Text

2007 Annual Radiological Environmental Operating Report
	ML081410299
Person / Time
Site:	Nine Mile Point
Issue date:	05/08/2008
From:	Syrell T; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081410299 (186)
	v • d • e

Constellation Energy-Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, New York 13093 May 8, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:

SUBJECT:

Document Control Desk Nine Mile Point Nuclear Station Unit Nos. 1 & 2; Docket Nos. 50-220 & 50-410 2007 Annual Radiological Environmental Operating Report In accordance with the Technical Specifications for Nine Mile Point Nuclear Station, Units 1 and 2, enclosed is the 2007 Annual Radiological Environmental Operating Report for the period January 1, 2007 through December 31, 2007.

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, Terry F. Syre I' Licensing Director TFS/KES

Enclosure:

2007 Annual Radiological Environmental Operating Report cc:

S. J. Collins, NRC Region I Administrator R.V. Guzman, NRC Project Manager J. Furia, NRC Senior NRC Resident Inspector

ENCLOSURE 2007 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Nine Mile Point Nuclear Station, LLC May 8, 2008

Constellation Energy Nine Mile Point Nuclear Station NINE MILE POINT NUCLEAR STATION, LLC 2007 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

NINE MILE POINT NUCLEAR STATION, LLC ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2007 - December 31, 2007 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.

82 Program Schedule 8-2 8.3 Acceptance Criteria 8-2 8.4 Program Results Summary 8-4 8.5 References 8-23 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 Requ ired Sample Collection and Analysis, Nine Mile Point Unit 2 3-6 Table 3.3-1 2007 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 Table 6-1 Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2007 6-2 Table 6-2 Concentrations of Gamma Emitters in Fish Samples - 2007 6-3 Table 6-3 Concentrations of Tritium in Surface Water Samples - 2007 6-6 Table 6-4 Concentrations of Gamma Emitters in Surface Water Samples - 2007 6-7 Table 6-5 Concentration of Tritium, Strontium, and Gamma Emitters in 6-12 Groundwater Samples - 2007 Table 6-6 Environmental Airborne Particulate Samples - 2007; Offsite Sample 6-13 Locations Table 6-7 Environmental Airborne Particulate Samples - 2007; Onsite Sample 6-15 Locations Table 6-8 Concentrations of Gamma Emitters in Quarterly Composites of 6-17 JAF/NMPNS Site Air Particulate Samples - 2007; Offsite Sample Locations Table 6-9 Concentrations of Gamma Emitters in Quarterly Composites of 6-19 JAF/NMPNS Site Air Particulate Samples - 2007; Onsite Sample Locations Table 6-10 Environmental Charcoal Cartridge Samples -2007; Offsite Sample 6-21 Locations Table 6-11 Environmental Charcoal Cartridge Samples - 2007; Onsite Sample 6-23 Locations Table 6-12 Direct Radiation Measurement Results - 2007 6-25 iii

LIST OF TABLES (continued)

Page Table 6-13 Concentrations of Iodine-131 and Gamma Emitters in Milk - 2007 6-2 8 Table 6-14 Concentrations of Gamma Emitters in Food Products - 2007 32 Table 6-15 Milk Animal Census - 2007 6-34 Table 6-16 ResidenceCensus - 2007 6-35 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 (NMPl) 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 NMP I 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 2007 there were 1945 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. Cesium-137 was detected in one aquatic pathway (shoreline sediment) at very low levels and was attributed to fallout from past weapons testing. The 2007 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 2007 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 NMPI and NMP2 remained significantly below the federally required dose limits specified in 10CFR20 and 40CFR190.

1-1

SECTION

2.0 INTRODUCTION

Nine Mile Point Units I 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 2007.

Nine Mile Point Unit I (NMP1) and Nine Mile Point Unit 2 (NMP2) Radiological Environmental Monitoring Program (REMP) requirements reside within the NMPI Offsite Dose Calculation Manual (ODCM) and NMP2 ODCM, respectively.

Throughout this report references will be made to the ODCM. This refers to both the NMP 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, NMPI, 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 NMPI 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 NMPI 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

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2.2 SITE DESCRIPTION The Nine Mile Point Site is located on the southeast shore of Lake Ontario in the town of Scriba, I

approximately 6.2 miles northeast of the city of Oswego. The nearest metropolitan area 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.,

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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 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 and/or Sample Number of Samples (a) and Locations Sampling and Collection Frequency (a)

Type of Analysis and Freciuency AIRBORNE

a. Radioiodine and Particulates Samples from five locations; Continuous sampler operation with sample collection weekly or as required by dust loading, whichever is more frequent.

Three samples from offsite locations in different sectors of the highest calculated site average D/Q (based on all site licensed reactors).

One sample from the vicinity of an established year round community having the highest calculated site average D/Q (based on all site licensed reactors).

One sample from a control location 10-17 miles distant and in a least prevalent wind direction (d) 32 stations with two or more dosimeters to be placed as follows: an inner ring of stations in the general area of 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.

Radioiodine Canisters -

analyze once/week for 1-131.

Particulate Samplers -

Gross beta radioactivity following filter change (b)

Composite (by location) for gamma isotopic analysis (c) once per 3 months, (as a minimum).

b. Direct Radiation (e)

Once per 3 months Gamma dose once per 3 months.

")

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 TABLE 3.0-1 (Continued)

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

Type of Analysis and Frequency WATERBORNE

a. Surface M One sample upstream.

Composite sample over 1 month period (g)

One sample from the site's downstream cooling water intake.

One sample from a'downstream area with existing or potential recreational value.

Gamma isotopic analysis (c) once/month. Composite for once per 3 months tritium analysis.

Gamma isotopic analysis (c)

b. Sediment from Shoreline Twice per year INGESTION

a. Milk Samples from milk sampling.locations in three locations within 3.5 miles distance having the highest calculated site average D/Q. If there are none, then one sample from milking animals in each of 3 areas 3.5 - 5.0 miles distant having the highest calculated site average D/Q (based on all site licensed reactors).

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

Twice per month, April -

December (samples will be collected in January - March if 1-131 is detected in November and December of the preceding year).

Gamma isotopic (c) and 1-13 1 analysis twice per month when animals are on pasture (April -

December); once/month at other times (January -

March) if required.

3-3

TABLE 3.0-1 (Continued)

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

Type of Analysis and Frequency

b. Fish

One sample each of two commercially or recreationally important species in the vicinity of a plant discharge (h) area One sample each of the same species from an area at least 5 miles distant from the site (d)

Samples of three different kinds of broad leaf vegetation (such as vegetables) grown nearest to each of two different off-site locations of highest calculated site average D/Q (based on all licensed site reactors).

One sample of each of the similar broad leaf vegetation grown at least 9.3 - 20 miles distant in a least prevalent wind direction.

Twice per year Gamma isotopic analysis (c) on edible portions twice per year.

c. Food Products Once per year during harvest season Gamma isotopic (c) analysis of edible portions (Isotopic to include 1-131 or a separate 1-131 analysis may be performed) once during the harvest season.

3-4 m

M M

m M

M M

M m m

m

-M mM 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.

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

Sampling and Collection Frequency Type of Analysis and Frequency AIRBORNE

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

Once per 3 months Gamma dose once per 3 months 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 (1) 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 (c)

(1)

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

3-6 M

M M

U M

M M

1

=

M M

nMml

M M

m m

M M

M u

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 and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Frequency Type of Analysis and Frequency

b. Airborne Radioiodine and Particulates Samples from five locations:

Three samples from offsite locations close to the site boundary (within one mile) in different sectors of the highest calculated annual site average ground-level D/Q (based on all site licensed reactors).

One sample from the vicinity of an established year-round community having the highest calculated annual site average ground-level D/Q (based on all site licensed reactors).

One sample from a control location at least 10 miles distant and in a least prevalent wind direction (c).

Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading Radioiodine Canister 1-131 analysis weekly Particulate Sampler Gross beta radioactivity analysis >_ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change (d),

Gamma isotopic analysis on each sample where gross beta activity is >10 times the previous yearly mean of control samples and gamma isotopic analysis (e) of composite sample (by location) once per 3 months.

WATERBORNE

a. Surface One sample upstream (c) (M Composite sample over 1-month period (9.

Gamma isotopic analysis (e) once per month and tritium analysis once per 3 months.

One sample from the site's downstream cooling water intake (Q.

3-7

TABLE 3.0-2 (Continued)

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

Sampling and Collection Frequency Type of Analysis and Frequency

b. Ground

c. Drinking

d.

Sediment from Shoreline Samples from one or two sources if likely to be affected (h)

One sample each of one to three of the nearest water supplies that could be affected by its discharge (i)

One sample from a downstream area with existing or potential recreational value.

Grab sample once per 3 months.

Composite sample over a 2-week period~g) when 1-131 analysis is performed; monthly composite otherwise.

Twice per year Gamma isotopic (e) and tritium analysis once per 3 months.

1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year. 0) Composite for gross beta and gamma isotopic analyses (e) monthly. Composite for tritium analysis once per 3 months.

Gamma isotopic analysis(e) 3-8 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 and/or Sample Number of Samples and Sample Locations (a)

Sampling and Collection Freauencv Type of Analysis and Freciuencv INGESTION

a.

Milk Samples from Milk Sampling Locations in three locations within 3.5 miles distance, having the highest calculated annual site average D/Q (based on all licensed site reactors). If there are none, then 1 sample from Milk Sampling Locations in each of three areas 3.5

- 5.0 miles distant having the highest calculated annual site average D/Q (based on all licensed site reactors).

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

One sample each of two commercially or recreationally important species in the vicinity of a plant discharge (k) area One sample of the same species in areas not influenced by station discharge (c).

Twice per month, April -

December (samples will be collected January - March if 1-131 is detected in November and December of the preceding year).

Gamma isotopic (e) and 1-131 analysis twice/month when animals are on pasture (April -

December); once per month at other times (January - March if required).

b.

Fish Twice per year Gamma isotopic analysis (e) on edible portions twice per year.

3-9

TABLE 3.0-2 (Continued)

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

Sampling and Collection Frequency Type of Analysis and Frequency

c. Food Products One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged (1).

At time of harvest (M)

Gamma isotopic (e) and 1-131 analysis of each 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).

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

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)

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.

(d)

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.

(e)

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

(f)

The "upstream" sample shall be taken ata distance beyond significant influence of the discharge.

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

(g)

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.

(h)

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.

(i)

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

(j)

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.

3 - 11

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NOTES FOR TABLE 3.0-2 (Continued)

(k)

In the event two commercially or recreationally important species are not available after three I

attempts of collection, then two samples of one species or other species not necessarily commercially or recreationally important may be utilized.

(1)

Applicable only to major irrigation projects within 9 miles of the site in the general downcurrent direction.

(m)

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.

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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 off shore from the site. One set of control samples are

collected at an off-site sample -transect located off shore 8 - 10 miles west of the site. Available species are selected using the following guidelines:

a.

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

b.

Samples are composed of 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 approximately 7.6 miles west of the site. This "upstream" location is considered a control location 3-13

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.

3 Samples from the JAFNPP facility are composited from automatic sampling equipment, which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitters. Samples from the Oswego Steam Station are also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample.

The monthly samples are analyzed for gamma emitting radionuclides.

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

3 In addition to the sample results for the JAFNPP and Oswego Steam Station collection sites, data is presented for the Nine Mile Point Unit I (NMP1) and Nine Mile Point Unit 2 (NMP2) facility 3

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 i

three locations are analyzed for gamma emitting nuclides, and quarterly composite samples are analyzed for tritium.

3 Sampling for groundwater and drinking water, as found in Section D 3.5.1 of the NMP2 ODCM, was not required during 2007. There was no groundwater source in 2007 that was 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 2007.

3 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 was established to i

determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids. Under the Groundwater Protection Initiative I

(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 I

several years. Samples collected from these locations are analyzed for tritium, gamma emitters, and strontium.

3 3-14

During the operating year 2007, 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 2007. There was no groundwater source in 2007 that was 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 2007.

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 DI, G, H, I, J, and K. These locations are within the site boundary of the NMPNS and JAFNPP.

One air sampling station is located Offsite in the 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 inch). The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis.

Sample volume is determined by use of calibrated gas flow meters located at the sample discharge. Gross beta analysis is performed on each particulate filter. Charcoal cartridges are analyzed for radioiodine using gamma spectral analysis. The particulate filters are composited quarterly. by location and analyzed for gamma emitting radionuclides.

3 -15

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

3 3.1.6 TLD (DIRECT RADIATION) 3 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% CaSO4: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:

I TLD Geographical Category Description I

Onsite TLDs placed at various locations within the Site Boundary and are 3

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 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 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*)

3-16

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*, l11, 113)

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

Two dosimeters are placed at each TLD monitoring location.

The TLDs are sealed in polyethylene packages to ensure dosimeter integrity, 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 four farms during the sampling year. These farms include three indicator locations and one control location. Samples are normally collected April through December of the sample year.

If. plant related radionuclides are detected 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 2007 as there were no positive detections of plant related radionuclides in samples collected during November and December 2006.

3-17

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.

I 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 3

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 3

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 3

similar type of vegetation when available.

Food product samples are analyzed for gamma emitters using gamma isotopic analysis.

3 Food product locations are shown in Section 3.3, Figure 3.3-5.

3 3.2 ANALYSES PERFORMED I

The following environmental sample analyses are performed by the JAFNPP Environmental Laboratory:

3

" Air Particulate Filter - Gross Beta

Air Particulate Filter Composites - Gamma Spectral Analysis 3

" Airborne Radioiodine - Gamma Spectral Analysis

Fish - Gamma Spectral Analysis

" Food Products (Vegetation) - Gamma Spectral Analysis

Milk - Gamma Spectral Analysis and 1-131

" Shoreline Sediment-Gamma Spectral Analysis 1

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

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 Section 3.3, Figures 3.3-1 through 3.3-6 provides maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps.

This section also contains an environmental sample 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 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 2007 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP DEGREES &

MEDIUM DESIGNATION FIGURE NUMBER LOCATION DESCRIPTION DISTANCE (1 & 2)

Shoreline Sediment 5*

Figure 3.3-5 Sunset Bay 82' at 1.4 miles Sunset Bay (3) 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 62' at 0.8 miles 00*

Figure 3.3-5 Oswego Transect - Control 237' at 5.9 miles Surface Water 03*

Figure 3.3-4 FitzPatrick Inlet 71' 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 319' at 0.3 miles 10 Figure 3.3-4 Oswego City Water 240' at 7.8 miles 11 Figure 3.3-4 NMP Unit 2 Inlet 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 92' at 1.8 miles Particulates R-2*

Figure 3.3-3 R-2 Station, Lake Road 106' at 1.1 miles R-3*

Figure 3.3-3 R-3 Station, Co. Rt. 29 134' at 1.4 miles R-4*

Figure 3.3-3 R-4 Station, Co. Rt. 29 145' at 1.8 miles R-5*

Figure 3.3-2 R-5 Station, Montario Point - Control 42' at 16.2 miles D1 Figure 3.3-3 Dl On-Site Station 73 0 at 0.3 miles G

Figure 3.3-3 G On-Site Station 2440 at 0.7 miles H

Figure 3.3-3 H On-Site Station 740 at 0.8 miles I

Figure 3.3-3 I On-Site Station 96' 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 Bm M

o m

M m

m M

M M

M

m m

m TABLE 3.3-1 (Continued) 2007 ENVIRONMENTAL SAMPLE LOCATIONS MAMPLE MAP -FIGURENUMBER LOCATION DESCRIPTION DEGREES &

MEDIUM DESIGNATION F

DISTANCE (I & 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 1430 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 2130 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 192' at 7.7 miles 13 Figure 3.3-2 G Off-Site Station 226' 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 83' 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 96' 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 60' 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-1 278' at 0.2 miles 39 Figure 3.3-3 North Fence NMP-1 296' 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 1680 at 19.7 miles 51 Figure 3.3-2 Oswego Steam Station, East 234' at 7.3 miles 52 Figure 3.3-2 Fitzhugh Park Elementary School, East 2270 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) 2007 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP DEGREES &

MEDIUM IDESIGNATION FIGURE NUMBER LOCATION DESCRIPTION DISTANCE (1 & 2)

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 2220 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 27' 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 86' 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 180' 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 2900 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 1120 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 1830 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 2240 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 3.6 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 M

M M

m m

m m m m

m m

TABLE 3.3-1 (Continued) 2007 ENVIRONMENTAL SAMPLE LOCATIONS SAMLE

-7..

FIGURE NUMBER LOCATION DESCRIPTION DEGREES&

MEDIUM DESIGNATION DISTANCE (1 & 2)

Thermoluminescent 105 Figure 3.3-3 Lakeview Road 199' 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 2710 at 0.3 miles 108 Figure 3.3-3 Lake Road 105' at 1.1 miles 109 Figure 3.3-3 Lake Road 104' at 1.1 miles 111 Figure 3.3-2 Sterling, NY - Control 2140 at 21.8 miles 112 Figure 3.3-2 EOF/Env. Lab, Oswego County Airport 175' at 11.9 miles 113 Figure 3.3-2 Baldwinsville, NY - Control 1780 at 24.7 miles Cows Milk 76 Figure 3.3-4 Indicator Location 120' at 6.3 miles 55 Figure 3.3-4 Indicator Location 970 at 8.8 miles 4

Figure 3.3-4 Indicator Location 115' at 7.6 miles 77*

Figure 3.3-4 Control Location 1900 at 16.0 miles Food Products 132*

Figure 3.3-5 Indicator Location 1100 at 2.0 miles 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 1600 at 0.3 miles GMXMW-2 Figure 3.3-6 Upland Well - Control 1980 at 0.3 miles Outfall 001 Figure 3.3-6 NMP2 Dewatering System - Indicator 32 0 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)

(3) New control location established due to shoreline erosion.

Sample location required by ODCM 3-23

FIGURE 3.3-1 NEW YORK STATE MAP CANADA VEIMONT NPV YORK

/V,0 8IJPAUO RIIVS

('W.A I

?

0\\N ALa4HY*

Mt8ANAHUSEtTS PENSYLVAH CONNECTICUT NINE MILE POINT SITE:

Nine Mile Point Nuclear Station Unit - 1 Nine Mile Point Nuclear Station Unit - 2 James A. FitzPatrick Nuclear Power Plant 3-24 mm-M M

M m

m m

m

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

Site Map 56.25" K

Lake Ontario 33.75.

m m

MAPinu of usui OSWEGO COUNTY New York Ge -a 3-27

10 MI0 3-28 II S

14 3 -28I

FIGURE 3.3-6 NMPNS ON-SITE GROUNDWATER MONITORING WELLS AND UNIT 2 STORM DRAIN OUTFALL Monitoring Well Location AA Storm Drain Outfall 001 I

LAKE ONTARIO MW-5

)utfall 001 MW-4 MW-3 MW-2 Unit 2 Storm SSE t2 GMX-MW-1 D

S 3 -29

I 3.4 LAND USE CENSUS I

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.

i 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 food product samples. The results of the garden census are not provided in this report. The results are used only to identify appropriate sample locations. The garden census is not required by the, ODCM if broadleaf vegetation sampling and analysis is performed.

3.5 CHANGES TO THE REMP PROGRAM The following changes were implemented during the 2007 sampling program:

A.

Food Product Sampling Program During the report period, one food product location was added and one food product location was removed to the REMP. These locations are used to implement the requirements of the NMPl ODCM, Part I, Table D 3.6.20-1 and the NMP2 ODCM, Part I, Table D 3.5.1-1. Sample locations selected were based on the 2007 annual land use census and were utilized to implement the 2007 food product requirements.

I B.

During the reporting period, one of the milk locations ceased milk production in May of 2007. Samples were obtained from Sample Location #4 during April and May 2007. This 3-30 II

location was used as indicator location even though NMP1 ODCM, Part I, Table D 3.6.20-1 and the NMP2 ODCM, Part I, Table D 3.5.1-1 does not require monitoring.

C.

During the reporting period, groundwater monitoring was implemented into the REMP.

Groundwater samples are used to implement the NEI Groundwater Protection Initiative.

3.6 DEVIATION AND EXCEPTIONS TO THE PROGRAM The noted exceptions to the 2007 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 NMP 1 ODCM and Section D 4.1.2 of the NMP2 ODCM.

A.

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

1. The flow control valve at air station pump R-2 was found chattering during the sample period of 1/30/07 to 2/6/07. The volumetric flow rate was outside of the acceptance criteria of the procedure. The sample pump was replaced and flow rate was return to normal.

2. The air sampling pump at the R-1 and R-2 Environmental Sampling Station was inoperable for approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during the sample period of 7/3/07 through 7/10/07. 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.

3.

The air sampling pump at the R-1 and R-2 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 9/10/07 through 9/18/07. 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-1 and R-2 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 9/25/07 through 10/2/07. 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.

3 -31

B.

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

The collective operable time period for the air monitoring stations was 43,656 hours0.00759 days 0.182 hours 0.00108 weeks 2.49608e-4 months out of a possible 43,680 hours0.00787 days 0.189 hours 0.00112 weeks 2.5874e-4 months . The air sampling availability factor for the report period was 99.95%.

3.7 STATISTICAL METHODOLOGY i

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

~I 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 II I

X 'Xi 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 -32

B.

Standard Deviation 1/2 n

S=

-*(Xi-

)2 L (N -1) j

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 x

xj i=l 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

B.

Error of the Mean (Reference 18)

ERROR MEAN =

(ERROR)2 N

Where, ERROR MEAN

= propagated error i

= individual sample ERROR

= I sigma* error of the individual analysis N, n

= number of samples with positive indications Sigma ((Y)

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.

3.7.3 LOWER LIMIT OF DETECTION (LLD)

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

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

4.66 Sb I

I I

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 volume);

Sb

=

the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

E

=

the counting efficiency (in counts per disintegration);

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 ofNMP 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 2007, 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 (DCi/i)

Airborne Particulate or Gases (pCi/mr3)

Fish (pCi/kg, wet)

Milk (pCi/I)

Food Products (pCi/kg, wet)

Sediment (pCi/kg, dry)

Gross Beta H-3 Mn-54 Fe-59 4

0.01 3000 (a)

Co-58, Co-60 Zn-65 Zr-95, Nb-95 1-131 Cs-134 Cs-137 Ba/La-140 15 30 15 30 15 130 260 130 260 15 (a) 15 18 15 0.07 0.05 0.06 1

130 150 15 18 15 60 60 80 150 180 (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 1-13 1.

3 -36

/----

/

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 I

3.9.2 Environmental Protection Agency (EPA)

The EPA, in 40CFRl90.10 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, I

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

U I

I Ij 3 -38 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 2.

2.

3.

4.

5.

6.

7.

Sample medium.

Type and number of analyses performed.

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).

The mean and range of the positive measured values of the indicator locations.

The mean, range, and location of the highest indicator annual mean. Location designations are keyed to Table 3.3-1 in Section 3.3.

The mean and range of the positive measured values of the control locations.

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

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2007*

Shoreline Sediment (pCi/kg-dry)

GSA (5):

Cs-134 Cs-137 150 180

<LLD

<LLD 0

0 38.3 (1/3) 38.3 No. 5:

38.3 (1/3) 1.4 miles at 840 38.3 F

+/-

I

+

4 GSA (22): (h)

Fish (pCi/kg-wet)

GSA (22): (h)

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 130 260 130 130 260 130 150

<LLD

<LLD 0

0 0

a -

S S

S 4-2

=1 M

M

ý

ý M

M M

Ml IMI Ml III-III IImm -I

-I III-I

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT I DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2007*

TYPE AND NUMIBER INDICATOR LOC)(ATION (b FHIHS CONTROL LCI10\\

NUMBER OF MEIM(NT)

\\,L'E*

LLD(a)

~LOCATIONS:

ANUAL MEN EN(f)/ RANGE NON ROUTFINE I RANG-E....

I iiN tiii IAN!:

.REPORTS*'*

MEAN (f) / A(1 LocATI 1N,1,t MEAN (1)/RAýNGEl

_FOT Surface Water H-3 (8):

(pCi/liter)

H-3 3000(c)

<LLD

<LLD 0

GSA (24):

Mn-54 15

<LLD

<LLD 0

Fe-59 30

<LLD

<LLD 0

Co-58 15

<LLD

<LLD 0

Co-60 15

<LLD

<LLD 0

Zn-65 30

<LLD

<LLD 0

Zr-95 15

<LLD

.<LLD 0

Nb-95 15

<LLD

.<LLD

.0 1-131 15(c)

<LLD

<LLD 0

Cs-134 15

<LLD

<LLD 0

Cs-137 18

<LLD

<LLD 0

BaILa-140 15

<LLD

<LLD 0

4-3

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2007*

TLD (mrem per standard month)

Gamma Dose (140)

(d) 4.9 (120/120) (i) 3.0-9.0 TLD #75 (g):

0.1 miles at 354' 8.5(4/4) 7.8-8.8 4.4 (20/20) 3.2-5.8 0

Air Particulates Gross Beta (260):

0.01 0.016 (208/208)

R-4 0.017 (52/52) 0.016 (52/52) 0 (pCi/m3 )

0.007 - 0.028 1.8 miles at 1450 0.007 - 0.027 0.008 - 0.028 1-131 (260):

0.07

<LLD

<LLD 0

GSA (60):

Cs-134 0.05

<LLD

<LLD 0

Cs-137 0.06

<LLD

<LLD 0

Milk GSA (58): (e) (h)

(pCi/liter)

Cs-134 15

<LLD

<LLD 0

Cs-137 18

<LLD

<LLD 0

Ba/La-140 15

<LLD

<LLD 0

1-131 (58):

1-131 1

<LLD

<LLD 0

4-4

ý

ý M

M M

i m

m

-M M

~

i m

m w

D m

m m

m mi m

m mlm m m

m m

TABLE 4.0-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT. 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 2007*

Food Products (pCi/kg-wet)

GSA (25): (h) 1-131 Cs-134 Cs-137 60 60 80

<LLD

<LLD 0

0 0

i~i I

i I

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 ODCMs. 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 ODCMs 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 ODCMs do not specify a particular LLD value to environmental TLDs. The NMP1 and NMP2 ODCM contains specifications for environmental TLD sensitivities.

(e)

=

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

(f)

=

Fraction of number of detectable measurements to total number of measurements. Mean and range results are based on detectable measurements only.

(g)

=

This dose is not representative of doses to a member of the public since this area is located near the north shoreline which is in close proximity to the generating facility and is not accessible to members of the public (See Section 5.2.4, TLDs).

(h)

=

Data includes results from optional samples in addition to samples required by the ODCMs.

(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

-Mm-m m

M m

m M

M mm

SECTION 5.0 DATA EVALUATION AND DISCUSSION

5.0 DATA EVALUATION AND DISCUSSION A.

Introduction Each year the results of the Annual Radiological Environmental Monitoring Program (REMP) are evaluated considering plant operations at the site, the natural processes in the environment and the archive of historical environmental radiological data.

A number of factors are considered in the course of evaluating and interpreting the Annual Environmental Radiological Data. This interpretation can be made using several methods including trend analysis, population dose estimates, risk estimates to the general population based on significance of environmental concentrations, effectiveness of plant effluent controls and specific research areas. The report not only presents the data collected during the 2007 sample program but also assesses the significance of radionuclides detected in the environment. It is important to note that detection of a radionuclide is not, of itself, an indication of environmental significance. Evaluation of the impact of the radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary to determine the true significance of any detection.

B.

Units of Measure Some of the units of measure used in this report are explained below.

Radioactivity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second.

Smaller units of the curie are used in this report. Two common units are the microcurie (uCi), which is one millionth (0.00000 1) 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

I C.

Dose/Dose to Man The dose or dose equivalent, simply put, is the amount of ionizing energy deposited or 3

absorbed in living tissue.

The amount of energy deposited or ionization caused is dependent on the type of radiation. For example, alpha radiation can cause dense localized ionization that can be up to 20 times the amount of ionization for the same energy imparted as from gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation.

The dose equivalent is measured in rem (roentgen. equivalent man).

In terms of environmental radiation, the rem is a large unit. Therefore, a smaller unit, the millirem (mrem) is often used. One millirem (mrem) is equal to 0.001 of a rem.

i The term "dose to man" refers to the dose or dose equivalent that is received by members 3

of the general public at or beyond' the site boundary. The dose is calculated based on concentrations of radioactive material measured in the environment.

The primary pathways that contribute to the dose to man are: the inhalation pathway, the ingestion I

pathway and direct radiation.

D.

Discussion There are three separate groups of radionuclides that were measured in the environment in I

the media analyzed for the 2007 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-occurring radioactive isotopes in the human body like potassium-40, medical procedures, man-made phosphate fertilizers (phosphates and uranium are often found together in i

nature), and household items like televisions. In the United States, a person's average annual exposure from background radiation is 360 mrem, as illustrated on the following Background Radiation Chart.

5-'I 5-23

Background Radiation ALL SOURCES RADIATION EXPOSURE 360 mremlyr MAN-MADE SOURCES RADON 55%

MEDCAL X-RAYS 11%

MAN

%NUCLEAR MEICINE4%

cosmIc 8%

MAN-MADE18%

CONSUMER PRODUCTS 3%

OTlercl%

Occupational 0.3%

Fallout

<0.3%

Nuclear Power 0.1%

Miscellaneous 0.1%

Radiation Exposure In the U.S.

(Percent of Total Effective Dose)

NCRP 93, 1987 A number of radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. These radionuclides are expected to be present in many of the environmental samples collected in the vicinity of the Nine Mile Point Site. Some of the radionuclides normally present include:

Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere,

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

Potassium -40 and radium-226, naturally occurring radionuclides found in the human body and throughout the environment, and o Fallout radionuclides from nuclear weapons testing, including cesium-137 and strontium-90.

Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are abundant, positive results for these radionuclides are reported in some cases in Section 6.0 of this report. Comparisons of program samples to natural background 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 radionucli des that were detected are a result of the detonation ofI thermonuclear devices in the earth's atmosphere. Atmospheric nuclear testing during the early 1 950s produced a measurable inventory of radionuclides presently found in the lower 3

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 testing3 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 many3 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 I

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 thoseI produced in atmospheric weapons testing and found in the Chernobyl fallout.

This commonality makes a determination of the source of these radionuclides that may be3 detected in environmental-samples difficult to determine. During 2007, Cs-137 was the only potential plant-related radionuclide detected in the REMP samples.

A number of factors must be considered in performing radiological sample data evaluation and interpretation.

The evaluation is made using several approaches including trend3 analysis and dose to man. An attempt has been made not only to report the data collected during 2007, 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 environmental3 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 2007.

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 2007 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 3

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 3

" Groundwater Section 6.0, Tables 6-1 through 6-5 present the analytical results for the aquatic samples collected for the 2007 sampling period.

5.1.1 SHORELINE SEDIMENT RESULTS 3

A.

Results Summary Shoreline sediment samples were obtained in April and October of 2007 at one offsite control location (Lang's Beach located near Oswego Harbor) and at one indicator location (Sunset Bay) which is an area east of the site considered to have recreational value.

A total of five sediment samples were collected for the 2007 sample program, three indicator and two control. Cs-137 was detected in one of the samples collected from the Sunset-Bay indicator location in 2007, measuring 0.038 pCi/g (dry). This result continues I

to show a. downward trend over the last 10 years. Cs-137 wasnot detected in samples collected from the control location during 2007; however, Cs-137 has been detected in the 3

control samples in 1993 at an average concentration of 0.03 pCi/g.

The general lack of Cs-137 at the control location is attributed to the differences in the 3

sediment types between the two sample locations (See Data Evaluation and Discussion). The source of the Cs-137 detected in the indicator shoreline sediment is considered to be the result 3

of fallout from atmospheric nuclear weapons testing and not from operations at the site. The mean concentration of Cs-137 measured in the 2007 indicator sample is consistent with 5-6

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 pCi/g in 1993 to a minimum of 0.038 pCi/g (dry) in 2007. The results for the 2007 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 2007 shoreline sediment samples.

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

The following is a graph of the average Cs-137 concentration in shoreline sediment samples over the previous ten years. This graph illustrates a general downward trend in the Cs-137 concentrations since 1998.

Shoreline Sediment Cs-137 0.09 0.08 0.07

~0.06 0.05 R) nnl U Control-U Indicator 0.03 -

0-1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year

< Lower 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 2007. The results of these sample collections are presented in Section 6.0, Table 6-1, "Concentrations of Gamma Emitters in Shoreline Sediment Samples - 2007". Cesium-137 (Cs-137) and Potassium-40 (K-40) were the significant radionuclides detected in the sediment samples.

5-7

Cs-137 was detected in the indicator sample collected in October for the 2007 program.

The measured concentration for this sample was 0.038 pCi/g (dry). The presence of Cs-137 in certain environmental sample media such as soil, shoreline sediment and fish is historically common.

Cs-137 is a fission product that is produced in nuclear power reactors and during atmospheric weapons testing. In addition to the Cs-137 found in the environment as a result of past weapons testing, a significant inventory of Cs-137 was also introduced globally as a result of the Chernobyl accident in 1986. Because Cs-137 is found in environmental samples as a result of weapons testing and Chernobyl, it is difficult to accurately determine the source of Cs-137 measured in the sediment sample. It is highly.

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

This assessment is further substantiated by the fact that Cs-137 was detected in the 1993 sediment control sample.

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

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

It is difficult to obtain control samples that are comparable in physical and chemical characteristics to the indicator, samples. Other factors, which include changing lake level and shoreline erosion, further complicate attempts at consistency in shoreline sediment sampling. Recent soil samples from locations beyond any expected influence from the site have contained levels of Cs-137 equal to* or greater than the concentrations found in the 2007 shoreline sediment samples. The Cs-137 is commonly found in soil samples and is attributed to weapons testing fallout. Shoreline samples containing soil or sediment are likely to contain Cs-137.5 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 radiation to the whole body and skin. Using the parameters provided in Regulatory Guide 1.109, the potential dose to man in mrem per year can be calculated.

The following 5-8

regulatory guide values and the maximum 2007 shoreline sediment indicator Cs-137 concentration were used in calculating the dose to man:

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

The sediment has a mass of 40 kg/m 2 (dry) to a depth of 2.5 cm,

" The shoreline width factor is 0.3, and

The maximum measured Cs-137 concentration of 0.038 pCi/g (dry).

Using these conservative parameters, the potential dose to the maximum exposed individual (teenager) would be 0.00013 mrem/year to the whole body and 0.00015 mrem/year to the skin. This calculated dose is very small and is insignificant when compared to the natural background annual exposure of approximately 60 mrem as measured by control TLDs in the vicinity of the site.

D.

Data Trends.

The mean Cs-137 concentration for the shoreline sediment indicator sample for 2007 was 0.04 pCi/g (dry). This is consistent with mean concentration measured at the indicator location over the past ten years.

The previous five years of data show a stable mean concentration values measured at the indicator locations. Over the five year period, mean concentrations ranged from a high of 0.08 pCi/g (dry) in 2005 to a low value of 0.04 pCi/g (dry) measured in 2004 and again in 2007. Cesium-137 was not detected in the control location samples over this same five year period.

The previous ten year data trend for indicator shoreline samples showed an overall downward trend in concentration measured at the indicator sample locations. Over the previous ten year period of 1998 through 2007, 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. The mean indicator concentration measured in 2007 of 0.04 pCi/g (dry) continues to support the long-term decreasing trend in Cs-137 concentration in shoreline sediment samples. Cesium-137 was not detected in the control samples collected over the previous ten years.

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

5-9

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 22 fish samples were collected for the 2007 sample -program. Species collected were: smallmouth bass, brown trout, chinook salmon, lake trout, and walleye.

The analytical results for the 2007 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 2007 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 2007 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 2007 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 30 years. Cs-137 was not detected in fish samples collected in 2003 to 2007 from indicator locations. The period of 2000 through 2007 as a group are the lowest results measured since the beginning of the Site Environmental Monitoring Program in 1969.

B.

Data Evaluation and Discussion Fish collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area) and at two locations in the vicinity of the lake discharges for the NMPNS and the JAFNPP facilities. The Oswego Harbor samples served as control samples while the NMPNS and JAFNPP samples served as indicator samples. All samples were analyzed for gamma emitters. Section 6.0, Table 6-2 shows individual results for all the samples collected in 2007 in units of pCi/g (wet).

The spring fish collection was made up of 11 individual samples representing four separate species. Walleye, smallmouth bass, lake trout and brown trout were collected.

5-10*

The total fall fish collection was comprised of 11 individual samples representing four individual species.

Chinook salmon, brown trout, smallmouth bass and walleye were collected.

Cs-137 was not detected in any of the fish species collected for the 2007 sample program 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.

Therefore, these fish are an integral part of the human food chain. The lack of detectable concentrations of plant-related radionuclides in the 2007 fish samples demonstrates that there is no attributable dose to man from operations at the site through the aquatic pathway.

D.

Data Trends The Cs-137 data for fish samples over the previous five years (2003 through 2007) show that the number of positive detections has decreased over this period relative to historical data. There were no positive detection 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 2007 and the previous ten years.

Annual Mean Fish Cs-137 Concentrations 0.035 E Control U Indicator 0.03 LLD : Lower Unit of Detection 0.025 0.02 S0.015 0.01 0.005 L LL LL L

1, 1, L L1 L L L 1, L 1, L 0D D

0D 11 Q D D D D n

)

D 0'

0' 0'

00 0

0 0

0n 0

0-0' 0'

0'>

0C 0

0 0

0 0D

-q C1

' rear el e

5-11

I I

The ten year data trend shows a consistent level of Cs-137 measured in fish between 1997 and 2000. After 2000, the number of positive detections drops off as noted in the five year trend. The 1997 through 2007 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.

I I

Fish Cs-137 1.6 U Control U Indicator 1.4 1.21.*

= < Lower Limit of Detection 9 0.8 Q 0.6 0.4 0.2 0

o 1-o 0 iC

. *.ClYr.

" I I"

r-0_

0 0r_

D D C Year I

I I

I 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 NMP1 Intake and the NMP2 Intake.

Gamma spectral analysis was performed on 24 monthly composite samples from the ODCM locations and on 36 monthly composite samples 5-12 I

I I

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 2007 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 2007 REMP program.

The results for the 2007 samples showed no positive detections of tritium. All results for

.2007 were below the established measurement sensitivity and are reported as less than the lower limit of detection (<LLD). There is no indication of a long-term buildup of tritium concentrations in the surface waters adjacent to the site.

B.

Data-Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples from five Lake Ontario sampling locations. No plant-related radionuclide were detected in 2007 samples.

This is consistent with historical data, which has not shown the presence of plant-related radionuclides in surface water samples.

Tritium samples are quarterly samples that are a composite of the applicable monthly samples for a given location. Tritium samples analyzed for the 2007 sample program were analyzed to an instrument detection level of 500 pCi/l.

The following table provides the specific LLDs for each sample location. The 2007 results had LLD values that ranged from <439 pCi/l to <476 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 <439 pCi/l to <476 pCi/l. The LLD values shown below are far below the ODCM required LLD of 3000 pCi/l.

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

JAF Inlet (Indicator)*

<439

<476

<452 Oswego Steam Inlet (Control)*

<439

<476

<452 NMP #1 Inlet

<443

<476

<453 NMP #2 Inlet

<439

<476

<452 Oswego City Water Supply

<439

<476

<452

Sample location required by ODCM 5-13

Tritium was not detected in any of the twelve optional Lake Ontario samples collected in the 3

2007 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.

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

4.

I 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 3

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 2007 LLD concentration of <476 pCi/l, the calculated dose would be less than 0.049 mrem to the child whole body and less than 0.049 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 i

radionuclides have not been detected in lake water samples.

Tritium results for the 2007 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 2002 to 2006 was <LLD pCi/l for the control and ranged from <LLD pCi/l to 297 pCi/l for the indicator location. By comparison, the mean 2007 tritium concentrations were <452 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 3

results measured at the site. The indicator data from the previous ten year period, 1997 through 2006, is representative of natural variations in environmental tritium concentrations with no significant levels of tritium measured. The 1999 mean control value of 337 pCi/l is i

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 3

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 i

the past 20 years at both an indicator and control location. Prior to 1985, the Oswego City 5-14

Water Supply results were used as control location data as this location closely approximates the Oswego Steam Station, the current control location.

Surface Water Tritium I-0.

500 450 400 350 300 250 200 150 100 50 0

U control M indicator S< Low er Linut of Dtection "I*

-II 00 00 ON ON 00 ON C.

N IT W

ON1 OaN O

ON1 ON ON O

NO Year ON 0

C11 C4

'I In,1

Cl 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 11 samples were collected for the 2007 sample program using two indicator locations and two control locations. The results for the 2007 samples showed no positive detections of tritium. All results in 2007 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 2007 samples.

5-15

Tritium samples analyzed for the 2007 sample program were analysed to a instrument I

detection limit of 500 pCi/L The tritium results for the control locations contained no positive detections and had LLD values that ranged from <442 pCi/l to <445 pCi/i. The indicator locations results showed no-positive detections and had LLD values that ranged from <440 pCi/l to <461 pCi/1.

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

I C.

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

ODCM, was not required during 2007. There was no groundwater source in 2007 that was tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge I

properties were suitable for contamination; therefore, drinking water was not a dose pathway during 2007.

3 D.

Data Trends There are no data trends for gamma emitters or strontium as these radionuclides have not been detected in groundwater samples.

3 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:

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 2007 reporting period.

I 5.2.1 AIR PARTICULATE GROSS BETA 3

5-16

A.

Results Summary Weekly air samples were collected and analyzed for particulate gross beta particulate activity. For the 2007 program, a total of 52 samples were collected from control location R-5 and 208 samples were collected from indicator locations R-1, R-2, R-3, and R-4.

These five locations are required by the ODCM. Additional air sampling locations are maintained and are discussed in Section 5.2.1.B below. The mean gross beta concentration for samples collectedfrom the control location (R-5) in 2007 was 0.016 pCi/m3. The mean gross beta concentration for the samples collected from the indicator locations (R-1, R-2, R-3, and R-4) in 2007 was 0.0 16 pCi/m3. The mean gross beta results for the indicator and the control stations were equivalent in 2007. 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 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 780 samples were collected and analyzed as part of the 2007 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.

The average annual gross beta indicator concentrations for the ODCM indicator stations (R-l, R-2, R-3 and R-4) was 0.016 pCi/m3.

The offsite ODCM control station (R-5) 5-17

I I

annual mean gross beta concentration was 0.016 pCi/mr3. The minimum, maximum and average gross beta results for sample locations required by the ODCM were as follows:

n Concentration pCi/m3 I

Location Minimum Maximum Mean R-1 R-2 R-3 R-4 R-5 (Control) 0.007 0.009 0.008 0.007 0.008 0.028 0.027 0.028 0.027 0.028 0.016 0.016 0.016 0.017 0.016 I

I I

The mean weekly gross following graphs:

beta concentrations measured in 2007 are illustrated in the I

Air Particulate Filter - Gross Beta (2007) 0.0300 0

Indicator Control 0.0250 0.0100 0.0050 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 #

I I

I 5-18

Air Particulate Filter - Gross Beta (2007) 030 Indicator Control iA020 A A o.0100 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 531 52 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/m3. The 1981 samples were affected by fallout from a Chinese atmospheric nuclear test which was carried out in 1980.

The mean gross beta concentrations measured in 1977 to 2007 are illustrated in the following graph:

5-19

I I

Air Particulate Filter - Gross Beta 0.18 0 -

Control U Indicator 0.16 1980: Atmospheric 0.14 Nuclear Tests 0.12 0.1 0.08 0.06 1986 Chernobyl 0.04 L

Accident 0.02 0

i.ll II Year I

I I

r The trend for the previous five years represents a base line concentration or natural background level for gross beta concentrations.

This trend is stable with minor fluctuations due to natural variations. The change in concentrations over the period of 1997 through 2007 is very small. This is illustrated by the following graph:

I Air Particulate Filter - Gross Beta 0.02 0.018 0.016 0.014 0.012 0.01 0.008 0.006 0.004 0.002 0

I I

m

._11 i

I-- Jl*.....

[

I F-0 0

I I

I 02 oi 8

a 0

CU YeU Year U

CU U

CU CU 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 0.013 pCi/m3 to 0.019 pCi/m3.

The mean annual concentrations for the indicator stations for this same time period were similar to the control and ranged from a minimum mean of 0.010 pCi/m 3 in 1997 to a maximum mean of 0.018 pCi/m3 in 2005.

5 - 20 I

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 Point site. Five of the 15 air monitoring stations are required by the ODCM and are located offsite near the site boundary and offsite as a control location. Ten additional air sampling stations are also maintained as part of the sampling program.

Together, these fifteen continuous air sampling stations make up a comprehensive environmental monitoring network for measuring radioactive air particulate concentrations in the environs of the site. Annually, the air monitoring stations provide 780 individual air particulate samples which are assembled by location into 180 monthly composite samples. The monthly composites are analyzed using gamma spectroscopy.

No plant-related gamma emitting radionuclides were detected in any of the air particulate filter samples collected during 2007.

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 2007 showed no detectable activity of plant related radionuclides.

The results of the monthly composite samples are presented in Section 6.0, Table 6-8 and 9.

5-21

I I

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 2007. 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.

I D.

Data Trends No plant related radionuclides were detected during 2007 at the offsite air monitoring locations.

1 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.

I Historical data shows that Cs-137 is the fission product radionuclide most frequently detected in the air particulate filter composites. Cs-137 was detected in each of the years from 1977 through 1983 at* both the control and indicator sampling locations.

The presence of Cs-137 in the air samples collected during these years was the result of atmospheric weapons testing.

Cs-137 was again detected in 1986 as a result of the Chernobyl accident.

Since 1986 there have been no detections of Cs-137 in the environment surrounding the Nine Mile Point site..

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

5-22I

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 780 samples analyzed for the 2007 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 2007 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 2007. 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.

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 1997 through 2007.

1-131 has previously been detected in samples collected during the last twenty year period 5 - 23

I in 1986 and 1987. The 1986 detection of 1-131 was the result of the Chernobyl accident, I

and the 1987 detection was the result of plant operations.

n 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/rn 3. During 1977 this mean decreased to 0.32 pCi/m3, and further decreased by a factor often to 0.03 pCi/m3 in 1978. 1-131 was not detected in samples collected from the control location during 1979 - 1981 and 1983 to 1985. 1-131 Was detected once at the control location during 1982 at a concentration of i

0.039 pCi/m 3.

Iodine-131 has been detected in samples collected from the on-site indicator locations i

during 1976 to 1978, 1980 to 1983 and 1986 to 1987. The mean concentrations ranged from 0.013 pCi/rn3 in 1980 to a maximum of 0.119 pCi/m3 in 1986. The maximum mean i

indicator 1-131 concentration of 0.119 pCi/mi3 was the result of the Chernobyl accident. I-131 was detected in a total of 75 weekly samples collected during the 1986 sample program. The 1986 measured concentrations ranged from a minimum of 0.023 pCi/m3 to a maximum of 0.36 pCi/mr.

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)

A.

Results Summary Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. As part of the 2007 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 2007. As a result of placing two TLDs at each location, the results presented in this report are the average of two TLD readings obtained for a given location.

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

Onsite (areas within the site boundary: 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),

0 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),

5-24 I

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 2007 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 14.8 5.6 Site Boundary (Inner Ring) * (1) 3.2 5.4 4.3 Offsite Sectors (Outer Ring)

3.1 5.1 4.2 Special Interest * (2) 3.0 5.1 4.2 Control * (3) 3.2 5.3 4.3 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.

The results for the 2007 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.

5 - 25

B.

Data Evaluation and Discussion Direct Radiation (Gamma Dose) measurements were taken at 72 different environmental locations during 2007, 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.

Onsite TLDs are optional and are subdivided into three categories for which direct radiation results are evaluated. The 2007 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 14.8 mrem per standard month.

2.

Results for TLDs located near the north shoreline of NMP1, NMP2 and Fitzpatrick I

facilities in close proximity to the Radwaste and NMP1 Reactor Building ranged from 3.2 to 30.6 mrem per standard month.

3.

Results for TLDs located onsite near the Energy Information Center and its associated shoreline ranged from 3.9 to 5.8 mrem per standard month.

Site Boundary TLD results ranged from 3.2 to 9.0 mrem per standard month in 2007. This range included all TLDs placed in each of the 16 meteorological sectors in the general area of the site boundary. The highest dose rate measured at a location required by the ODCM was 9.0 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 NMP2 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.

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 5.4 mrem per standard month resulting in an average dose rate of 4.3 mrem per standard month.

5 5 -26 fl

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 3.1 to 5.1 mrem per standard month with an average dose rate of 4.2 mrem per standard month.

Special Interest TLDs from all locations ranged from 3.0 to 5.1 mrem per standard month with an annual average dose rate of 4.2 mrem per standard month.

The Control TLD group required by the ODCM utilizes locations positioned well beyond the site. 2007 Control TLD results ranged from 3.2 to 5.3 mrem per standard month with an annual average dose rate of 4.3 mrem per standard month. These results include both the ODCM required control TLDs and the additional control TLDs.

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

C.

Dose evaluation 2007 annual mean dose rates for each geographic follows:

Site Boundary:

4.3 mrem per standard month Offsite Sectors:

4.2 mrem per standard month location required by the ODCM are as (TLDs: 78, 79, 80, 81, 82, 83, 84, 7, 18)

(TLDs: 88, 89, 90, 91, 92, 93, 94, 95)

Special Interest:

4.2 mrem per standard month (TLDs: 15, 56, 58, 96, 97, 98)

Control:

4.3 mrem per standard month (TLDs 14, 49)

The measured mean dose rate in the proximity of the closest resident was 4.5 mrem per standard month (TLD #s: 108, 109) which is consistent with the control measurements of 4.3 mrem per standard month.

The mean annual dose for each of the geographic location categories demonstrates that there is no statistical difference in the annual dose as a function of distance from the site.

The TLD program verifies that operations at the site do not measurably contribute to the levels of direct radiation present in the offsite environment.

5 - 27

I I

I D.

Data Trends A comparison of historical TLD results can be made using the different geographical categories of measurement locations. These include Site Boundary TLDs located in each of the 16 meteorological sectors, TLDs located offsite in each land based sector at a distance of 4 to 5 miles from the site, TLDs located at special interest areas and TLDs located at control locations.

Site Boundary, Offsite Sector and Special Interest TLD locations became effective in 1985; therefore, trends for these results can only be evaluated from 1985 to the present.

The following graph illustrates TLD results for the Control, Site Boundary, Offsite Sectors and Special Interest groups from 1998 through 2007:

TLD Data 6

M Control 0 Site Boundary 01 ff 5

4 S2 0

SI-0 U

I I

I 00 0ý 0t-000 0'

0 0

0 Yfear TLDs located at the site boundary averaged 4.3 mrem per standard month during 2007 (Site Boundary average results do not include TLDs influenced by radwaste buildings and radwaste shipping activities). This result is consistent with the previous five year average of 4.3 mrem per standard month.

Offsite Sector TLDs averaged 4.2 mrem per standard month during 2007. 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 4.2 mrem per standard month during 2007 which is consistent with the previous five year average of 4.1 mrem per standard month.

5 - 28 I

I

The last group of TLD locations required by the ODCM is the Control Group. This group utilized TLD locations positioned well beyond the site.

2007 control results from all Control TLDs averaged 4.3 mrem per standard month, consistent with the previous five year average of 4.2 mrem per standard month. The 2007 TLD program results, when compared to the previous twenty years, showed no significant trends relative to increased dose rates in the environment.

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

5.2.5 MILK A.

Results Summary A total of 58 milk samples were collected during the 2007 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 58 milk samples collected in 2007 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 2007. 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 2007 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.

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 2007. Sample location #4 ceased operation in May 2007 and therefore was sampled only during the month of April and May. 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 5 -29

I samples were collected from a farm located 16.0 miles from the site and in a low frequency I

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 4*

ESE 7.6 77 (Control)

SSW 16.0

Ceased operation in May 2007.

Samples were collected from Indicator location #4 during April and May, while 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 2007 as a result of 1-131 not having been detected in samples collected during November and December of 2006, 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 2007 are provided in Section 6.0, Table 6-13.

I Iodine-131 was not detected in any indicator or control milk samples analyzed during 2007. All 1-131 milk results were reported as Lower Limits of Detection (LLD). The LLD results for all samples ranged from <0.45 to <0.84 pCi/liter. No plant-related radionuclides were detected in any milk sample collected in 2007.

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 1312 to 1789 pCi/liter. Cs-137 was not detected in any indicator or control milk sample collected in 2007.

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

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.

I 5-30

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 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 2007 data to historical results over the operating life of the plants shows that Cs-137 and 1-131 levels have decreased significantly since 1983.

Historical data of milk sample results for Cs-137 and 1-131 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 25 food product samples collected and analyzed for the 2007 program.

Detectable levels of naturally occurring K-40 were measured in all control and indicator samples collected for the 2007 program. Be-7 a naturally-occurring radionuclide, was also detected intermittently in samples collected in 2007. These results are consistent with the levels measured in 2006 and previous years.

The results of the 2007 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.

5-31

I I

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 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.

i.

Food product samples collected during 2007 included one variety considered to be an edible broadleaf vegetable. Collards, an edible broadleaf vegetable, were collected from one indicator location. Collards were not available from the control location. The general lack of edible broadleaf vegetation samples was the result of grower preference and such i

varieties were not available in local gardens.

Where broadleaf vegetables were not available, non-edible broadleaf vegetation was collected. Non-edible vegetation consisting of squash leaves, zucchini leaves, rhubarb, grape leaves, pumpkin leaves, corn leaves, horseradish leaves, green* bean leaves, and pepper leaves were collected for the 2007 program.

The leaves of these plants were sampled as representative of broadleaf I

vegetation which is a measurement of radionuclide deposition. In addition to the broadleaf vegetation, tomato samples were collected from all locations except #134. 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 2007 did not detect any plant-related radionuclides.

Results for the past five years also demonstrate that there is no buildup of plant-related radionuclides in the garden food products grown in areas close to the site.

Naturally-occurring Be-7 and K-40 were detected in food product samples.

The concentration of Be-7 in vegetation samples ranged from <0.062 to 1.98 pCi/g (wet). The concentration of K-40 in indicator and control samples ranged from 1.49 to 5.33 pCi/g (wet). The results for naturally-occurring radionuclides are consistent with the data of prior years, Analytical results for food products are found in Section 6*0, Table 6-14.

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 5-32

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 2007 sample programs.

Historicaldata 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 2007, a milk animal census, a nearest resident census and a garden census were performed.

The results of the closest residence census conducted in 2007 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 2007. See Table 3.3-1 for 2007 sampling locations.

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 5-33

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 381 cows and 6 goats based on the 2007 land use census. The number of cows has decreased by 92, when compared to the 2006 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.

The second type of census conducted is a residence census. The census is conducted in order to identify the closest residence within 5 miles in each of the 22.5 degree land-based meteorological sectors. There are only eight sectors over land where residences are located within 5 miles. The water sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW.

The results of the residence census, showing the applicable sectors and degrees and distance of each of the nearest residence, are found in Section 6.0, Table 6-16. There were no changes identified in the 2007 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

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 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 5-34

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 2007 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 2007 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 detected one potential plant-related radionuclide in the sample media collected during 2007. Cs-137 was detected in one shoreline sediment sample. The source of the Cs-137 measured in this sample is considered to be fallout from past atmospheric nuclear weapons testing. The measured concentration of Cs-137 in the sample was small and consistent with historical results for shoreline sediment.

The impact of these Cs-l37 concentrations are minimal in terms of dose to man.

Dose from man-made sources in the environment is very small when compared to the dose originating from naturally-occurring sources of radioactivity.

Radiation from naturally-occurring radionuclides such as K-40 and Ra-226 contributed the vast majority of the total annual dose to members of the general public. The dose to members of the, public, resulting from plant operations, is extremely small in comparison to the dose contribution from natural background levels and sources other than the plants.

The whole body dose in 5-35

I Oswego County due to natural sources is approximately 50 - 60 mrem per individual per year as I

demonstrated by control environmental TLDs. The fraction of the annual dose to man, attributable to site operation, remains insignificant.

I Based upon the overall results of the 2007 Radiological Environmental Monitoring Program, it can be concluded that the levels and variation of radioactivity in the environment samples were consistent with background levels that would be expected for the lakeshore environment of the site.

5.4 REFERENCES

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 I

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 I

Specifications for Nuclear Power Plants", December, 1975.

4.

U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, I

"An Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979.

5.

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

6.

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

7.

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

8.

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

9.

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

5-36

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 6.1 Environmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive values and LLD values where

-applicable.

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

.explanation).

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

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

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

6-1

TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES - 2007 Results in Units of pCi/kg (dry) A: I Sigma Collection GAMMA EMITTERS Sam ple Location Dae*_ _

_I

__*I

_I

__Date K-40 Co-60 Cs-134 Cs-137 Zn-65 Others t Sunset Bay (05)*

04/19/07 18460 +/- 1547

< 116:4

< 117.9

< 118.8

< 385.8

<LLD 10/18/07 18220 +/-643.

< 61.0

< 53.6 38.3 +/- 16.5

< 90.3

<LLD 10/18/07 18250 +/- 892

< 81.4

< 69.4

< 71.2

< 136.7

<LLD Lang's Beach (06, Control) 04/19/07 13170 +1-1034

< 115.0

< 71.5

< 52.1

< 304.4

<LLD 10/18/07 14510 +/- 694

< 74.4

< 60.0

< 45.4

< 136.0

<LLD

Sample required by the ODCMl Corresponds to sample location noted on Figure 3.3-5 I Plant related radionuclides 6-2 m

m m

m

TABLE 6-2 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2007 Results in Units of pCi/kg (wet) + 1 Sigma

___FITZPATRICK

(03)-**

DaeI4 M

4,

C 8

GAMMA EMITTERS I

Z Oe Date.

.Discription....

K 40._

.. n-4.

.. C -58_...._ Fe-59.

.C -60.

Cs-134 t

Cs.137

, i-t 6/8/2007, BROWNTROUT 4547 +1-589

< 52

< 61

< 249

< 89

< 52

< 47

< 155

<LLD 6/13/2007 WALLEYE 5245 +/- 547

< 56

< 65

< 153

< 38

< 50

< 56

< 141

<LLD 6/13/2007 SMALLMOUTH BASS 5903 +/- 562

< 55

< 46

< 202

< 59

< 58

< 46

< 146

<LLD 9/6/2007 CHINOOK SALMON 5283 +/, 463

< 58

< 56

< 129

< 61

< 51

< 49

< 159

<LLD 9/6/2007 WALLEYE 5274 +/- 444

< 53

< 61

< 116

< 60

< 44

< 36

< 158

<LLD 9/6/2007 SMALLMOUTH BASS 4838 +/- 508

< 61

< 41

< 141

< 67

< 44

< 55

< 129

<LLD 9/6/2007 BROWN TROUT 4389 +/- 532

< 64

< 96

< 238

< 69

< 58

< 74

< 130

<LLD Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 f

Plant related radionuclides 6-3

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN. FISH SAMPLES - 2007 Results in Units-of pCi/kg (wet) +/- 1 Sigma NINE MILE POINT * (02)***

GAMMA EMITTERS Date Discription K-40 Mn-54 I Co-58 Fe-59 I Co-60 Cs-134 JCs-137 Zn-65 Others t 6/8/2007 BROWN TROUT 4662 +/- 429

< 56

< 51

< 177

< 43

< 44

< 46

< 142

<LLD 6/8/2007 WALLEYE 4517 +/-1-564

< 76

< 53

< 235

< 83

< 57

< 62

< 182

<LLD 6/8/2007 SMALLMOUTH BASS 5660 +/-/-522

< 58

< 82

<.257

< 75

< 57

< 47

< 206

<LLD 6/8/2007 LAKETROUT (ANCILLARY 5510 +/-438

< 61

< 45

< 167

< 51

< 37

< 50

< 120

<LLD 9/6/2007 SMALLMOUTH BASS 5454 +/- 714

< 96

< 78

< 249

< 90

< 75

< 82

< 252

<LLD 9/6/2007 WALLEYE 5522 +1-549

< 55

< 64

< 155

< 67

< 49

< 54

< 162

<LLD 9/11/2007 CHINOOK'SALMON 6819 +/-/-667

< 46

< 63

< 237

< 67 1<

56

< 65

< 141

<LLD Sample required by the ODCM Corresponds to sample location noted on Figure 3.3-5 t

Plant related radionuclides 6-4

TABLE 6-2 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES - 2007 Results in Units of pCi/kg (wet) +/-: I Sigma OSWEGO HARBOR (CONTROL) * (00)***

.....

GAMMA EMITTERS-_-._,__..

Date Discription K-40 I.. M[-.54..

Co-58

._Fe-59 C-60 [ Cs-134 VCS13.

Zn-65 ýOthers t" 6/8/2007 BROWN TROUT 5235 +/-582

< 41

< 80

< 197

< 47

< 64

< 52,

< 140

<LLD 6/8/2007 WALLEYE

3961 +/-478

< 72

< 77

< 192

< 72

< 65

< 67

< 128

<LLD 6/13/2007 SMALLMOUTH 4978 +/- 515

< 70

< 78

< 218

< 71

< 48

< 60

< 150

<LLD 6/13/2007 LAKE TROUT 4480 +/- 439

< 47

< 59

< 156

< 45

< 40

< 49

< 114

<LLD 9/7/2007 CHINOOK SALMON 4637 +/-482

< 55

< 53

< 159

< 61

< 49

< 58

< 79

<LLD 9/7/2007 WALLEYE 4234. +/-460

< 46

< 61

< 123

< 71

< 51

< 54

< 149

<LLD 9/7/2007 SMALLMOUTH BASS 6.185 +/-462

< 45

< 42

< 153

< 47

< 42

< 51

< 109

<LLD 9/7/2007 BROWN TROUT 5795.+/- 534

< 59

< 71

< 170

< 77

< 54

< 57

< 147

<LLD Sample requited 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 - 2007 (QUARTERLY COMPOSITE SAMPLES)

Results ini Units of pCi/I +/- 1 Sigma I STATION CODE PERIOD DATE TRITIUM First Quarter 01/02/07 04/02/07

< 476 FITZPATRICK*

Second Quarter 04/02/07 06/29/07

< 443 (03, INLET)***

Third Quarter

.06/29/07 10/01/07

<448 Fourth Quarter 10/01/07 01/02/08

< 439 First Quarter 12/29/06 03/29/07,

< 476 OSWEGO STEAM STATION*

Second Quarter 03/29/07 06/29/07

< 443 (08, CONTROL)***

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/28/07

< 439 First Quarter 12/29/06 03/29/07

< 476 NINE MILE POINT UNIT I **

Second Quarter 03/29/07 06/29/07

< 443 (09, INLET)***

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/28/07

< 445 First Quarter 12/29/06 03/29/07

< 476 NINE MILE POINT UNIT 2**

Second Quarter 03/29/07 06/29/07

< 443 (11, INLET)***

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/28/07

< 439 First Quarter 12/29/06 03/29/07

< 476 OSWEGO CITY WATER**

Second Quarter 03/29/07.

06/29/07

< 443 (10)***

Third Quarter 06/29/07 09/28/07

< 449 Fourth Quarter 09/28/07 12/28/07

< 439 Sample location required by ODCM Optional Sample location Corresponds to sample location noted on Figure 3.3-4 6-6 I

m m

I-

-Im m

TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma OSWEGO STEAM STATION * (08, CONTROL)***

NUCLIDE January FebrUary March April May June 1-131

< 0.55

< 0.92

< 0.67

< 0.95

< 0.56

< 0.68 Cs-134

< 2.71

< 4.66

< 4.14

< 4.05

< 5.53

< 3.71 Cs-137

< 2.70

< 3.29

< 3.50

< 3.93

< 5.33

< 3.46 Zr-95

< 5.05

< 9.18

< 7.63

< 7.73

< 8.96

< 7.63 Nb-95

< 3.94

< 5.34

< 6.25

< 5.91

< 8.12

< 5.12 Coý58

< 3.28

< 4.92

< 4.38

< 4.87

< 4.98

< 4.64 Mn-54

< 2.50

< 4.47

< 4.09

< 4.12

< 5.42

< 3.38 Fe-59

< 11.13

< 13.36

< 12.53

< 14.53

< 13.68

< 11.78 Zn-65

< 5.64

< 11.25

< 8.00

< 9.93

< 11.73

< 9.12 Co-60

< 3.05

< 4.59

< 4.10

< 4.46

< 4.72

< 4.26 K-40 303.9 +/- 17.25 152.1 +/- 19.96 321.7 +/- 24.70 136.1 +/- 20.73 188.8 +/- 28.57 257.6 +/- 22.71 BaILa-140

< 9.73

< 11.54

< 10.65

< 14.52

< 13.84

< 9.55 NUCLIDE July August September October-November December 1-131

< 0.54

< 0.71

< 0.69

< 0.64

< 0.85

< 0.63 Cs-134

< 4.57

< 3.17

< 3.93

< 3.96

< 4.34

< 2.78 Cs-137

< 4.46

< 3.30

< 4.30

< 3.25

< 4.75

< 4.23 Zr-95

.< 7.68

< 5.95

< 8.13 K 5.98

< 9.70

< 7.36 Nb-95

< 5.25

< 4.54

< 4.79

< 4.33

< 6.85

< 5.73 Co-58

< 5.07

< 3.49

< 5.15

< 3.60

< 4.88

< 4.78 Mn-54

.< 4.33

< 3.05

< 3.77

< 3.48

< 4.71

< 4.17 Fe-59

< 15.69

< 10.78

< 13.70

< 9.50

<,14.41

< 11.20 Zn-65

< 9.91

< 7.19

< 10.21

< 8.31

< 5.49

< 9.71 Co-60

< 4.19

< 3.48

< 4.52

< 3.26

< 4.28

< 3.91 K-40 191 +/- 22.76 109.7 +/- 16.66 146.9 +/- 20.98 187.7 +/- 18.16 322.6 +/- 26.68 147.1 +/- 20.53 BaILa-140

< 8.82

< 9.19

< 11.85

< 10.02

< 14.41

< 10.77 Sample Location required by ODCNM Corresponds to sample location noted on Figure 3.3-4.

6-7

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter A-1 Sigma OSWEGO CITY WATER** (10)***

NUCLIDE January February March

, April May June 1-131

< 14.53

< 14.10

< 11.20

< 12.63

< 11.76

< 13.53 Cs-134

< 2:60

< 4.31

< 2.40

< 2.12

< 3.27

< 3.57 Cs-137

< 2.89

< 4.00

< 3.06

< 3.36

< 5.01

< 3.64 Zr-95

< 5.66

< 7.43

< 6.37

< 6.00

< 10.04

< 7.98 Nb-95

< 4.00

< 5.15

< 3.94

< 4.77

< 5.64

< 5.83 Co-58

< 2.93

< 3.68

< 3.44

< 3.32

< 5.26

< 3.82 Mn-54

< 2.41

< 2.93

< 3.24

< 3.07

< 4.72

< 3.60 Fe-59

< 9.69

< 14.48

< 9.46

< 9.68

< 16.92

< 13.81 Zn-65

< 5.82

< 9.30

< 8.41

< 4.10

< 11.29

< 9.14 Co-60

< 2.94

< 4.11

< 3.26

< 3.03

< 6.09

< 4.19 K-40 302.7 +/-

17.71 130.7 +/-

19.18 93.75 +/-

14.14 133.4 +/- 15.33 230.4 +/- 27.62 269.0 +/- 24.12 Ba/La-140

< 9.82

< 11.05

< 7.35

< 8.41

< 14.46

< 1.00 NUCLIDE July August September October November December 1-131

< 13.36

< 14.49

< 14.44

< 9.95

< 12.64

< 12.97 Cs-134

< 4.08

< 3.52

< 5.22

< 2.09

< 2.96

< 3.54 Cs-137

< 3.53

< 3.00

< 4.50

< 2.86

< 2.44

< 3.67 Zr-95

< 7.10

< 5.77

< 10.06

< 5.34

< 4.82

< 7.69 Nb-95

< 5.52

< 4.41

< 6.20

< 3.38

< 3.12

< 5.19 Co-58

< 4.02

< 3.50

< 5.46

< 3.42

< 2.84

<,4.09 Mn-54

< 4:22

< 3.01

< 4.95

< 2.99

< 2.52

< 3.62 Fe-59

< 11.44

< 9.00

< 17.00

< 9.86

< 8.81

< 9.11 Zn-65

< 9.31

< 3.93

< 11.28

< 6.71

< 5.38

< 4.74 Co-60

< 3.93

< 3.16

< 5.33

< 2.85

< 2.90

< 3.85 K-40 311.9 +/- 25.37 279.0 +/- 18.77

< 64.11 134.9 +/- 12.95 165.7 +/- 14.20 293.8 +/- 22.45 Ba/La-140

< 9.11

< 8.65

< 14.63

< 7.24

< 10.45

< 10.95

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

TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma FITZPATRICK* (03, INLET)***

1NUCLIDE aur erayMrh,.A ArilV a

ue 1-131

< 0.62

< 0.51

< 0.53

< 0.51

< 0.60 Cs-134

< 3.15

< 4.85

< 2.95

< 1.45

< 5.69

< 6.71 Cs-137

< 4.20

< 4.37

< 4.72

< 2.19

< 5.33

< 5.05 Zr-95

< 8.04

< 6.61

< 8.92

< 3.83

< 11.11

< 14.09 Nb-95

< 4.99

< 5.35

< 5.88

< 2.75

< 7.71

< 7.66 Co-58

< 4.66

< 4.81

< 5.23

< 2.41

< 6.40

< 5.51 Mn-54

< 3.76 K 3.77

< 4.51

< 2.22

< 4.65

< 6.80 Fe-59

< 14.48

< 12.59

< 14.09

< 5.94

< 15.24

< 21.46 Zn-65

< 9.68

< 8.98

< 11.88

< 2.77

< 13.81

< 14.25 Co-60

< 4.05

< 5.59

< 5.23

< 1.86

< 5.37

< 7.96 K-40 131.9 +/- 21.93 132.9 +/- 20.48 132.2 +/- 21.11 126.9 +/- 10.63 382.3 +/- 35.31 201.0 +/- 33.41 Ba/La-140

< 10.56

< 9.46

< 6.79

< 4.88

< 10.03

< 14.25 NUCLIDE..

July.

August eptenber Octbe Noven ib Ja-nuia,,

1-131

< 0.46

< 0.56

< 0.50

< 0.53

< 0.49

< 0:46 Cs-134

< 2.38

< 4.31

< 4.57

< 3.78.

< 3.84

< 7.69 Cs-137

< 3.57

< 3.93-

< 3.71

< 3.30

< 2.88

< 5.89 Zr-95

< 9.08

< 7.26

< 8.34

< 6.47

< 6.75

< 10.92 Nb-95

< 4.78

< 5.44

< 4.69

< 4.32

< 3.90

< 6.25 Co-58

< 4.20

< 5.16

< 5.11

< 4.07

< 3.97

< 7.07 Mn-54

< 3.69

< 4.55

< 4.04

< 2.99

< 3.60

< 6.36 Fe-59

< 12.42

< 14.25

< 12.06

< 10.98

< 10.05

< 24.46 Zn-65

< 9.78

< 3.63.

< 10.05

< 8.96

< 7.89

< 14.85 Co-60

< 4.18

< 5.87

< 4.19

< 3.86

< 3.29

<.5.99 K-40 269.8 +/- 23.86 168.5 +/- 23.43 125.2 +/- 22.09 126.5 +/- 17.41 130.4 +/-

17.22 113 +/- 26.74 Ba/La-140

< 8.39

< 11.40

< 9.45

< 9.07

< 7.97

< 12.90 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 - 2007 Results in Units of pCi/liter :- 1 Sigma NINE MILE POINT UNIT 1 ** (09, INLET)***

NUCLIDE.

January February.

March April...

May.

June 1-131

< 12.69

< 13.11

< 14.41

< 14.71

< 12.27

< 14.22 Cs-134

< 1.79

< 4.83

< 3.34

< 3.95

< 3.65

< 4.05 Cs-137

< 2.08

< 3.76

< 4.61

< 3.68

< 3.76

< 3.76 Zr-95

< 4.92

< 9.38

< 10.88

< 7.34

< 8.17

< 8.54 Nb-95

< 3.43

< 5,04

< 5.96

< 5.13

< 5.47

< 4.80 Co-58

< 2.71

< 5.26

< 5.98

< 4.16

< 4.55

< 4.19 Mn-54

< 2.22

< 3.97

< 4.98

< 3.80

< 3.89

< 4.30 Fe-59

< 7.66

< 13.87

< 17.14

< 11.53

< 13.61

< 12.58 Zn-65

< 5.21

< 9.61

< 13.42

< 9.53

< 10.37

< 8.26 Co-60

< 2.40

< 4.33

< 5;72

< 4.02

< 4.52

< 3.83 K-40 129.6 +/- 10.95 127.8 +/- 20.42 261.7 +/- 27.51 284.2 +/- 23.03 178.0 +/- 23.27 170.1 +/- 20.61 Ba/La-140

< 8.40

< 10.08

< 13.66

< 9.57

< 11.98

< 11.96 NUCLIDE July

[

August.

September October.

Novemberi Decemiber-.

1-131

< 10.55

< 13.67

< 13.97

< 11.93

< 14.18

< 14.37 Cs-134

< 2.23

< 3.54

< 4.07

< 2.65

< 2.49

< 4.63 Cs-137

< 2.90

< 3.1 f

< 4.06

< 3.50

< 3.25

< 3.48 Zr-95

< 6.13

< 8.04

< 8.64 K 7.43

< 6.52

< 6.96 Nb-95

< 4.53

< 4.88

< 4.97

< 5.03

< 3.82.

< 5.17 Co-58

< 3.72

< 4.11

< 4.34

< 3.99

< 4.08 K 4.99 Mn-54

< 3.00

< 3.34

< 4.35

< 3.82

< 3.55

< 4.70 Fe-59

< 9.63

< 11.89

< 15.15

< 12.31

< 10.55

< 17.40 Zn-65

< 6.48

< 7.84

< 9.10

< 9.57

< 8.08

< 10.37 Co-60

< 3.56

< 3.37

< 4.13

< 3.90

< 3.60

< 4.53 K-40 120.3 +/- 15.59 138.9 +/- 17.91 175.8 +/- 24.11 275.1 +/- 24.81 137.2 +/- 14.84 272.5 +/- 24.02 BaILa-140

< 7.74

< 8.79

< 11.70

< 10.80

< 8.83

< 13.63 Optional Sample Location Corresponds to sample location noted on Figure 3.3-4 6-10 i

M

-M M

M M

m

-M M

M M

m m

m mm

-m m---

n-m TABLE 6-4 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter + 1 Sigma NINE MILE POINT UNIT 2 ** (11, INLET)***

NUCLIDE January February.

March April:,

May June 1-131

< 14.78

< 13.79

< 14.38 1 10.66

< 13.73

< 12.82 Cs-134

< 4.13

< 4.27

< 3.87

< 2.55

< 2.59

< 3.49 Cs-137

< 2.82

< 3.46

< 3.35

< 3.57

< 3.84

< 3.65 Zr-95

< 6.72

< 7.30

< 6.99

< 7.03

< 7.62

< 8.97 Nb-95

< 4.77

< 5.02

< 4.72

< 4.84

< 6.25

< 5.82 Co-58

< 3.57

< 4.41

< 4.34

< 4.33

< 5.19

< 4.86 Mn-54

< 3.13

< 3.95.

< 3.05

< 3.98

< 4.34

< 4.48 Fe-59

< 10.75

< 11.19

< 12.07

< 12.60

< 14.78

< 13.81 Zn-65

< 7.76

< 8.23

< 8.97

< 8.89

< 8.98

< 8.73 Co-60

< 3.15

< 3.56

< 4.40

< 4.49

< 5.14

< 4.05 K-40 134.0 +/- 16.80 286.8 +/- 23.95 274.7 +/- 21.31 211.6 +/- 21.18 149.6 +/- 26.20 142.3 +/- 22.18 Ba!La-140

< 10.09

< 9.38

< 9.42

< 14.85

< 11.61

< 9.01

[ NUCLIDE July.

August Septembet.

October.

November

]

December 1-131

< 14.63

< 13.28

< 12.62

< 13.77

< 11.13

< 14.53 Cs-134

< 4.98

< 3.01

< 4.45

< 2.83

< 2.75

< 4.09 Cs-137

< 4.29

< 2.62

< 4.05

< 3.74

< 2.63

< 3.82 Zr-95

< 9.01

< 6.21

< 7.41

< 7.20

< 5.76

< 7.45 Nb-95

< 4.68

< 4.26

< 5.76

< 4.61

< 3.48

< 4.70 Co-58

< 4.69

< 3.31

< 4.09

< 4.08

< 3.14

< 4.10 Mn-54

< 3.89

< 3.24

< 3.80

< 3.70

< 2.57

< 3.89 Fe-59

< 12.00

< 9.31

< 12.45

< 10.02

< 10.35

< 11.61 Zn-65

< 8.92

< 7.30

< 8.79

< 9.36

< 5.75

< 9.20 Co-60

< 4.26

< 3.58

< 3.75

< 3.33

< 2.35

< 4.28 K-40 149.7 +/- 21.12 151.6 +/- 15.97 344.7 +/- 26.05 134.9 +/- 15.81 290.7 +/- 17.03 121.8 +/- 17.80 BaILa-140

< 11.98

< 10.78 K 10.38

< 10.56

< 8.37

< 9.25 Optional Sample Location Corresponds to sample location noted on Figure 3.3-4 6-11

Table 6-5 CONCENTRAION OF TRITIUM, STRONTIUM AND GAMMA EMITTERS IN GROUNDWATER SAMPES - 2007 Results in Units of pCi/I - 1 sigma Indicator Date Trti Sr-90 GAMMA EMITTERS

.Location*

...IK4 M__-54 Co-58 Fe-59 Co-60 [ Cs-134 Cs-137 Zn-65 I Other ["

1/2912007

<461 144

< 6.82

<7.29

<20.9

<7.29

<6.13

<4.85

<14.9

<LLD NMP2 4/4/2007

<441 216

<6.94

<6.21

<16.5

<6.47

<7.26

<6.55

<14.6

<LLD Depression 6/18/2007

<440 250+/- 45

<7.07

<8.08

<23.0

<8.13

<8&67

<7.57

<23.2

<LLD Cone 9/17/2007

<445 1186+/- 31

<4.52

<6.24

<16.6

<6.66

<7.08

<5.78

<13.2

<LLD 12/3/2 0 07 J *7 2...

Sampled at the discharge of the NMIP2 Storm Drain t

Plant related radionuclides

'"' ~ I jO t_

_-e_

Locationr t

I

.I K-40 Mn-54 i Co-58 Fe-59 Co-60 Cs-134 Cs-137 Zn-65 j Other -

MW-2 6/26/2007

<444 351 +/-39

<7.05

<5.70

<19.0

<5.52

<5.90

<6.44

<7.05

<LLD MW-3 6/26/2007

<444

, 174+/-43

<8.43

<7.66

<20.6

<7.41

<9.31

<8.22

<20.0

<LLD MW-1 10/25/2007

<442

<2 202 +/- 24

<5.01

<4.40

<10.9.

<5.10

<4.73

<4.58

<7.47

,<LLD MW-5 10/25/2007

<442 1

<2 193 +/- 261

<5.31

<6.06

<13.6

<5.50

<5.60

<5.14

<7.18

<LLD

Sampled at wells located in the north east corner of the protected area t Plant related radionuclides Control Date Tritium Sr-90 GAMMAEMITTERS Location*

__._K-40 Il n-54.. C0o-58 Fe-59 Co-60 [ Cs-134 [ Cs-137 Zn-46-5 Other I GMX-MW1 6/21/2007

<445 143+/-30

<6.30

<7.30

<17.6

<7.94 ( <6.42

<4.85

<7.80

<LLD GMX-MW2 6/21/2007

<445 151 +/-33

<5.38

<8.03

<21.6

<6.42

<6.15

<5.90

<14.6 1 <LLD GMX-MW1 10/22/2007

<442 L<2 210 +/- 33

<5.82 1 <6.35

<14.7

<7.02

<5.97

<5.72

<7.10 j

<LLD Sampled at wells located south of the protected area t Plant related radionuclides 6-12 m -m m -

m

-m m-m

TABLE 6-6 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCi/ in3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS Sampl.e R-R2*

I RR2-*

-R53*

R-4*

R-5*

D-2**

EF

F*

O**

Datei

...1 1/3/2007 0.013 + 0.001 0.015 + 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.017 +/- 0.001 1/9/2007 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.002 0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 1/16/2007 0.014 +/- 0.001 0.016 + 0.001 0.013 +/- 0.001 0.016 : 0.001 0.018 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0,001 0.014 +/- 0.001 1/23/2007 0.020 +/- 0.001 0.020 +/- 0.001 0.023 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0.002 0.017 +/- 0.001 0.022 +/- 0.002 0.019 +/- 0.001 0.019 +/- 0.001 1/30/2007 0.02-1 +/- 0.002 0.020 +/- 0.001 0.020 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0.002 0.020 + 0.001 0.024 +/- 0.002 0.020 +/- 0.001 0.018 +/- 0.001 2/6/2007 0.015 + 0.001 0.020 +/- 0.002 0.023 +/- 0.002 0.019 +/- 0.002 0.018 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.018 + 0.001 0.021 +/- 0.002 2/13/2007 0.019 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.019 +/- 0.002 0.019 +/- 0.002 0.019 +/- 0.002 0.017 +/- 0.001 2/20/2007 0.017 + 0.001 0.018 +/- 0.001 0.017 +/- 0.001 0.020 +/- 0.002 0.020 +/- 0.001 0.020 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.002 0.018 +/- 0.001 2/27/2007 0.015 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 3/6/2007 0.012 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 3/13/2007 0.021 +/- 0.002 0.019 +/- 0.001 0.019 +/- 0.001 0.021 + 0.002 0.021 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0.001 0.020 +/- 0.001 3/20/2007 0.021 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.001 0.020 +/- 0.002 0.017 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.002 0.017 +/- 0.001 0.019 +/- 0.001 3/27/2007 0.013 +/- 0.001 0.015 + 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001, 0.014 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 4/3/2007 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 4/10/2007 0.009 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 4/17/2007 0.010 L 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.008 +/- 0.001 0.011 +/- 0.001 0.010 L 0.001 0.008 +/- 0.001 0.007 +/- 0.001 4/24/2007 0.015 +/- 0.001 0.015 +/- 0.001 0,015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 5/1/2007 0.010 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 0.010 L 0.001 0.010 +/- 0.001 5/8/2007 0.012 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 5/15/2007 0.020 +/- 0.002 0.020 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 5/22/2007 0.014 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.011 + 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 5/30/2007 0.020 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.001 0.019 +/- 0.001 6/5/2007 0.025 +/- 0.002 0.025 +/- 0.002 0.028 +/- 0.002 0.024 +/- 0.002 0.028 +/- 0.002 0.025 +/- 0.002 0.026 +/- 0.002 0.024 +/- 0.002 0.025 +/- 0.002 6/12/2007 0.013 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 6/19/2007 0.013 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 6/26/2007 0.014 + 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 Sample location required by ODCM

- Optional sample location 6-13

TABLE 6-6 (continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCi/rm3 L 1 Sigma

.. OFFSITE SAMPLE LOCATIONS Sample R-1 1 R-2 R-3

R-4 R-5*

D i*

F Date i_

i_

_1 D 2 7/3/2007 0.016 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.011 + 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 7/10/2007 0.021 +/- 0.002 0.022 +/- 0.002 0.018 +/- 0.001 0.021 +/- 0.002 M0019 + 0.001 0.022 +/- 0.002 0.017 +/- 0.001 0.019 +/- 0.001 0.021 +/- 0.002 7/17/2007 0.015 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 7/24/2007 0.015 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/-L 0.001 0.015 +/- 0.001 0.010 +/- 0.001 0.018 + 0.001 0.015 +/- 0.001 7/31/2007 0.020 4-0.002 0.018 +/- 0.001 0.019 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 8/7/2007 0.024 +/- 0.002 0.020 :L 0.001 0.017 +/- 0.001 0.022 :L 0.002 0.024 +/- 0.002 0.025 +/- 0.002 0.024 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 8/14/2007 0.019 +/- 0.002.0.016 +/-: 0.001 0.017 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.015 + 0.001 0.013. +/- 0.001 0.015 +/- 0.001 8/21/2007 0.009 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.010 : 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 8/28/2007 0.012 +/-.0.001 0.012 +/- 0.001 0.009 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 9/5/2007 0.013 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0.001 0.015 + 0.001 0.015 +/- 0.001 0.016 +/- 0.001 9/11/2007 0.020 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.017 +/- 0.002 9/18/2007 0.010 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.007 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 9/25/2007 0.023 +/- 0.002 0.025 +/- 0.002 0.023 +/- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.023 +/- 0.002 0.019 +/- 0.001 0.025 + 0.002 0.022 +/- 0.002 10/2/2007 0.018 + 0.001, 0.018 +/- 0.001 0.019 +/- 0.001 0.018 +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 0.014. +/- 0.001 0.016 +/- 0.001 0.019 +/- 0.001 10/9/2007 0.025

+/- 0.002 0.027 L-0.002 0.025 +/- 0.002 0.027 +/- 0.002 0.025 : 0.002 0.025 L 0.002 0.023 +/- 0.002 0.023+

0.002 0.026 +/- 0.002 10/16/2007 0.007 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.009 +/-- 0.001 0.009 + 0.001 0.008 + 0.001 0.008 +/- 0.001 10/23/2007 0.028 +/- 0.002 0.026 1 0.002 0.025 +/-L 0.002 0.025 :L 0.002 0.027 L 0.002 0.029 +/- 0.002 0.025 +/- 0.002 0.027 +/- 0.002 0.027 +/-: 0.002 10/30/2007 0.011 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.013 + 0.001 0.014 + 0.001 0.012 +/- 0.001 0.015 +/- 0.001 11/6/2007 0.020 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.001 0.015 +/- 0.001 !0.018 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.002 11/13/2007 0.013 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 11/20/2007 0.014 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.015 +/- 0.001 11/27/2007 0.016 +/- 0.001 0.014 +/- 0.001 0.013 1 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 12/4/2007 0.017 +/- 0.001 0.019 +/- 0.001 0.016 +/- 0.001 0.015 +/- 0.001 0.016 +/-L 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 12/11/2007 0.019 +/- 0.001 0.015 j: 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.017 +/- 0.001 0.019 :1 0.001 0.018 +/--0.001 12/19/2007 0.023 +/- 0.002 0.022 +/- 0.001 0.021 +/- 0.001 0.025 +/- 0.002 0.020 +/- 0.001 0.022 +/- 0.001 0.022 +/-L 0.001 0.025 +/- 0.002 0.020 +/- 0.001 12/26/2007 0.021 +/- 0.002 0.022 +/- 0.002 0.023 +/- 0.002 0.026 +/- 0.002 0.023 +/- 0.002 0.018 +/- 0.001 0.017 +/- 0.001 0.023 +/- 0.002 0.019 +/- 0.002 Sample location required by ODCI l

- Optional samnple location 6-14 m

-m

m m

TABLE 6-7 ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES -2007 GROSS BETA ACTIVITY pCi/rm3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS S a n p l I -....

I.........ý Sape~.

D-i**

G_*_"

H**

J _" __ ___,

D a te -.....

1/2/2007 0.017

+/-

0.001 0.013

+/-

0.001 0.014

+/-

0.001 0.017

+/-

0.001 0.014

+/-

0.001 0.018

+/-

0.001 1/8/2007 0.013

+

0.001 0.013

+/-

0.001 0.014

+/-

0.001 0.014

+/-

0.001 0.012

+/-

0.001 0.012

+/-

0.001 1/15/2007 0.016

+/-

0.001 0.017

+/-

0.001 0.011

+/-

0.001 0.015

+/-

0.001 0.015 0.001 0.015

+

0.001 1/22/2007 0.021

+/-

0.002 0.018 0.001 0.017

+/-

0.001 0.022

+/-

0.002 0.018

+

0.001 0.020

+/-

0.002 1/29/2007 0.021

+/-

0.002 0.021

+/-

0.002 0.022

+

0.002 0.018

+/-

0.001 0.022

+/-

0.002 0.024 0.002 2/5/2007 0.021

+/-

0.002 0.019

+/-

0.001 0.018

+/-

0.001 0.020

+/-

0.002 0.016

+

0.001 0.018

+/-

0.001 2/12/2007 0.012

+/-

0.001 0.016

+/-

0.001 0.010 0.001 0.015

+/-

0.001 0.016

+/-

0.001 0.014

+

0.001 2/19/2007 0.017

+/-

0.001 0.017

+/-

0.001

, 0.018

+/-

0.001 0.018

+/-

0.001 0.020

+/-

0.001 0.018

+/-

0.001 2/26/2007 0.017

+/-

0.001 0.015

+/-

0.001 0.015

+/-

0.001 0.017

+

0.001.

0.016

+

0.001 0.016

+/-

0.001 3/5/2007 0.012

+/-

0.001 0.011

+

0.001 0.013

+/-

0.001 0.011

+/-

0.001 0.013

+/-

0.001 0.013

+/-

0.001 3/12/2007 0.018

+/-

0.001 0.022

+/-

0.002 0.020

+/-

0.001 0.022

+/-

0.002 0.021

+

0.002 0.025

+/-

0.002 3/19/2007 0.020

+/-

0.001 0.019

+/-

0.001 0.019

+/-

0.001 0.022

+/-

0.002 0.021

+/-

0.002 0.019

+

0.001 3/26/2007 0.020

+

0.002 0.020

+

0.001 0.026

+

0.002 0.016

+/-

0.001 0.016

+

0.001 0.017

+/-

0.001 4/2/2007 0.015

+/-

0.001 0.017

+/-

0.001 0.014

+/-

0.002 0.014

+/-

0.001 0.014

+/-

0.001 0.014

+/-

0.001

-4/9/2007 0.010

+/-

0.001 0.009

+

0.001 0.009

+/-

0.001 0.010

+/-

0.001 0.007

+/-

0.001 0.009

+/-

0.001 4/16/2007 0.010

+/-

0.001 0.009

+/-

0.001 0.012

+/-

0.001 0.008

+/-

0.001 0.008

+

0.001 0.010

+/-

0.001 4/23/2007 0.017

+/-

0.001 0.015

+/-

0.001 0.012

+/-

0.001 0.015

+/-

0.001 0.012

+/-

0.001 0.013

+/-

0.001 4/30/2007 0.012

+/-

0.001 0.011

+/-

0.001 0.011

+/-

0.001 0.014

+/-

0.001 0.011

+/-

0.001 0.011

+/-

0.001 5/7/2007 0.012

+/-

0.001 0.011

+/-

0.001 0.014

+/-

0.001 0.009

+/-

0.001 0.013

+/-

0.001 0.013 0.001 5/14/2007 0.017

+/-

0.001 0.015

+/-

0.001 0.014

+/-

0.001 0.016

+/-

0.001 0.021

+/-

0.002 0.017

+/-

0.001 5/21/2007 0:017

+/-

0.001 0.015

+/-

0.001 0.014

+/-

0.001 0.015

+/-

0.001 0.013

+/-

0.001 0.015

+/-

0.001 5/29/2007 0.018

+/-

0.001 0.019

+/-

0.001 0.016

+/-

0.001 0.019

+/-

0.001 0.017

+

0.001 0.017

+/-

0.001 6/4/2007 0.027

+/-

0.002 0.023

+/-

0.002 0.023

+/-

0.002 0.024

+/-

0.002 0.023

+/-

0.002 0.021

+/-

0.002 6/11/2007 0.011

+/-

0.001 0.012

+/-

0.001 0.007

+/-

0.001 0.010

+/-

0.001 0.009 0.001 0.011

+/-

0.001 6/18/2007 0.018

+/-

0.001 0.013

+/-

0.001 0.014

+/-

0.001 0.016

+/-

0.001 0.016

+/-

0.001 0.016

+/-

0.001 6/25/2007 0.013

+/-

0.001 0.007

+/-

0.001 0.010

+/-

0.001 0.012

+

0.001 0.012

+/-

0.001 0.011

+

0.001 Optional sample location 6-15

TABLE 6-7 (continued)

ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCi/ in3 +/- 1 Sigma ONSITE SAMPLE LOCATIONS Sample D

I I

I K**

Date D-...

H..

7/2/2007 0.017

+/-

0.001 0.015

+/-

0.001 0.014

+/-

0.001 0.015

+/-

0.001 0.018 0.001 0.017

+/-

0.001 7/9/2007 0.016

+/-

0.001 0.013

+/-

0.001

.0.015

+/-

0.001 0.015

+

0.001 0.015

+/-

0.001 0.014

+/-

0.001 7/16/2007 0.018

+/-

0.001 0.018

+/-

0.001.

0.017

+/-

0.001 0.019

+/-

0.001 0.016

+/-

0.001 0.019 0.001 7/23/2007 0.014

+

0.001 0.012

+/-

0.001 0.014

+/-

0.001 0.011

+/-

0.001 0.015

+/-

0.001 0.015 1

0.001 7/30/2007 0.020

+/-

0.002 0.019

+/-

0:001 0.021

+/-

0.001 0.019

+/-

0.001 0.019

+/-

0.001 0.019

+/-

0.001 8/6/2007 0.023

+/-

0.002 0.026

+/-

0.002 0.021

+/-

0.002 0.020

+/-

0.002 0.022

+/-

0.002 0.023

+/-

0.002 8/13/2007 0.020

+/-

0.002 0.020

+/-

0.001 0.019

+/-

0.001 0.017

+/-

0.001 0.018

+/-

0.001 0.020

+/-

0.002 8/20/2007 0.011

+/-

0.OO1 0.012

+/-

0.001 0.011

+/-

0.001 0.011

+/-

0.001 0.012

+/-

0.001 0.010

+/-

0.001 8/27/2007 0.009

+/-

0.001 0.013

+/-

0.001 0.011

+/-

0.001 0.013

+/-

0.001 0.011

+/-

0.001 0.008

+/-

0.001 9/4/2007 0.018

+/-

0.001t 0.018

+/-

0.001 0.017

+/-

0.001 0.015

+/-

0.001 0.018

+/-

0.001 0.017

+/-

0.001 9/10/2007 0.021

+/--0.002 0.019

+/-

0.002 0.017

+/-

0.001 0.022

+/-

0.002 0.021

+/-

0.002 0.017

+/-

0.002 9/17/2007 0.009

+/-

0.001 0.014

+/-

0.001 0.009

+/-

0.001 0.012

+/-

0.001 0.009

+/-

0.001 0.008

+/-

0.001 9/24/2007 0.022

+/-

0.002 0.022

+/-

0.002 0.022

+/-

0.002 0.017

+/-

0.001 0.022

+/-

0.002 0.019

+/-

0.002 10/1/2007 0.021

+/-

0.002 0.020

+/-

0.002 0.019

+/-

0.001 0.019

+/-

0.001 0.017

+

0.001 0.018

+/-

0.001 10/8/2007 0.026

+/-

0.002 0.029

+/-

0.002 0.027

+/-

0.002 0.026

+/-

0.002 0.025

+/-

0.002 0.026

+/-

0.002 10/15/2007 0.013

+/-

0.001 0.008

+/-

0.001 0.009

+/-

0.001 0.010

+/-

0.001 0.010

+/-

0.001 0.008

+/-

0.001 10/22/2007 0.025

+/-

0.002 0.024 zL 0.00.2 0.023

+/-

0.002 0.027

+/-

0.002 0.024

+/-

0.002 0.024

+/-

0.002 10/29/2007 0.013

+

0.001 0.016

+/-

0.001 0.013

+/-

0.001 0.016

+/-

0.001 0.015

+/-

0.001 0.015

+/-

0.001 11/5/2007 0.021

+/-

0.002 0.019

+/-

0.002 0.022

+/-

0.002 0.022

+/-

0.002 0.020

+/-

0.001 0.022

+/-

0.002 11/12/2007 0.014

+/-

0.001 0.013

+/-

0.001 0.014

+/-

0.001 0.015 6 0.001 0.016

+

0.001 0.015

+/-

0.001 11/19/2007 0.016

+/-

0.001 0.017

+/-

0.001 0.014

+/-

0.001 0.015

+/-

0.001 0.014

+/-

0.001 0.015

+/-

0.001 11/26/2007 0.014

+/-

0.001 0.016

+/-

0.001 0.018

+/-

0.001 0.012

+/-

0.001 0.012

+/-

0.001 0.014

+/-

0.001 12/3/2007 0.020

+/-

0.002 0.019

+/-

0.001 0.017

+/-

0.001 0.017

+/-

0.001 0.019

+/-

0.001 0.020

+/-

0.001 12/10/2007 0.014

+/-

0.001 0.014

+/-

0.001 0.017

+/-

0.001 0.014

+/-

0.001 0.013

+

0.001 0.015

+/-

0.001 12/17/2007 0.023

+/-

0.002 0.022 * +/-

0.002 0.025

+/-

0.002 0.021

+/-

0.002 0.021

+/-

0.001 0.022

+/-

. 0.002 12/26/2007 0.022

+/-

0.001 0.024

+/-

0.001 0.022

+/-

0.001 0.018

+/-

0.001 0.022

+/-

0.001 0.023

+/-

0.001 12/31/2007 0.023

+/-

0.002 0.028

+/-

0.002 0.021

+/-

0.002 0.016

+/-

0.002 0.025

+/-

0.002 0.021

+/-

0.002

- Optional sample location 6-16 m

m m

m-m mm m

m m

mmmmmmm m

mmmmmmm mm m

m mn TABLE 6-8 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m3 1+

1 Sigma OFFSITE SAMPLE LOCATIONS - 1ST QTR 2007 Nuclide R-i*

R-2*

R-3*

R-4*

R-5 D-2 E**

F**

G**

Be-7 134.2 +/- 22.8 106.6 +/- 23.4 86.3 +/- 20.9 127.8 +/- 24.5 87.3 +/- 20.6 71.7 +/- 22.2 114.2 +/- 22.5 140.3 +/- 22.9 81.5 +/- 28.1 Cs-134

< 2.6

< 5.0

< 4.3

< 3.2

< 2.8

< 4.4

< 5.1

< 3.7

< 4.3 Cs-137

< 2.9

< 2.5

< 2.2

< 1.0

< 2.5

< 0.8

< 2.5

< 2.2

< 4.7 Zr-95

< 7.5

< 2.8

< 6.9.

< 3.1

< 2.8

< 2.6

< 7.9

< 6.6

< 14.8 Nb-95

< 6.1

< 6.3

< 7.5

< 7.3

< 2.3.

< 10.2

< 6.4

< 9.4

< 3.5 Co-58

< 1.5

< 4.6

< 6.0

< 1.8

< 5.9

< 1.5

< 4.7

< 1.4

< 2.5 Mn-54

< 1.0

< 3.3

< 2.9

< 4.1

< 1.1

< 3.9

< 1.2

< 3.5

< 1.8 Zn-65

< 2.8

< 11.1

< 7.2

< 3.4

< 3.1

< 11.2

< 9.0

< 2.6

< 4.8 Co-60

< 1.5

< 1.7

< 5.5

< 1.8

< 1.6

< 5.4

< 1.7

< 1.3

< 2.6 K-40

< 14.7

< 67.2

< 13.9

< 18.2

< 56.8

< 38.9

< 17.0

< 13.4

< 26.0

ODCMv! Required Sample Loction

- Optional Sample Location OFFSITE SAMPLE LOCATIONS - 2ND QTR 2007 Nuclide R-i

R-2*

R-3*

R-4*

R-5*

D-2**

E**

G Be-7 113.5 +/- 14.1 131.7 +/- 13.5 120.2 +/- 12.7 114.4 +/-

16.6 132.3 +/- 13.6 103.8 +/- 16.9 106.6 +/- 13.1 105.4 +/- 13.1 128.4 +/-

12.7 Cs-134

< 1.8

< 1.4

< 1.6

< 2.2

< 1.0

< 1.7

< 1.6

< 1.1 Cs-137

< 1.4

< 1.0

< 0.9

< 0.5

< 1.2

< 1.9

< 1.3

< 1.2

< 1.3 Zr-95

< 2.9

< 2.7

< 4.0

< 1.6

< 3.7

< 8.1

< 3.6

< 3.6 Nb-95

< 3.6

< 2.8

< 3.9

< 3.3

< 3.4

< 3.1

< 3.4

< 3.3 Co-58

< 2.8

< 2.2

< 0.5

< 2.3

< 0.5

< 0.8

< 1.8

< 2.0

< 1.4 Mn-54

< 1.5

< 1.1

< 1.9

< 0.6

< 1.6

< 2.7

< 1.0

< 1.7

< 0.3 Zn-65

< 3.0

< 2.8

< 4.0

< 1.8

< 6.0

< 6.8

< 2.9

< 3.1 Co-60

< 1.7

<1.5

< 2.2

< 1.0

< 2.1

< 0.8

< 1.6

< 1.4 K-40

< 20.5

< 18.7 43.9 +/- 9.2

< 9.8 40.8 +/- 9.1

< 8.3

< 15.7

< 19.7

< 12.6 ODCM Required Sample Loction

- Optional Sample Location 6-17

TABLE 6-8 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma OFFSITE SAMPLE LOCATIONS - 3RD QTR 2007 Date R-1*

R-2*

R-3*

R-4 R-5 *D-2 E**

F G**

Be-7 131.2 +/- 15.8 100.5 +/- 11.5 113.8 +/- 12.4 117.7 +/- 11.9 101.8 +/- 15.3 84.4 +/- 11.9 112.2 +/- 14.8 118.6 +/- 12.8 92.0 +/- 11.0 Cs-134

< 1.6

< 1.3

< 1.4

< 1.7

< 2.1

< 2.2

< 1.5

< 1.1 Cs-137

< 1.4

< 1.0

< 1.2

< 0.8

< 1.9

< 1.5

< 1.6

< 0.9 Zr-95

< 4.4

< 0.9

< 3.1

< 5.3

< 4.2

< 2.4

< 5.0

< 3.9

< 2.5 Nb-95

< 4.2

< 3.5

< 3.3

< 3.0

< 1.2

< 2.5

< 5.0

< 3.6

< 3.0 Co-58

< 3.8

< 1.6

< 0.5

< 1.2

< 0.8

< 1.4

< 0.7

< 1.4

< 2.6 Mn-54

< 1.5 1.2

< 1.4

< 1.3

-< 1.6

< 2.1

< 1.8

< 1.0

< 1.5 Zn-65

< 5.6

< 1.0

< 4.0

< 4.2

< 4.7

< 2.7

< 3.8

< 2.7

< 0.9 Co-60

< 0.8

< 2.4

< 1.7

< 1.8

< 0.9

< 1.6

< 3.1

< 1.5

< 1.4 K-40

< 7.6

< 5.1

< 13.2 31.4 +/- 7.0

< 24.6

< 20.7

< 21.2

< 5.3

< 5.0 ODCM Required Sample Loction

- Optional Sample Location OFFSITE SAMPLE LOCATIONS - 4TH QTR 2007 Date R-

R-2*

R-3*

R4R-5 D-2**

E**

F G

Be-7 85.0 +1-14.2 87.1 +1-11.3 77,1 +/- 11.3 81.6 +/- 11.1 64.1 12.2 85.5 +/-

11.4 76.3 +/-

12.6 79.0 +/- 11.4 82.5 +/- 11.7 Cs-134

< 1.9

< 1.6

< 1.2

< 1.7

< 2.3

< 1.9

< 2.1

< 2.4

< 1.7 Cs-137

< 1.1

< 1.0

< 1.1

< 1.5

< 1.4

< 0.9

< 1.1

< 1.8

< 0.7 Zr-95

< 3.7

< 4.0

< 3.0

< 5.0

< 3.9

< 4.3

< 3.7

< 2.5

< 3.5 Nb-95

< 5.0

< 3.0

< 2.9

< 2.7

< 4.0

< 3.8

< 3.0

< 2.5

< 2.8 Co-58

< 3.1

< 2.0

< 26

< 2.1

< 2.9

< 1.4

< 2.6

< 2.2 Mn-54

< 1.5

< 1.6

< 1.7

< 1.6

< 2.1

< 1.7

< 1.5

< 1.3

< 1.2 Zn-65

< 1.4

< 1.0

< 4.5

< 3.4

< 6.1

< 4.3

< 3.8

< 4.3

< 4.0 Co-60

< 2.2

< 0.5

< 1.4

< 1.3

< 0.9

< 2.1

< 2.2

< 0.6

< 2.0 K-40

< 7.8

< 5.1

< 14.0 27.1 +/- 9.4

< 9.3

< 5.1

< 7.6

< 15.0_

< 13.9

-uL'IVI Kequn'eU zample Loction

- Optional Sample Location 6-18 M

M M

M

-M M

M nib M

M M

I

mn mmm m

m m

n m

m TABLE 6-9 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m3 + 1 Sigma ONSITE SAMPLE LOCATIONS - IST QTR 2007 Nuclide D-1**

G J

K+*

Be-7 92.5 +/-

20.8 140.5 +/-

24.4 104.7 +/-

19.8 126.7 +/-

25.0 70.9 +/-

20.8 118.7 +/-

24.3 Cs-134

< 1.1

< 1.0

< 3.9

< 4.1

< 4.5

< 2.9 Cs-137.

< 1.0

< 0.9

< 0.8

< 2.6

< 1.0

< 0.9 Zr-95

< 3.1

< 2.9

< 2.7

< 8.2

< 11.3

< 8.5 Nb-95

< 7.3

< 2.4

< 2.2

< 8.5

< 10.8

< 2.4 Co-58

< 4.5

< 4.7

< 1.5

< 6.2

< 1.8

< 4.8 Mn-54

< 4.0

< 1.1

< 5.1

< 1.2

< 1.2 Zu-65

< 9.0

< 3.1

< 7.7

< 9.2

< 3.3

< 3.2 Co-60

< 1.8

< 4.7

< 1.5

< 1.7

< 1.8

< 1.7 K-40

< 17.7

< 16.6

< 14.9

< 17.5

< 17.9

< 17.1

- Optional Sample Location ONSITE SAMPLE LOCATIONS - 2ND QTR 2007 Nuclide D-1 **

G **

H **

i **

J **

K **

Be-7 126.3 +/-

14.3 128.7 +/-

13.3 128.2 +/-

13.4 143.6 +/-

18.5 117.4 +/-

14.0 107.7 +/-

16.1 Cs-134

< 1.0

< 1.2

< 2.0

< 2.4 Cs-137

< 0.3

< 1.3

< 1.4

< 2.2

< 1.1

< 1.2 Zr-95

< 4.2

< 3.4

< 3.2

< 6.0

< 3.9

< 1.4 Nb-95

< 3.5

< 4.0

< 4.3

< 1.4

< 2.2

< 3.9 Co-58

< 0.6

< 2.5

< 2.6

< 0.9

< 2.6

< 2.9 Mn-54

< 1.0

< 0.4

< 1.3

< 1.8

< 1.1

< 2.4 Zn-65

< 1.1

<3.5

< 2.5

< 1.9

< 5.7

< 6.1 Co-60

< 0.6

< 0.5

< 1.8

< 2.6

< 1.7

< 3.0 K-40

< 22.8

< 18.6 30.5 +/-

8.0

< 10.2

< 22.7

< 23.6

- Optional Sample Location 6-19

TABLE 6-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF JAF/NMPNS SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 19E-3 pCi/m 3 +/-: 1 Sigma ONSITE SAMPLE LOCATIONS - 3RD QTR 2007 Nuclide D-1 G**

H" J**

K**

Be-7 116.2 +/-

16.4 132.0 +/-

13.7 98.1 +1 11.2 102.2 +/

11.7 95.9 +/-

14.6 86.1 +/-

11.8 Cs-134

< 1.6

< 1.5

< 1.9

< 1.8

< 1.4

< 1.7 Cs-137

< 1.9

< 1.0

< 0.7

< 1.1*

< 0.5

< 0.9 Zr-95

< 5.1

< 0.9

< 5.3

< 4.1

< 6.4

< 2.5 Nb-95

< 4.3

< 2.2

< 2.6

< 3.4

< 3.2

< 3.4 Co-58

< 2.1

< 2.5

< 2.3

< 2.9

< 2.8

< 1.5 Mn-54

< 0.5

< 1.2

< 1.0

< 1.1

< 2.1

< 1.3 Zn-65

< 3.8

< 2.7

< 0.9

< 2.8

< 6.0

< 5.4 Co-60

< 2.7

< 05

< 0.5

< 1.6

< 3.4

< 2.0 K-40

< 7.5

< 17.8

< 4.8 34.8 +/-

8.9

< 24.9

< 16.4

- Optional Sample Location ONSITE SAMPLE LOCATIONS - 4TH QTR 2007 Nuclide D-I

G *H J*ý K*

Be-7 68.9 +/-

12.3 88.6 +/-

11.9 89.0 +/-

10.9 90.8 +/-

10.9 74.6 +/-

13.1 87.5 +/-

12.1 Cs-134

< 1.9

< 1.5

< 1.7

< 1.0

< 2.0

< 1.9 Cs-137

< 1.9

< 1.1

< 1.2

< 1.1

< 1.3

< 1.0 Zr-95

< 3.8

< 3.7

< 2.4

< 3.8

< 4.9

< 2.5 Nb-95

< 3.2

< 2.6

< 3.2

< 1.9

< 4.7

< 2.1 Co-58

< 0.8

< 2.5

< 0.5

< 2.1

< 3.4

< 2.1 Mn-54

< 1.9

< 0.4

< 1.0

< 1.5

< 2.1

< 1.6 Zn-65

< 5.8

< 3.0

< 3.4

< 4.4

< 1.7

< 4.0 Co-60

< 0.8

< 1.9

< 0.5

< 0.4

< 0.9

< 2.5 K-40

< 7.8

< 15.1

< 13.8 33.9 +/-/-

7.9

< 9.1

< 5.3

- Optional Sample Location 6-20 m

M M

M m -

-M M

M M

m

TABLE 6-10 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/ in3 =+/- 1 Sigma OFFSITE SAMPLE LOCATIONS Sample ae R-I*

R-2*

R-3*

R-4 R-5*

D-2 **E**

F*

G Date 01/03/07

< 0.022

< 0.028

< 0.024

< 0.026

< 0.033

< 0.027

< 0.028

< 0.023

< 0.028 01/09/07

< 0.028

< 0.024

< 0.036

< 0.031

< 0.032

< 0.024

< 0.022

< 0.026

< 0.025 01/16/07

< 0.023

< 0.021

< 0.028

< 0.018

< 0.038

< 0.026

< 0.015

< 0.017

< 0.022 01/23/07

< 0.023

< 0.020

< 0.006

< 0.029

< 0.039

< 0.025

< 0.014

< 0.012

< 0.015 01/30/07

< 0.029

< 0.020

< 0.019

< 0.030

< 0.025

< 0.031

< 0.024

< 0.027 02/06/07

< 0.031

< 0.038

< 0.026

< 0.035

< 0.028

< 0.019

< 0.015

< 0.025

< 0.036 02/13/07

< 0.057

< 0.035

< 0.036

< 0.053

< 0.034

< 0.044

< 0.049

< 0.032

< 0.033 02/20/07

< 0.012

< 0.031

< 0.024

< 0.038

< 0.032

< 0.033

< 0.045

< 0.038

< 0.029 02/27/07

< 0.046

< 0.011

< 0.040

< 0.011

<0.027

< 0.015

< 0.033

< 0.010

< 0.029 03/06/07

< 0.035

< 0.024

< 0.034

< 0.029

< 0.025

< 0.022

< 0.013

< 0.025

< 0.027 03/13/07

< 0.016

< 0.031

< 0.035

< 0.039

< 0.034

< 0.056

< 0.015

< 0.043

< 0.011 03/20/07

< 0.008

< 0.028

< 0.022

< 0.026

< 0.023

< 0.024

< 0.015 03/27/07

< 0.057

< 0.028

< 0.046

< 0.039

< 0.043

< 0.052

< 0.033

< 0.030 04/03/07

< 0.046

< 0.050

< 0.028

< 0.011

< 0.044

< 0.035

< 0.047

< 0.028

< 0.047 04/10/07

< 0.016

< 0.034

< 0.044

< 0.028

< 0.027

< 0.054

< 0.016

< 0.043

< 0.011 04/17/07

< 0.016

< 0.043

< 0.034

< 0.042

< 0.034

< 0.057

< 0.047

< 0.011

< 0.041 04/24/07

< 0.017

< 0.022

< 0.027

< 0.025

< 0.021

< 0.015

< 0.029

< 0.025

< 0.016 05/01/07

< 0.016

< 0.047

< 0.027

< 0.034

< 0.036

< 0.056

<. 0.031

< 0.011

< 0.011 05/08/07

< 0.068

< 0.041

< 0.035

< 0.056

< 0.041

< 0.027

< 0.067

< 0.035

< 0.044 05/15/07

< 0.060

< 0.033

< 0.042

< 0.035

< 0.039

< 0.044

< 0.011

< 0.042

< 0.028 05/22/07

< 0.016

< 0.011

< 0.039

< 0.036

< 0.045

< 0.047

< 0.058

< 0.033

< 0.033 05/30/07

< 0.045

< 0.043

< 0.038

< 0.032

< 0.024

< 0.037

< 0.041

< 0.047

< 0.025 06/05/07

< 0.022

< 0.032

< 0.026

< 0.037

< 0.019

< 0.016

< 0.036

< 0.032

< 0.028 06/12/07

< 0.026

< 0.019

< 0.028

< 0.022

< 0.021

< 0.017

< 0.028

< 0.033 06/19/07

< 0.017

< 0.024

< 0.008

< 0.019

< 0.018

< 0.028

< 0.017

< 0.024

< 0.028 06/26/07

< 0.034

< 0.024-

< 0.023'

< 0.026

< 0.022

< 0.038

< 0.025

< 0.026 ODCNM1 Required Sample

- Optional sample location Location 6-21

TABLE 6-10 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/m 3== 1 Sigma OFFSITE SAMPLE LOCATIONS Sample R-1*

R-2*

R-3*

R-4*

R-5*

D-2 *E*

F *G*

D ate 07/03/07

< 0.027

< 0.016

< 0.029

< 0.024

< 0.013

< 0.021

< 0.025

< 0.017

< 0.018 07/10/07

< 0.024

< 0.025

< 0.021

< 0.027

< 0.025

< 0.023

< 0.025

< 0.015

< 0.028 07/17/07

< 0.034

< 0.027

< 0.013

< 0.025

< 0.020

< 0.008

< 0.025

< 0.022

< 0.018 07/24/07

< 0.039

< 0.021

< 0.023

< 0.027

< 0.020

< 0.024

< 0.021

< 0.032

< 0.034 07/31/07

< 0.020

< 0.014

< 0.013

< 0.017

<. 0.020

< 0.021

< 0.020

< 0.018 08/07/07

< 0.021

< 0.019

< 0.026

< 0.027

< 0.026

< 0.032

< 0.021

< 0.014

< 0.032 08/14/07

< 0.036

< 0.027

< 0.025

< 0.030

< 0.032

< 0.025

< 0.028

< 0.029.

< 0.009 08/21/07

< 0.029

< 0.016

< 0.022

< 0.034

< 0.025

< 0.020

< 0.022

< 0.030 08/28/07

< 0.022

<. 0.021

< 0.027

< 0.017

< 0.023

< 0.022

< 0.021

< 0.023 09/05/07

< 0.018

< 0.022

< 0.016

< 0.018

< 0.020

< 0.013

< 0.018

< 0.021 09/11/07

< 0.009

< 0.023

< 0.024

< 0.030

< 0.025

< 0.033

< 0.034

< 0.019

< 0.010 09/18/07

< 0.029

< 0.021

< 0.014

< 0.009

< 0.014

< 0.038

< 0.027

< 0.014

< 0.025 09/25/07

< 0.037

< 0.021

< 0.018

< 0.024

< 0.023

< 0.021

< < 0.015

< 0.028 10/02/07

< 0.028

< 0.013

< 0.026

< 0.018

< 0.021

< 0.028

< 0.026

< 0.023

< 0.021 10/09/07

< 0.046

< 0.021

< 0.022

< 0.021

< 0.028

< 0.018

< 0.023

< 0.021

< 0.026 10/16/07

< 0.030

< 0.006

< 0.017

< 0.005

< 0.022

< 0.020

< 0.027

< 0.024

< 0.009 10/23/07

< 0.024

< 0.021

< 0.034

< 0.029

< 0.028

< 0.022

< 0.021

< 0.028

< 0.027 10/30/07

< 0.044

< 0.024

< 0.017

< 0.022

< 0.028

< 0.027

< 0.032.

< 0.026

< 0.033 11/06/07

< 0.029

< 0.022

< 0.019

< 0.020

< 0.028

< 0.026

< 0.028

< 0.023

< 0.019 11/13/07

< 0.024

< 0.027

< 0.035

< 0.015.

< 0.031

< 0.016

< 0.024 11/20/07

< 0.043

< 0.015

< 0.019

< 0.025

< 0.021

< 0.033

< 0.020

< 0.022

< 0.026 11/27/07

< 0.008

< 0.022

< 0.025

< 0.029

< 0.031

< 0.019

< 0.031

< 0.016

< 0.023 12/04/07

< 0.034

< 0.026-0.033

< 0.034

< 0.023

< 0.015

< 0.027

< 0.022

< 0.040 12/11/07

< 0.022

< 0.024

< K 0.008

< 0.026

< 0.029

< 0.022

< 0.029

< 0.005 12/19/07

< 0.032

< 0.020

< 0.026

< 0.023

< 0.0.19

< 0.027

< 0.022

< 0.023

< 0.022 12/26/07

< 0.022

< 0.021

< 0.023

< 0.029

< 0.022

< 0.028

< 0.029

< 0.024

< 0.018 ODCM Required Sample Location

- Optional sample location 6 - 22 M

M M

-M M

M M

M

TABLE 6-11 ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/ m3 1 1 Sigma ONSITE SAMPLE LOCATIONS Samiiple Date D-1 G**

H**

01/02/07

< 0.017

< 0.012

< 0.016

< 0.021

< 0.022

< 0.015 01/08/07

< 0.033

< 0.024

< 0.031

< 0.026

< 0.030 01/15/07

< 0.034

< 0.030

< 0.020

< 0.026

< 0.019

< 0.008 01/22/07

< 0.027

< 0.021

< 0.022

< 0.034

< 0.014

< 0.019 01/29/07

< 0.023

< 0.028

< 0.019

< 0.024

< 0.030

< 0.030 02/05/07

<.,0.044

< 0.024

< 0.034

< 0.031

< 0.035 02/12/07

< 0.034

< 0.033

< 0.028

< 0.008

< 0.026 02/19/07

< 0.052

< 0.033

< 0.034

< 0.030

< 0.032

< 0.035 02/26/07

< 0.061

< 0.032

< 0.037

< 0.057

< 0.035

< 0.048 03/05/07

< 0.035

< 0.016

< 0.017

< 0.025

< 0.024

< 0.027 03/12/07

< 0.016

< 0.011

< 0.027

< 0.043

< 0.042

< 0.049 03/19/07

< 0.047

< 0.033

< 0.038

< 0.010

< 0.012

< 0.029 03/26/07

< 0.046

< 0.015

< 0.060

< 0.064

< 0.035

< 0.049 04/02/07

< 0.067

< 0.033

< 0.041

0.011

< 0.038

< 0.057 04/09/07

< 0.016

< 0.033

< 0.041

< 0.029

< 0.050

< 0.038 04/16/07

< 0.046

< 0.011

< 0.035

< 0.028

< 0.010

< 0.037 04/23/07

< 0.024

< 0.026

< 0.018

< 0.022

< 0.005.

< 0.032 04/30/07

< 0.016

< 0.049

< 0.028

< 0.036

< 0.037

< 0.047 05/07/07

< 0.058

< 0.042

< 0.040

< 0.030

< 0.028

< 0.037 05/14/07

< 0.058

< 0.011

< 0.041

< 0.030

< 0.037

< 0.029 05/21/07

< 0.015

< 0.011

< 0.039

< 0.037

< 0.017

< 0.033 05/29/07

< 0.051

< 0.037

< 0.032

< 0.028

< 0.026

< 0.057 06/04/07

< 0.015

< 0.046

< 0.028

< 0.040

< 0.027

< 0.027 06/11/07

< 0.037

< 0.021

< 0.016

< 0.030

< 0.025

< 0.029 06/18/07

< 0.033

< 0.029

< 0,013

< 0.026

< 0.027

< 0.005 06/25/07

< 0.036

< 0.021

< 0.018

< 0.029

< 0.014

< 0.032

- Optional sample location 6 -23

TABLE 6-11 (Continued)

ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCi/mn 3 -

1 Sigma ONSITE SAMPLE LOCATIONS Sample D-1 **G**

H**

I k

Date 07/02/07

< 0.036

< 0.026

< 0.005

< 0.016

< 0.009

< 0.022 07/09/07

< 0.022

< 0.026

< 0.028

< 0.030

< 0.014

< 0.028 07/16/07

< 0.014

< 0.013

< 0.024

< 0.017

< 0.020 07/23/07

< 0.016

< 0.027

< 0.021

< 0.017

< 0.015

< 0.028 07/30/07

< 0.008

< 0.026

< 0.022

< 0.029

< 0.028

< 0.023 08/06/07

< 0.023

< 0.016

< 0.014

< 0.020

< 0.019 08/13/07

< 0.029

< 0.016

< 0.021

< 0.036

< 0.023

< 0.026 08/20/07

< 0.035

< 0.030

< 0.021

< 0.030

< 0.027

< 0.028 08/27/07

< 0.024

< 0.026

< 0.021

< 0.026

< 0.036

< 0.027 09/04/07

< 0.032

< 0.028

< 0.013

< 0.031

< 0.020

< 0.021 09/10/07

< 0.034

< 0.027

< 0.018

< 0.015

< 0.007

< 0.033 09/17/07

< 0.032

< 0.022

< 0.018

< 0.013

< 0.016

< 0.022 09/24/07

< 0.039

< 0.033

< 0.013

< 0.024

< 0.007

< 0.018 10/01/07

< 0.028

< 0.022

< 0.024

< 0.008

< 0.018

< 0.026 10/08/07

< 0.033

< 0.031:

< 0.025

< 0.028

< 0.042

< 0.023 10/15/07

< 0.023

< 0.025

< 0.016

< 0.021

< 0.016

< 0.032 10/22/07

< 0.039

< 0.023

< 0.017

< 0.030

< 0:032

< 0.032 10/29/07

< 0.033

< 0.024

< 0.033

< 0.018

< 0.020

< 0.024 11/05/07

< 0.008

< 0.006

< 0.018

< 0.025

< 0.024

< 0.039 11/12/07

< 0.036

< 0:023

< 0:030

< 0.014

< 0.032 11/19/07

< 0.030

< 0.029

< 0.021

< 0.020

< 0.015-

< 0.028 11/26/07

< 0.037

< 0.036

< 0.027

<K 0.022

< 0.023 12/03/07

< 0.028

< 0.022

< 0.021

< 0.022

< 0.025

< 0.028 12/10/07

< 0.034

< 0.024

< 0.031

< 0.024

< 0.014

< 0.033 12/17/07

< 0.029

< 0.025

< 0.022

< 0.020

< 0.006

< 0.026 12/26/07

< 0.025

< 0.022

< 0.019

< 0.021

< 0.019

< 0.005 12/31/07

< 0.043

< 0.034

< 0.039

< 0.034

< 0.040

< 0.029 Optional sample location 6 - 24 M

M M

-M M

M M

TABLE 6-12 DIRECT RADIATION MEASUREMENT RESULTS - 2007 Results in Units of mrem/std. Month +/- 1 Sigma Location First Second -

Third Fourth Number I Location Quarter Quarter_.

Quarter.

Quarter Degrees & Distance (1) 3 D1 Onsite 13.4

+

0.7 14.8

+

0.7 12.7

+/-

0.4 12.5 0.6 690 at 0.2 miles 4

D2 Onsite 4.1

+

0.2 5.2

+/-

0.2 4.7

+

0.2 4.9

+/-

0.2 1400 at 0.4 miles 5

E Onsite 4.0

+/-

0.2 5.3

+/-

0.2 4.9

+/-

0.3 4.9

+/-

0.3 1750 at 0.4 miles 6

F Onsite 3.3

+/-

0.2 4.7

+

0.2 4.4

+

0.2 4.6

+

0.2 2100 at 0.5 miles 7*

G Onsite 3.2

+

0.1 4.4

+/-

0.2 4.0

+/-

0.2 4.2

+/-

0.3 2440 at 0.7 miles 8

R-5 Offsite 4.3

+/-

0.2 5.8

+

0.3 5.5

+

0.2 5.5

+/-

0.3 420 at 16.4 miles 9

D1 Offsite 3.7

+

0.3 4.8

+/-

0.3 4.5

+/-

0.3 4.5

+/-

0.3 800 at 11.4 miles 10 D2 Offsite 3.4

+/-

0.2 4.6

+/-

0.2 4.3

+

0.3 4.4 0.2 1170 at 9.0 miles 11 E Offsite 3.5 0.1 4.6

+/-

0.2 4.4 0.2 4.5

+/-

0.3 1600 at 7.2 miles 12 F-Offsite 3.5

+/-

0.2 4.5

+

0.2 4.5

+

0.2 4.6

+/-

0.2 1900 at 7.7 miles 13 G Offsite 3.8

+/-

0.2 4.9

+/-

0.2 4.6

+/-

0.3 4.7

+/-

0.2 2250 at 5.3 miles 14*

DeMass Rd., SW Oswego - Control 3.8

+/-

0.2 5.3

+/-

0.4 5.0

+/-

0.2 4.8

+/-

0.2 2270 at 12.5 miles 15*

Pole 66, W. Boundary - Bible Camp 3.3

+

0.2 4.4

+/-

0.2 4.1

+/-

0.2 4.1

+/-

0.3 2390 at 0.9 miles 18*

Energy Info. Center - Lamp Post, SW 3.9

+/-

0.2 5.4

+/-

0.3 4.9

+

0.3 4.9

+/-

0.2 2660 at 0.5 miles 19 East Boundary - JAF, Pole 9 4.0

+/-

0.3 5.0

+/-

0.3 4.8

+/-

0.3 5.0

+/-

0.4 810 at 1.3 miles 23*

H Onsite 4.6

+/-

0.2 6.0

+/-

0.2 5.7

+

0.3 5.7

+/-

0.3 740 at 0.8 miles 24 1 Onsite 4.0

+/-

0.2 5.4

+/-

0.2 5.0

+/-

0.3 4.8

+/-

0.3 980 at 0.8 miles 25 J Onsite 3.6

+

0.2 5.0

+

0.2 4.7

+

0.2 4.6

+/-

0.2 1100 at 0.9 miles 26 K Onsite 3.7

+/-

0.2 5.0

+/-

0.2 4.7

+

0.3 4.5

+/-

0.3 1320 at 0.5 miles 27 N. Fence, N. of Switchyard, JAF 20.5

+/-

0.8 21.8

+/-

1.5 20.2

+

1.0 19.8

+/-

1.3 600 at 0.4 miles 28 N. Light Pole, N. ofScreenhouse, JAF 26.8

+

1.6 30.6

+/-

2.1 26.6

+/-

1.0 28.8

+/-

1.2 680 at 0.5 miles 29 N. Fence, N. of W. Side 26.5

+

1.4 24.8

+/-

1.5 24.6

+/-

1.5 21.5

+/-

1.7 650 at 0.5 miles 30 N. Fence, (NW) JAF 12.9

+/-

0.9 12.0

+/-

0.9 12.2

+/-

0.8 11.5

+/-

0.8 570 at 0.4 miles 31 N. Fence, (NW) NMP-I 6.3

+/-

0.3 8.0

+/-

0.3 7.5

+/-

0.3 7.9

+/-

0.3 2760 at 0.2 miles 6-25 m

m m

m

~

m

m-----mm m---mm

--nn m

m -

m m

TABLE 6-12 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2007 Results in Units of mrem/std. Month +/- 1 Sigma Locati1n First Second Third

[

Fourth I Degrees & Distance.

ri Location j

Quarter

Quarter, Quarter Quarter (i) 39 N. Fence, Rad. Waste-NMP-1 8.6

+

0.6 9.1 0.4 10.2

= 0.4 9.6 0.6 2920 at 0.2 miles 47 N. Fence, (NE) JAF 7.7

+

0.4 7.0

+

0.4 7.2

+/-

0.8 7.4

+

0.4 69' at 0.6 miles 49*

Phoenix, NY-Control 3.2

+

0.1 4.1

+/-

0.2 4.2

+/-

0.3 4.0

+/-

0.2 1680 at miles 51 Liberty & Bronson Sts., E of OswegoSteam Station 3.7

+/-

0.2 4.8

+

0.2 4.5

+/-

0.3 4.6

+/-

0.2 2330 at 7.4 miles 52 E. 12th & Cayuga Sts., Oswego School 3.5

+/-

0.2 4.5

+/-

0.3 4.1

+

0.2 4.4

+/-

0.2 2270 at 5.8 miles 53 Broadwell & Chestnut Sts. Fulton H.S.

3.7

+

0.2 5.1

+/-

0.2 4.9

+/-

0.3 4.8

+/-

0.3 183' at miles 54 Liberty St. & Co. Rt. 16 Mexico H.S.

3.4

+

0.2 4.4

+/-

0.2 4.4

+

0.2 4.2

+/-

0.2 1150 at 9.3 miles 55 Gas Substation Co. Rt. 5-Pulaski 3.5 0.2 4.7

+/-

0.2 4.4

+

0.2 4.4

+

0.3 750 at miles 56*

Rt. 104-New Haven Sch. (SE Comer) 3.0

+

0.2 4.3

+/-

0.2 4.1

+/-

0.2 4.0

+/-

0.3 1240 at 5.2 miles 58*

Co Rt. IA-Alcan (E. of E. Entrance Rd.)

3.6

+

0.2 5.1

+

0.2 4.9

+/-

0.2 4.9

+/-

0.3 2220 at 3.0 miles 75*

Unit 2, N. Fence, N. of Reactor Bldg.

7.8

+/-

0.3 8.8

+

0.5 8.5

+/-

0.3 8.8

+/-

0.5 3540 at 0.1 miles 76*

Unit 2, N. Fence, N. of Change House 5.2

+/-

0.2 6.3

+/-

0.3 5.9

+/-

0.2 6.2

+/-

0.4 27'

-at 0.1 miles 77*

Unit 2, N. Fence, N. of Pipe Bldg.

6.2

+/-

0.3 7.2

+/-

0.4 6.6 0.3 7.1

+

0.4 370 at 0.2 miles 78*

JAF. E. of E. Old Lay Down Area 3.7

+

0.2 4.9

+

0.2 4.8

+/-

0.2 4.9

+

0.3 86' at 1.0 miles 79*

Co. Rt. 29, Pole #63, 0.2 mi. S. of Lake Rd.

3.4

+/-

0.2 4.6

+

0.2 4.4

+

0.3 4.6

+

0.2 1210 at 1.2 miles 80*

Co. Rt. 29, Pole #54, 0.7 mi. S. of Lake Rd.

3.4

+

0.2 4.8

+

0.3 4.5

+/-

0.3 4.7 0.3 1360 at 1.5 miles 81*

Miner Rd., Pole #16, 0.5 mi. W. of Rt. 29 3.5

+/-

0.2 4.6

+/-

0.2 4.6

+/-

0.2 4.6 0.3 1600 at 1.7 miles 82*

Miner Rd., Pole # 1-1/2, 1.1 mi. W. of Rt. 29 3.5

+/-

0.2 4.4

+/-

0.2 4.3

+

0.2 4.6

+

0.2 1800 at 1.6 miles 83*

Lakeview Rd., Tree 0.45 mi. N. of Miner Rd.

3.4

+/-

0.3 4.1

+

0.3 4.0

+/-

0.2 4.3

+/-

0.2 2030 at 1.2 miles 84*

Lakeview Rd., N, Pole #6117, 200ft. N. of Lake Rd.

3.6

+

0.2 4.8

+

0.2 4.5

+

0.2 4.7

+

0.3 2250 at 1.1 miles 85*

Unit 1, N. Fence, N. of W. Side of Screen House 7.5

+/-

0.4 9.0

+/-

0.5 8.4

+/-

0.4 8.8

+/-

0.4 2900 at 0.2 miles 86*

Unit 2, N. Fence, N of W. Side of Screen House 7.2

+/-

0.5 7.9

+/-

0.3 7.8

+/-

0.5 8.4

+/- 0.7 3100 at 0.1 miles 87*

Unit 2, N. Fence, N. of E. Side of Screen House 7.5

+/-

0.6 9.0

+/-

0.5 7.8.

+/-

0.4 8.3

+

0.6 3320 at 0.1 miles 88*

Hickory Grove Rd., Pole #2, 0.6 mi. N. of Rt. 1 3.5

+

0.2 4.7

+

0.3 4.3

+

0.2 4.5

+/-

0.3 970 at 4.5 miles 6 - 26

m mm m

mm m

m -

m TABLE 6-12 (Continued)

DIRECT RADIATION MEASUREMENT RESULTS - 2007 Results in Units of inrem/std. Month

- 1 Sigma Location QFirst T

Second Third Fourth Number Location Quarter Quarter Quarter Quarter De2rees & Distance (1) 89*

Leavitt Rd., Pole #16, 0.4 Wi. S. of Rt.1 3.6

+

0.2 4.8

+

0.2 4.9

+/-

0.2 5.1 0.3 1110 at 4.3 miles 90*

Rt. 104, Pole #300, 150 ft. E. ofKeefe Rd.

3.4 7

0.2 4.3 -

0.2 4.1 0.2 4.4

+/-

0.3 135' at 4.2 miles 9l*

Rt 5 IA, Pole #59, 0.8 mi. W. ofRt. 51 3.1 4

0.1 4.4

+

0.3 4.1

+

0.2 4.2 4

0.2 1560 at 4.9 nilles 92*

Maiden Lane Rd., Power Pole, 0.6 mi. S. of Rt. 104 3.5

+

0.2 5.0

+

0.2 4.8 0.2 4.9 0.3 1830 at 4.5 miles 93*

Rt. 53 Pole 1-1, 120 ft. S. of Rt. 104 3.5

+

0.2 4.5 0.2 4.3 0.2 4.5

+

0.3 2060 at 4.4 miles 94*

Rt. 1, Pole #82, 250 ft. E. ofKocher Rd. (Co. Rt. 63) 3.3

+

0.2 4.4

+

0.2 4.1

+

0.2 4.4 0.2 2240 at 4.4 miles 95*

Alcan W access Rd., Joe Fultz Blvd, Pole #21 3.3 0.3 4.2 0.2 3.8

+

0.2 3.8

+

0.2 239' at 3.7 miles 96*

Creamery Rd., 0.3 mi.

S. of Middle Rd., Pole 1-1/2 3.4

+

0.1 4.4

+/-

0.2 4.1

+/-

0.2 4.3 0.2 199' at 3.7 miles 97*

Rt. 29, Pole #50, 200ft. N. of Miner Rd.

3.5 0.2 4.5

+/-

0.2 4.3

+/-

0.2 4.4 0.2 145' at 1.8 miles 98*

Lake Rd., Pole #145, 0.15 mi. E. ofRt 29 3.6 0.2 4.6

+

0.2 4.6

+

0.3 4.6

+

0.3 1030 at 1.2 miles 99 NWP Rd., 0.4 min. N. of Lake Rd., Env. Station RI 3.7 0.2 4.9 0.2 4.7

+

0.2 4.8 0.3 880 at 1.8 miles 100 Rt. 29 & Lake Rd., Env. Station R2 3.7 0.3 4.8

+/-

0.2 4.7

+/-

0.3 4.8

+/-

0.2 1040 at 1.1 miles 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 3.3 0.2 4.3

+/-

0.2 4.2

+/-

0.2 4.4 0.3 1320 at 1.5 miles 102 EOF/Env. Lab, Rt 176, E. Driveway, Lamp Post 3.6

+/-

0.2 4.2

+/-

0.2 4.1

+

0.2 4.3

+/-

0.2 175' at 11.9 miles 103 EIC, East Garage Rd., Lamp Post 4.0 4

0.2 4.9

+

0.2 4.7 0.3 4.8 0.3 2670 at 0.4 miles 104 Parkhurst Rd., Pole #23, 0.1 ml. S. of Lake rd.

3.5

+

0.2 4.6

+/-

0.2 4.5 0.2 4.7 0.4 1020 at 1.4 miles 105 Lake view Rd. Pole #36, 0.5 ml. S. of Lake Rd.

3.7

+/-

0.3 4.5 0.2 4.3

+

0.3 4.5

+/-

0.2 1980.

at 1.4 miles 106 Shoreline Cove, W. of NMP-l, Tree on W. Edge 4.5

+/-

0.2 5.7 0.2 5.8

+/-

0.3 5.5 0.3 2740 at 0.3 miles 107 Shoreline Cove, W. of NMIP-1, 30 ft SSW.of#106 4.2 0.3 5.4

+/-

0.2 5.5

+/-

0.2 5.8 0.2 2720 at 0.3 miles 108 Lake Rd., Pole #142, 300 ftE. ofRt. 29 S.

3.7 0.2 4.7 0.3 4.5

+

0.2 4.7 0.2 1040 at 1.1 miles 109 Tree North of Lake Rd., 300 ft E. of Rt. 29 N 4.2 0.5 4.7

+/-

0.2 4.6

+

0.2 4.8 0.3 1030 at 1.1 miles 11I State Route 38, Sterling NY. - Control 3.5 0.2 4.4 0.3 4.0

+/-

0.3 4.3 0.3 166' at 26.4 miles 112 EOF/Env. Lab, Oswego County Airport 4.0

+/-

0.3 4.6 0.2 4.3 0.3 4.5 0.3 1750 at' 11.9 miles 113 Baldwinsville, NY - Control 3.5

+/-

0.2 4.2

+/-

0.2 4.0

+/-

0.2 4.1 0.2 214' at 21.8 miles (1)

Direction and distance based on NMP-2 reactor centerline and sixteen 22.5o sector grid TLD required by ODCM 6 - 27

TABLE 6-13 CONCENTRATIONS OF IODINE-131 AND GAMMIA EMITTERS IN MILK - 2007 Results in Units of pCi/liter +/- 1 Sigma Sam nle Location ** No.55 ***

Date I-1-131 Cs-134 Cs-137 K-40 Ba/La-140 Others t 04/09/07

< 0.704

< 8.51

< 8.26 1647 +/-

97.0

< 7.19

<LLD 04/23/07

< 0.644

< 8.42

< 7.16 1792 +1-91.7

< 6.24

<LLD 05/07/07

< 0.618

< 12.37

< 9.73 1754 +1-126.5

< 11.17

<LLD 05/21/07

< 0.595

< 11.93

< 6.92 1500 +/-

113.6

< 13.07

<LLD 06/04/07

< 0.569

< 9.21

< 6.62 1642 +/-

100.3

< 9.54

<LLD 06/18/07

< 0.583

< 8.05

< 7.16 1711 +/-

87.9

< 7.37

<LLD 07/09/07

< 0.598

< 9.21

< 7.57 1612 +/-

97.0

< 11.81

<LLD 07/23/07

< 0.502

< 8.67

< 11.17 1554 +/-

106.8

< 11.09

<LLD 08/06/07

< 0.598

< 7.95

< 8.03 1580 +/-

96.1

< 6.21

<LLD 08/20/07

< 0.487

< 8.68

< 7.99 1580 +1-96.8

< 10.71

<LLD 09/10/07

< 0.525

< 4.60

< 7.01 1430 +/-

94.6

<.11.10

<LLD 09/24/07

< 0.499

< 7.40

< 7.31 1788 +/-

91.3

< 7.81

<LLD 10/09/07

< 0.521

< 8.30

< 7.78 1577 +/-

96.4

< 6.26

<LLD 10/22/07

< 0.611

< 7.36

< 7.37 1610 +/-

102.8

< 9.46

<LLD 11/05/07

< 0.668

< 8.09

,< 7.25 1530 +/-

96.8

< 11.69

<LLD 11/19/07

< 0.593

< 9.38

< 9.28 1606 +/-

98.9

< 9.17

<LLD 12/03/07

< 0.494

< 7.17

< 6.43 1735 +/-

74.7

< 6.21

<LLD 12/17/07 1

. 0.475

< 8.43

< 8.22 1718 +/-

88.2

< 7.28

<LLD t

Sample location is Optional Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclides 6 - 28 M

M M

m M M

M M M

M u

m-m mn m

m m

m mm TABLE 6-13 (Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2007 Results ill Units of pCi/liter + 1 Sigma Sample Location ** No.04 ***

Date 1-131 Cs-134 Cs-137 K-40 Ba/La-140 Others t 04/09/07

< 0.646

< 8.68

< 6.36 1513 +/-

93.7

< 9.55

<LLD 04/23/07

< 0.577

< 8.68

< 7.99 1432 +/-

93.4

< 11.81

<LLD 05/07/07

< 0.569

< 11.81

< 14.02 1312 +/-

126.4

< 9.79

<LLD 05/21/07

< 0.669

< 7.01

< 12.57 1604 +1-126.2

< 11.87

<LLD Sample location is Optional

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

Plant related radionuclides Note: Milk production ceased from this sample location at the end of May 2007 6-29

TABLE 6-13 (Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2007 Results ini Units of pCi/liter + I Sigma Sample Location ** No.76 *'-*

Date 1-_131_Cs-__

3__

Cs-137 K-40 Ba/La-140 Others t 04/09/07

< 0.675

< 10.57

< 9.34 1627 +/-

100.0

< 12.34

<LLD 04/23/07

< 0.620

< 7.26

< 8.36 1640 +/-

86.1

< 7.36

<LLD 05/07/07

< 0.651

< 10.84

< 11.58 1538 +/-

133.8

< 3.66

<LLD 05/21/07

< 0.842

< 5.27

< 10.59 1637 +/-

120.4

< 13.64

<LLD 06/04/07

< 0.588

< 7T93

< 6.71 1484 +/-

84.1

< 9.09

<LLD 06/18/07

< 0.503

< 7.12

< 8.18 1730 +1-104.5

< 9.35

<LLD 07/09/07

< 0.673

< 7.53

< 7.16 1595 +/-

85.8

< 4.85

<LLD 07/23/07

< 0.563

< 9.68

< 9.52 1586 +/-

95.3

< 6.22

<LLD 08/06/07

< 0.539

< 9.81

< 10.04 1578 +/-

101.8

< 12.39

<LLD 08/20/07

< 0.548

< 7.80

< 7.72 1550 +/-

84.3

< 9.06

<LLD 09/10/07

< 0.609

< 6.33

< 8.20 1608 +/-

107.4

< 10.43

<LLD 09/24/07

< 0.557

< 9.18

< 7.74 1789 +/-

104.6

< 12.34

<LLD 10/09/07

< 0.586

< 6.67

< 7.58 1672 +/-

86.1

< 6.80

<LLD 10/22/07

< 0.548

< 6.91

< 6.96 1741 +/-

90.9

< 8.56

<LLD 11/05/07

< 0.649

< 12.26

< 8.33 1813 +/-

129.0

< 14.16

<LLD 11/19/07

< 0.634

< 6.78

< 8.98 1368 +1-91.1

< 8.46

<LLD 12/03/07 K 0.525

< 4.87

< 5.75 1478 +/-/-

59.8

< 5.47"

<LLD 12/17/07

< 0.451

< 5.49

< 7.51 1617 +/-

97.5

< 5.05

<LLD Sample location is Optional Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclides 6 - 30 m-m m

m m

m

-m-

_m m

m-

m mnm m

m m

m m-m mm m

m TABLE 6-13(Continued)

CONCENTRATIONS OF IODINE-131 AND GAMMA EMITTERS IN MILK - 2007 Results in Units of pCi/liter +/- 1 Sigma Sample Location

No.77,(Control)

Date 1-131 Cs-134 Cs-137

. K-40 Ba/La-140 J

Others t 04/09/07

< 0.568

< 11.40

< 10.13 1393 +/-

115.6

< 10.12

<LLD.

04/23/07

< 0.577

< 9.21

< 7.57 1383 +1-92.4

< 9.56

<LLD 05/07/07

< 0.813

< 10.20

< 8.01 1608 +/-

101.2

< 8.22

<LLD 05/21/07

< 0.577

< 14.07

< 10.96 1402 +/-

129.4

< 14.57

<LLD 06/04/07

< 0.589

< 9.40

< 8.59 1779 +/-

109.8

< 10.46

<LLD 06/18/07

< 0.710

< 8.68

< 7.99 1655 +/-

99.1

< 11.86

<LLD 07/09/07

< 0.638

< 8.14

< 8.26 1554 +/-

94.6

< 8.05

<LLD 07/23/07

< 0.565

< 10.57

< 10.99 1499 +/-

96.3

< 10.47

<LLD 08/06/07

< 0.480

< 9.58

< 9.73 1661 +/-

125.6

< 11.79

<LLD 08/20/07

< 0.561

< 8.33

< 8.26 1303 +/-

88.7

< 11.11

<LLD 09/10/07

< 0.718

< 9.04

< 8.77 1674 +/-

99.9

< 8.89

<LLD 09/24/07

< 0.573

< 8.68

< 6.87 1489 +/-

94.6

< 8.14

<LLD 10/09/07

< 0.607

< 8.69

< 8.70 1567 +/-

96.6

< 10.02

<LLD 10/22/07

< 0.495

< 6.65

< 8.18 1629 +/-

85.1

< 6.95

<LLD 11/05/07

< 0.629

< 11.97

< 9.51 1685 +/-

125.3

< 10.04

<LLD 11/19/07

< 0.660

< 10.65

< 10.07 1559 +/-

121.4

< 14.27

<LLD 12/03/07

< 0.659

< 8.63

< 7.76 1560 -I-81.1

<K 7.58

<LLD 12/17/07

< 0.476

< 9.19

< 8.50 1413 +/-

89.2

< 10.50

<LLD Sample location is Optional Corresponds to sample location noted on Figure 3.3-4 Plant related radionuclides 6-31

TABLE 6-14 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2007 Results in Units of pCi/kg (wet) +/- 1 sigma Location

Date Discription I

Be-7 K-40 1-131 Cs-134 I Cs-137,1 Zn-65 Others 132**

09/12/07 SQUASH LEAVES 561 +/- 122 1549 +/-/-253

< 23.6

< 39.8

< 26.4

< 58.1

<LLD 09/12/07 ZUCCHINI LEAVES 411 +-65 1844 +/-174

< 17.8

< 21.0

< 18.2

< 53.7

<LLD 09/12/07 TOMATOES 178 2685 +/-261

< 22.1

< 28.7

< 27.5

< 72.9

<LLD 09/12/07 PEPPER LEAVES 297 +/- 65 4419 +/-250

< 15.5

< 16.8

< 17.1

< 54.2

<LLD Location ***

Date

[

Discription

.Be-7 K-40 1-131 Cs-134 Cs-137 I Zn-65 1Others tj 133

09/13/07 TOMATOES 108 3060 +/-223

< 12.2

< 17.8

< 17.4

< 49.0

<LLD 09/13/07 RHUBARB LEAVES 287 +/-54 3309 +/-236

< 14.4

< 23.6

< 18.3

< 68.5

<LLD 09/13/07 GREEN BEAN LEAVES 644 +/- 117 2780

/-293

< 24.1

< 25.5

< 23.7

< 72.1

< LLD 09/13/07 COLLARD GREENS 153 3285 +/-297

< 20.3

< 25.5

< 20.8

< 70.6

<LLD Location.***

Date I

Discription T

Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 Others t]

i134"*

09/13/07 GRAPE LEAVES 1148 +/- 212 1493 +/-371

< 42.6

< 38.4

< 42.6

< 223.1

< <LLD Location ***

Date Discription Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 Othert 484**

09/07/07 PUMPKIN LEAVES 288 +/- 56 3269 +/- 203

< 16.0

< 19.8

< 16.0

< 50.3

<LLD 09/07/07 SQUASH LEAVES 518 +/- 65 2221 +/- 166

< 17.4

< 12.7

< 13.5

< 50.1

<LLD 09/07/07 TOMATOES 125 2012 +1-170

< 14.3

< 15.2

< 12.9

< 41.3

<LLD Sample location required by the ODCM

- Sample location is Optional Corresponds to sample location noted on Figure 3.3-5 t

Plant related radionuclides 6 - 32

-ý M

mM m

-M-

m mm m

m m

-m m

m m

TABLE 6-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCTS - 2007 Results in Units of pCi/kg (wet) +/- 1 sigma

[ Location Date Discription Be-7

[.

.. K-40 1-131 Cs-134 Cs-137 jZri-65 Others t 142

09/12/07 SQUASH LEAVES 1331 +/- 120 1556 +/- 187

< 25.5

< 30.7

< 26.0

< 33.5

<LLD 09/12/07 TOMATOES 184 3163 +/-3.16

< 19.7

< 30.1

< 29.4

< <.61.0

<LLD 09/12/07 GRAPE LEAVES 1979 +/- 112 2130 +/- 178

< 17.6

< 23.5

< 21.1

< 58.2

<LLD Loca t ion"***

Date Discription Be-7 K-40 1-131 Cs-134 Cs-137 Zn-65 Otherstj 144' 09/07/07 SQUASH LEAVES 884 +/99 1519 +/203

< 24.3

< 2 7.6

< 20.7

< 6 7.3

< LLD 09/07/07 HORSERADISH LEAVES 62 +/- 36 3082 +/- 176

< 9.7

< 14.9

< 14.6

< 40.2

< LLD 09/07/07 TOMATOES 103 2590 +/- 164

< 13.2

< 16.9

< 13.0

< 40.1

<LLD 09/07/07 CORNLEAVES 1018 +/- 142 5329 +-450

< 34.0

< 36.3

< 30.8

< 131.2

< LLD Location

.*aescpo Be-7_

K-40 1-131 Cs-134 Cs-37 Zn-65 Others_

145 (Control)*

09/06/07 SQUASH LEAVES 626 +/- 94 2776 +/-270

< 24.3

< 22.2

< 27.4

< 75.9

<LLD 09/06/07 RHUBARB LEAVES 145 3441 +/-209

< 15.0

< 13.8

< 19.6

< 36.1

< LLD 09/06/07 ZUCCHINI LEAVES 231 3827 +/-405

< 24.6

< 44.9

< 36.7

< 106.3

<LLD 09/06/07 TOMATOES 120 2977 +/- 198

< 12.0

< 20.0

< 16.2

< 53.8

<LLD 09/06/07 HORSERADISH LEAVES 278 3250 +/- 380

< 26.1

< 38.0

< 31.8

< 120.7

<LLD

__ 09/06/07 GREEN BEAN LEAVES 298 +/- 89 2048 +/- 328

< 22.4

< 38.2

< 43.2

< 83.5

<LLD Sample location required by the ODCMI

- Sample location is Optional

- - Corresponds to sample location noted on Figure 3.3-5 t

Plant related radionuclides 6 - 33

TABLE 6-15 MILK ANIMAL CENSUS - 2007 Location

(

2

)

Distance(2)

Number of.Milk Town or Area Designation(1 )

egrees 2 (Miles)

Animals Scriba 62 1840 6.6 4G 75 145°0 7.6 2G

.4*(3) 1130 7.8 None New Haven 9(4) 970 4.8 40C 64 1070 7.9 46C 78 1280 8

20C 14 1230 9.4 55C 60 910 9.5 25C Mexico 76*

1200 6.3 35C 55*

950 9

57C 21 1120 10.3 72C 72 1000 9.6 31 C Granby 77**

1910 13.9 60C Total milk animals including control locations:

441 Cows 6 Goats Total milk animals excluding control locations:

381 Cows 6 Goats I

I I

I 1

I I

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 NMP2 reactor building centerline (3) - Sample location no longer in the dairybusiness (4) - Dairy business does not wish to participate in REMP.

6 - 34 1

I I

I

TABLE 6-16 RESIDENCE CENSUS - 2007 Meteorological(2()

Sector Location Map Location T Degrees2 )

Distance(2 )

N NNE NE ENE E

West Sunset Bay Road A

1000 1.3 ESE Lake Road B

1040 1.1 SE County Route 29 C

1250 1.4 SSE Miner Road D

1580 1.7 S

Miner Road E

171 0 1.6 SSW Lakeview Road F

2080 1.2 SW Lakeview Road G

2170 1.1 WSW Bilbie Camp Retreat H

2370 1.4 W

WNW NW NNW Notes:

- This meteorological sector is located over Lake Ontario. There are no residence five miles of the site.

(1) - Corresponds to Figure 3.3-5 (2) - Degrees and distance are~based on NMP2 reactor building centerline.

6 - 35

SECTION 7.0 HISTORICAL DATA TABLES Q

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

Cs-137 (pCi/g (dry)).

Co-60 (pCi/g (dry))

YEARýý

-F 'MIN.

ý'MAX.ENMN MAX.

MEA 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 (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.

7-1

TABLE 7-2 HISTORICAL ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT (INDICATOR) (1)

Cs-137 (pCi/ g(dry))

Co-60 (pCi/g (dr))

'YEAR "MIN.

N;X.

_MEAýN

'"M[N, MX

ýMEAN 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 (1) Location was off-site at Sunset Beach (closest location with recreational value).

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

I I

I 1

I I

?

7-2 I

TABLE 7-3 HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL) (1)

Cs-137 (pCi/g (wet))

YEARý,

MIN.-

MAX.

MEffiA'N 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 (1) Control location was at an area beyond the influence of the site (westerly direction).

7-3

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

Cs-137 (pCi/g (wet))

YERMIN.

NIMAX I

'II EAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.5 0.13 0.03 0.02 0.03 0.03 0.034 0.033 0.033 0.018 0.009 0.024 0.020 0.020 0.024 0.021 0.013 0.021 0.011 0.016 0.014 0.015 0.021 0.016 LLD LLD 0.016 LLD LLD LLD LLD LLD 3.9 0.79 0.10 0.55 0.10 0.10 0.064 0.056 0.061 0.044 0.051 0.063 0.074 0.043 0.115 0.035 0.034 0.038 0.028 0.019 0.016 0.017 0.021 0.018 LLD LLD 0.016 LLD LLD LLD LLD LLD 1.4 0.29 0.08 0.10 0.06 0.06 0.048 0.045 0.043 0.030 0.028 0.033 0.034 0.035 0.044 0.027 0.026 0.030 0.020 0.018 0.015 0.016 0.021 0.017 LLD LLD 0.016 LLD LLD LLD LLD LLD I

I I

i I

I I

I (1) Indicator locations are in the general area of the NMNPI and J. A. FitzPatrick cooling water discharge structures.

I I

I 7-4

TABLE 7-5 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CONTROL) (3)

Cs-137 (pCi/liter)

Co-60 (pCi/liter)

LYEAR MIN.

MAX.

!MEAN MIN.

'MAX.

['MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 (1)

(2)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(2)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(2)

LLD 2.5 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

.LLD LLD LLD LLD LLD LLD LLD

LLD, LLD LLD LLD LLD (1)

(2)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

LLD LLD (1)

(2)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD

.LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(2)

LLD LLD 1.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(2)

No gamma analyses performed (not required).

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.

7-5

TABLE 7-6 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (INDICATOR) (3)

Cs-137 (pCi/liter)

Co-60 (pCi/liter)

YEAXM.N.

.MEAN M.

MAX.

"MEAN 1976

)(1()

()()()

1977 (2)

(2)

(2) 1978 LLD LLD LLD (2)

(2)

(2) 1979 LLD LLD LLD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD 1981 LLD LLD LLD LLD LLD LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 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 LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD LLD LLD LLD 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD 2005 LLD LLD LLD LLD LLD LLD 2006 LLD LLD LLD LLD LLD LLD 2007 LLD LLD LLD LLD LLD LLD (1)

No gamma analyses performed (not required).

(2)

Data showed instrument background results.

(3)

Location was the J. A. FitzPatrick inlet canal.

I I

I 7-6

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

TRITIUM (pCi/liter)

YER' MIN.

MAX.

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 180 200 190 1992 190 310 242 1993 160 230 188 1994 250 250 250 1995 230 230 230 1996 LLD LLD LLD 1997 LLD LLD LLD 1998 190 190 190 1999 220 510 337 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.

(1)

Control location is the City of Oswego drinking water for 1976 - 1984 and the Oswego Steam Station inlet canal for 1985 - 2007.

7-7

I I

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

TRITIUM (pCi/liter)

'YEAR

MIN. "

MAX.

I MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 365 380 377 176 150 212 194 249 110 250 260 160 430 210 220 250 240 200 180 320 LLD 160 190 180 161 LLD 297 LLD LLD LLD LLD LLD 889 530 560 276 306 388 311 560 370 1200 (2) 500 410 480 350 290 390 300 280 260 320 LLD 160 190 270 198 LLD 297 LLD LLD LLD LLD LLD 627 455 476 228 227 285 266 347 280 530 380 322 460 280 250 310 273 242 220 320 LLD 160 190 233 185 LLD 297 LLD LLD LLD LLD LLD I

I I

I (1) Indicator location is the FitzPatrick inlet canal.

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

7-8 I

TABLE 7-9 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (CONTROL) (1)

TRITIUM (pCi/liter)

YEAR M.N MAX.

MEAN 2005

<854

<854 200612)

<447

<825

<636 2007

<442

<445

<444 (1)

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

(2)

Required LLD changed to 500 pCi/l from 1000 pCi/l 7-9

TABLE 7-10 HISTORICAL ENVIRONMENTAL SAMPLE DATA GROUNDWATER TRITIUM (INDICATOR) (1)

TRITIUM (pCi/liter)

YEAR

MIN.

MAX MEAN 2005

<854

<871

<863 2006(2)

<462

<933

<823 2007

<440

<461

<445 (1) Indicator locations are down gradient wells located in the north-east corner of the protected areaand samples collected from the NMP2 depression cone system.

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

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I 7-10 I

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

GROSS BETA (pCi/m3 )

YEAR

'MIN.

MAX.

MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.001 0.01 0.010 0.009 0.016 0.011 0.007 0.013 0.013 0.008 0.009 0.008 0.007 0.003 0.006 0.006 0.007 0.008 0.006 0.008 0.006 0.004 0.010 0.006 0.006 0.008 0.004 0.008 0.008 0.007 0.008 0.484 0.66 0.703 0.291 0.549 0.078 0.085 0.051 0.043 0.272 0.037 0.039 0.039 0.027 0.028 0.020 0.022 0.025 0.023 0.023 0.025 0.034 0.032 0.027 0.034 0.027 0.032 0.032 0.034 0.033 0.028 0.125 0.16 0.077 0.056 0.165 0.033 0.024 0.026 0.024 0.039 0.021 0.018 0.017 0.013 0.014 0.012 0.013 0.015 0.014 0.014 0.013 0.014 0.017 0.015 0.016 0.016 0.015 0.016 0.019 0.016 0.016 (1) Locations used for 1977 - 1984 were C offsite, D1 offsite, D2 offsite, E offsite, F offsite, and G offsite. Control location R-5 offsite was used for 1985 - 2007 (formerly C offsite location).

7-11

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

GROSS BETA (pCi/m 3)

YEAR MIN.

MAX.

'MEAN 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.002 0.01 0.001 0.002 0.004 0.001 0.002 0.002 0.010 0.007 0.009 0.007 0.007 0.005 0.007 0.005 0.005, 0.006 0.004 0.006 0.001 0.002 0.009 0.005 0.004 0.006 0.005 0.003 0.007 0.005 0.007 0.326 0.34 0.271 0.207 0.528 0.113 0.062 0.058 0.044 0.289 0.040 0.040 0.041 0.023 0.033 0.024 0.025 0.025 0.031 0.025 0.018 0.040 0.039 0.033 0.037 0.026 0.035 0.037 0.040 0.035 0.028 0.106 0.11 0.058 0.044 0.151 0.031 0.023 0.025 0.023 0.039 0.021 0.018 0.017 0.014 0.015 0.013 0.014 0.015 0.014 0.013 0.010 0.015 0.017 0.015 0.016 0.016 0.015 0.016 0.018 0.015 0.016 I

I I

(1)

Locations used for 1977 - 1984 were D1 onsite, D2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, J onsite, and K onsite as applicable. 1985 - 2007 locations were R-I offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-12

TABLE 7-13 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (CONTROL) (1)

Cs-137 (pCi/m 3)

Co-60 (pCi/m3)

!YEAR:

MN MAX.

MEAN, M.

M.E 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 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009

.1980 0.0015 0.0018 0.0016 LLD LLD LLD 1981 0.0003 0.0042

.0.0017 0.0003 0.0012 0.0008 1982 0.0002.

0.0009 0.0004 0.0004 0.0007 0.0006 1983 0.0002 0.0002 0.0002 0.0007 0.0007 0.0007 1984 LLD LLD LLD 0.0004 0.0012 0.0008 1985 LLD LLD LLD LLD LLD LLD 1986 0.0075 0.0311 0.0193 LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD LLD 1997 LLD LLD LLD LLD LLD LLD 1998 LLD LLD LLD LLD LLD LLD 1999 LLD LLD LLD LLD LLD LLD 2000 LLD LLD LLD LLD LLD LLD 2001 LLD LLD LLD LLD LLD LLD 2002 LLD LLD LLD LLD LLD LLD 2003 LLD LLD LLD LLD LLD LLD 2004 LLD LLD LLD LLD LLD LLD 2005 LLD LLD LLD LLD LLD LLD 2006 LLD LLD LLD LLD LLD LLD 2007 LLD LLD LLD LLD LLD LLD (1) Locations included composites of C, DI, E, F, and G offsite air monitoring locations for 1977 - 1984. Sample location included only R-5 air monitoring location for 1985 - 2007.

7-13

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

Cs-137 (pCi/m3),

Co-60 (pCi/m 3)

YAR f MW. [

A.j EN MfN ]MAMA 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.0001 0.0003 0.0003-0.0005 0.0002 0.0001 0.0002 LLD LLD 0.0069 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0105 0.0026 0.0020 0.0019 0.0045 0.0006 0.0003 LLD LLD 0.0364 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0043 0.0016 0.0010 0.0011 0.0014 0.0004 0.0002 LLD LLD 0.0183 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD.

LLD LLD 0.0003

.0.0003 0.0003 0.0016 0.0002 0.0003 0.0003 0.0007 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD 0.0711 0.0153 0.0007 0.0016 0.0017 0.0010 0.0017 0.0017 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD 0.0179 0.0023 0.0005 0.0016 0.0006 0.0005 0.0007 0.0012 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.0048 LLD LLD LLD LLD LLD LLD LLD I

I I

(1)

Locations included composites oflD1, D2, E, F, G,' H, 1, J, and K onsite air monitoring locations for 1977 -

1984. Locations included R-1 through R-4 air monitoring locations for 1985 - 2007.

7 - 14

TABLE 7-15 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (CONTROL) (1 IODINE-131 (pCi/m3)

YEAR MIN.

J MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0.01 0.02 0.03 LLD LLD LLD 0.039 LLD LLD LLD 0.041 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 5.88 0.82 0.04 LLD LLD LLD 0.039 LLD LLD LLD 0.332 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.60 0.32 0.03 LLD LLD LLD 0.039 LLD LLD LLD 0.151 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

Locations Dl offsite, D2 offsite, E offsite, F offsite, and G offsite used for 1976 - 1984. Location R-5 offsite used for 1985 - 2007.

7-15

I TABLE 7-16 I

HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (INDICATOR) ( )

IODINE-131 (pCi/M3)

____MIN.

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 (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 - 2007 were RI offsite, R-2 offsite, R-3 offsite, and R-4 offsite.

7-16 I

I I

I

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

DOSE (mrem per standard month)

YEAR MIN.

MAX.

'MEAN Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 (1) 6.0 2.0 2.2 2.2 2.7 4.8 3.2 4.0 3.3 3.3 3.8 3.5 3.8 4.9 4.7 4.5 (4.4)*

5.3 (5.5)*

4.6 (4.6)*

4.4 (4.8)*

2.9 (2.9)*

3.7 (3.7)*

3.8 (3.8)*

2.6 (2.6)*

3.4 (3.4)*

3.1 (3.1)*

3.4 (3.4)*

3.7 (3.9)*

3.7 (3.7)*

3.6 (3.7)*

3.7 (3.7)*

3.6 (3.9)*

3.4 (3.4)*

3.3 (3.3)*

3.3 (3.4)*

3.3 (3.3)*

3.2 (3.2)*

(1) 7.3 6.7 6.2 6.9 8.9 6.0 7.2 8.0 4.7 5.7 5.8 5.9 6.1 7.2 8.2 7.6 (6.8)*

7.5 (7.2)*

6.6 (5.8)*

6.8 (6.8)*

6.4 (5.6)*

6.0 (5.9)*

5.4 (5.3)*

5.0 (4.7)*

5.6 (5.2)*

5.0 (4.6)*

5.7 (4.9)*

5.6 (5.6)*

6.2 (5.2)*

5.6 (4.8)*

7.1 (4.7)*

7.3 (5.5)*

5.4 (5.0)*

5.5 (5.2)*

5.5 (4.8)*

5.9 (5.9)*

5.1 (4.5)*

5.3 (4.4)*

5.8 (5.3)*

(1) 6.7 4.3 4.4 4.7 5.6 5.5 5.4 5.3 4.3 4.7 4.9 4.8 5.1 5.8 6.2 5.6 (5.4)*

6.3 (6.3)*

5.4 (5.2)*

5.6 (5.4)*

4.7 (4.6)*

4.8 (4.6)*

4.5 (4.3)*

4.1 (3.9)*

4.4 (4.3)*

4.1 (3.9)*

4.4 (4.2)*

4.3 (4.2)*

4.7 (4.6)*

4.4 (4.2)*

4.6 (4.4)*

4.7 (4.3)*

4.4 (4.4)*

4.3 (4.1)*

4.2 (4.2)*

4.3 (4.5)*

4.1 (4.0)*

4.4 (4.3)*

(1) Data not available.

(2)

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

()*

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

7-17

I I

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

DOSE (mrem ner ~tRndnrd mnntW~

YEAR MrN.

'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 (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.

I I

I 7-18

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

DOSE (mrem per standard month)

YEAR MINI.

MAX.MEAN 1985 (1) 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 1988 3.8 7.0 5.3 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 1991 3.6 5.6 4.5 1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 1994 3.0 5.1 4.0 1995 3.2 5.2 4.2 1996 3.2 5.3 4.2 1997 3.5 5.8 4.5 1998 3.5 5.0 4.2 1999 3.6 5.6 4.4 2000 3.4 6.6 4.5 2001 3.6 5.4 4.4 2002 3.1 5.3 4.2 2003 3.4 4.8 4.1 2004 3.2 6.7 4.4 2005 3.2 4.7 4.0 2006 3.3 4.4 4.0 2007 3.1 5.1 4.2 (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.

7-19

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

DOSE (mrem per standard month)

-EAR, 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 (1)

Not required prior to 1985.

(2)

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

(3)

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

I I

I 7-20 I

I

TABLE 7-21 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (ONSITE INDICATOR) (2)

DOSE (mrem per standard month)

'YEAR:

"MIN.

MEAN Preop (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 (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.

7-21

I I

TABLE 7-22 HISTORICAL ENVIRONMENTAL SAMPLE DATA.

ENVIRONMENTAL TLD (OFFSITE INDICATOR) (2)

DOSE (mrem per standard month)

YEAR

'MIN.

' MAX.

,MEAN Preop 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 (1) 5.0 1.1 1.8 2.2 2:4 4.5 3.4 3.7 2.7 3.0 3.1 3.6 4.0 4.6 4.6 4.6 5.0 4.4 4.2 2.8 3.8 3.4 3.1 3.2 3.0 3.9 3.3 3.7 3.9 3.8 3.8 3.7 3.6 3.1 3.2 3.6 3.9 3.4 (1) 8.0 7.7 6.6 6.9 8.9 7.1 7.2 8.0 4.7 5.7 5.8 5.9 6.2 7.2 8.2 7.7 7.6 6.6 6.6 6.4 6.0 5.4 5.2 5.6 5.0 5.7 5.5 6.2 5.6 7.1 7.3 5.9 5.5 5.5 6.5 5.1 5.3 5.8 (1) 6.7 4.5 4.4 4.1 5.3 5.5 5.2 5.3 3.7 4.0 4.6 4.7 5.2 5.6 6.1 5.5 6.1 5.2 5.4 4.6 4.8 4.3 4.1 4.3 4.1 4.4 4.1 4.7 4.4 4.6 4.6 4.5 4.4 4.4 4.5 4.2 4.2 4.5 I

I I

I (1)

No data available.

(2)

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

7 - 22 I

TABLE 7-23 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (CONTROL) (2)

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

'YEAR MIN. JMAX.

-,MEAN

MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 (1)

(1) 2.4 LLD 3.6 3.9 LLD LLD LLD LLD 5.3 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(1) 7.8 LLD 5.6 3.9 LLD LLD LLD LLD 12.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD

(1)

(1) 5.8 LLD 4.5 3.9 LLD LLD LLD LLD 8.4 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(1)

LLD LLD 1.4 LLD LLD LLD LLD LLD 0.8 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(1)

LLD LLD 1.4 LLD LLD LLD LLD LLD 29.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

(1)

LLD LLD 1.4 LLD LLD LLD LLD LLD 13.6 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD (1)

No data available (samples not required).

(2)

Location used was an available milk sample location in a least prevalent wind direction greater than ten miles from the site.

7 - 23

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

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

YEAR MIN.

'MAX. I MEAN MIN.

MAX.

MEAN 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 4.0 11.0 3.4 3.2 3.2 3.5 3.5 3.3 LLD LLD 6.1 5.5 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 15.0 22.0 33.0 53.0 21.0 29.0 14.0 10.9 LLD LLD 11.1 8.1 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 9.3 17.1 9.9 9.4 8.1 8.6 5.7 7.2 LLD LLD 8.6 6.8 10.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.02 0.01 0.19 LLD 0.3 LLD LLD LLD LLD LLD 0.3 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 45.00 49.00 0.19 LLD 8.8 LLD LLD LLD LLD LLD 30.0 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.20 6.88 0.19 LLD 3.8 LLD LLD LLD LLD LLD 5.2.

LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 0.50 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I

I I

I (1)

Locations sampled were available downwind locations within ten miles with high radionuclide deposition potential.

7 - 24 I

TABLE 7-25 HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (CONTROL) (1)

Cs-137 (pCi/g (wet))

YEAR MMN.

MX.

MEAN 1980 (2) 0.02 0.02 0.02 1981 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (3)

LLD LLD LLD 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 0.007 0.007 0.007 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 (1)

Location was an available food product sample location in a least prevalent wind direction greater than ten miles from the site.

(2)

Data comprised of broadleaf and non-broadleaf vegetation (1980 - 1984, 2007).

(3)

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

7 - 25

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

Cs-137 (pCi/g (wet))

YEAR M

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 1.998 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 (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).

(3)

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

7-26 I

I I

I 1

I I

.I I

I I

SECTION 8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM

8.0 QA/QC 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 two independent laboratories to provide quality assurance comparison samples.

The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S. Department of Commerce's National Institute of Standards and Technology (NIST) in Gaithersburg, Maryland.

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 JAF Environmental Laboratory using standard laboratory procedures.

Analytics issues a statistical summary report of the results. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

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

The program includes distribution to sponsoring utilities. The samples are prepared by NIST to present specific challenges to participating laboratories. NIST supplies sample media as blind sample spikes. These samples are prepared and analyzed by the JAFNPP Environmental Laboratory, and the results are submitted to the Entergy Nuclear Northeast representative for evaluating the laboratory's performance.

The performance results along with the NIST Report of Test (Certifies what activities are present in the sample) are forwarded to the laboratory.

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.

8-1

8.2 PROGRAM SCHEDULE Water Gross Beta I

Water Tritium 3

Water 1-131 4

Water Mixed Gamma 4

Air Gross Beta 3

Air 1-131 4

Air Mixed Gamma 2

Milk 1-131 3

Milk Mixed Gamma 3

Soil Mixed Gamma I

Vegetation Mixed Gamma 2

TOTAL SAMPLE INVENTORY 30 2

I I

I 8.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

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

8-2

An Environmental Laboratory analytical result is evaluated using the following calculation for the error resolution.

The error resolution Reference Result Reference Results Error (1 sigma).

Using the appropriate row under the Error Resolution column in Table 8.3-1 below, a corresponding Ratio of Agreement interval is given using the following calcualtion.

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

TABLE 8.3-1

<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 Analytics and NIST 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 8.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 8.4-1.

i 8.4.1 ANALYTICS QA SAMPLES RESULTS 3

Thirty QA blind spike samples were analyzed as part of Analytics 2007 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 I

Water: 1-13 1, Mixed Gamma Emitters, Tritium, Gross Beta Soil: Mixed Gamma Emitters Milk: 1-13 1, Mixed Gamma Emitters Vegetation: Mixed Gamma Emitters The JAFNPP Environmental Laboratory performed 126 individual analyses on the 30 QA I

samples. Of the 126 analyses performed, 126 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

i There were no non-conformities in the 2007 program.

8.4.2 NIST QA SAMPLES RESULTS In 2007, JAFNPP Environmental Laboratory participated in the NEI/NIST Measurement I

Assurance Program. Two QA blind spike samples were analyzed. The following sample media were evaluated as part of the comparison program.

i Air Particulate Filter: Mixed Gamma Emitters Water: Mixed Gamma Emitters 3

The JAF Environmental Laboratory performed 8 individual analyses on the two QA samples. Of the 8 analyses performed, 8 were in agreement using the NRC acceptance I

criteria for a 100% agreement ratio.

There were no non-conformities inthe 2007 program.

i 8-4

8.4.3 NUMERICAL RESULTS TABLES TABLE 8.4-1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi+/- 1 sigma pCi +/-2 sigma RATIO (1) 06/14/2007 E5352-05 Filter 78.3

+/-

2.2 GROSS BETA 79.6 2.3 72.8

+/-

2.43 1.07 A

76.6 2.2 Mean 78.2 1.3 06/14/2007 E5346-09 Filter 78.0

+

2.2 GROSS BETA 82.0 2.3 75.0

+/-

3 1.07 A

80.0 2.3 Mean 80.0 1.3 12/06/2007 E5767-05 Filter 76.6

+/-

2.2 GROSS BETA 82.2 2.3 73.8

+/-

2.46 1.06 A

76.8

+/-

2.2 Mean =

78.5 1.3 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-5

TABLE 8.4-1 (Continued)

Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/liter+l sigma pCi/liter +/-2 sigma RATIO (1) 3/22/2007 E5331-05 Water H-3 5510 177 5584 179 5010

+/-

167 1.10 A

5490 178 Mean=

5528 103 12/6/2007 E5542-09 Water H-3 9671

+/-

208 9901

+/-

210 9000

+/-

300 1.09 A

Mean=

9786

+

148 12/6/2007 E5543-09 Water H-3 9684

+/-

209 9843

+/-

210

.9000

+/-

300 1.08 A

Mean 9764

+/-

148 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable I

I I

I 8-6 I

TABLE 8.4-1 (Continued)

Gross Beta Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma RATIO (1) 11/09/2007 A21998-05 Water 9.11 E+05

+/-

1.50E+04 GROSS BETA 8.95E+05 1.49E+04 9.30E+05 +/- 5.58E+04 0.97 A

8.91 E+05

+/-

1.48E+04 Mean=

8.99E+05

+/-

8.60E+03 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-7

TABLE 8.4-1 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi +1 sigma pCi +/-2 sigma RATIO (1)

E5315-09 3/22/2007 Air 66.8

+

4.46 69.8

+

4.55 1-131 61.7

+/-

3.99 70.0

+/-

2.3 0.97 A

72.7

+/-

5.2 Mean =

67.8

+/-

2.29 E5355-05 6/14/2007 Air.

72.7

+

4.22 1-131

79.

5.09 79.0

+/-

2.63 0.99 A

83.0

+

4.16 Mean 78.5

+/-

2.60 E5466-05 9/13/2007 Air 74.4 3.46 1-131 65.7 3.92 69.6

+/-

2.32 0.98 A

64.5

+

3.13 Mean =

68.2

+

2.03 E5446-09 9/13/2007 Air 67.8

+/-

3.34 1-131 61.8 3.27 70.0

+

2 0.93 A

66.3

+/-

3.18 Mean 65.3

+/-

1.88 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable I

I I

I 8-8 I

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE I

ID NO.

MEDIUM [ ANALYSIS[

pCi/liter +1 sigma pCi/liter +/-2 sigma [RATIO (1) 4/18/2007 1 E5332-05 Water Ce-141 153 151 148 Mean 151

+-

+/--

A-7.98 2.4 3.63 3.0 140

+/-

4.65 1.08 A

115 12.1 Cr-51 139 15.4 104 3.47 1.22 A

Mean =

127

+/-

9.8 83.0

+/-

6.11 Cs-134 94.3 2.03 91.2 3.04 1.02 A

102 A-2.43 Mean =

93.1

+/-

2.3 201 7.53 Cs-137 195 2.41 196 6.53 1.01 A

197,

3.08 Mean=

198

.2.8 65.6 6.04 Co-58 67.0 1.71 63.5

+/-

2.12 1.01 A

59.8 2.27 Mean 64.1 A-2.2 168

+/-

7.48 Mn-54 146 2.36 144

+/--

4.79 1.08 A

154 A-2.89 Mean 156 2.8 63.1 6.4 Fe-59 58.1 2.26 58.0

+/-

1.93 1.03 A

58.6 A

2.5 Mean =

59.9

+/-

2.4 830

+/-

23 Zn-65 817 t

7.46 776

+/-

25.9 1.06 A

825 9.26 Mean 824

+/-

8.6 123 4.79 128

+/--

1.6 Co-60 129 1.9 126 A

4.2 1.01 A

129 A-1.95 Mean =

127 4-1.8 1-131**

100 99.4 90.9 104 Mean 98.6 A:

A:

+/-

A:

4.75 4.9 4.32 4.32 2.3 89.8

+/-

2.99 11.10 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-9

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/liter+/-l sigma pCi/liter +/-2 sigma RATIO (1) 6/14/2007 1 E5345-09 Water Ce-141 158 181 169 Mean=

169 4-4-

3.78 3.47 9.27 3.5 160

+/-

5 1.06 A

428

+/-

20.1 Cr-51 420 16.3 411

+/-

14 1.06 A

461 52.3 Mean 436

+

19.5 208

+/-

3.6 Cs-134 204

+/-

2.73 194

+/-

6 1.05 A

202 10.3 Mean 205

+/-

3.7 132 2.99 Cs-137 141 2.34 135 5

1.01 A

140

+/-

8.12 Mean=

138 3.0 164

+/-

3.3 Co-58 166 2.49 159 5

1.05 A

170 8.93 Mean=

167 3.3 147 3.32 Mn-54 154

+

2.41 133 4

1.15 A

159 8.67 Mean=

153 3.2 141 4.05 Fe-59 145 2.81 134

+/-

4 1.03 A

130 10.4 Mean 139

+/-

3.8 277

+/-

7.04 Zn-65 293 5.05 268

+/-

9 1.08 A

300

+

18.7 Mean 290 6.9 192

+/-

2.79 Co-60 195 2

191

+/-

6 1.01 A

189

+/-

7.36 Mean 192

+/-

2.7 I

I I

I 1

U I

I I

1-131**

108 102 103 Mean=

104

+/-

4-4-

8.97 2.13 2.37 3.2 102

+/-

3 1.02 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable I

I 8-10

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water

, SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUMJI ANALYSIS pCi/liter +/-1 sigma pCi/liter +2 sigma tRATIO (1) 9/13/2007 1 E5463-05 Water Ce-141 198

+

9.06 179

+/-

9:53 188

+/-

10.8 188

+/-

5.7 182

+/-

6.05 11.03 A

Mean 253

+/-

37.5 Cr-51 245

+/-

41.3 249

+/-

8.29 0.93 A

200

+/-

42.5 Mean 233

+

23.4 134

+

8.9 Cs-134 134 9.08 127

+/-

4.22 1.10 A

150

+/-

8.93 Mean=

139

+

5.2 105

+/-

6.75 Cs-137 107 7.68 112

+/-

3.74 0.96 A

109

+/-

7.87 Mean=

107

+

4.3 103

+/-

6.62 Co-58 103 7.11 98.1

+/-

3.27 0.99 A

86.5

+/-

7.35 Mean =

97.5

+/-

4.1 173

+

8.22 Mn-54 161

+

8.73 144

+

4.8 1.14 A

158

+/-

8.93 Mean=

164

+/-

5.0 105

+/-

7.93 Fe-59 106 8.51 95.1

+/-

3.17 1.15 A

117

+/-

9.07 Mean =

109

+

4.9 204

+/-

13.8 Zn-65 212

+/-

15.9 174

+

5.8 1.26 A

208

+/-

16.3 Mean =

208

+

8.9 121

+/-

5.3 Co-60 128

+/-

6.28 127

+/-

4.24 1.03 A

144

+/-

6.72 Mean=

131

+

3.5 1-131**

83.5

+/-

1.77 80.3

+/-

2.51 86.1

+/-

2.38 Mean=

83.3

+

1.3 80.1

+/-

2.67 1.04 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-11

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE ANALYSIS JAF ELAB RESULTS REFERENCE LAB*

DATE SAMPLE.

MEDIUM ANLSSpCi/liter

+/-l sigma pCi/liter++/-2 sigma RATIO (1) 12/6/2007 1 E5544-09 Water Ce-141 156 155 153 Mean 155

+/-

+

10.7 8.47 11.5 5.9 157

+/-

5 0.99 A

657

+

52 Cr-51 557

+/-

40.6 572

+

19 1.06 A

611 58.7 Mean 608

+/-

29.4 168 ME 8.91 Cs-134 155 7.61 153 5

1.05 A

161

+/-

9.97 Mean=

161 4

5.1 191 4

8.36 Cs-137 177 4

7.05 185 6

0.97 A

172

+/-

9.27 Mean 180 4.8 214 4

8.97 Co-58 223 7.81 194 6

1.10 A

202

+/-

10.1 Mean 213

+/-

5.2 240

+

9.27 Mn-54 228 7.81 212 7

1.10 A

231

+/-

10.9 Mean 233

+

5.4 177 4

9.99-Fe-59 182

+/-

8.84 166 6

1.06 A

169

+/-

11.6 Mean =

176

+/-

5.9 296 4

16.6 Zn-65 287 14.3 261 9

1.10 A

278 19.3 Mean=

287 9.7 229

+/-.

6.95 Co-60 228

+

6.05 236 8

0.98 A

237

+/-

8.36 Mean 231 4

4.1 I

I I

I 1

I I

1-131**

73.7 74.5 76.3 74.8 4-

+/--

3.53 1.97 3.37 1.8 72.0

+/-

2 1.04 A

Mean (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-12

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IID NO.

MEDIUM IANALYSIS pCi/liter~l sigma pCi/liter +/-2 simaRATIO (1) 3/22/2007 1 E5316-09 MILK Ce-141 304 304 293 Mean 300

+

4.2 5.4 5.5 2.9 297

+/-

9.9 1.01 A

227

+/-

16.6 Cr-51 204

+/-

22.1 245

+/-

8.2 0.90 A

227

+/-

22.9 Mean =

219

+/-

12.0 110

+/-

2.8 Cs-134 111

+/-

3.2 112

+

3.7 0.98 A

107

+

3.5 Mean =

109

+/-

1.8 227

+/-

3.5 Cs-137 232

+/-

4.1 234

+/-

7.8 0.98 A

232

+/-

4.7 Mean =

230

+/-

2.4 95.6

+/-

3.1 Co-58

.101

+/-

3.3 99.0

+/-

3.3 0.99 A

98.0

+/-

3.8 Mean 98.2

+/-

2.0 189

+/-

3.6 Mn-54 189 3

182

+/-

6.1 1.04 A

189

+/-

4.5 Mean 189

+/-

2.3 114

+/-

3.8 Fe-59 127 4.1 106

+/-

3.5 1.12 A

114

+/-

4.6 Mean 118

+/-

2.4 1040

+/-

11.6 Zn-65 1090 12.9 1000

+/-

33.3 1.06 A

1050

+/-

14.7 Mean 1060

+/-

7.6 144

+/-

2.4 Cor60 146 2.6 152

+/-

5.1 0.95 A

144

+/-

3.0 Mean 145

+/-

1.5 Iq131**

97 91.2 95.5 Mean =

94.6

+/-

+/-.

3.9 4.1 5.3 2.6 85.0

+/-

2.8 1.11 A

(1) Ratio = Reported/Analytics.

(1) Ratio = Reported/Analyti cs.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-13

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/liter -1 sigma pCi/liter +/-2 sigma RATIO (1) 6/14/2007 1 E5353-05 I MILK Ce-141 209 205 192 202 4.33

+/--

5.94

+-

4.16

+/--

2.82 200

+/-

6.66 1.01 A

Mean =

519

+

22.1 575

+/-

26.9 Cr-51 512 17.1 1.07 A

543 19.2 Mean =

546 13.3 249 4.19 Cs-134 257 4.55 242 8.06 1.06 A

260 3.47 Mean =

255 2.36 162 3.45 Cs-137 169 3.86 169 5.63 0.99 A

170 3.06 Mean =

167 2.00 198 3.81 Co-58 211 4.14 198

+/-

6.61 1.04 A

208 3.30 Mean=

206 2.17 177 3.55 Mn-54 185

+/-

.94 166 5.53 1.10 A

185 3.19 Mean=

182 2.06 184 4.42 Fe-59 182 4.75 167 5.56 1.09 A

181 3.78 Mean 182 2.50 352 7.63 Zn-65 4

10.6 34-11.1 1.08 A

354 6.73 Mean 362 4.90 237 3.02 Co-60 242 3.27 238 7.93 1.01 A

240 2.62 Mean=

240 1.72 I

I I

1-131**

Mean =

65.4 65.9 65.9 65.7

+/--

2.07

+/--

2.29

+/--

1.87 1.20 70.1

+/-

2.34 0.94 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-14

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-2 sigma tRATIO (1) 9/13/2007 1 E5465-05 I

MILK Ce-141 188 239 198 Mean =

208

+/-

10.8

+

10.5

+/-

9.94

+/-

6.02 211

+/-

7.04 0.99 A

200

+/-

42.5 Cr-51 250 41.4 289

+/-

9.65 0.89 A

320

+/-

42.1 Mean =

257

+/-

24.3 150

+/-

8.93 Cs-134

156, 8.74 147

+/-

4.91 1.03 A

149

+/-

8.69 Mean =

152

+/-

5.07 109

+/-

7.87 Cs-137 144 8.32 131

+/-

4.35 0.96 A

126

+/-

7.38 Mean =

126

+/-

4.54 86.5

+/-

7.35 Co-58 127 8.17 114

+/-

3.80 0.95 A

111

+/-

7.19 Mean =

108

+/-

4.38 158

+/-

8.93 Mn-54 176 9.18 168

+/-

5.59 1.03 A

184

+/-

8.60 Mean =

173

+/-

5.14 117

+/-

9.07 Fe-59 113

+/-

9.94 111

+/-

3.69 1.04 A

117i 8.44 Mean =

116

+/-

5.29 208

+/-

16.3 Zn-65 226 17.5 202

+/-

6.74 1.10 A

232

+/-

15.7 Mean =

222

+/-

9.54 144

+/-

6.72 Co-60 151 6.83 148

+/-

4.94 0.98 A

139

+/-

5.89 Mean =

145

+/-

3.75 1-131**

77.6 76.4 72.7 Mean=

75.6

+/-

2.52

+

2.34

+/-

3.10

+/-

1.54 85.2

+/-

2.84 0.89 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 8-15

I I

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi +1 sigma pCi +/-2 sigma IRATIO (1) 3/22/2007 1 E5333-05 I FILTER Ce-141 234 230 246 Mean 237

-4

+-

3.01 2.54 8.32 3.07 233

+

7.78 1.02 A

206

+/-

15.8 Cr-51 197

+

15.6 192 6.41 1.10 A

230

+/-

40.0 Mean 211

+

15.3 95.8

+/-

1.99 Cs-134 76.8 3.02 87.9

+

2.93 1.02 A

95.6 5.43 Mean 89.4

+/-

2.17 188

+

2.43 Cs-137 179 2.04 185

+/-

6.15 1.00 A

186 6.48 Mean 184

+

2.41 76.9

+

2.18 77-58+/-

2.09 Co-58

.0 77.7

+

2.59 0.99 A

76.4 6.07 Mean =

76.8 2.26 160 2.62 150 4-2.17 Mn-54 144 4.78 1.08 A

157

+

6.71 Mean 156

+/-

2.51 93.1

+/-

3.46 Fe-59 84.2 2.94 83.1

+

2.77 1.08 A

93.1

+/-

8.98 Mean=

90.1

+/-

3.35 870 8.82 Zn-65 852

+/-

7.55 787

+/-

26.2 1.09 A

856 23.5

.Mean 859

+/-

8.74 I

1 I

I I

Co-60 114 118 111 Mean 114

-4

+-

-4

-4 1.69 1.46 4.42 1.65 120

+/-

3.99 0.95 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable I

I I

I 8-16

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-2 sigma RATIO (1) 9/13/2007 E5464-05 FILTER Ce-141 195 194 209 199 4-4-

5.84 5.05 6.01 3.3 207 6.90 0.96 A

Mean 238

+/-

27.9 256

4.

23 Cr-51 256

+/-

3 284 9.46 0.94 A

307

+

33.5 Mean =

267 16.4 163 8.66 Cs-134 151 6.52 145

+/-

4.82 1.13 A

177 10.2 Mean =

164 5.0 117 6.54 Cs-137 123 5.42 128 4.27 0.94 A

120 7.64 Mean =

120 3.8 109

+/-

7 Co-58 112 5.44 112 3.73 0.99 A

113 7.41 Mean =

111

+/-

3.9 179

+/-

8.69 Mn-54 166 6.59 164 5.48 1.04 A

168 9.02 Mean =

171 4.7 117

+/-

8.96 Fe-59 130 7.02 108 3.61 1.10 A

110 9.8 Mean =

119 5.0 211 15.1 Zn-65 239 12.6 198 6.61 1.16 A

237 18.5 Mean =

229 9.0 Co-60 141 140 135 Mean 139

+/--

4-4-

4-6.38 4.88 7

3.6 145 4.84 0.96 A

(1) Ratio Reported/Analytics.

(1) Ratio = Re ported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-17

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-2 sigma RATIO (1) 6/14/2005 E5354-05 SOIL Ce-141 0.164 0.144 0.190 Mean 0.166

-4 0.007 0.014 0.012 0.007 0.178

+/-

0.006 1 0.93 A

0.413 0.041 Cr-51 0.401 0.071 0.456

+/-

0.015 0.88 A

0.387 0.057 Mean =

0.400 0.033 0.218 0.007 Cs-134 0.218 0.013 0.215

+/-

0.007 1.02 A

0.220 0.009 Mean =

0.219 0.006 0.242 0.007 0.249

.+

0.013 Cs-137 0.248

+/-

0.008 1.00 A

0.251 0.008 Mean =

0.247 0.006 0.166

+/-

0.006 Co-58 0.154 0.012 0.176

+/-

0.006 0.93 A

0.169

+/-

0.007 Mean 0.163 0.005 0.137 0.006 Mn-54 0.161 0.011 0.148

+/-

0.005 1.01 A

0.152 0.007 Mean 0.150 0.005 0.141

+/-

0.009 Fe-59 0.147 0.016 0.148

+/-

0.005 0.97 A

0.144 0.009 Mean 0.144

+/-

0.007 0.315

+

0.013 0.305

+/-

0.023 Zn-65 0.297

+/-

0.010 1.04 A

0.306

+/-

0.014 Mean 0.309

+/-

0.010 I

I I

K I

I I

Co-60 0.201 0.192 0.196 Mean=

0.196

+-

4-

+/-

0.005 0.010 0.005 0.004 0.212

+/-

0.007 0.93 A

(1) Ratio =Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-18

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*

(

DATE ID NO.

MEDIUM ANALYSIS pCi/g +/-1 sigma 4

pCi/g -2 sigma

]RATIO(1) 6/14/2007 1 E5356-05 VEG Ce-141 0.158

+

0.010 0.145 0.005 0.154

+

0.007 Mean 0.152

+

0.004 0.161

+/-

0.005 0.95 A

0.404

+

0.050 0.349

+

0.028 Cr-51 0.413

+/-

0.014 0.92 A

0.388

+/-

0.043 Mean =

0.380

+/-

0.024 0.210

+/-

0.010 Cs-134 0.215 0.006 0.195

+/-

0.007 1.11 A

0.222

+/-

0.009 Mean =

0.216

+/-

0.005 0.132

+/-

0.008 Cs-137 0.134 0.005 0.136

+/-

0.005 0.96 A

0.126

+/-

0.008 Mean =

0.131

+/-

0.004 0.145

+/-

0.010 Co-58 0.151

+/-

0.005 0.160

+/-

0.005 0.98 A

0.173

+/-

0.008 Mean =

0.156

+/-

0.005 0.144

+/-

0.009 Mn-54 0.137 0.005 0.133

+/-

0.004 1.05 A

0.138

+

0.008 Mean =

0.140

+/-

0.004 0.122

+/-

0.013 Fe-59 0.141 0.007 0.135

+/-

0.005 1.00 A

0.143

+/-

0.011 Mean =

0.135

+

0.006 0.241

+/-

0.021 Zn-65 0.275 0.011 0.270

+/-

0.009 0.98 A

0.279

+/-

0.018 Mean=

0.265

+/-

0.010 Co-60 0.188

+/-

0.008 0.182

+/-

0.004 0.193

+/-

0.007 Mean=

0.188

+

0.004 0.192

+/-

0.006 0.98 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-19

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS'j pCi/g +/-1 sigma I

pCi/g +2 sigma RATIO (1) 9/13/2007 1 E5447-09 VEG Ce-141 0.342 0.298 0.312 Mean=

0.317

+

0.016 0.015 0.014 0.009 0.333

+/-

0.011 0.95 A

0.409

+/-

0.070 Cr-51 0.392 0.068 0.457

+/-

0.015 0.90 A

0.433

+

0.063 Mean =

0.411

+

0.039 0.269

+

0.026 Cs-134 0.221 0.018 0.233

+

0.008 1.05 A

0.243

+/-

0.016 Mean =

0.244

+/-

0.012 0.224

+/-

0.015 Cs-137 0.206, 0.014 0.206

+/-

0.007 1.05 A

0.220

+/-

0.014 Mean =

0.217

+

0.008 0.161

+/-

0.013 Co-58 0.166 0.014 0.180

+/-

0.006 0.94 A

0.179

+/-

0.013 Mean =

0.169

+/-

0.008 0.282

+/-

0.016 Mn-54 0.275 0.016 0.265

+/-

0.009 1.00 A

0.240

+/-

0.014 Mean =

0.266

+/-

0.009 0.178

+

0.017 Fe-59 0.169

+/-

0.019 0.175,

+/-

0.006 1.01 A

0.185

+/-

0.017 Mean =

0.177

+/-

0.010 0.346

+/-

0.032 0.392

+/-

0.031 Zn-65 0.319

+/-

0.001 1.17 A

0.379

+/-

0.029 Mean=

0.372

+/-

0.018 I

I I

Co-60 0.244 0.235 0.235 Mean 0.238

+/-

0.012 0.012 0.012 0.005 0.234

+/-

0.008 1.02 A

(1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable 8-20

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of NIST Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS Bq/g +/-1 sigma Bq/g +/-2 sigma RATIO (1 4/23/2007 1911-4 Water 300.8

+/-

2.09 Co-57 299.7

+/-

2.09 310.7

+/-

2.05 0.97 A

303.4

+/-

2.10 Mean 301.3

+/-

1.21 306.4

+/-

2.38 Ba-133 312.7 2.35 326.7

+/-

3.1 0.95 A

312.3

+/-

2.27 Mean=

310.4

+/-

1.35 283.8

+/-

2.32 290.1 2.31 Cs-137 308.4

+/-

2.31 0.94 A

291.9

+/-

2.22 Mean =

288.6

+/-

1.32 190.6

+/-

1.69 Co-60 196.5 1.69 202.4

+/-

1.01 0.96 A

193.9

+

1.57 Mean =

193.6

+/-

0.95 (1) Ratio = Reported/Analytics.

Sample provided by NIST A=Acceptable U=Unacceptable 8-21

TABLE 8.4-1 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of NIST Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO.

MEDIUM ANALYSIS Bq/filter+/-1 sigma Bq/filter +/-2 sigma RATIO (1) 4/23/2007 1912-11 Filter 1077

+/-

4.0 Co-57 1073

+/-

4.6 1089

+/-

10.9 1.01 A

1143

+/-

4.8 Mean =

1098

+/-

2.6 1006

+/-

5.2 Ba-133 1003 6.0 1048

+/-

10.5 0.96 A

1006

+/-

5.4 Mean 1005

+/-

3.2 743.7

+/-

4.9 Cs-137 725.2

+/-

5.7 766.1

+/-

7.7 0.98 A

777.0

+/-

5.0 Mean =

748.6

+/-

3.0 969.4

+/-

5.2 Co-60 962.0 6.1 987.0

+/-

9.9 0.98 A

976.8

+/-

4.9 Mean=

969.4

+/-

3.1 (1) Ratio Reported/Analytics.

Sample provided by NIST A=Acceptable U=Unacceptable I

I I

8-22

8.5 REFERENCES

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

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

8-23

ML081410299

Contents

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SUBJECT:

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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

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ML081410299

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

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