLD 0.0004 0.0002 LLD 0.0004 0.0007 0.0004 0.0007 0.0007 0.0012 0.0006 0.0007 0.0008 I

1985 1986 1987 LLD 0.0075 LLD LLD 0.0311 LLD LLD 0.0193 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1988 1989 1990 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

LLD LLD LLD LLD LLD LLD LLD I

1991 1992 1993 LLD LLD LLD LLD LLD LLD LLD LLD LLD

.LLD LLD

.LLD LLD LLD LLD LLD LLD LLD I

1994 LLD LLD LLD LLD LLD LLD 1995 1996 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1997 LLD LLD LLD LLD LLD LLD 1998 1999 LLD LLD LLD LLD LLD LLD

LLD LLD LLD LLD LLD LLD I

2000 LLD LLD LLD LLD LLD LLD 2001 2002 LLD LLD

'LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2003 LLD LLD LLD LLD LLD LLD 2004 2005 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I 2006 LLD LLD LLD LLD LLD LLD 2007 2008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I (1) Locations included composites of C, D1, E, F, and G offsite air monitoring locations for 1977 - 1984. Sample location included only R-5 air monitoring location for 1985 - 2008. 1 7-14 I I

TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (INDICATOR) (1)

Cs-137 (pCi/mr3) Co-60 (pCi/m3)

YEAR MIN. I MAX. J MEAN MIN. J MAX. MEAN 1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0.0016 0.0003 0.0153 0.0023 1979 0.0003 0.0020 0.0010 0.0003 0.0007 0.0005 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0.0002 0.0045 0.0014 0.0002 0.0017 0.0006 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003 0.0002 0.0003 0.0017 0.0007 1984 LLD LLD LLD 0.0007 0.0017 0.0012 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 2006 LLD LLD LLD LLD LLD LLD 2007 LLD LLD LLD LLD LLD LLD 2008 LLD LLD LLD LLD LLD LLD (1) Locations included composites of D1, D2, E, F, G, H, I, J, and K onsite air monitoring locations for 1977 -

1984. Locations included R-1 through R-4 air monitoring locations for 1985 - 2008.

7-15

I I

TABLE 7-15 I HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (CONTROL) (1)

I IODINE- 131 (pCi/m3) I YEAR MIN. I MAX. MEAN 1976 0.01 5.88 0.60 I

1977 0.02 0.82 0.32 1978 1979 0.03 LLD 0.04 LLD 0.03 LLD I 1980 LLD LLD LLD 1981 1982 1983 LLD 0.039 LLD LLD 0.039 LLD LLD 0..039 LLD I

1984 1985 1986 LLD LLD 0.041 LLD LLD 0.332 LLD LLD 0.151 I

1987 1988 1989 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1990 1991 1992 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1993 LLD 1994 1995 LLD LLD LLD LLD LLD LLD LLD LLD I

1996 LLD LLD LLD 1997 1998 LLD LLD LLD LLD LLD LLD I

1999 LLD LLD LLD 2000 2001 LLD LLD LLD LLD LLD LLD I

2002 LLD LLD LLD 2003 2004 LLD LLD LLD LLD LLD LLD I 2005 LLD LLD LLD 2006 2007 2008 LLD LLD LLD LLD LLD LLD I LLD LLD LLD (1) Locations D1 offsite, D2 offsite, E offsite, F offsite, and G offsite used for 1976 - 1984. Location R-5 offsite used for 1985 - 2008.

I 7-16 I I

TABLE 7-16 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (INDICATOR) ()

IODINE-131 (pCi/m 3)

YEAR MIN. I MAX. MEAN 1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1983 0.022 0.035 0.028 1984 LLD LLD LLD 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 2006 LLD LLD LLD 2007 LLD LLD LLD 2008 LLD LLD LLD (1) Locations used for 1976 - 1984 were DI onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite, as applicable. Locations used for 1985 - 2008 were R1 offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-17

I I

TABLE 7-17 HISTORICAL ENVIRONMENTAL SAMPLE DATA I ENVIRONMENTAL TLD (CONTROL) (2)

I DOSE (mrem oer standard month)

YEAR 1969 MIN. MAX. I MEAN I (1) (1) (1) 1970 1971 1972 6.0 2.0 2.2 7.3 6.7 6.2 6.7 4.3 4.4 I

1973 2.2 6.9 4.7 1974 1975 1976 2.7 4.8 3.2 8.9 6.0 7.2 5.6 5.5 5.4 I

1977 4.0 8.0 1978 1979 3.3 3.3 4.7 5.7 5.3 4.3 4.7 I

1980 3.8 5.8 4.9 1981 1982 1983 3.5 3.8 4.9 5.9 6.1 7.2 4.8 5.1 5.8 I

1984 4.7 8.2 6.2 1985 1986 1987 4.5 (4.4)*

5.3 (5.5)*

4.6 (4.6)*

7.6 (6.8)*

7.5 (7.2)*

6.6 (5.8)*

5.6 (5.4)*

6.3 (6.3)*

5.4 (5.2)*

I 1988 1989 1990 4.4 (4.8)*

2.9 (2.9)*

3.7 (3.7)*

6.8 (6.8)*

6.4 (5.6)*

6.0 (5.9)*

5.6 (5.4)*

4.7 (4.6)*

4.8 (4.6)*

I 1991 3.8 (3.8)* 5.4 (5.3)* 4.5 (4.3)*

1992 1993 1994 2.6 (2.6)*

3.4 (3.4)*

3.1 (3.1)*

5.0 (4.7)*

5.6 (5.2)*

5.0 (4.6)*

4.1 (3.9)*

4.4 (4.3)*

4.1 (3.9)*

I 1995 3.4 (3.4)*

I 5.7 (4.9)* 4.4 (4.2)*

1996 3.4 (3.4)* 5.6 (5.6)* 4.3 (4.2)*

1997 3.7 (3.9)* 6.2 (5.2)* 4.7 (4.6)*

1998 3.7 (3.7)* 5.6 (4.8)* 4.4 (4.2)*

1999 2000 2001 3.6 (3.7)*

3.7 (3.7)*

3.6 (3.9)*

7.1 (4.7)*

7.3 (5.5)*

5.4 (5.0)*

4.6 (4.4)*

4.7 (4.3)*

4.4 (4.4)*

I 2002 3.4 (3.4)* 5.5 (5.2)* 4.3 (4.1)*

2003 2004 2005 3.4 (3.4)*

3.3 (3.3)*

3.3 (3.4)*

5.5 (4.8)*

5.9 (5.9)*

5.1 (4.5)*

4.2 (4.2)*

4.3 (4.5)*

4.1 (4.0)*

I 2006 2007 2008 3.3 (3.3)*

3.2 (3.2)*

3.3(3.3)*

5.3 (4.4)*

5.8 (5.3)*

5.1(4.8)*

4.1 (4.0)*

4.4 (4.3)*

4.1(4.0)*

I (1)

(2)

()*

Data not available.

TLD #8, 14, 49, 111 and 113 where applicable.

TLD result based on the ODCM required locations (TLD #14 and 49).

I 7-18 I I

TABLE 7-18 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SITE BOUNDARY) (2)

DOSE (mrem per standard month)

YEAR MIN. MAX. MEAN 1985 (1) 4.1 12.6 6.2 1986 4.4 18.7 7.0 1987 4.4 14.3 6.1 1988 3.4 17.9 6.4 1989 2.8 15.4 5.9 1990 3.6 14.8 5.8 1991 3.2 16.7 5.7 1992 3.2 10.4 4.8 1993 3.3 11.6 .5.3 1994 2.8 12.4 5.2 1995 3.5 9.6 5.4 1996 3.2 9.1 5.2 1997 3.5 10.2 5.9 1998 3.7 9.4 5.4 1999 3.3 12.3 5.8 2000 3.6 10.0 5.5 2001 3.6 10.3 5.7 2002 3.5 9.4 5.4 2003 3.2 8.9 5.4 2004 3.3 10.8 5.6 2005 3.4 9.2 5.5 2006 3.5 9.2 5.4 2007 3.2 9.0 5.6 2008 3.2 8.8 .5.2 (1) Not required prior to 1985.

(2) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 7, 18, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, and 87.

7-19

I I

TABLE 7-19 HISTORICAL ENVIRONMENTAL SAMPLE DATA I ENVIRONMENTAL TLD (OFFSITE SECTORS) (2)

I DOSE (mrem per standard month)

YEAR MIN. MAX. MEAN I 1985 (1) 4.0 7.1 5.0 1986 1987 1988 4.6 4.3 3.8 8.6 6.0 7.0 6.0 5.2 5.3 I

1989 2.5 6.8 4.9 1990 1991 3.6 3.6 6.3 5.6 4.7 4.5 I

1992 2.9 5.0 4.1 1993 1994 3.4 3.0 6.3 5.1 4.5 4.0 I 1995 3.2 5.2 4.2 1996 1997 1998 3.2 3.5 3.5 5.3 5.8 5.0 4.2 4.5 4.2 I

1999 3.6 5.6 4.4 2000 2001 3.4 3.6 6.6 5.4 4.5 4.4 I

2002 3.1 5.3 4.2 2003 2004 2005 3.4 3.2 3.2 4.8 6.7 4.7 4.1 4.4 4.0 I

2006 3.3 4.4 4.0 2007 2008 3.1 3.2 5.1 4.5 4.2 3.8 I

(1) No data available (not required prior to 1985).

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

7 - 20

TABLE 7-20 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SPECIAL INTEREST) (2)(3)

DOSE (mrem per standard month)

YEAR MIN. MAX. MEAN 1985 (1) 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 7.0 4.8 1990 3.2 6.3 4.7 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 4.0 1995 3.4 4.9 4.3 1996 3.2 5.3 4.2 1997 3.5 5.4 4.5 1998 3.7 4.9 4.3 1999 3.6 5.5 4.4 2000 3.6 6.3 4.5 2001 3.8 5.0 4.3 2002 3.5 4.7 4.1 2003 3.4 5.0 4.2 2004 3.0 5.9 4.2 2005 3.4 4.7 3.9 2006 3.5 4.6 4.0 2007 3.0 5.1 4.2 2008 3.1 4.6 3.9 (1) Not required prior to 1985.

(2) TLD locations initiated in 1985 as required by the new Technical Specifications. TLD's included are numbers 15, 56, 58, 96, 97 and 98.

(3) TLD locations include critical residences and populated areas near the site.

7-21

TABLE 7-21I HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (ONSITE INDICATOR) (2)I 1 DOSE (mnremn per standard month)I VP'A P 1 ,INI MAAY XAA 1969 (1) (1) (1) 1970 4.7 9.0 6.0 1971 1.5 7.7 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3.1 10.6 5.7 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 1977 3.0 15.3 5.7 1978 3.0 9.0 4.3 1979 2.7 8.3 4.3 1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3 1983 5.0 16.5 6.9 1984 4.6 13.2 7.0 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 14.5 6.0 1990 3.6 12.9 5.5 1991 3.2 11.6 5.1 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 7.7 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 2006 3.5 14.4 5.3 2007 3.2 14.8 5.6 2008 3.2 13.8 5.2 (1) No data available.

(2) 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 - 2007). Locations are existing or previous onsite environmental air monitoring locations.

7 - 22

TABLE 7-22 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (OFFSITE INDICATOR) (2)

DOSE (mrem per standard month)

YEAR MIN. MAX. MEAN 1969 (1) (1) (1) 1970 5.0 8.0 6.7 1971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 2.7 4.7 3.7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 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 6.0 4.8 1991 3.4 5.4 4.3 1992 3.1 5.2 4.1 1993 3.2 5.6 4.3 1994 3.0 5.0 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 4.4 1999 3.8 7.1 4.6 2000 3.8 7.3 4.6 2001 3.7 5.9 4.5 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 2006 3.9 5.3 4.2 2007 3.4 5.8 4.5 2008 3.3 5.1 4.1 (1) No data available.

(2) Includes TLD numbers 8, 9, 10, 11, 12, and 13 (offsite environmental air monitoring locations).

7 - 23

I U

TABLE 7-23 I HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (CONTROL) (2) I Cs-137 (pCi/liter) 1-131 (pCi/lite r) I YEAR MIN. =MAX. MEAN MIN. MAX. MEAN 1976 (1)

(l)

(1)

(I)

(1)

I 1977 1978 1979 1980 2.4 LLD 3.6 7.8 LLD 5.6 5.8 LLD 4.5 LLD LLD 1.4 LLD LLD 1.4 LLD LLD 1.4 I

1981 1982 1983 3.9 LLD LLD 3.9 LLD LLD 3.9 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1984 1985 1986 LLD LLD 5.3 LLD LLD 12.4 LLD LLD 8.4 LLD LLD 0.8 LLD LLD 29.0 LLD LLD 13.6 I

1987 1988 1989 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1990 LLD 1991 1992 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1993 LLD LLD LLD LLD LLD LLD 1994 1995 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1996 LLD LLD LLD LLD LLD LLD 1997 1998 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1999 LLD LLD LLD LLD LLD LLD 2000 2001 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

2002 LLD LLD LLD LLD LLD LLD 2003 2004 2005 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I LLD LLD LLD LLD LLD LLD 2006 2007 2008 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

(1)

(2)

No data available (samples not required).

Location used was an available milk sample location in a least prevalent wind direction greater than ten miles I

from the site.

7 - 24 I I

TABLE 7-24 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (INDICATOR) (1)

Cs-137 (pCi/liter) 1-131 (pCi/liter)

YEAR MIN. MAX. MEAN MIN. MAX. MEAN 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLD LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1983 3.3 10.9 7.2 LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 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 0.50 0.50 0.50 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD 2005 LLD LLD LLD LLD LLD LLD 2006 LLD LLD LLD LLD LLD LLD 2007 LLD LLD LLD LLD LLD LLD 2008 LLD LLD LLD LLD LLD LLD (1) Locations sampled were available downwind locations within ten miles with high radionuclide deposition potential.

7 - 25

I TABLE 7-25 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA I FOOD PRODUCTS (CONTROL) ()

I Cs-137 (pCi/g (wet))

YEAR MIN. MAX. MEAN I 1980 (2) 0.02 0.02 0.02 1981 1982 LLD LLD LLD LLD LLD LLD I 1983 LLD LLD LLD 1984 1985 (3) 1986 LLD LLD LLD LLD LLD LLD LLD I LLD LLD 1987 1988 1989 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1990 1991 1992 LLD LLD LLD LLD LLD LLD LLD LLD LLD I

1993 0.007 0.007 0.007 1994 1995 LLD LLD LLD LLD LLD LLD I

1996 LLD LLD LLD 1997 1998 LLD LLD LLD LLD LLD LLD I

1999 LLD LLD LLD 2000 2001 LLD LLD LLD LLD LLD LLD I

2002 LLD LLD LLD 2003 2004 LLD LLD LLD LLD LLD LLD I

2005 LLD LLD LLD 2006 2007 LLD LLD LLD LLD LLD LLD I 2008 LLD LLD LLD (1) Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

I (2) Data comprised of broadleaf and non-broadleaf vegetation (1980 - 1984, 2007, & 2008).

(3) Data comprised of broadleaf vegetation only (1985 - 2006).

7 - 26

TABLE 7-26 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (INDICATOR) (1)

Cs-137 (pCi/g (wet))

YEAR MIN. MAX. MEAN 1976 (2) LLD LLD LLD 1977 LLD LLD LLD 1978 LLD LLD LLD 1979 0.004 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (3) 0.047 0.047 0.047 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 0.008 0.008 0.008 1989 0.009 0.009 0.009 1990 LLD LLD LLD 1991 0.040 0.040 0.040 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 0.004 0.011 0.008 1995 0.010 0.012 0.011 1996 LLD LLD LLD 1997 0.012 0.012 0.012 1998 LLD LLD LLD 1999 0.008 0.008 0.008 2000 LLD LLD LLD 2001 LLD LLD LLD 2002 LLD LLD LLD 2003 LLD LLD LLD 2004 LLD LLD LLD 2005 LLD LLD LLD 2006 LLD LLD LLD 2007 LLD LLD LLD 2008 LLD LLD LLD (1) Indicator locations were available downwind locations within ten miles of the site and with high radionuclide deposition potential.

(2) Data comprised of broadleaf and non-broadleaf vegetation (1976 - 1984, 2007 & 2008).

(3) Data comprised of broadleaf vegetation only (1985 - 2006).

7 - 27

SECTION 8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM

8.0 QUALITY ASSURANCE/QUALITY CONTROL PROGRAM 8.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), for NMP1 and NMP2, Part II, Section 4.0 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 JAFNPP Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.

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

The JAFNPP Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples. The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts.

It is important to note that the JAFNPP Environmental Laboratory has participated in the Nuclear Energy Institute (NEI)/National Institute of Standards and Technology (NIST)

Measurement Assurance Program (MAP) for several years. The NEI/NIST MAP is no longer being sponsored by NEI. As a result, the NIST blind sample program was reduced and, therefore, did not meet the requirements for the JAFNPP quality assurance program for 2008.

8-1

I I

8.2 PROGRAM SAMPLE SCHEDULE I

SAMPLE LABORATORY ANALYSIS SAMPLE PROVIDER I

MEDIA Water Gross Beta ANALYTICS 3 I Water Tritium 5 Water 1-131 4 I Water Mixed Gamma 4 Air Gross Beta 3 I Air 1-131 4 Air Mixed Gamma 2 I Milk 1-131 3 Milk Mixed Gamma 3 I Soil Mixed Gamma 1 Vegetation Mixed Gamma 2 I TOTAL SAMPLE INVENTORY 34 I

8.3 ACCEPTANCE CRITERIA I

Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below. I 8.3.1 SAMPLE RESULTS EVALUATION I

Samples provided by Eckert & Ziegler Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the vendor laboratory's known value (reference I

result).

8-2

The analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

Error resolution = Reference Result Reference Results Error (1 sigma)

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

TABLE 8.3.1 Error Resolution/Ratio of Agreement ERROR RATIO OF RESOLUTION AGREEMENT

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 51 to 200 0.8 to 1.25

>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The NRC method generally results in an acceptance range of approximately + 25% of the known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally-required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

8-3

I I

8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8.4-1. i 8.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2008 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131

Air Particulate Filter: Mixed Gamma Emitters, Gross Beta

Water: 1-13 1, Mixed Gamma Emitters, Tritium, Gross Beta

Soil: Mixed Gamma Emitters

Milk: 1-131, Mixed Gamma Emitters

Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 130 individual analyses on the 34 QA samples. Of the 130 analyses performed, 130 were in agreement with the expected values using the NRC acceptance criteria, for a 100% agreement ratio.

There were no non-conformities in the Interlaboratory Comparison Program's Quality Assurance Program in 2008.

8.5 REFERENCES

3 1.0 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

2.0 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R.,

McGraw Hill, New York (1969).

8-4

- --- mmmm-mm-mnm-- m TABLE 8.4-1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAFNPP ELAB RESULTS REFERENCE LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma (1) 06/19/2008 E5914-05 Filter 57.0 11.9 GROSS 57.8 1.9 52.2 + 0.871 1.07 A BETA 52.9 11.9 Mean = 55.9 + 1.1 06/19/2008 E5940-09 Filter 51.7 + 0.8 GROSS 51.4 + 0.8 49,2 0.822 1.04 A BETA 51.0 + 0.8 Mean = 51.4 +/- 0.5 12/11/2008 E6368-05 Filter 123.6 + 1.9 GROSS i25.5 1.9 1 113 1.89 1.09 A BETA 119.9 + 1.9 Mean= 123.0 + 1.1 (1) Ratio Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-5

TABLE 8.4-1 (Continued)

Tritium Analysis of Water SAMPLE JAFNPP ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter+/-1 sigma 3/20/2008 E5822-05 Water H-3 4265 +/- 170 4244 + 170 4010 67 4201 +/- 169 Mean= 4237 +/- 98 6/19/2008 E5913-05 Water H-3 860 +/- 136 994 +/- 137 843 + 14.1 832 +/- 136 Mean 895 +/- 79 9/18/2008 E6248-05 Water H-3 1017 +/- 134 978 +/- 134 996 16.6 937 +/- 134 Mean = 977 +/- 77 12/11/2008 E6359-09 Water H-3 10501 - 207 10401 207 1.02E+04 + 1.70E+02 10441 +/- 207 Mean = 10448 +/- 120 12/11/2008 E6360-09 Water H-3 10483 + 207 10564 +/- 208 1.02E+04 +/- 1.70E+02 10355 +/- 206 Mean= 10467 + 120

.1)\ nallo __epor tewnlytcs

1) fcato = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-6 m m m m M M M M M M M M M M M M M M M

m mm mm m mm*m- m m m m m m TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Water SAMPLE JAFNPP ELAB RESULTS REF. LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-=1 sigma pCi/liter +/-1 sigma (1) 2.26E+02 + 2.30E+00 03/20/2008 E5822-05 Water Gross Beta 2.29E+/-02 2.30E+/-00 2.30E+02 +/- 3.84E+00 0.98 A 2.23E+02 + 2.30E+00 Mean = 2.26E+02 + 1.33E+00 1.38E+02 + 1.80E+00 06/19/2008 E5919-05 Water Gross Beta 1.40E+02 1.80E+00 1.49E+02 + 2.49E+00 0.93 A 1.37E+02 11.70E+00 Mean = 1.38E+02 +/- 1.02E+00 2.76E+02 +/- 2.60E+00 09/18/2008 E6253-05 Water Gross Beta 2.76E+02 2.60E+00 2.90E+02 +/- 4.85E+00 0.95 A 2.75E+02 +/- 2.60E+00 Mean = 2.76E+02 +/- 1.50E+00 (1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-7

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM 1-131 Gamma Analysis of Air Charcoal SAMPLE JAFNPP ELAB RESULTS REF. LAB*

DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 65.8 +/- 2.95 3/20/2008 E5845-09 Air 1-131 63.7 +/- 2.88 60.0 +/- 1.0 1.06 A 61.7 +/- 3.13 Mean = 63.7 +/- 1.73 79.8 + 4.1 6/19/2008 E5917-05 Air 1-131 81.4 +/- 3.02 84.8 + 1.42 0.97 A 85.8 +/- 3.51 Mean = 82.3 + 2.06 87.4 +/- 2.6 9/18/2008 E6301-09 Air 1-131 85.3 2.62 87.7 + 1.46 1.01 A 92.5 +/- 2.86 Mean = 88.4 +/- 1.56 83.6 +/- 3.29 9/18/2008 E6252-05 Air 1-131 90.1 2.57 82.0 + 1.37 1.04 A 83.1 + 2.69 Mean 85.6 +/-. 1.66 (1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-8 M M- M Mm m m m m M M Mm M m M

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAFNPP ELAB RESULTS REF. LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma (1) 3/20/2008 E5820-05 Water 208 5.87 200 8.89 Ce-141 198 +/- 3.31 1.04 A 210 8.46 Mean 206 4.5 320 +/- 27.1 Cr-51 280 34.8 286 +/- 4.77 1.11 A 349 +/- 33.4 Mean = 316 5 18.4 105 5 3.89 Cs-134 10999.7 1.67 1.08 A 109 5 5.42 Mean = 108 A: 3.0 120 +/- 4.23 Cs-137 137 6.1 116 5+/- 1.94 1.07 A 116 5= 5.64 Mean = 124 + 3.1 55.7 +/- 3.55 Co5866.1 5+ 4.81 Co-58 6 51.8 5= 4.7 4.76 56.4 +/- 0.941 1.03 A Mean = 57.9 5 2.5 79.6 5 3.87 Mn-54 84.7 5 4.98 84n-5.18 84 5= 5.18 75 .+ 1.25 1.10 A Mean = 82.8 A: 2.7 97.2 5 5.38 F5975.8 5= 6.29 Fe-59 7.

87.8 5= 6.2 6.72 81.4 +/-: 1.36 1.07 A Mean = 86.9 +/- 3.6 108 5 7.79 Zn-65 129 10.6 109 +/- 1.82 1.05 A 106 A: 10.3 Mean = 114 A: 5.6 198 5= 4.15 180 5= 5.46 Co-60 180 5.56 188 +/- 3.14 1.02 A 198 A 5.56 1Mean = 192 5= 2.9 72.9 :1- 1.9 72.2 A= 1.88 1-131** +/-= 70.4 +/- 1.18 1.04 A 73.8 3.6 Mean 73.0 .+/- 1.5 (1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analvtics. A=Acceptable

Sample provided by Eckert & Ziegler Analytics U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

8-9

I TABLE 8.4-1 (Continued) I INTERLABORATORY INTERCOMPARISON PROGRAM SAMPLE Gamma Analysis of Water JAFNPP ELAB RESULTS REF. LAB* RATIO I

DATE ID NO. MEDIUM ANALYSIS pCi/liter +1 sigma pCi/liter +1 sigma (1) 6/19/2008 E5939-09 Water Ce-141 252 235 +

3.35 7.01 237 5+/- 3.96 1.04 A I

252 2.93 Mean = 246 213 +/-

2.8 13.8 I Cr-51 192 23.4 188 +/- 3.14 1.10 A 215 - 13.1 Cs-134 Mean = 207 112 115 10.1 1.71 4.29 104 +/- 1.74 I

1.08 A 109 + 1.58 Mean = 112 - 1.6 i 160 - 1.95 Cs-137 154 4.46 158 +/- 2.64 1.00 A 161 - 1.84 Mean = 158 - 1.7 90 - 1.66 Co-58 Mean =

91 89 4-

+/-

3.85 1.59 84 +/- 1.41 1.06 A I 90 - 1.5 Mn-54 208 192 207 2.22 4.95 2.11 184 +/- 3.07 1.10 A I Mean = 202 + 1.9 Fe-59 139 136 133

+/-

2.48 5.47 2.51 125 +/- 2.08 1.09 A I

Zn-65 Z-5185 Mean = 136 192 1

+

4-2.2 3.29 7.78

3. 172 2.88 1.08 I

180 + 3.12 +/- A Co-60 Mean = 186 147 145

+

3.0 1.4 3 142 - 2.37 1.03 A I

Mean 148 147 47 1.35 1.3 4.17 I

+

37 2.24 1-131**

Mean 44 40 42 4-

+/--

1.04 2.5 1.4 45.3 +/- 0.756 0.92 A I

(1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 1 I

8-10 I

I

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAFNPP ELAB RESULTS REF. LAB* RATIO I DATE 9/18/2008 1 ID NO.

E6249-05 MEDIUM Water T

ANALYSIS r

DCi/liter +/-1 sigma 108 +/--

+-

6.03 r

tpCi/liter +/-1 sima 1 (1) r 113 4.98 Ce-141 109 4.9 107 +/- 1.78 1.04 A

+-

115 4.42 Mean= 111 2.6 335 - 31.3 268 - 20.8 Cr-51 297 - 23.3 279 - 4.65 1.08 A 307 - 20.7 Mean 302 - 12.2 197 - 5.89 143 - 8.08 Cs-134 168 - 4.9 154 + 2.56 1.11 A 176 - 4.14 Mean= 171 - 3.0 116 +/- 5.11 114 + 3.98 Cs-137 102 - 3.88 107 +/-L 1.79 1.03 A 110 - 3.46 Mean 111 - 2.1 128 - 5.16 125 - 3.98 Co-58 119 - 4 118 - 1.97 1.06 A 128 - 3.77 Mean 125 - 2.1 122 - 5.4 118 +/- 4.02 Mn-54 131 - 4.24 110 - 1.84 1.13 A 127 - 3.68 Mean= 125 - 2.2 111 - 6.1 105 - 4.37 Fe-59 103 - 4.5 96 - 1.6 1.13 A 115 - 4.11 Mean = 109 - 2.4 218 - 10.9 217 - 8.18 Zn-65 239 - 8.68 211 - 3.53 1.05 A 216 +/- 7.7 Mean 223 - 4.5 162 - 4.47 149 - 3.39 Co-60 158 - 3.52 155 - 2.59 1.02 A 163 - 3.08 1 Mean= 158 - 1.8 109 +/-k 2.21 4-102 2.06 1-131** +/-- 105 +/- 1.75 11.00 A 105 2.03 Mean 105 4- 1.2 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Eckert & Ziegler Analytics U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

8-11

I TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I

SAMPLE Gamma Analvsis of Water JAFNPP ELAB RESULTS REF. LAB* RATIO I

DATE ID NO. j MEDIUM ANALYSIS pCi/liter +/-1 sigma j pCi/liter +/-1 sigma J (1) 12/11/2008 E6361-09 Water Ce-141 240 229 4.38 5.95 224 +/- 3.74 1.06 A I

244 + 4.4 Mean 238 324

+

+/-

2.9 20.5 I Cr-51 274 +/- 26.6 288 +/- 4.81 0.99 A Mean =

254 284 169

+

+/-

22.8 13.5 2.4 I

Cs-134 162 3.46 157 +/- 2.62 1.05 A I

+/-

165 +/- 2.76 Mean = 165 + 1.7 139 + 2.2 Cs-137 136 140

+/-

2.95 2.63 140 +/- 2.34 0.99 A I

Mean = 138 +/- 1.5 Co-58 123 126 125

+/-

2.29 3.24 2.71 122.0 +/- 2.03 1.02 A I Mn-54 Mean = 124.7 189 183

+/-

+/- 3 1.6 2.59 178 +/- 2.97 1.04 A I

183 +/- 3.01 Mean = 185 136

+/-

1.7 3.26 I

Fe-59 122 +/- 4.29 117.0 +/- 1.96 1.09 A Mean =

126 128 +/-

+/- 3.97 2.2 I

222 +/- 4.54 Zn-65 Mean =

228 230 227

+/-

6.06 5.21 3.1 214 +/- 3.57 1.06 A I

Co-60 163 162 160

+

+/-

1.79 2.36 2.16 156 16 +/-

+/- 2.6 26 1.04 10 A i Mean = 162 + 1.2 74.8

7.12 58.3

4.07 1-131** 64.1 +/- 1.07 1.03 A 64.1 +/- 7.2 (1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics Mean = 65.7 +/- 3.6 A=Acceptable I

U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

I 8-12

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamnia-Ahalysis of Milk SAMPLE JAFNPP ELAB RESULTS REF. LAB*

pCi/liter +/-+1 RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1) 3/20/2008 E5846-09 Milk 240 4- 13.8 245 4- 11.9 Ce-141 4-249 +/- 4.2 0.97 A 236 6.8 Mean = 240 :1- 6.5 371 +/- 65.6 Cr-51 384 50.4 359 6.0 1.04 A 370 - 30.2 Mean = 375 +/- 29.4 115 +/- 11.4 Cs-134 121 8.0 125 +/- 2.1 0.96 A 124 +/- 6.0 Mean = 120 : 5.1 147 - 10.9 Cs-137 143 8.9 146 +/- 2.4 0.97 A 135 - 5.1 Mean= 142 +/- 5.0 70.2 +/- 10.1 Co-58 64.2 7.2 71.0 +/- 1.2 0.96 A 70.4 + 4.6 Mean = 68.3 + 4.4 95.2 - 10.6 Mn-54 107 8.1 94 +/- 1.6 1.08 A 102 + 4.7 Mean= 101 - 4.7 120 - 15.2 Fe-59 125 10.6 102 +/- 1.7 1.12 A 98 + 6.6 Mean = 114 +/- 6.6 119 - 27.3 Zn-65 158 15.1 137 +/- 2.3 0.99 A 128 - 9.9 Mean = 135 +/- 10.9 239 - 10.9 Co-60 225 8.4 236 +/- 4.0 0.98 A 229 +/- 5.1 Mean = 231 +/- 4.9 59.6 8.6 61.7 6.5 1-131** +/- 60.0 +/- 1.0 1.01 A 60.7 5.5 Mean = 60.7 -+/- 4.0 (1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analvtics. A=Acceptable

Sample provided by Eckert & Ziegler Analytics U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

8-13

I TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I

Gamma Analysis of Milk SAMPLE JAFNPP ELAB RESULTS REF. LAB*

pCd/liter 4I RATIO I

DATE ID NO. MEDIUM ANALYSIS pCi/liter +1 sigma sigma (1) 6/19/2008 E5915-05 Milk Ce-141 173 177 i- 6.4 7.9 174 +/- 2.91 1.01 A I

177 6.8 Mean 176 185 4 4.1 24.7 I Cr-51 163 30.8 138 +/- 2.31 1.21 A Mean =

152 167 81

+/-

30.7 16.7 3.6 I

Cs-134 Mean =

80 85 82

+

+/-

5.3 4.4 2.6 77 +/- 1.28 1.07 A I

113 + 4.1 Cs-137 114 122 +/-

5 5.0 116 +/- 1.94 1.00 A I

Mean = 116 +/- 2.8 Co-58 59.6 54.961.9 70.1

+/-

4 3.6 4+/-

4.4 1.03 0.99 A I Mean = 61.5 145

+/-

2.4 4.5 I Mn-54 146 149 4- 661 5.5 135 2.26 1.09 A Mean = 147 94

+/-

4 3.1 4.9 I

Fe-59 99 6.9 92 +/- 1.53 1.05 A Mean =

97 97

+/-

5.7 3.4 I

120 +/- 7.5 Zn-65 132 123 +/-

10.1 9.3 127 +/- 2.12 0.98 A i

Mean = 125 +/- 5.2 Co-60 111 104 108

+/-

3.2 4.1 3.8 104 +/- 1.74 1.04 A I

+

Mean= 108 58.9 66.6 4-5:

2.1 2.7 2.9 I

1-131** +/--

71 +/- 1.19 0.88 A 62.1 3.0 (1) Ratio = Reported/Analvtics.

Mean = 62.5 5: 1.7 A=Acceptable I

Sample provided by Eckert & Ziegler Analytics U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

I 8-14

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamm'a Aiialvsis of Milk REF. LAB*

SAMPLE JAFNPP ELAB RESULTS pCi/liter +1 RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/--1 sigma sigma (1) 9/18/2008 1 E6251-05 Milk 168 7.29 172 :1- 7.69 Ce-141 4- 161 +/- 2.69 1.05 A 168 6.76 Mean = 169 4.19 411 A- 34.9 429 4- 37.2 Cr-51 459 456 4- 32 32.0 421 +/- 7.03 1.03 A Mean = 432 A- 20.1 241 A- 7.47 241 A- 7.81 Cs-134 236 236 4- 6.49 6.49 232 +/- 3.87 1.03 A Mean= 239 - 4.20 167 - 5.86 Cs-137 173 A- 6.86 162 +/-- 2.71 1.02 A 155 - 5.23 Mean = 165 - 3.48 188 A- 6.03 Co-58 177 177 4- 6.60 5.34 179 +/-- 2.98 1.01 A Mean = 181 - 3.47 193 A- 6.24 Mn-54 189 A- 7.16 166 +/-- 2.77 1.14 A 184 A- 5.65 Mean = 189 - 3.68 150 - 6.92 Fe-59 143 7.97 144 +/- 2.41 1.04 A 158 - 3.63 Mean= 150 A- 3.72 326 A- 13.3 Z65302 A- 15.1 Zn-65 3 342 4- 11 11.9 319 +/- 5.33 1.01 A Mean = 323 - 7.79 242 - 5.31 Co-60 242 - 6.25 234 +/- 3.91 1.02 A 231 - 4.75 Mean = 238 - 3.16 61.3 A- 2.17 61.6 A- 1.73 1-131** +/-- 67.9 +/- 1.13 0.89 A 59.3 1.75 Mean = 60.7 4- 1.09 (1) Ratio = Reoorted/Analvtics.

(1) Ratio = Renorted/Analvtics. A=Accentable

Sample provided by Eckert & Ziegler Analytics U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

8-15

I TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I

Gamma Analysis of Air Particulate Filter 1 [REF. LAB* TRATIO DATE SAMPLE ID NO. MEDIUM J ANALYSIS [

JAFNPP ELAB RESULTS pCi +/-1 sigma pCi +/-1 sigma (1) I 3/20/2008 1 E5821-05 Filter Ce-141 204 192 189

+/-

+

2.42 4.23 4.24 179 +/- 2.99 1.09 A I Mean 195 +/- 2.15 Cr-51 305 300

+/- 10.7 18.0 259 +/- 4.32 1.15 A I

289 +/- 20.9 Mean= 298 102

+/-

9.86 2.64 I

Cs-134 107 4.06 90.2 +/- 1.51 1.18 A Mean =

110 106.3 115

+/-

4.50 2.20 2.40 I

Cs-137 Mean =

116 120 117

+/-

3.81 4.42 2.10 105 +/- 1.75 1.11 A I

57 +/- 2.00 Co-58 56.4 55.5 +/-

3.06 3.48 51.0 +/- 0.852 1.10 A I Mean = 56.3 + 1.68 Mn-54 80.6 85.3

+/- 2.18 3.48 67.8 +/- 1.13 1.23 A I

85.1 +/- 4.19 Mean = 84 94.7

+/-

1.96 3.03 I Fe-59 86.3 4.94 73.7 +/- 1.23 1.22 A Mean =

88.9 90.0 116

+/-

5.80 2.73 4.59 I

124 7.13 Zn-65 Mean=

111 117

+

+/-

8.56 4.02 98.6 +/- 1.65 1.19 A I

182 2.55 I

+

181 +/- 3.91 Co-60 170 +/- 2.84 1.06 A 176 +/- 4.65 Mean = 180 +/- 2.20 I

___________ I ____________ .1 .1 .1. ______________________________ j._________________ +/- ________

(1) Ratio =Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable I

I 8-16 I

I

TABLE 8.4-4 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM

'"amma Analysis of"'AirParticulate Filter SAMPLE JAFNPP ELAB RESULTS I REF. LAB* RATIO DATE [ ID NO. [ MEDIUM I ANALYSIS pCi +/-1 sigma pCi +1 sigma j (1) 9/18/2008 E6250-05 Filter 170 +/- 4.28 Ce-141 170 +/- 3.6 159 +/- 2.65 1.07 A 172 +/- 3.95 Mean= 171 + 2.3 431 +/- 25.1 Cr-51 452 21.2 415 +/- 6.92 1.11 A 497 +/- 21.6 Mean 460 +/- 13.1 267 +/- 7.48 Cs-134 257 6.33 229 +/- 3.82 1.16 A 270 +/- 6.1 Mean= 265 +/- 3.8 163 +/- 5.88 Cs-137 163 4.96 160 +/- 2.67 1.02 A 162 + 4.71 Mean = 163 +/- 3.0 179 +/- 6.18 Co-58 200 5.36 176 +/- 2.93 1.08 A 191 + 4.91 Mean = 190 +/- 3.2 185 + 6.69 Mn-54 196 5.68 164 +/- 2.73 1.18 A 199 +/- 5.21 Mean = 193 +/- 3.4 169 +/- 7.73 Fe-59 164 6.55 142 +/- 2.37 1.16 A 160 + 5.79 Mean = 164 +/- 3.9 345 +/- 14 Zn-65 371 12.6 314 +/- 5.25 1.15 A 366 + 10.8 Mean= 361 +/- 7.2 228 +/- 5.87 238 +/- 4.89 Co-60 231 +/- 3.85 1.01 A 231 +/- 4.45 Mean= 232 +/- 2.9 (1) Ratio =Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-17

I TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil I

DATE

'i SAMPLE ID NO.

6/19/2008 1 E5916-05 MEDIUM Soil ANALYSIS JAFNPP ELAB RESULTS pCi/g =il sigma 0.359 4- 0.015 REF. LAB*

pCi'g +/-1 sigma I RATIO (1) I

+/-i Ce-141 0.364 0.381 0.386

+/--

0.014 0.008 0.013 0.380 +/- 0.006 0.98 A I Mean= 0.373 +/-i 0.006 0.345 0.276 +/-

+/- 0.089 0.056 I

Cr-51 0.346 +/- 0.035 0.302 + 0.005 1.03 A Mean 0.277 0.311 0.173

+/-

0.059 0.031 0.011 I

Cs-134 0.167 0.164 0.182

+/-

0.010 0.005 0.006 0.167 A: 0.003 1.03 A I Mean= 0.172 0.317 0.324

+/-

0.004 0.012 0.012 I

Cs-137 0.334 +/- 0.006 0.340 +/- 0.006 0.96 A Mean 0.333 0.327

+/-

0.007 0.005 I

0.117 +/- 0.011 Co-58 0.122 0.118 0.123

+/-

0.009 0.005 0.006 0.135 + 0.002 0.89 A I Mean = 0.120 0.289 0.301

+/-

0.004 0.013 0.012 I

Mn-54 Mean 0.314 0.294 0.300

+/-

+/-:

0.006 0.007 0.005 0.295 : 0.005 1.02 A I

Fe-59 0.173 0.194 0.185

+/-

0.015 0.014 0.007 0.200 +/- 0.003 0.93 A I

0.190 +/- 0.010 Mean= 0.186 0.257

+/-

0.006 0.020 I

0.289 +/- 0.018 Zn-65 Mean =

0.281 0.256 0.271

+/-:

+/-

+/-:

0.009 0.011 0.008 0.277 + 0.005 0.98 A I

Co-60 0.220 0.206 0.214 A:

+/-

0.009 0.008 0.004 0.228 +/- 0.004 1 0.93 A I

A:

(1) Ratio = Reported/Analytics.

Mean 0.208 0.212 0.005 0.003 A=Acceptable I

Sample provided by Eckert & Ziegler Analytics I

U=Unacceptable 8-18 I

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAFNPP ELAB RESULTS REF. LAB*1 RATIO DATE I ID NO. MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-1 sigma (1) 6/19/2008 E5918-05 Vegetation 0.381 4- 0.019 0.371 4- 0.015 Ce-141 0.390 +/- 0.007 0.95 A 0.358 4- 0.013 Mean 0.370 4-

= 0.009 0.311 +/- 0.081 Cr-51 0.371 +/- 0.065 0.309 +/- 0.005 1.14 A 0.378 +/-- 0.054 Mean = 0.353 +/- 0.039 0.171 a: 0.016 Cs-134 0.176 +/- 0.013 0.172 +/-4 0.003 1.03 A 0.184 +/-- 0.010 Mean = 0.177 +/- 0.008 0.272 +/- 0.015 Cs-137 0.257 +/- 0.013 0.260 +/- 0.004 0.98 A 0.235 +/- 0.011 Mean = 0.255 +/- 0.008 0.152 +/- 0.013 Co-58 0.142 0.011 0.138 +/- 0.002 1.03 A 0.131 +/-- 0.009 Mean = 0.142 +/- 0.006 0.293 +/- 0.016 Mn-54 0.325 +/- 0.015 0.302 +/-- 0.005 1.02 A 0.306 +/- 0.012 Mean = 0.308 +/-- 0.008 0.207 +/-- 0.018 Fe-59 0.215 +/- 0.017 0.205 +/- 0.003 1.04 A 0.219 +/- 0.014 Mean = 0.214 +/- 0.009 0.306 +/-: 0.027 Zn-65 0.240 +/- 0.022 0.284 +/- 0.005 0.97 A 0.282 +/-- 0.019 Mean = 0.276 +/- 0.013 0.216 A- 0.011 0.235 A-0.011 Co-60 +/-- 0.233 +/- 0.004 0.95 A 0.212 0.008 Mean 0.221 4- 0.006 (1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable 8-19

I TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I

Gamma Analysis of Vegetation DATE I SAMPLE ID NO. MEDIUM ANALYSIS JAFNPP ELAB RESULTS pCi/g +/-1 sigma REF. LAB*

pci/g + sigma RATIO (1)

I 9/18/2008 1 E6302-09 I Vegetation Ce-141 0.447 0.447 0.473

+/-

0.023 0.017 0.018 0.474 +/- 0.008 0.96 A I

0.011 Cr-51 Mean 0.456 1.200 1.160

+

+/-

0.129 0.086 1.240 +/- 0.021 0.95 A I

1.170 +/- 0.098 Mean = 1.177 0.760

+/-

0.061 0.031 I

Cs-134 0.738 0.024 0.683 +/- 0.011 1.08 A I

+/-

0.708 +/- 0.026 Mean = 0.735 +/- 0.016 0.407 +/- 0.024 Cs-137 Mean=

0.422 0.417 0.415

+/-

0.017 0.020 0.012 0.477 +/- 0.008 0.87 A I

Co-58 0.552 0.500 0.492

+/-

+

0.027 0.019 0.020 0.525 +/- 0.009 0.98 A I Mean 0.515 +/- 0.013 Mn-54 0.467 0.503

+

+/-

0.027 0.019 0.489 +/- 0.008 1.01 A I

0.518 +/- 0.022 Mean 0.496 0.382

+/-

0.013 0.030 I Fe-59 0.432 +/- 0.021 0.425 +/- 0.007 0.97 A Mean 0.428 0.414 0.808

+/-

+

0.025 0.015 0.056 I

Zn-65 Mean=

0.917 0.930 0.885

+/-

0.040 0.046 0.027 0.939 +/- 0.016 0.94 A I

+/-

0.673 0.024 Co-60 0.659 0.632

+

4-0.016 0.018 0.690 +/- 0.012 0.95 A I Mean = 0.655 0.008 (1) Ratio = Reported/Analytics.

Sample provided by Eckert & Ziegler Analytics I A=Acceptable U=Unacceptable I

8-20

ML091390825

Contents

Text

SUBJECT:

Enclosure:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

Navigation menu

ML091390825

Text

SUBJECT:

Enclosure:

SUMMARY

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

2.0 INTRODUCTION

2.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

5.3 CONCLUSION

5.4 REFERENCES

SUMMARY

8.5 REFERENCES

Navigation menu

Search