ML12089A580

Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000311 - Indian Point, Units 1, 2 and 3, Annual Radiological Environmental Operating Report for 2008

ML12089A580
Person / Time
Site:	Indian Point
Issue date:	05/14/2009
From:	Robert Walpole Entergy Nuclear Operations, Indian Point
To:	Atomic Safety and Licensing Board Panel, Document Control Desk, Office of Nuclear Reactor Regulation
SECY RAS
Shared Package
ML12089A579	List: ML12089A580 ML12089A582 ML12093A216
References
RAS 22128, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12089A580 (143)

Text

ENT000311 Submitted: March 29, 2012 Indian Point Energy Center

~

450 Broadway, GSB P.O. Box 249

~'Entergy Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Manager, Licensing NL-09-061 May 14, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 2008 Indian Point Units 1, 2 & 3 Docket Nos.50-003, 50-247, 50-286 License Nos. DPR-5, DPR-26, DPR-64 Dear Sir or Madam; Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (lPEC) site Annual Radiological Environmental Operating Report for the period January 1, 2008 to December 31, 2008.

This report is submitted in accordance with facility Technical Specification section 5.6.2 for DPR-5, DPR-26, and DPR-64, Indian Point Unit Nos. 1, 2 and 3 respectively. No commitments are being made by this report.

Should you or your staff have any questions, please contact Mr. Dennis Loope, Radiation Protection Manager at 914-736-8401.

Sincerely yours, Enclosure cc: wlo enclosure Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 Mr. Theodore B. Smith, Project Manager NRC Resident Inspectors, IP2 and IP3 Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service Mr. Tim Rice, New York State DEC

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ENTERGY NUCLEAR INDIAN POINT NUCLEAR GENERATING STATION UNITS 1,2, AND 3 Docket No.50-003 Indian Point Unit 1 (IP1)

Docket No. 50-247 Indian Point Unit 2 (IP2)

Docket No. 50-286 Indian Point Unit 3 (IP3)

January 1 - December 31,2008

TABLE OF CONTENTS Page 1.0 EXECUTIVE

SUMMARY

1-1

2.0 INTRODUCTION

2-1 2.1 Site Description 2-1 2.2 Program Background 2-1 2.3 Program Objectives 2-1 3.0 PROGRAM DESCRIPTION 3-1 3.1 Sample Collection 3-1 3.2 Sample Analysis 3-1 3.3 Sample Collection and Analysis Methodology 3-1 3.3.1 Direct Radiation 3-1 3.3.2 Airborne Particulates and Radioiodine 3-2 3.3.3 Hudson River Water 3-2 3.3.4 Drinking Water 3-2 3.3.5 Hudson River Shoreline Soil 3-3 3.3.6 Broad Leaf Vegetation 3-3 3.3.7 Fish and Invertebrates 3-3 3.3.8 Hudson River Aquatic Vegetation 3-3 3.3.9 Hudson River Bottom Sediment 3-4 3.3.10 Precipitation 3-4 3.3.11 Soil 3-4 3.3.12 Groundwater Samples 3-4 3.3.13 Land Use Census 3-4 3.4 Statistical Methodology 3-6 3.4.1 Lower Limit of Detection and Critical Level 3-6 3.4.2 Determination of Mean and Propagated Error 3-7 3.4.3 T able Statistics 3-8

TABLE OF CONTENTS {continued}

Page 4.0 RESULTS AND DISCUSSION 4-1 4.1 Direct Radiation 4-3 4.2 Airborne Particulates and Radioiodine 4-4 4.3 Hudson River Water 4-5 4.4 Drinking Water 4-5 4.5 Hudson River Shoreline Soil 4-5 4.6 Broad Leaf Vegetation 4-6 4.7 Fish and Invertebrates 4-6 4.8 Aquatic Vegetation 4-7 4.9 Hudson River Bottom Sediment 4-7 4.10 Precipitation 4-8 4.11 Soil 4-8 4.12 Groundwater 4-8 4.13 Land Use Census 4-9 4.14 Conclusion 4-9

5.0 REFERENCES

5-1 APPENDICES:

A. ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS A-1 B. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B-1 RESUL TS

SUMMARY

C. HISTORICAL TRENDS C-1 D. INTERLABORATORY COMPARISON PROGRAM D-1 ii

LIST OF FIGURES FIGURE TITLE Page A-1 Sampling Locations (Within Two Miles) A-5 A-2 Sampling Locations (Greater Than Two Miles) A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, 1998 to 2008 C-3 C-2 Radionuclides in Air - Gross Beta, 1998 to 2008 C-5 C-3 Radionuclides in Hudson River Water, 1998 to 2008 C-7 C-4 Radionuclides in Drinking Water, 1998 to 2008 C-9 C-5 Radionuclides in Shoreline Soil, 1998 to 2008 C-11 C-6 Broad Leaf Vegetation - Cs-137, 1998 to 2008 C-13 C-7 Fish and Invertebrates - Cs-137, 1998 to 2008 C-15 iii

LIST OF TABLES TABLE TITLE Page A-1 Indian Point REMP Sampling Station Locations A-2 A-2 Lower Limit of Detection Requirements for Environmental Sample Analysis A-8 A-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A-9 8-1 Summary of Sampling Deviations, 2008 8-2 8-1a 2008 Air Sampling Deviations 8-3 8-1 b 2008 TLD Deviations 8-3 8-1c 2008 Other Media Deviations 8-3 8-2 ODCM Annual Summary, 2008 8-4 8-3 2008 Direct Radiation, Quarterly Data 8-9 8-4 Direct Radiation, 1998 through 2008 Data 8-10 8-5 2008 Direct Radiation, Inner and Outer Rings 8-11 8-6 Environmental Airborne Particulate Samples - 2008 Gross 8eta Activity 8-12 8-7 Concentrations of Gamma Emitters in Quarterly Composites of Site Air Particulate Samples, 2008 8-14 8-8 Environmental Charcoal Cartridge Samples - 2008 1-131 Activity 8-16 8-9 Concentrations of Gamma Emitters in Surface Water Samples, 2008 8-18 8-10 Concentrations of Tritium in Surface Water Samples, 2008 8-20 8-11 Concentrations of Gamma Emitters in Drinking Water Samples, 2008 8-21 8-12 Concentrations of Tritium in Drinking Water Samples, 2008 8-23 8-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2008 8-24 8-14 Concentrations of Gamma Emitters in 8road Leaf Vegetation Samples, 2008 8-26 iv

LIST OF TABLES (Continued)

TABLE TITLE Page 8-15 Concentrations of Radionuclides in Fish Samples, 2008 8-35 8-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2008 8-39 8-17 Concentrations of Gamma Emitters in 8ottom Sediment Samples, 2008 8-40 8-18 Concentrations of Radionuclides in Rainwater Samples, 2008 8-42 8-19 Concentrations of Gamma Emitters in Soil Samples, 2008 8-44 8-20 Concentrations of Radionuclides in Monitoring Well Samples, 2008 8-45 8-21 Land Use Census - Residence and Milch Animal Results, 8-57 2008 8-22 Land Use Census, 2008 8-58 C-1 Direct Radiation Annual Summary, 1998 tc? 2008 C-2 C-2 Radionuclides in Air, 1998 to 2008 C-4 C-3 Radionuclides in Hudson River Water, 1998 to 2008 C-6 C-4 Radionuclides in Drinking Water, 1998 to 2008 C-8 C-5 Radionuclides in Shoreline Soil, 1998 to 2008 C-10 C-6 8road Leaf Vegetation - Cs-137, 1998 to 2008 C-12 C-7 Fish and Invertebrates - Cs-137, 1998 to 2008 C-14 D-1 QA Program Schedule D-2 D-2 Ratio of Agreement D-3 D-3 Interlaboratory Comparison Program D-5 v

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2008 Radiological Environmental Monitoring Program (REMP) for the Indian Point site. The Indian Point site consists of Units 1, 2 and 3. Units 1, 2 and 3 are owned and operated by Entergy Nuclear Operations, Inc. Unit 1 was retired as a generating facility in 1974, and as such, its reactor is no longer operated.

The REMP is used to measure the direct radiation and. the airborne and waterborne pathway activity in the vicinity of the Indian Point site. Direct radiation pathways include radiation from buildings and plant structures, airborne material that might be released from the plant, cosmic radiation, fallout, and the naturally occurring radioactive materials in soil, air and water. Analysis of thermoluminescent dosimeters (TLDs), used to measure direct radiation, indicated that there were no increased radiation levels attributable to plant operations.

The airborne pathway includes measurements of air, precipitation, drinking water, and broad leaf vegetation samples. The airborne pathway measurements indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.

The waterborne pathway consists of Hudson River water, fish and invertebrates, aquatic vegetation, bottom sediment, and shoreline sediment. Measurements of the media comprising the waterborne pathway indicated that there was no adverse radiological impact to the surrounding environment attributed to Indian Point Station operations.

This report contains a description of the REMP and the conduct of that program as required by the IPEC Offsite Dose Calculation Manual, herein referred to as ODCM. This 2008 AREOR also contains summaries and discussions of the results of the 2008 program, trend analyses, and potential impact on the environment, land use census, and inter-laboratory comparisons.

During 2008, a total of 1223 analyses were performed. Table B-1 presents a summary of the collected sample analyses results.

An investigation of groundwater contamination with tritium and other radionuclides has been ongoing since 2005 and continued throughout 2008. This investigation of potential onsite sources of contamination is not the focus of this Annual Radiological Environmental Operating Report; however, in 2006, Entergy agreed to several changes in the REMP to assure that all pathways were being evaluated. Specifically, two new groundwater wells (non-drinking water) were 1-1

designated as "boundary wells" and were sampled as groundwater samples for tritium and strontium-gO analyses and also gamma spectroscopy analysis. These wells (MW-40 and MW-51) were designated as REMP sample stations 104 and 105. In addition, a change was made to the existing fish and invertebrate samples and shoreline sediment samples. The locations and frequency remained the same; however, strontium-gO was added to the required analyses. These additions were committed to in 2006 with the sampling and analyses conducted in 2008. These changes are captured in the ODeM. Groundwater sample results for 2008 are summarized in Table 8-20.

In summary, the levels of radionuclides in the environment surrounding Indian Point were within the historical ranges, i.e., previous levels resulting from natural and anthropogenic sources for the detected radionuclides. Further, Indian Point operations in 2008 did not result in exposure to the public greater than environmental background levels.

1-2

SECTION 2 INTRODUCTION

2.0 INTRODUCTION

2.1 Site Description The Indian Point site occupies 239 acres on the east bank of the Hudson River on a point of land at Mile Point 42.6. The site is located in the Village of Buchanan, Westchester County, New York. Three nuclear reactors, Indian Point Unit Nos. 1, 2 and 3, and associated buildings occupy approximately 35 acres. Unit 1 has been retired as a generating facility. Units 1, 2, and 3 are owned and operated by Entergy Nuclear.

2.2 Program Background Environmental monitoring and surveillance have been conducted at Indian Point since 1958, which was four years prior to the start-up of Unit 1. The pre-operational program was designed and implemented to determine the background radioactivity and to measure the variations in activity levels from natural and other sources in the vicinity, as well as fallout from nuclear weapons tests. Thus, as used in this report, background levels consist of those resulting from both natural and anthropogenic sources of environmental radioactivity. Accumulation of this background data permits the detection and assessment of environmental activity attributable to plant operations.

2.3 Program Objectives The current environmental monitoring program is designed to meet two primary objectives:

1. To enable the identification and quantification of changes in the radioactivity of the area, and

2. To measure radionuclide concentrations in the environment attributable to operations of the Indian Point site.

To identify changes in activity, the environmental sampling schedule requires that analyses be conducted for specific environmental media on a regular basis. The radioactivity profile of the environment is established and monitored through routine evaluation of the analytical results obtained.

The REMP designates sampling locations for the collection of environmental media for analysis. These sample locations are divided 2-1

into indicator and control locations. Indicator locations are established near the site, where the presence of environmental radioactivity of plant origin is most likely to be detected. Control locations are established farther away (and upwind/upstream, where applicable) from the site, where the level would not generally be affected by plant discharges.

The use of indicator and control locations enables the identification of potential sources of detected radioactivity, thus meeting one of the program objectives.

Verification of expected radionuclide concentrations resulting from effluent releases attributable to the site is another program objective.

Verifying projected concentrations through the REMP is difficult since the environmental concentrations resulting from plant releases, are consistently too small to be detected. Plant related radionuclides were detected in 2008; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2008 REMP sample results supports the premise that radiological effluents were well below regulatory limits.

2-2

SECTION 3 PROGRAM DESCRIPTION

3.0 PROGRAM DESCRIPTION To achieve the objectives of the REMP and ensure compliance with the ODCM, sampling and analysis of environmental media are performed as outlined in Table A-1 and described in section 3.3.

3.1 Sample Collection Entergy Nuclear Northeast Nuclear Environmental Monitoring (NEM) personnel perform collection of environmental samples for the Indian Point site, with the exception of groundwater and fish/invertebrate samples.

The groundwater (monitoring well) samples are collected by a contracted environmental vendor, GZA Geo Environmental, Inc.

Assistance in the collection of fish and invertebrate samples was provided by a contracted environmental vendor - Normandeau Associates, Inco 3.2 Sample Analysis The analysis of Indian Point environmental samples is performed by the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Environmental Laboratory in Fulton, New York. The JAFNPP lab at Fulton currently analyzes nearly all samples, except for groundwater samples and some tritium and strontium analyses on other media. These samples were analyzed at other New York State Department of Health Environmental Laboratory Approval Program (ELAP) certified laboratories.

3.3 Sample Collection and Analysis Methodology 3.3.1 Direct Radiation Direct gamma radiation is measured using integrating calcium sulfate thermoluminescent dosimeters (TLDs), which provide cumulative measurements of radiation exposure (Le., total integrated exposures in milli-roentgen, mR) for a given period. The area surrounding the Indian Point site is divided into 16 compass sectors. Each sector has two TLD sample locations. The inner ring is located near the site boundary at approximately 1 mile (1.6 km). The outer ring is located at approximately 5 miles (8 km) from the site (6.7- 8.0 km), see Figures A-1 and A-2.

3-1

An additional TLD sample site is located at Roseton (20.7 miles north) as a control, and there are eight other TLD sample locations of special interest.

In total, there are 41 TLD sample sites, designated DR-1 through DR-41 , with two TLDs at each site. TLDs are collected and processed on a quarterly basis. The results are reported as mR per standard quarter (91 days). The mR reported is the average of the two TLDs from each sample site.

3.3.2 Airborne Particulates and Radioiodine Air samples were taken at nine locations varying in distance from 0.28 to 20.7 miles (0.4 to 33 km) from the plant. These locations represent one control at sampling station 23 (A5) and eight indicator locations.

These indicator locations are at sampling stations 4 (A1), 5 (A4), 22, 27, 29, 44, 94 (A2), and 95 (A3). The locations are shQwn on Figures A-1, A-2, and A-3. The air samples are collected continuously by means of fixed air particulate filters followed by in-line charcoal cartridges. Both are changed on a weekly basis. The filter and cartridge samples are analyzed for gross beta and radioiodine, respectively. In addition, gamma spectroscopy analysis (GSA) is performed on quarterly composites of the air particulate filters.

Sampling station 22 (Lovett) was retired in mid-April with the closure of the Lovett generating station and support facilities.

3.3.3 Hudson River Water Hudson River water sampling is performed continuously at the intake structure (sampling station 9, Wa1) and at a point exterior to the discharge canal where Hudson River water and water from the discharge canal mix (sampling station 10, Wa2);' see Figure A-1. An automatic composite sampler is used to take representative samples.

On a weekly basis, accumulated samples are taken from both sample points. These weekly river water samples are composited for monthly gamma spectroscopy analysis, and quarterly for tritium analysis.

3.3.4 Drinking Water Samples of drinking water are collected monthly from the Camp Field Reservoir (3.4 miles NE, sample station 7, sample designation Wb1) and New Croton Reservoir (6.3 Mi SE, sample station 8); see Figure A-

3. Each monthly sample is approximately 4 liters and is analyzed for gamma-emitting radionuclides. They are also composited quarterly and analyzed for tritium.

3-2

3.3.5 Hudson River Shoreline Soil Shoreline soil samples are collected at three indicator and two control locations along the Hudson River. The indicator locations are at sampling stations 53 (Wc1), 28, and 17. The control locations are at sampling stations 50 (Wc2) and 84. Figures A-1, A-2, and A-3show these locations. The samples are gathered at a level above low tide and below high tide and are approximately 2-kg grab samples. These samples are collected at greater than 90 days apart and are analyzed by gamma spectroscopy and for strontium-90.

3.3.6 Broad Leaf Vegetation Broad leaf vegetation samples are collected from three locations during the growing season. The indicator locations are sampling stations 94 (lc2) and 95 (lc1), and the control location is at Roseton, sampling station 23 (lc3).

See Figures A-1 and A-2. The samples are collected monthly, when available, and analyzed by gamma spectroscopy. These samples consist of at least 1 kg of leafy vegetation and are used in the assessment of the food product and milk ingestion pathways.

3.3.7 Fish and Invertebrates Fish and invertebrate samples are obtained from the Hudson River at locations upstream and downstream of the plant discharge. The indicator location (downstream sample point) is designated as sampling station 25 (lb1) and the control location (upstream) is at Roseton, sampling station 23 (lb2). See Figures A-1 and A-2. These samples are collected in season or semiannually if they are not seasonal. The fish and invertebrates sampled are analyzed by gamma spectroscopy, for Sr-90 and for Ni-63.

3.3.8 Hudson River Aquatic Vegetation During the spring and summer, aquatic vegetation samples are collected from the Hudson River at two indicator locations (sampling stations 17 and 28) and one control location (84); see Figure A-3.

Samples of aquatic vegetation are obtained depending on sample availability. These samples are analyzed by gamma spectroscopy.

3-3

3.3.9 Hudson River Bottom Sediment Bottom sediment and benthos qre sampled at four locations: three indicator locations (sampling stations 10, 17, and 28) and one control location (84), along the Hudson River, once each spring and summer; see Figure A-3. These samples are obtained using a Peterson grab sampler or similar instrument. The bottom sediment samples are analyzed by gamma spectroscopy.

3.3.10 Precipitation Precipitation samples are continuously collected at one indicator location (sampling station 44) and one control location (23); see Figure A-3. They are collected in sample bottles designed to hinder evaporation. They are composited quarterly and analyzed for tritium.

They are also analyzed by gamma spectroscopy.

3.3.11 Soil Soil samples are collected from two indicator locations (sampling stations 94 and 95), and one control location (23) on an annual basis; see Figure A-3. They are approximately 2 kg in size and consist of about twenty 2-inch deep cores. The soil samples are analyzed by gamma spectroscopy.

3.3.12 Groundwater Samples Based on recent site hydrology evaluations and the addition of a number of groundwater sampling wells, two new monitoring wells were installed in 2006 and designated as REMP sample stations 104 (MW-

40) and 105 (MW-51). These wells have sample points at six different elevations which were specifically designed to be representative of groundwater moving towards the site boundary. The locations of the groundwater samples are shown in Figure A-3.

Groundwater samples from these wells were obtained quarterly and analyzed for tritium, Sr-90, Ni-63 and by gamma spectroscopy.

3.3.13 Land Use Census Each year a land use census consisting of milch animal and residence surveys is conducted during the growing season to determine the.

current utilization of land within 5 miles (8 km) of the site. These surveys are used to determine whether there are changes in existing conditions that warrant changing the sampling program.

3-4

For example, the milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. This census consists of visual field surveys of the areas where a high probability of milch animals exists and confirmation through personnel such as feed suppliers who deal with farm animals and dairy associations (See Tables 8-21 and 8-22).

Visual inspections were made of the 5-mile area around the Indian Point Site during routine sample collections and emergency plan equipment inspections in the area throughout the year. An extensive land survey was conducted of the 5-mile area in an attempt to identify new residential areas, commercial developments and to identify milch animals in pasture. Previous locations were visited and verified by dispatching Nuclear Environmental Technicians to the various locations.

Note: These actions were taken while performing quarterly environmental badge change out and field inspections through out the four surrounding counties.

• Orange County was surveyed during through the summer and fall.

• Rockland County was surveyed during summer and fall.

• Putnam County was surveyed during the summer and fall.

• Westchester County was surveyed during the spring, summer and fall.

Although there are presently no animals producing milk for human consumption within 5 miles (8 km) of the site, the census is performed to determine if a milk-sampling program needs to be conducted.

A residence census is also performed to identify the nearest residence(s) to the site in each of the 16 sectors surrounding Indian Point. See Table 8-22.

A garden census was not performed, as the ODCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census. The sectors are chosen to be in the pre-dominant wind directions.

Note: An aerial survey was not conducted of the 5-mile area this year.

3-5

3.4 Statistical Methodology There is a number of statistical calculation methodologies used in evaluating the data from the Indian Point REMP. These methods include determination of Lower Limits of Detection (LLD) and Critical Levels (Lc), and estimation of the mean and associated propagated error.

3.4.1 Lower Limit of Detection (LLD) and Critical Level (Lcl The LLD is a predetermined concentration or activity level used to establish a detection limit for the analytical procedures.

The Nuclear Regulatory Commission (NRC) specifies the maximum acceptable LLDs for each radionuclide in specific media. The LLDs are determined by taking into account overall measurement methods. The equation (from the ODCM) used to calculate the LLD reduces to:

LLD =4.66 K Sb, where: Sb =standard deviation of the background count rate, and K consists of variables, which account for such parameters as:

- Instrument characteristics (e.g., efficiency)

- Sample size

- Counting time

- Media density (self-absorption)

- Radioactive decay

- Chemical yield In the ODCM program, LLDs are used to ensure that mlnrmum acceptable detection capabilities for the counting system are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement process and not as an "a posteriori" (after the fact) limit for a particular measurement. Table A-2 presents the ODCM required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the ODCM required LLDs represent the maximum allowed.

3-6

The critical level (Le) is defined as that net sample counting rate which has a 5% probability of being exceeded when the actual sample activity is zero (e.g., when counting background only). It is determined using the following equation.

Lc =ka Sb (1 + TtlTsl 5 in cpm where:

ka =1.645 (corresponds to a 95% confidence level)

Sb =standard deviation of the background count rate =(RbITb )o.5 Rb =background count rate (cpm)

Tb = background count time (min)

Ts = sample count time (min)

For the REMP, net sample results which are less than the Le value are considered not detected, and the Le value is reported as the "less than" value, unless otherwise noted. Values above the Le are considered positively detected radioactivity in the environmental media of interest (with a 5% chance of false positive).

3.4.2 Determination of Mean and Propagated Error In accordance with program policy, recounts of positive samples are performed. When the initial count reveals the presence of radioactivity, which may be attributed to plant operations, at a value greater than the Le , two recounts are performed to verify the positive results. The recounts are not performed on; air samples with positive results from gross beta analysis, since the results are always positive due to natural background radioactive material in the air, or tritium in water samples, since an outside contractor provides these activities. 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 sample result is available, the mean of the sample results and the estimated error for the mean are reported in the Annual Report.

The mean (X) and the propagated error (PE) are calculated using the following equations:

3-7

N

-o IXi X -i- =1 N

where: Xi = value of each individual observation N = number of observations N

I (ERRil PE = ~i=-,--1_ __

N where: ERRi = 1 sigma error of the individual analysis N = number of observations 3.4.3 Table Statistics The averages shown in the summary table (Table B-2) are the averages of the positive values in accordance with the NRC's Branch Technical Position (BTP) to Regulatory Guide 4.8 (Reference 14).

Samples with n<" values are not included in the averages.

It should be noted that this statistic for the mean using only positive values tends to strongly bias the average high, particularly when only a few of the data are measurably positive. The REMP data show few positive values; thus the corresponding means are biased high.

Exceptions to this include direct radiation measured by TLDs and gross beta radioactivity in air, which show positive monitoring results throughout the year.

In the data tables B-6 through B-20, values shown are based on the Lc value, unless otherwise noted. If a radionuclide was detected at or

° above the Lc value in two or more counts, the mean and error are calculated as per Section 3.4.2, and reported in the data table. Values listed as ,,<n in the data tables are the Lc values for that sample, unless otherwise noted. If multiple counts were performed on a sample and a radionuclide's values are "< Lc " each time, the largest critical level is reported in the data table.

The historical data tables contain the annual averages of the positive values for each year. The historical averages are calculated using only the positive values presented for 1998 through 2007. The 2008 average values are included in these historic tables for purposes of comparison.

3-8

SECTION 4 RESULTS AND DISCUSSION

4.0 RESULTS AND DISCUSSION The 2008 Radiological Environmental Monitoring Program (REMP) was conducted in accordance with Indian Point's Offsite Dose Calculation Manual ODCM. The ODCM contains requirements for the number and distribution of sampling locations, the types of samples to be collected, and the types of analyses to be performed for measurement of radioactivity.

The REMP at Indian Point includes measurements of radioactivity levels in the following environmental pathways.

Hudson River Water Shoreline Soil Fish and Invertebrates Aquatic Vegetation Bottom Sediment Airborne Particulates and Radioiodine Precipitation Drinking Water Terrestrial Broad Leaf Vegetation Direct Gamma Radiation Soil Groundwater An annual land use and milch animal census is also part of the REMP.

To evaluate the contribution of plant operations to environmental radioactivity levels, other man-made and natural sources of environmental radioactivity, as well as the aggregate of past monitoring data, must be considered. It is not merely the detection of a radionuclide, but the evaluation of .the location, magnitude, source, and history of its detection that determines its significance. Therefore, we have reported the data collected in 2008 and assessed the significance of the findings.

A summary of the results of the 2008 REMP is presented in Table B-2. This Table lists the mean and range of all positive results obtained for each of the media sampled at ODCM indicator and control locations. Discussions of these results and their evaluations are provided below.

The radionuclides detected in the environment can be grouped into three categories: (1) naturally occurring radionuclides; (2) radionuclides resulting from weapons testing and other non-plant related, anthropogenic sources; and (3) radionuclides that could be related to plant operations.

4-1

The environment contains a broad inventory of naturally occurring radionuclides which can be classified as, cosmic ray induced (e.g., Be-7, H-

3) or geologically derived (e.g., Ra-226 and progeny, Th-228 and progeny, and K-40.) These radionuclides constitute the majority of the background radiation source and thus account for a majority of the annual background dose detected. Since the detected concentrations of these radionuclides were consistent at indicator and control locations, and unrelated to plant operations, their presence is noted only in the data tables and will not be discussed further.

The second group of radionuclides detected in 2008 consists of those resulting from past weapons testing in the earth's atmosphere. Such testing in the 1950's and 1960's resulted in a significant atmospheric radionuclide inventory, which, in turn, contributed to the concentrations in the lower atmosphere and ecological systems. Although reduced in frequency, atmospheric weapons testing continued into the 1980's. The resultant radionuclide inventory, although diminishing with time (e.g., through radioactive decay and natural dispersion processes), remains detectable.

In 2008, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 and perhaps Sr-90 in some media. The levels detected were consistent with the historical levels of radionuclides resulting from weapons tests as measured in previous years.

The final group of radionuclides detected through the 2008 REMP comprises those that may be attributable to current plant operations. During 2008 Cs-137, 1-131, Sr-90 and tritium (H-3) were the only potentially plant-related radionuclides detected in some environmental samples.

H-3 may be present in the local environment due to either natural occurrence, other man-made sources, or as a result of plant operations.

Small amounts of H-3 were detected in groundwater boundary wells in 7 of 40 samples at levels which were much lower than the required Lower Limit of Detection (3000 pCi/L); however, they were detectable.

Cs-137 and Cs-134 are both produced in and released from fission reactors and were introduced into the environment from the accident at Chernobyl in 1986. Because Cs-134 has a short half-life relative to Cs-137, Cs-134 from Chernobyl is not likely to be present in 2008. Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. In 2008, there were three detections of Cs-137 in shoreline sediment (2 indicator samples and one control sample), bottom sediment (6 indicator samples). The fact that there was no Cs-134 present (recent plant releases would contain Cs-134) and that there was detection also at a control location indicates that the activity was likely due to 4-2

atmospheric weapons testing, with some contribution from plant releases from several years past.

Sr-90 was found in two indicator fish samples in the vicinity of the plant (VOP) and in two fish samples at the Roseton control location. The Roseton samples are of a higher mean value and range than the VOP samples, so the results do not point to the plant as the activity origin.

1-131 is also produced in fission reactors, but can result from non-plant related anthropogenic sources, e.g., medical administrations, such as in previous years. 1-131 was detected in aquatic vegetation indicator and control location (1 each).

Co-58 and Co-60 are activation/corrosion products also related to plant operations. They are produced by neutron activation in the reactor core. As Co-58 has a much shorter half-life, its absence "dates" the presence of Co-60 as residual from releases of both radionuclides in the past. If Co-58 and Co-60 are concurrently detected in environmental samples, then the source of these radionuclides is considered to be from recent releases.

When significant concentrations of Co-60 are detected but no Co-58, there is an increased likelihood that the Co-60 is due to residual Co-60 from past operations. There was no Co-58 or Co-60 detected in the 2008 REMP, though they (Co-58 and Co-60) can be observed in historical data.

In the following sections, a summary of the results of the 2008 REMP is presented by sample medium and the significance of any positive findings discussed. It should be noted that naturally occurring radionuclides are omitted from the summary table (Table 8-2) and further discussion.

4.1 Direct Radiation The environmental TLDs used to measure the direct radiation were TLDs supplied and processed by AREVA NP via the JAF Laboratory.

In 2008, the TLD program produced a consistent picture of ambient background radiation levels in the vicinity of the Indian Point Station. A summary of the annual TLD data is provided in Table 8-2 and all the TLD data are presented in Tables 8-3, 8-4 and 8-5. TLD sample site DR-40 is the control site for the direct radiation (DR) series of measurements.

Table 8-3 provides the quarterly and annual average reported doses in mR per standard quarter for each of the direct radiation sample points, DR-1 through DR-41. The table also provides the sector for each of the DR sample points. Table 8-4 provides the mean, standard deviation, minimum and maximum values in mR per standard quarter for the years 1998 through 2006. The 2008 means are also presented in 4-3

Table 8-4. Table 8-5 presents the 2008 TLD data for the inner ring and outer ring of TLDs.

The 2008 mean value for the direct radiation sample points was 14.4 mR per standard quarter. At those locations where the 2008 mean value was higher, they are within historical bounds for the respective locations.

The DR sample locations are arranged so that there are two concentric rings of TLDs around the Indian Point site. The inner ring (DR-1 to DR-

16) is close to the site boundary. The outer ring (DR-17to DR-32) has a radius of approximately 5 miles from the three Indian Point units. The results for these two rings of TLDs are provided in Table 8-5. The annual average for the inner ring was 14.3 mR per standard quarter and also average for the outer ring was 14.5 mR per standard quarter.

The control location average for 2008 was 17.3 mR per standard quarter.

Table C-1 and Figure C-1 present the 10-year historical averages for the inner and outer rings of TLDs. The 2008 averages are consistent with the historical data. The 2008 and previous years' data show that there is no measurable direct radiation in the environment due to the operation of the Indian Point site.

4.2 Airborne Particulates and Radioiodine An annual summary of the results of the 2008 air particulate filter and charcoal cartridge analyses is presented in Table 8-2. As shown, there were no radionuclides detected in the air attributable to plant operations.

The results of the analyses of weekly air particulate filter samples for gross beta activity are presented in Table 8-6, and the results of the gamma spectroscopy analyses of the quarterly composites of these samples are in Table 8-7.

Gross beta activity was found in air particulate samples throughout the year at all indicator and control locations. The average gross beta activity for the eight indicator air sample locations was 0.014 pCi/m 3 and the average for the control location was 0.013 pCilm 3 . The activities detected were consistent for all locations, with no significant differences in gross beta activity in any sample due to location. Gamma spectroscopy analyses of the quarterly composite air sam'ples showed that no reactor-related radionuclides were detected and that only naturally-occurring radionuclides were present at detectable levels.

4-4

The mean annual gross beta concentrations and Cs-137 concentrations in air for the past 10 years are presented in Table C-2. From this table and Figure C-2, it can be seen that the average 2008 gross beta concentration was consistent with historical levels. Cs-137 has not been detected since 1987. This is consistent with the trend of decreasing ambient CS-137. concentrations in recent years.

The charcoal cartridge analytical results are presented in Table B-8.

"Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/m 3 ) in the charcoal cartridge samples, which is consistent with historical trends.

From the data, it can be seen that no airborne radioactivity attributable to the operatipn of Indian Point was detected in 2008.

4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table B-2. Data resulting from analysis of monthly Hudson River water samples for gamma emitters, and H-3 analysis of quarterly composites, are presented in Tables B-9 and B-10, respectively.

No radionuclides other than those that are naturally occurring were detected in the Hudson River Water samples. Additionally, Table C-3 indicates the absence of Cs-137 which is consistent with. historical data.

4.4 Drinking Water The annual program summary table (Table B-2) contains a summary of the 2008 drinking water sample analysis results. Results of the gamma spectroscopy analyses of the monthly drinking water samples are in Table B-11 and results of tritium analysis of quarterly composites are in Table B-12. Other' than naturally occurring radionuclides, no radionuclides were detected in drinking water samples.

A summary and illustration of historic trends of drinking water are provided in Table C-4 and Figure C-4, respectively. An examination of the data indicates that operation of the Indian Point units had no detectable radiological impact on drinking water.

4.5 Hudson River Shoreline Soil A summary of the radionuclide concentrations detected in the shoreline soil samples is contained in Table B-2. Table B-13 contains the results of the gamma spectroscopic and strontium-90 analyses of the shoreline soil samples. '

4-5

In addition to the naturally occurring radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2008. Cs-137 was detected at the Verplanck location in both samples from that location, for a total of two positive values out of eight samples from indicator locations. Cs-137 was detected at the control location (Manitou Inlet) in one of two samples (236 pCilkg). The average concentration for the indicator locations that had positive indication of Cs-137 was 163 pCi/kg-dry with a maximum concentration of 181 pCi/kg, dry.

An historical look at Cs-137 detected in shoreline soil at indicator and control locations can be viewed in Table C-5 and Figure C-5. Cs-137 has been and continues to be present in this media, both at indicator and control locations, at a consistent level over the past ten years.

Cs-134 and Cs-137 are both discharged from the plant in similar quantities. The lack of Cs-134 activity is an indication that the primary source of the Cs-137 in the shoreline soil is legacy contamination from weapons fallout.

4.6 8road Leaf Vegetation Table 8-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2008 samples are presented in Table 8-14. Analyses of broad leaf vegetation samples revealed only naturally occurring radionuclides.

Table C-6 contains an historical summary and Figure C-6 is an illustration of the broad leaf vegetation analysis results. The detection of low levels of Cs-137 has occurred sporadically at both indicator and control locations at relatively low concentrations for the past ten years; however, Cs-137 was not detected in 2008.

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table 8-2. Table 8-15 contains the results of the analysis of fish and invertebrate samples for 2008. There were no plant related radionuclides detected as a result of the GSA.

Strontium-90 was added to the analyte list in 2007. Ni-63 was added with an aDCM revision in 2008. Sr-90 was found in two of six indicator samples in the vicinity of the plant (8.8. pCi/kg average) and in two of six Roseton control samples (16.3 pCi/kg average).

4-6

A summary of historical fish and invertebrate analytical data is presented in Table C-7 and illustrated in Figure C-7. Data are consistent with historical trends.

4.B Aquatic Vegetation A summary of the aquatic sample analysis results is presented in Table B-2. Table B-16 contains the results of the analysis of aquatic vegetation samples for 200B. 1-131 was detected at one of three indicator station samples and at one of the two control station samples.

The concentration of 1-131 in the indicator sample was 54 pCi/kg. The control location sample indicated 35 pCi/kg.

The historical data for these two locations are:

Location Value (pCi/kg, wet)

Off Verplanck June 2006 <10.4 Off Verplanck August 2006 < 21.5 Off Verplanck June 2007 < 17.1 Off Verplanck June 2008 < 8.8 Off Verplanck September 2008 54 Cold Spring June 2006 < B.2 Cold Spring September 2006 <16.4 Cold Spring June 2007 < 10.9 Cold Spring June 2008 < 11.7 Cold Spring September 2008 35 The detected 1-131 was reviewed against plant discharge records for the calendar year. The discharge records do not support the locally detected 1-131. The remote nature of the Cold Spring location, certainly for B-day half-life 1-131, is also a factor. In both the indicator and control locations, the single instances of detection are not due to station operations and may be of medical administration origin.

4.9 Hudson River Bottom Sediment A summary of the Hudson River bottom sediment analysis results is presented in Table B-2. Table B-17 contains the results of the analysis of bottom sediment samples for 200B. Cs-137 was detected at 6 of 6 indicator station samples, and at 2 of 2 control station samples. Cs-134 was not detected in any bottom sediment samples. The lack of Cs-134 suggests that the primary source of the Cs-137 in bottom sediment is from historical plant releases at least several years old and from residual weapons test fallout.

4-7

This detection of Cs-137 in bottom sediment has been generally decreasing over the last 10 years, and Cs-134 has not been detected in bottom sediment since 2002. The data for 2008 are consistent with but slightly lower than historical levels.

4.10 Precipitation A summary of the precipitation sample analysis results is presented in Table 8-2. Table 8-18 contains the results of the precipitation samples for 2008. Other than naturally occurring radionuclides, no radionuclides were detected in precipitation samples.

A review of historical data over the last 10 years indicates tritium had been detected in both indicator and control precipitation samples in 1998; however, there have been no instances of positive values since that time.

4.11 Soil A summary of the soil sample analysis results is presented in Table 8-

2. Table 8-19 contains the results of the soil samples for 2008. Other than naturally occurring radionuclides, no activity was detected in any of the soil samples.

4.12 Groundwater A summary of the groundwater samples for 2008 is contained in Table 8-2. Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, and Sr-90 are given in Table 8-20.

Tritium was detected at very low concentrations in 7 of the 40 groundwater samples analyzed. The amount detected ranged from 193 to 329 pCi/L and averaged 244 pCilL - which are well below the required LLD of 3000 pCi/L.

Other than tritium, there were no potentially plant-related radionuclides detected in the groundwater samples.

Detection of tritium (owing to natural levels and laboratory sensitivity) and sporadic detection of Sr-90 and Cs-137 are expected. These radionuclides are normally present in the environment as "background radioactivity" as a consequence of both natural radioactivity and man-made activities un-related to the plant's operations. The concentrations detected by this monitoring program are in the expected range of normal background and based on site hydrogeology are not likely a 4-8

result of plant activities. Additionally, these detected concentrations well below any applicable or relevant regulatory standards.

4.13 Land Use Census A census was performed in the vicinity of Indian Point in 2008. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables 8-21 and 8-22.

The results of the 2008 census were generally same as the 2007 census results. The New York Agricultural Statistic Service showed there were no animals producing' milk for human consumption found within 5 miles (8 km) of the plant. Field observations also yielded no milching animal locations within five miles.

The second part of this census revealed that the two nearest residences in different sectors are located 0.44 miles (0.71 km) ESE and 0.73 miles (1.13 km) S of the plant. The 2008 land use census indicated there were no new residences that were closer in proximity to IPEC.

The ODCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis results for these two sectors are discussed in Section 4.6 and presented in Table 8-14, Table C-6 and Figure C-6.

4.14 Conclusion The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of Indian Point operations on the environment. The preceding discussions of the results of the 2008 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The 2008 REMP results demonstrate the relative contributions of different radionuclide sources, both natural and anthropogenic, to the environmental concentrations. The results indicate that the fallout from previous atmospheric weapons testing continues to cause sporadic detection of Cs-137 and Sr-90 in environmental samples. Other anthropogenic sources (e.g. medical administrations) may have been the cause of low-level 1-131 detection in a couple of aquatic vegetation samples. There are infrequent detections of plant related radionuclides in the environs; however, the radiological effects are very low and are significantly less than those from natural background and other anthropogenic sources.

4-9

4-10 SECTION 5 REFERENCES

5.0 REFERENCES

1. Entergy Nuclear Northeast, Nuclear Environmental Monitoring Procedures, Radiological Support Procedures, Indian Point Station.

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

3. Eisenbud, M., Environmental Radioactivity, Academic Press, New York, 1987.

4. Glasstone, S., and W. H. Jordan, Nuclear Power and Its Environmental Effects, American Nuclear Society, La Grange Park, IL, 1980.

5. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U.S. NRC Regulatory Guide 1.109, Revision 1, 1977.

6. Cohen N., and Eisenbud M., Radiological Studies of the Hudson River, Progress Report Institute of Environmental Medicine, New York University Medical Center, December 1983.

7. U.S. Nuclear Regulatory Commission. Regulatory Guide 4.15, Revision 1, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment February 1979.

8. J. W. Poston, Cesium-137 and Other Man-Made Radionuclides in the Hudson River: A Review of the Available Literature, Applied Physical Technology, Inc., report to NYPA, September 1977.

9. U.S. Environmental Protection Agency Report EPC-520/1 80-012, Upgrading Environmental Radiation Data, August 1980.

10. Andrews, Howard L. and Lapp, Ralph E. Nuclear Radiation Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1972.

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

12. Eichholz, Geoffrey G., Environmental Aspects of Nuclear Power, Lewis Publishers, Inc., Chelsea, Michigan, 1985.

13. Kelly, J. J. (Ed.), Effluent and Environmental Radiation Surveillance, ASTM STP #698, Philadelphia, PA, 1978.

14. Entergy Nuclear Northeast, James A. FitzPatrick Nuclear Power Plant, Radiological and Environmental Services Department Environmental Surveillance Procedures.

15. Knoll, Glenn F., Radiation Detection and Measurement, first edition, John Wiley and Sons, New York, 1979.

5-1

16. Dixon, Wilfred J., Introduction to Statistical Analysis, third edition, McGraw-Hili Inc., 1969.

17. National Council on Radiation Protection. NCRP Report No.94, Exposure of the Population in the United States and Canada from Natural Background Radiation December 1987.

18. National Council on Radiation Protection. NCRP Report No. 62, Tritium in the Environment, March 1979.

19. IPEC Offsite Dose Calculation Manual, Units 1, 2 and 3

20. Kuhn, W.,et aI., The Influence of Soil Parameters on Cs-137 Uptake by Plants from Long-Term Fallout on Forest Clearings and Grasslands, Health Physics Journal, 46(5), p. 1083, May 1984.

21. Garner, J.,et aI., High Radiocesium Levels in Granite Outcrop Vegetation and Reductions Through Time, Health Physics Journal, 60(4), p. 533, April 1991.

22. McGee, E., et aI., The Variability in Fallout Content of Soils and Plants and the Design of Optimum Field Sampling Strategies, Health Physics Journal, 68(3), March 1995.

23. Consolidated Edison Company of New York, Safety Evaluation for Amendment #45 to Unit 1 Provisional Operating License, January 1996.

24. U.S Nuclear Regulatory Commission, Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, November 1979.

25. Office of Environmental Management, Semi-Annual Report of the Department of Energy, Quality Assessment Program, EML 617, June 2003.

26. Office of Environmental Management, Semi-Annual Report of theDepartment of Energy, Quality Assessment Program, EML 618, December 2003.

27. McFarland, R.C., et aI., The Counting Room: Special Edition, Radioactivity and Radiochemistry, Caretaker Publications, Atlanta, Georgia, 1994.

28. Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw Hill, 1969.

29. ENN-Ll-102, Corrective Action Process

30. Technical Information Document 2003-011 "Justification for the Removal of the Radiological Environmental Monitoring Blind Spike Program at IPEC" 5-2

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS REQUIREMENTS

APPENDIX A Environmental media are sampled at the locations specified in Table A-1 and shown in Figures A-1, A-2, and A-3. The samples are analyzed according to criteria established in the ODCM. These requirements include: methods of sample collection; types of sample analysis; minimum sample size required; lower limit of detection, which must be attained for each medium, sample, or analysis type, and environmental concentrations requiring special reports.

Table A-1 provides the sampling station number, location, sector, distance from Indian Point, sample designation code, and sample type. This table gives the complete listing of sample locations used in the 2008 REMP.

Three maps are provided to show the locations of REMP sampling. Figure A-1 shows the sampling locations within two miles of Indian Point. Figures A-2 and A-3 show the sampling locations within ten miles of Indian Point.

The ODCM required lower limits of detection (LLD) for Indian Point sample analyses are presented in Table A-2. These required lower limits of detection are not the same as the lower limits of detection or critical levels actually achieved by the laboratory. The laboratory's lower limits of detection and critical levels must be equal to or lower than the required levels presented in Table A-2.

Table A-3 provides the reporting level for radioactivity in various media. Sample results that exceed these levels and are due to plant operations require that a special report be submitted to the NRC.

In addition to the sampling outlined in Table A-1, there is an environmental surveillance requirement that an annual land use and milch animal census be performed. See Tables 8-21 and 8-22 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS Onsite -

3 DR8 Service Center Building Direct Gamma 0.35 Mi (SSE) at 1580 A1 Onsite - 0.28 Mi (SW) at Air Particulate 4 Algonquin Gas Line A1 234 0 Radioiodine A4 Air Particulate 5 A4 NYU Tower Radioiodine DR10 Direct Gamma 7 Wb1 Camp Field Reservoir Drinking Water 8 Croton Reservoir Drinking Water Onsite -

9 Wa1 Plant Inlet (Hudson River Intake)*. HR Water 0.16 Mi (W) at 273 0 Wa2 Onsite - HR Water 10 Discharge Canal (Mixing Zone)

• • 0.3 Mi (WSW) at 249 0 HR Bottom Sediment Onsite -

14 DR7 r Meter House Direct Gamma 0.3 Mi (SE) at 133 0 HR Aquatic Vegetation 17 Off Verplanck 1.5 Mi (SSW) at 202S HR Shoreline Soil HR Bottom Sediment Cortlandt Yacht Club 20 DR38 1.5 Mi (S) at 180 0 Direct Gamma (AKA Montrose Marina)

Air Particulate 22 Lovett Power Plant 1.6 Mi (WSW) at 244 0 Radioiodine Precipitation A5 Air Particulate, A5 Radioiodine 23 DR40 Roseton* 20.7 Mi (N) at 35r Direct Gamma Ic3 Broad Leaf Vegetation Soil Ib2 Fish & Invertebrates 25 Ib1 Downstream Downstream Fish & Invertebrates Air Particulate 27 ** Croton Point 6.36 Mi (SSE) at 1560 Radioiodine DR41 Direct Gamma HR Shoreline Soil DR4 Direct Gamma 28 Lent's Cove 0.45 Mi (ENE) at 069 0 HR Bottom Sediment

• • HR etation Air Particulate 29 Grassy Point 3.37 Mi (SSW). at 1960 Radioiodine DR39 Direct Gamma

• = Control location

• • = Locations listed do not have sample designation locations specified in the ODCM HR = Hudson River RIS = Reuter Stokes A-2

TABLE A*1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 33 DR33 Hamilton Street (Substation) 2.88 Mi (NE) at 053 0 Direct Gamma Onsite -

34 DR9 South East Corner of Site Direct Gamma 0.52 Mi (S) at 1790 Onsite -

35 DR5 Broadway & Bleakley Avenue Direct Gamma 0.37 Mi (E) at 092 0 38 DR34 Furnace Dock (Substation) 3.43 Mi (SE) at 141 0 Direct Gamma

• • Precipitation 0

44 ** Peekskill Gas Holder Bldg 1.84 Mi (NE) at 052 Air Particulate

• • Radioiodine 50 Wc2 Manitou Inlet* 4.48 Mi (NNW) at 34JO HR Shoreline Soil Wc1 HR Shoreline Soil 53 White Beach 0.92 Mi (SW) at 226 0 DR11 Direct Gamma 0

56 DR37 IVerplanck - Broadway & 6th Street 1.25 Mi (SSW) at 202 Direct Gamma 0

57 DR1 Roa Hook 2 Mi (N) at 005 Direct Gamma 58 DR17 Route 90 - Garrison 5.41 Mi (N) at 358 0 Direct Gamma 0

59 DR2 Old Pemart Avenue 1.8 Mi (NNE) at 032 Direct Gamma Gallows Hill Road & Sprout Brook 60 DR18 5.02 Mi (NNE) at 029 0 Direct Gamma Road 61 DR36 Lower South Street & Franklin Street 1.3 Mi (NE) at 052 0 Direct Gamma Westbrook Drive 62 OR19 5.03 Mi (NE) at 062 0 Direct Gamma (near the Community Center)

Lincoln Road - Cortlandt 64 OR20 4.6 Mi (ENE) at 06JO Direct Gamma (School Parking Lot) 66 OR21 Croton Avenue - Cortlandt 4.87 Mi (E) at 083 0 Direct Gamma 0

67 DR22 Colabaugh Pond Road - Cortlandt 4.5 Mi (ESE) at 114 Direct Gamma 69 DR23 Mt. Airy & Windsor Road 4.97 Mi (SE) at 12JO Direct Gamma 0

71 DR25 Warren Ave - Haverstraw 4.83 Mi (S) at 188 Direct Gamma 72 DR26 Railroad Avenue & 9W - Haverstraw 4.53 Mi (SSW) at 203 0 Direct Gamma Willow Grove Road & Captain 73 DR27 4.97 Mi (SW) at 226 0 Direct Gamma Faldermeyer Drive 74 DR12 West Shore Drive - South 1.59 Mi (WSW) at 252 0 Direct Gamma 0

75 DR31 Palisades Parkway 4.65 Mi (NW) at 225 Direct Gamma 0

76 DR13 West Shore Drive - North 1.21 Mi (W) at 276 Direct Gamma 77 DR29 Palisades Parkway 4.15 Mi (W) at 272 0 Direct Gamma 78 DR14 Rt. 9W across from RlS #14 1.2 Mi (WNW) at 295 0 Direct Gamma 79 DR30 Anthony Wayne Park 14.57 Mi (WNW) at 296 0 Direct Gamma

• = Control location

• • = Locations listed do not have sample designation locations specified in the aDeM HR = Hudson River RIS = Reuter Stokes A-3

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 81 DR28 4.96 Mi (WSW) at 310 0 Direct Gamma 82 DR16 1.01 Mi (NNW) at 334 0 Direct Gamma 0

83 DR32 Route 9W - Fort Montgomery 4.82 Mi (NNW) at 339 Direct Gamma HR Aquatic Vegetation 84 Cold Spring

• 10.88 Mi (N) at 356 0 HR Shoreline Soil HR Bottom Sediment 88 DR6 R/S Pole #6 0.32 Mi (ESE) at 1180 Direct Gamma Highland Ave & Sprout Brook Road 89 DR35 Mi (NNE) at 025 0 Direct Gamma (near rock cut) 90 DR3 Charles Point Direct Gamma 92 DR24 Warren Road - Cortlandt Direct Gamma A2 Air Particulate A2 Onsite- 0.39 Mi (S) at Radioiodine 94 IPEC Training Center Ic2 193 0 Broad Leaf Vegetation Soil A3 Air Particulate A3 Onsite - Radioiodine 95 Meteorological Tower Ic1 0.46 Mi (SSW) at 208 0 Broad Leaf Vegetation

• • Soil MW-40 Boundary Well, lower parking 104 Onsite - 0.21 mi (SW) Groundwater lot MW-51 Boundary Well, middle 105 ** Onsite - 0.18 mi (SSW) Groundwater parking lot

• = Control location

• • = Locations listed do not have sample designation locations specified in the aDCM HR = Hudson River RIS = Reuter Stokes A-4

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point N

~

Peekskill Westchester County Rockland County Indian ..&r-pOint~.A:

Ib1 rn (7) 1 mile 13l12l Hudson Ic1 Ic2 11 9

. . . ~ . . . -@m Buchanan Key: ~ - Waterborne: Surface (HR) Wa# Ic# - Broadleaf Vegetation o - Direct Radiation Sample Location DR# Ib1 - Fish and Invertebrates o -Air Particulate & Radioiodine A# (where available downstream)

<:> - HR Shoreline Sediment Wc#

A-5

FIGURE A-2 SAMPLING LOCATIONS Greater Than 2 Miles From Indian Point N

~ Roseton (20.7 mi. N): IT] @ Ic3 Upstream: Ib2 Orange County Putnam County Bear Mountain Bridge 5 miles Rockland County Westchester County Key: o -Direct Radiation Sample Location DR# Ic3 - Broadleaf Vegetation o - Air Particulate & Radioiodine A# Ib2 - Fish and Invertebrates

<>- HR Shoreline Sediment Wc# (where available upstream) o -Waterborne: Drinking Wb#

A-6

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

.~. Rqs$ton (20*7 rril. NY: 4~ : p

• Orange county Putnam county Gqld Spring (1'0.88 mi. N) : 84 :T 6;

Beqr MQWrjta inBrigge.

10:+

104/105'gw

22

• 29:. _ _ _.....

Westchester County Rockland county o* 8:dw 5ri:liles Key: .,- Air Particuli3te:&Radioibdine <>:- HR Shoreiin~SedifTlent

.. - Aquatic Vegetation +-Soil ' . "'

• - HR BottomSedimerit gw-Ground w~ter~oundary Monitoring p - Prepipitatioh' ,. . . . (see detailed site map) "

dw-DfirikiriQ Water A-7

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLE ANALYSIS (a) (b) 130 260 130 0.07 60 15 15 5,000 (a) This list shows required LLD's, but other radionuclides are considered. Other identifiable peaks from gamma spectroscopy shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Reference 27).

(c) LLD for drinking water samples. If no drinking water pathway exists, a value of 3000 pCi/L may be used.

(d) LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pC ilL may be used.

(e) The Sr-90 water LLD is only for groundwater samples locations 104 and 105 (see Table A-1)

A-a

TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 Sr-90 8 40 (a) For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCilL may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.

A-9

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 200B Annual Radiological Environmental Monitoring Program Summary ,

The results of the 200B radiological environmental sampling program are presented ,in Tables B-2 through B-21. Table B-2 is a summary table of the sample results for 200B. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.B (Reference 4),

and NRC Branch Technical Position to Regulatory Guide 4.B (Reference 14). In addition, the data obtained from the analysis of samples are provided in Tables B-3 through B-21.

REMP samples were analyzed by various counting methods as appropriate.

The methods are; gross beta, gamma spectroscopy analysis, liquid scintillation, radiochemical analysis, and TLD processing. Gamma spectroscopy analysis was performed for the following radionuclides; Be-7, K-40, Mn-54, Co-5B, Co-60, Fe-59, Zn-65, Zr-95, Nb-95, Ru-103,Ru-106, 1-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and AclTh-22B. Radiochemical analyses were performed for 1-131 and Sr-90 for specific media and locations as required in the ODCM.

B.2 Land Use Census In accordance with Sections IP2-D3.5.2 and IP3-2.B of the ODCM, a land use census was conducted to identify the nearest milch animal and the nearest residence. The results of the milch animal and land use census are presented in Tables B-22 and B-23, respectively. In lieu of identifying and sampling the nearest garden of greater than 50 m2 , at least three kinds of broad leaf vegetation were sampled near the site boundary in two sectors and at a designated control location (results are presented in Table B-14).

B.3 Sampling Deviations During 200B, environmental sampling was performed for 12 media types addressed in the ODCM and direct radiation. A total of 1223 samples/measurements were obtained without any deviation. 1243 were scheduled. Eighteen of the twenty deviations involved under-sampling at air monitoring stations - mostly from power outages affecting week-long sampling.

Of the scheduled samples/measurements, 9B.4% were performed for the program as intended. Sampling deviations are summarized in Table B-1.

Discussions of the reasons for the deviations are provided in Table B-1 a for air samples, B-1 b for TLDs and B-1c for other environmental media.

B.4 Analytical Deviations See Table B-1 c for analytical deviations information.

B.5 Special Reports No special reports were required under the REMP.

B-1

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2008 MEDIA PARTICULATES IN AIR 432 9 97.9% See Table B-1a CHARCOAL FILTER 432 9 97.9% N/A 164 2 99% Se Table B-1b HUDSON RIVER WATER 32 0 100% N/A DRINKING WATER 32 0 100% N/A SHORELINE SOIL 10 0 100% N/A BROAD LEAF ATION 54 0 100% N/A FISH & INVERTEBRATES 23 0 100% N/A AQUATIC VEGETATION 5 0 100% N/A HUDSON RIVER BOnOM 8 0 100% N/A SEDIMENT SOIL 3 0 100% N/A PRECIPITATION 8 0 100% N/A SPECIAL WATER PLES 40 0 100% N/A TOTALS 1243 20 98.4%

TOTAL NUMBER OF ANALYSES REPORTED = 1223

• Samples not collected, partially collected, or unable to be analyzed. Power outages at air samplers simultaneously affect the filter paper and charcoal media. Deviation is taken if sample run-time loss is significant.

8-2

TABLE B-1a I B-1b I B-1c TABLE B-1a 2008 Air Sampling Deviations

".'~l$jJ)~ml(jff~~:'~......,'.-

....~.. ;!i.t;;~l!~!=Et:s:;

".jW.)),

.. .... ", ...:il:;' 1_~~BQ~t:=J;M;!;'.(CmlaNSJ;9Je~t;\VlE~IJ~EGllJRRENE*ii;g;));;17\;'

ALGONQUIN 6/10/2008 105 sampling hours lost. Air sampler failed and required replacement. (CR-IP2-2008-03064)

CROTON POINT 6/10/2008 71 sampling hours lost due to induced power loss from electrical storm'(CR IP2-2008-03061 )

CROTON POINT 10/28/2008 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> lost; local overnight power outage noted.(CR-IP2-2008-04858)

GRASSY POINT 515/2008 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> lost; pump was running at beginning and end of week-long sampling period (CR-IP2-2008-02523)

MET TOWER 2112/2008 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> lost due to GFI trip over a weekend (CR-IP2-2008-00707)

MET TOWER 3/18/2008 53 hours6.134259e-4 days <br />0.0147 hours <br />8.763227e-5 weeks <br />2.01665e-5 months <br /> lost from tree falling on power lines (CR-IP2-2008-01270)

NYU 6/24/2008 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> lost on GFI trip, proable electrical storm ((CR-IP2-2008-03156)

Air sample was not running when we went to change it out. The pump had PEEKSKILL GAS HOLDER 1212212008 failed and we lost 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of sample this past week (CR-IP2-2008-03156)

TRAINING BUILDING 2/19/2008 91 hours0.00105 days <br />0.0253 hours <br />1.50463e-4 weeks <br />3.46255e-5 months <br /> lost due to power interruption; secondary power obtained for temporary use (CR-IP2-2008-00820)

TABLE B-1b 2008 TlD Deviations

'.($iFAlIfQN .j~; ... tj~~; QUABi!iER.$'~}l~";

,:cL_ .1*e8~!!~.5M!UA9:rIQNS)T9Pol~EY~Nifi~J::9.YJ~~REJitgE . . '

FURNACE DOCK 7/10/2008 (2nd) DR-34 missing with no apparent reason, but DR-34 placed in a more (Substation) secure location (CR-IP2-2008-03317)

RTE. 9D GARRISON 7/10/2008 (2nd) DR-17 missing on utility pole; fade TLD also missing; vehicle accident suspected of knocking items off the mounting pole (CR-IP2-2008-03317)

TABLE B-1c 2008 Other Media Deviations

.SWAml~~ .. ::S,,!,*:i" ,:t;;~i§~MBlEEtS-0J11EIDl!JI!E~;;t71\.ag(jSlEEMW1'<<CffilqNS'li0~pgE~EN[Jlt;.fYRR~N.~g~:2e!!:II Roseton Eel, Roseton August 2008 Required MDC (LLD) not met: target MDC is 5 pCi/kg and the attained Catfish, Roseton Blue Crab, MOC was up to 10 pCi/kg. In four sample analyses, however, the net signal Roseton Striped Bass, IPEC levels were negative. In the fifth sample, the net signal was positive and .

Striped Bass yielded a computed 1 pCi/kg concentration; the MOC for this sample was 6.7 pCi/kg. The basic data and results do not suggest significant or true deviations. In four other samples the required MOC was not met but the results were greater than attained MOC and reported as positive values.

The laboratory has been contacted.

B-3

TABLE B-2 (Continued) aDCM ANNUAL

SUMMARY

- 2008 DIRECT RADIATION (mR 1 standard quarter)

TLD Reads N/A 14.4 (160/160) /

West Shore Drive - North 1.21 Mi (W) at 276 0 DR13 I 17.3 (4/4) /

0 164 9.6 - 22.6 15.9 - 18.6 8-3 20.5 (4/4) / 18.0 - 22.6 AIR PARTICULATES #22 Lovett Power Plant 0.013 (380/380) / 0.014 (52152) /

AND RADIOIODINE G8 (432) 0.01 1.6 Mi (WSW) at 244 0 0 0.005 - 0.028 0.006-0.027 (pCilm 3) 8-6, 8-7, 8-8 0.015 (16/16) 1 0.003-0.025 1-131 (432) 0.07 <Lc <Lc <Lc 0 GSA (34) 0.05 <Lc <Lc <Lc 0 Cs-134 GSA (34) 0.06 <Lc <Lc <Lc 0 Cs-137 SURFACE HUDSON RIVER WATER (pC ilL) H-3 (8) 3000 (c) I <Lc <Lc <Lc 0 8-9,8-10 GSA (24)

Mn-54 15 <Lc <Lc <Lc 0 Co-58 15 <Lc <Lc <Lc 0 Fe-59 30 <Lc <Lc <Lc 0 Co-60 15 <Lc <Lc <Lc 0 Zn-65 30 <Lc <Lc <Lc 0 Zr/Nb-95 15 <Lc <Lc <Lc 0 1-131 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 8a/La-140 15 <Lc <Lc <Lc 0 (a) Positive values when above Lc; Groundwater positive when above MDC (b) Required a priori LLD; se Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCi/L 8-4

TABLE B-2 (Continued)

ODCM ANNUAL

SUMMARY

- 2008 DRINKING WATER H-3 (8) 2000 <Lc <Lc N/A N/A (pCi/L) 8-11,8-12 GSA (24)

Mn-54 15 <L" <L" N/A 0 Co-58 15 <Lc <Lc N/A 0 Fe-59 30 <Lc <Lc N/A 0 Co-60 15 <Lc <Lc N/A 0 Zn-65 30 <Lc <Lc N/A 0 Zr/Nb-95 15 <Lc <Lc N/A 0 1-131 15 <Lc <Lc N/A 0 Cs-134 15 <Lc <Lc N/A 0 Cs-137 18 <Lc <Lc N/A 0 8a/La-140 15 <Lc <Lc N/A 0 GSA (10)

HUDSON RIVER SHORELINE SOIL Cs-134 150 <Lc <Lc <Lc 0 (pCi/kg - dry) 8-13

1. 17 Off Verplanck #50 Manitou Inlet 4.48 163 (2/8) /

Cs-137 180 1.5 mi (SSW) at 202.5" mi. (NNW) at 347 0 I 0

<Lc -181 163 (2/2) / 141 - 184 236 (112)

Sr-90 (10) 5000 <Lc <Lc <Lc 0 (a) Positive values when above Lc; Groundwater positive when above MDC (b) Required a priori LLO; se Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pC ilL 8-5

TABLE B-2 (Continued) aDCM ANNUAL

SUMMARY

- 2008 8ROAOLEAF VEGETATION GSA (54)

(pCi/kg - wet) 8-14 1-131 60 <Lc <Lc <Lc 0 Co-60 N/A <Lc <Lc <Lc 0 Cs-134 60 <Lc <Lc <Lc 0 Cs-137 80 <Lc <Lc <L- 0 AND GSA (23)

INVERTE8RATES pCilkg (wet) 8-15 Mn-54 130 <Lc <Lc <Lc 0 Co-58 130 <Lc <Lc <Lc 0 Fe-59 260 <Lc <Lc* <Lc 0 Co-60 130 <Lc <Lc <Lc 0 2n-65 260 <Lc <Lc <Lc 0 Cs-134 130 <Lc <Lc _ <Lc 0 Cs-137 150 <Lc <Lc <Lc 0 B.B (2/6) / Vicinity of Plant - White Perch #23 Roseton 20 Mi (N) __I Sr-90 (12) 5 0

<Lc -10.3 8.8 (2/6) 7.3 - 10.3 3570 16.3 (12 - 20.6)

Ni-63 (12) N/A <MOC <MOC <MOC 0 AQUATIC VEGETATION GSA (5)

(pCilkg - WET) 8-16 Co-60 N/A <Lc <Lc <Lc 0

1. 17 Off Verplanck

1. 84 Cold Spring 10.9 54 (1/3) 1.5 mi (SSW) at 202S 1-131 N/A 54 (1/2) mi. (N) at 356 0

I 0 Lc - 54 35 (1/2)

<Lc - 54 Cs-134 N/A <Lc <Lc <Lc 0 Cs-137 N/A <Lc <Lc <Lc 0 (a) Positive values when above Lc; Groundwater positive when above MOC (b) Required a priori LLD; se Table A-2 (c) Not a drinking water pathway; the required LLO is 3000 pCilL 8-6

TABLE B-2 (Continued) aDCM ANNUAL

SUMMARY

- 2008 (pCilkg - DRY) 8-17 Co-50 N/A <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0

1. 28 Lents Cove 0.45 Mi 239 (6/6) /

Cs-137 180 (ENE) at 059 0 334 (2/2) 1 I < Lc 0 137 - 452 215 - 452 PRECIPITATION GSA (8)

(pC ilL) 8-18 H-3 3000 (c) <Lc <Lc <Lc 0 Co-50 15 <Lc <Lc <Lc 0 Cs-134 15 <Lc <Lc <Lc 0 Cs-137 18 <Lc <Lc <Lc 0 SOIL GSA (3)

(pCi/kg - DRY) 8-19 Co-50 N/A <Lc <Lc <Lc 0 Cs-134 150 <Lc <Lc <Lc 0 Cs-137 180 <Lc <Lc <Lc 0 (a) Positive values when above Lc; Groundwater positive when above MDC (b) Required a priori LLD; 5e Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCilL 8-7

TABLE B-2 (Continued) aDCM ANNUAL

SUMMARY

- 2008 GROUNDWATER GSA (40)

(pCilL) 244 (7140) 1 MW-51-40 0.18 mi (SSW)

B-20 H-3 (40) 3000 (c) N/A 0

< L c - 329 329 (1/4) 1 <Lc - 329 Co-50 (40) 15 <Lc <Lc N/A 0 Cs-134 (40) 15 <Lc <Lc N/A 0 Cs-137 (40) 18 <Lc <Lc N/A 0 Sr-90 (40) <Lc <Lc N/A 0 Ni-53 (24) <Lc <Lc N/A 0 (a) Positive values when above Lc; Groundwater positive when above MDC (b) Required a priori LLD; se Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pC ilL 8-8

TABLE B-3 2008 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER)

DR-01 N 15.25 +/- 1.69 16.59 +/- 0.64 14.65 +/- 0.85 16.09 +/- 0.66 15.6 62.6 DR-02 NNE 15.45 +/- 0.81, 15.12 +/- 0.59 12.62 +/- 0.52 16.64 +/- 1.89 15.0 59.8 DR-03 NE 12.52 +/- 0.68 12.72 +/- 0.55 10.32 +/- 0.51 12.95 +/- 0.62 12.1 48.5 DR-04 ENE 14.06 +/- 0.79 14.92 +/- 0.92 11.81 +/- 0.71 14.99 +/- 0.71 13.9 55.8 DR-05 ENE 14.01 +/- 0.91 14.75 +/- 0.84 12.49 +/- 0.70 15.43 +/- 0.70 14.2 56.7 DR-06 ESE 14.74 +/- 0.83 14.61 +/- 0.62 12.59 +/- 0.89 15.47 +/- 0.85 14.4 57.4 DR-07 SE 16.32 +/- 0.89 18.07 +/- 1.71 14.16 +/- 0.74 18.04 +/- 1.71 16.6 66.6 DR-08 SSE 12.88 '+/- 1.22 13.23 +/- 0.57 10.97 +/- 0.74 13.53 +/- 0.86 12.7 50.6 DR-09 S 14.15 +/- 0.77 14.08 +/- 0.82 11.65 +/- 0.68 15.06 +/- 0.62 13.7 54.9 DR-10 SSW 14.98 +/- 1.01 15.14 +/- 0.67 12.72 +/- 0.55 15.91 +/- 1.45 14.7, 58.8 DR-11 SW 11.58 +/- 0.65 . 11.84 +/- 0.84 9.56 +/- 0.63 12.48 +/- 0.75 11.4 45.5 DR-12 WSW 15.31 +/- 0.65 16.79 +/- 1.17 13.47 +/- 0.71 17.57 +/- 0.72 15.8 63.1 DR-13 WSW 20.91 +/- 2.29 20.52 +/- 0.62 18.05 +/- 0.86 22.64 +/- 0.78 20.5 82.1 DR-14 WNW 13.26 +/- 0.63 14.78 +/- 0.78 12.07 +/- 0.56 15.16 +/- 1.00 13.8 55.3 DR-15 NW 12.86 +/- 0.55 14.46 +/- 0.85 11.61 +/- 0.54 14.66 +/- 0.59 13.4 53.6 DR-16 NNW 13.79 +/- 0.78 15.75 +/- 0.92 13.13 +/- 0.55 16.68 +/- 1.11 14.8 59.4 DR-17 N 13.81 +/- 0.69 12.77 +/- 0.56 16.03 +/- 0.69 14.2 42.6 DR-18 NNE 15.03 +/- 0.69 15.12 +/- 0.66 13.02 +/- 0.65 15.38 +/- 0.53 14.6 58.6 DR-19 NE 15.22 +/- 0.73 15.75 +/- 0.67 13.64 +/- 0.54 16.10 +/- 0.73 15.2 60.7 DR-20 ENE 14.15 +/- 0.75 14.21 +/- 0.66 12.21 +/- 0.63 14.63 +/- 1.13 13.8 55.2 DR-21 E 14.82 +/- 1.08 15.03 +/- 0.63 12.63 +/- 0.74 15.03 +/- 0.61 14.4 57.5 DR-22 ESE 12.27 +/- 0.68 12.41 +/- 0.57 9.57 +/- 0.44 12.25 +/- 0.62 11.6 46.5 DR-23 SE 15.05 +/- 0.66 14.65 +/- 0.84 12.27 +/- 0.60 16.08 +/- 0.91 14.5 58.1 DR-24 SSE 15.31 +/- 0.80 15.00 +/- 0.89 12.62 +/- 0.58 15.99 +/- 1.18 14.7 58.9 DR-25 S 11.94 +/- 0.55 13.40 +/- 0.71 10.90 +/- 0.46 14.16 +/- 0.54 12.6 50.4 DR-26 SSW 13.48 +/- 0.90 14.54 +/- 0.59 12.05 +/- 0.52 15.60 +/- 0.71 13.9 55.7 DR-27 SW 13.17 +/- 1.00 13.72 +/- 0.94 11.88 +/- 0.52 14.88 +/- 0.63 13.4 53.7 DR-28 NW 18.86 +/- 1.62 20.31 +/- 0.92 18.04 +/- 0.77 21.25 +/- 0.95 19.6 78.5 DR-29 W 13.67 +/- 0.63 15.39 +/- 0.94 13.05 +/- 0.54 15.69 +/- 1.12 14.5 57.8 DR-30 SNS 13.78 +/- 0.83 15.20 +/- 0.93 13.69 +/- 1.61 16.34 +/- 0.86 14.8 59.0 DR-31 WSW 16.17 +/- 0.96 17.13 +/- 0.74 .14.72 +/- 0.62 17.30 +/- 0.90 16.3 65.3 DR-32 NNW 12.95 +/- 0.80 14.64 +/- 0.72 11.08 +/- 0.48 14.31 +/- 0.87 13.2 53.0 DR-33 NE 14.79 +/- 1.17 14.15 +/- 0.85 11.83 +/- 0.51 14.09 +/- 0.87 13.7 54.9 DR-34 SE 13.08 +/- 0.56 11.47 +/- 0.45 13.92 +/- 0.75 12.8 38.5 DR-35 NNE 13.60 +/- 0.57 14.05 +/- 0.88 11.49 +/- 0.62 14.27 +/- 0.91 13.4 53.4 DR-36 NE 15.80 +/- 0.80 15.08 +/- 1.07 13.05 +/- 0.72 16.24 +/- 0.92 15.0 60.2 DR-37 SSW 14.64 +/- 0.88 15.11 +/- 1.64 12.14 +/- 0.46 16.09 +/- 0.94 14.5 58.0 DR-38 S 13.86 +/- 1.41 14.58 +/- 0.95 12.57 +/- 0.66 14.97 +/- 0.85 14.0 56.0 DR-39 SSW 14.57 +/- 0.63 15.75 +/- 0.70 13.57 +/- 0.59 16.10 +/- 0.83 15.0 60.0 DR-40** N 18.10 +/- 1.72 18.62 +/- 1.00 15.91 +/- 0.64 16.73 +/- 0.56 17.3 69.4 DR-41 SSE 13.13 +/- 0.56 10.15 +/- 0.55 11.27 +/- 0.60 13.86 +/- 0.52 12.1 48.4

• Data not available

• • Control Location 8-9

TABLE B-4 DIRECT RADIATION 1998 THROUGH 2008 DATA (mR per standard quarter basis)

DR-01 62.9 2.8 58.4 68.0 62.6 DR-02 62.4 8.9 53.6 79.2 59.8 DR-03 47.9 1.9 44.0 50.0 48.5 DR-04 53.7 3.6 46.8 58.8 55.8 DR-05 54.3 2.4 48.4 57.2 56.7 DR-06 53.8 3.0 46.4 56.8 57.4 DR-07 63.6 3.6 55.6 68.8 66.6 DR-08 51.7 2.9 47.2 56.4 50.6 DR-09 53.0 3.0 47.2 58.0 54.9 DR-10 56.5 2.2 53.2 60.0 58.8 DR-11 45.0 2.3 40.8 48.4 45.5 DR-12 67.5 3.5 62.4 76.0 63.1 DR-13 76.1 3.9 68.0 81.2 82.1 DR-14 53.9 3.0 50.0 60.4 55.3 DR-15 54.2 4.0 46.4 60.0 53.6 DR-16 59.6 2.8 55.2 63.6 59.4 DR-17 60.4 2.9 56.4 66.8 42.6 DR-18 56.8 2.5 52.4 60.8 58.6 DR-19 59.7 2.5 55.2 62.8 60.7 DR-20 54.4 3.7 47.6 59.2 55.2 DR-21 55.2 3.1 50.0 60.8 57.5 DR-22 46.4 3.4 40.4 52.0 46.5 DR-23 55.9 2.8 49.6 58.8 58.1 DR-24 56.3 2.9 49.2 60.0 58.9 DR-25 49.6 2.3 44.8 52.8 50.4 DR-26 55.4 2.8 50.4 58.8 55.7 DR-27 55.4 3.9 46.8 61.6 53.7 DR-28 66.3 7.8 57.2 78.8 78.5 DR-29 65.4 8.6 54.8 77.2 57.8 DR-30 63.3 6.2 52.4 71.2 59.0 DR-31 72.0 5.8 62.0 80.4 65.3 DR-32 53.0 3.3 46.0 57.2 53.0 DR-33 45.5 9.2 34.0 55.2 54.9 DR-34 53.0 4.6 43.2 60.8 38.5 DR-35 56.6 4.0 48.8 61.2 53.4 DR-36 61.4 4.9 52.4 70.4 60.2 DR-37 54.6 3.0 48.8 58.8 58.0 DR-38 52.2 2.8 48.8 58.4 56.0 DR-39 62.4 4.1 55.2 66.8 60.0 DR-40" 63.6 6.1 54.8 75.2 69.4 DR-41 52.4 3.8 44.4 58.0 48.4

• • Control Location 8-10

TABLE B-5 2008 DIRECT RADIATION Inner and .Outer Rings (mR per standard quarter basis) 8-11

TABLE B-6 IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2008 3

.GROSS BET A ACTIVITY pCiI m +/- 1 Sigma SAMPLE STATION #

.. ;.<,...t>"~ ,,.,,.,"'<\""'> *.*. *. ,.,':",':,,"'.,',, :',:,.

l~i;~l~~i::

<,~

',.:4,,",':\

• • • • • • 95/'*;'* '. .\':.<"'" 'i*t:~!'@lj*~' ", 1:':':';27 \:',(

.;: :.*,': ' .*,.,:. ~:':4:~,'!:J,.,:;i: ,*'!

~' ,::" "",':' ',.:,.,.:;.:,:',"':'" ""'.'>." '.':' ;.',:" .....

I 118/2008 0.024 +/- 0,002 0.024 +/- 0.001 0.025 +/- 0.002 0.023 +/- 0,002 0.024 +/- 0.002 0,025 +/- 0,002 0.023 +/- 0,001 0,018 +/- 0,001 0.023 +/- 0,002 2 III 5/2008 0.009 +/- 0,001 0.010 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0,001 0.014 +/- 0,001 0,013 +/- 0,001 0.010 +/- 0,001 0,022 +/- 0,002 0.011 +/- 0,001 3 1122/2008 0.018 +/- 0,001 0.019 +/- 0.001 0.016 +/- 0.001 0.018 +/- 0,001 0.016 +/- 0.001 am 7 +/- 0,001 0,016 +/- 0,001 0.012 +/- 0,001 0,016 +/- 0.001 4 1129/2008 0.020 +/- 0.002 0.023 +/- 0.002 0.017 +/- 0,001 0,019 +/- 0,002 0.017 +/- 0,001 0,021 +/- 0,002 0,021 +/- 0.001 0.016 +/- 0,001 0,020 +/- 0.002 5 2/5/2008 0.022 +/- 0.002 0.022 +/- 0.002 0.020 +/- 0,002 0.024 +/- 0.002 0.027 +/- 0,002 0,024 +/- 0,002 0,020 +/- 0.002 0.021 +/- 0.001 0,020 +/- 0.002 6 2/12/2008 0.016 +/- 0.001 0.019 +/- 0,001 oms +/- 0,001 0,010 +/- 0.001 0,012 +/- 0,001 0,017 +/- 0,001 0,01 7 +/- 0.001 0.022 +/- 0.001 0,016 +/- 0.001 7 2119/2008 0,014 +/- 0.001 0.013 +/- 0.001 0,020 +/- 0.002 0,014 +/- 0.001 0,015 +/- 0,001 0,015 +/- 0.001 0,013 +/- 0.001 0.015 +/- 0.001 0,017 +/- 0.001 8 2/26/2008 oms +/- 0,001 0.012 +/- 0.001 0,014 +/- 0,001 0,012 +/- 0.001 0,016 +/- 0,001 0,012 +/- 0.001 0,015 +/- 0.001 0,016 +/- 0.001 0,015 +/- 0.001 9 3/4/2008 0,014 +/- 0.001 0,012 +/- 0.001 0,013 +/- 0,001 0,012 +/- 0.001 0,013 +/- 0,001 0.014 +/- 0.001 amI +/- 0,001 0,016 +/- 0.001 0,010 +/- 0,001 10 311 112008 0,013 +/- 0,001 0.010 +/- 0,001 0,012 +/- 0,001 am 1 +/- 0.001 0,014 +/- 0,001 0.014 +/- 0.001 am 1 +/- 0,00 1 oms +/- 0.001 0.011 +/- 0,001 11 311812008 0,013 +/- 0,001 0,012 +/- 0.001 0,014 +/- 0,001 0,008 +/- 0.002 0,013 +/- 0.001 0.015 +/- 0,001 0,016 +/- 0,001 0,013 +/- 0,001 0.013 +/- 0,001 12 3/25/2008 0,012 +/- 0,001 0,011 +/- 0,001 0,010+/- 0,001 0,010 +/- 0,001 0,011 +/- 0.001 0.013 +/- 0,001 0,012 +/- 0,001 0,014 +/- 0,001 0.011 +/- 0,001 13 4/112008 0,012 +/- 0,001 am 1 +/- 0.001 0,014 +/- 0,001 0,013 +/- 0,001 0.011 +/- 0.001 0,012 +/- 0,001 0.011 +/- 0,001 0,010 +/- 0,001 0,015 +/- 0.001 14 4/8/2008 0,009 +/- 0,001 0,009 +/- 0,001 0,008 +/- 0,001 0.009 +/- 0,001 0,009 +/- 0.001 0,012 +/- 0,001 0.010 +/- 0,001 0,013 +/- 0,001 0,010 +/- 0.001 15 4/1512008 0,007 +/- 0,001 0,005 +/- 0,001 0,006 +/- 0,001 0.005 +/- 0,001 0,006 +/- 0.001 0,008 +/- 0,001 0.006 +/- 0.001 0.009 +/- 0,001 0,006 +/- 0.001 16 4/22/2008 0,0 19 +/- 0,002 oms +/- 0,001 0,015 +/- 0,001 am 8 +/- 0,002 oms +/- 0,001 0,012 +/- 0,002 0.013 +/- 0.001 0.007 +/- 0,001 0,017 +/- 0.001 17 4/29/2008 0,010 +/- 0,001 0,013 +/- 0,001 0,011 +/- 0.001 0.011 +/- 0,001 0.015 +/- 0,001 0.013 +/- 0.001 0.013 +/- 0,001 0,015 +/- 0,001 18 5/6/2008 0.015 +/- 0,001 0,015 +/- 0,001 0,013 +/- 0.001 0.014 +/- 0,001 0.010 +/- 0,001 oms +/- 0.001 0,015 +/- 0.001 0,011 +/- 0,001 19 5/13/2008 0.012 +/- 0,001 0,012 +/- 0,001 0,011 +/- 0.001 0.013 +/- 0,001 0.014 +/- 0,001 0,013 +/- 0.001 0,007 +/- 0.001 0,014 +/- 0,001 20 5120/2008 0.011 +/- 0,001 0,010 +/- 0,001 0,009 +/- 0,001 0.011 +/- 0,001 0.013 +/- 0,001 0,009 +/- 0,001 0,013 +/- 0.001 0,010 +/- 0,001 21 5/27/2008 0.008 +/- 0.001 0,007 +/- 0,001 0,007 +/- 0,001 0,009 +/- 0,001 0.008 +/- 0,001 0,007 +/- 0,001 0,009 +/- 0.001 0.010 +/- 0,001 22 6/312008 0.013 +/- 0.001 0,014 +/- 0,001 0.014 +/- 0.001 0,014 +/- 0,001 0,014 +/- 0,001 0,013 +/- 0,001 0,006 +/- 0.001 0.015 +/- 0.001 23 6110/2008 0.008 +/- 0.002 0.009 +/- 0,001 0.008 +/- 0,001 0,010 +/- 0,001 0.009 +/- 0,001 0,009 +/- 0,002 0,013 +/- 0.001 0.010 +/- 0.001 24 6/17/2008 0.014 +/- 0.001 0.013 +/- 0,001 0.014 +/- 0,001 0,015 +/- 0.001 0.015 +/- 0.001 0,013 +/- 0,001 0,009 +/- 0,001 0.013 +/- 0.001 25 6124/2008 0.011 +/- 0.001 0.006 +/- 0,001 0,008 +/- 0,001 0,008 +/- 0.001 0,009 +/- 0.001 0,008 +/- 0,001 0.014 +/- 0,001 0.007 +/- 0.001 26 7/1/2008 0.015 +/- 0.001 0.012 +/- 0,001 0.012 +/- 0,001 0,011 +/- 0.001 0,015 +/- 0.001 0.015 +/- 0.001 0.011 +/- 0,001 0,015 +/- 0.001

• • Control sample location 8-12

TABLE B-6 (Continued)

IPEC ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 2008 GROSS BETA ACTIVITY pCi/ m3 +/- 1 Sigma

': :': : : :, SAMPLE STATION #

R~

• 'i:H;,::"iC.*,:*:** ...,;,',. I.""." .,;y*.*.m;,',,',',:,:':, .':::, .... ' , : ' " ..,.:':"':' ......, ' . . , : . ' > , ' , : : t:;:::::ii:'Y:::~i!!i!

1:;*****9~;:;>":*',:,f,2\'ii::;::' :": i,,:(*"

• 27 7/812008 0.012 +/- 0.001 H'::~:::,;;::::5"""'>';:."::'OA':\'"

• .**:; I.i?")::{i::.:; ....*,.,.'./:;::'::; ,***:****:*:,:E""':;; I'" .<:"';",':""

0.010 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.001

.,:. I.t:,,:,,

c::

0.013 +/- 0.001 i)"~,

""", )i29':':I:.::::;:,A4 0.014 +/- 0.001 0.011 +/- 0.001 28 711512008 0.011 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 29 7/2212008 0.023 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.001 0.025 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.002 0.019 +/- 0.001 0.022 +/- 0.002 30 7/29/2008 oms +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 oms +/- 0.001 0.014 +/- 0.001 oms +/- 0.001 oms +/- 0.001 0.012 +/- 0.001 31 8/512008 0.012 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 oms +/- 0.001 oms +/- 0.001 32 8112/2008 0.009 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.008 +/- 0.001 33 8/1912008 0.013 +/- 0.001 0.014 +/- 0.001 0.017 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.001 0.017 +/- 0.002 34 8126/2008 0.012 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.011 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 35 91212008 0.011 +/- 0.001 0.010 +/- 0.001 0.014 +/- 0.001 oms +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 36 91912008 0.016 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 om8 +/- 0.001 0.019 +/- 0.002 0.014 +/- 0.001 0.017 +/- 0.001 0.016 +/- 0.002 37 9116/2008 0.010 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.011 +/- 0.001 0.009 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 38 9/23/2008 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.007 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.009 +/- 0.001 39 913012008 0.008 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.001 0.005 +/- 0.001 40 101712008 0.012 +/- 0.001 0.012 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 41 1011412008 0.022 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.021 +/- 0.002 0.021 +/- 0.002 0.023 +/- 0.002 0.020 +/- 0.001 0.018 +/- 0.002 42 10/2112008 0.013 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.010 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 43 10/2812008 0.010 +/- 0.001 0.010 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 44 111412008 oms +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 oms +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 45 11110/2008 0.017 +/- 0.002 0.015 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.015 +/- 0.001 0.012 +/- 0.061 oms +/- 0.001 0.015 +/- 0.001 46 1111812008 0.005 +/- 0.001 0.006 +/- 0.001 0.005 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 47 11124/2008 0.009 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.012 +/- 0.001 48 121212008 0.017 +/- 0.001 oms +/- 0.001 0.017 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 oms +/- 0.001 0.017 +/- 0.001 49 12/912008 0.012 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 50 12115/2008 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 0.011+/- 0.001 0.012 +/- 0.001 51 12/2312008 0.014 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 oms +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 52 12/30/2008 0.028 +/- 0.002 0.026 +/- 0.002 0.023 +/- 0.002 0.025 +/- 0.002 0.022 +/- 0.001 0.026 +/- 0.002 0.022 +/- 0.001 0.023 +/- 0.002

• • Control sample location 8-13

TABLE B-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 1 E-3 pCil m3 +/- 1 Sigma Nuciide Algonquin Sta #4 NYU Tower #5 Croton Point #27 Training Bldg #94 Met Tower #95 Lovett #22 Roseton#23** Grassy Point #29 Peekskill #44 .

Be-7 120.4 +/- 14.2 129.1 +i- 13.5 88.7 +/- 13.9 102.0 +/- 12.5 108.1 +/- 13.8 105.5 +/- 12.9 138.0 +/- 28.6 112.9 +/- 13.6 130.4 +/- 12.5 Cs-134 < 0.7 < 0.7 < 1.2 < 0.7 < 0.5 < 0.9 < 2.5 < 0.8 < 0.5 Cs-137 < 0.5 < 0.4 < 0.8 < 0.5 < 0.5 < 0.8 < 3.5 < 0.7 < 0.5 Zr-95 < 1.2 < 1.3 < 1.7 < 1.6 < 1.8 < 1.7 < 4.3 < 2.1 < 1.1 Nb-95 < 1.4 < 1.1 < 2.2 < 0.6 < 0.6 < 2.0 < 5.3 < 1.5 < 1.1 Co-58 < 0.7 < 1.4 < 1.0 < 0.5 < 0.8 < 0.6 < 3.0 < 0.9 < 0.6 Mn-54 < 0.4 < 0.7 < 0.5 < 0.4 < 0.5 < 0.9 < 2.2 < 0.7 < 0.6 Zn-65 < 2.1 < 1.2 < 2.9 < 1.7 < 1.7 < 1.8 < 3.5 < 1.9 < 1.0 Co-60 < 0.6 < 0.4 < 1.3 < 0.6 < 0.4 < 0.6 < 2.1 < 0.5 < 0.3 K-40 49.0 +/- 10.1 < 5.9 64.0 +/- 14.0 < 5.8 < 8.2 < 6.2 < 31.1 54.4 +/- 10.6 < 3.4 SAMPLE LOCATIONS - 2ND QTR 2008 Nuclide *AlgonquinSta #4 NYU Tower #5 . Croton Point#27 Training Bldg #94 Met Tower #95 Lovett #22~ Roseton#23** . Grassy Point #29 Peekskill #44 Be-7 142.5 +/- 14.4 109.8 +/- 16.5 126.8 +/- 13.8 144.2 +/- 13.6 129.6 +/- 14.6 138 +/- 29 101.7 +/- 14.2 99.9 +/- 11.1 172.3 +/- 19.6 Cs-134 < 0.8 < 1.0 < 0.7 < 0.8 < 0.8 < 2.5 < 1.2 < 0.4 < 0.7 Cs-137 < 0.5 < 0.4 < 0.7 < 0.4 < 0.6 < 3.5 < 0.8 < 0.5 < 0.8 Zr-95 < 1.4 < 2.4 < 1.3 < 1.2 < 0.9 < 4.3 < 1.9 < 1.3 < 3.3 Nb-95 < 1.3 < 2.6 < 1.6 < 1.0 < 0.7 < 5.3 < 2.2 < 1.3 < 2.3 Co-58 < 0.9 < 1.2 < 0.8 < 0.6 < 0.7 < 3 < 0.9 < 0.5 < 0.7 Mn-54 < 0.9 < 0.7 < 0.6 < 0.7 < 0.5 < 2.2 < 0.8 < 0.6 < 0.9 Zn-65 < 1.7 < 3.5 < 1.6 < 1.4 < 2.1 < 3.5 < 2.1 < 1.9 < 2.7 Co-60 < 0.9 < 1.0 < 0.7 < 0.4 < 0.8 < 2.1 < 0.7 < 0.6 < 1.0 K-40 < 4.3 87.3 +/- 17.3 < 5.5 < 5.6 < 10.0 < 31.1 53.8 +/- 11.8 < 3.3 92.3 +/- 17.9

• 3 samples

• • Control Sample Location 8-14

TABLE B-7 CONCENTRATIONS OF GAMMA EMITIERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 1E-3 pCi/ m3 +/- 1 Sigma SAMPLE LOCATIONS - 3RD QTR 2008 Nuclide Algonql,Ji ll Sta #,4 NYU Tower #5 . Croton Point #2.1 Training Bldg #9.4 Met Tower #95 . Lovett #22 ~oseton #23** c:;rassyPoint #29 . Peekskill #44

...cC Be-7 135.1 +/- 13.3 105.7 +/- 14.0 99.3 +/- 13.1 110.4 +/- 14.4 137.0 +/- 16.1 retired 115.2 +/- 11.1 123.8 +/- 10.3 111.4 +/- 12.5 Cs-134 < 0.7 < 0.6 < 0.6 < 0.9 < 1.2 < 0.4 < 0.4 < 0.8 Cs-137 < 0.3 < 0.5 < 0.5 < 0.6 < 0.8 < 0.2 < 0.3 < 0.5 Zr-95 < 1.7 < 1.2 < 1.8 < 2.0 < 2.2 < 1.0 < 0.8 < 1.1 Nb-95 < 0.8 < 0.9 < 0.7 < 1.4 < 2.0 < 0.8 < 0.8 < 0.9 Co-58 < 0.5 < 0.8 < 0.9 < 0.8 < 0.7 < 0.7 < 0.5 < 0.6 Mn-54 < 0.6 < 0.4 < 0.5 < 0.6 < 0.6 < 0.4 < 0.4 < 0.5 Zn-65 < 1.4 < 1.5 < 2.2 < 1.5 < 2.1 < 0.8 < 0.9 < 1.8 Co-60 < 0.8 < 0.7 < 0.7 < 0.8 < 0.8 < 0.4 < 0.4 < 0.7 K-40 < 4.0 < 5.3 < 4.8 36.7 +/- 9.6 68.7 +/- 16.1 < 5.2 < 5.0 < 4.3 SAMPLE LOCATIONS

---

---_ - 4TH

. _QTR

--- 2008 ---

Nuclide Algonquin Sta #4 NYU Tower #5 Croton Point#27 Training I?,ldg. #94 . . Met tower#9~ '.' Lovett #22 Roseton#23** Grassy Point#29l Peekskill #44 Be-7 64.4 +/- 15.1 58.4 +/- 10.0 100.2 +/- 11.4 97.6 +/- 11.6 90.9 +/- 11.5 retired 91.5 +/- 12.4 114.2 +/- 10.8 100.0 +/- 15.6 Cs-134 < 0.9 < 0.8 < 0.7 < 0.5 < 0.9 < 1.0 < 0.7 < 0.8 Cs-137 < 1.0 < 0.7 < 0.4 < 0.7 < 0.4 < 0.4 < 0.4 < 0.4 Zr-95 < 2.3 < 1.0 < 0.8 < 1.6 < 1.7 < 2.0 < 1.4 < 1.7 Nb-95 < 3.1 < 1.3 < 1.0 < 0.6 < 1.4 < 1.0 < 0.9 < 2.2 Co-58 < 1.7 < 0.8 < 0.8 < 0.8 < 0.6 < 1.1 < 0.4 < 1.8 Mn-54 < 0.9 < 0.4 < 0.6 < 0.5 < 0.8 < 0.6 < 0.4 < 1.0 Zn-65 < 4.0 < 1.6 < 0.9 < 1.2 < 1.7 < 1.0 < 0.9 < 3.5 Co-60 < 1.5 < 0.6 < 0.4 < 0.7 < 0.4 < 0.9 < 0.3 < 0.8 K-40 91.4 +/- 16.4 < 7.9 < 4.5 < 5.0 < 5.9 35.7 +/- 9.4 < 3.4 90.8 +/- 16,6

• • Control Sample Location B-15

TABLE B-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2008 3

1-131 ACTIVITY pCiI m +/- 1 Sigma 01115108 < 0.025 < 0.040 < 0.023 < 0.026 < 0.026 < 0.040 < 0.025 < 0.032 < 0.036 3 01122/08 < 0.008 < 0.032 < 0.023 < 0.028 < 0.022 < 0.026 < 0.022 < 0.Q]5 < 0.027 4 01129/08 < 0.027 < 0.024 < 0.032 < 0.036 < 0.039 < 0.041 < 0.024 < 0.028 < 0.032 5 02/05108 < 0.025 < 0.026 < 0.029 < 0.020 < 0.038 < 0.032 < 0.020 < 0.024 < 0.038 6 02/12/08 < 0.027 < 0.021 < 0.025 < 0.037 < 0.032 < 0.046 < 0.025 < 0.026 < 0.035 7 02/19/08 < 0.026 < 0.023 < 0.067 < 0.033 < 0.022 < 0.027 < 0.029 < 0.Q]5 < 0.027 8 02/26/08 < 0.031 < 0.029 < 0.025 < 0.024 < 0.027 .< 0.042 < 0.028 < 0.021 < 0.032 9 03/04/08 < 0.023 < 0.025 < 0.026 < 0.024 < 0.041 . < 0.045 < 0.036 < 0.023 < 0.028 10 03111108 < 0.035 < 0.038 < 0.026 < 0.041 < 0.025 < 0.053 < 0.022 < 0.012 < 0.039 11 03118/08 < 0.052 < 0.040 < 0.017 < 0.042 < 0.030 < 0.054 < 0.022 < 0.016 < 0.042 12 03/25108 < 0.032 < 0.006 < 0.025 < 0.032 < 0.026 < 0.030 < 0.050 < 0.023 < 0.036

. 13 04/01/08 < 0.030 < 0.020 < 0.026 < 0.038 < 0.040 < 0.028 < 0.030 < 0.021 < 0.046 14 04/08/08 < 0.030 < 0.028 < 0.006 < 0.006 < 0.029 < 0.038 < 0.041 < 0.024 < 0.047 15 04/15108 < 0.020 < 0.032 < 0.019 < 0.007 < 0.030 < 0.031 < 0.016 < 0.030 < 0.034 16 04/22/08 < 0.026 < 0.034 < 0.027 < 0.044 < 0.044 < 0.065 < 0.022 < 0.017 < 0.019 17 04/29/08 < 0.024 < 0.032 < 0.014 < 0.022 < 0.030 < 0.024 < 0.022 < 0.039 18 05106/08 < 0.017 < 0.029 < 0.024 < 0.035 < 0.028 < 0.024 < 0.032 < 0.028 19 05/13/08 < 0.037 < 0.021 < 0.021 < 0.033 < 0.034 < 0.035 < 0.022 < 0.037 20 05120108 < 0.033 < 0.029 < 0.025 < 0.039 < 0.042 < 0.034 < 0.024 < 0.045 21 05127/08 < 0.032 < 0.022 < 0.027 < 0.039 < 0.038 < 0.007 < 0.020 < 0.029 22 06/03/08 < 0.023 < 0.034 < 0.016 < 0.034 < 0.040 < 0.024 < 0.036 < 0.040 23 06110108 < 0.064 < 0.029 < 0.028 < 0.029 < 0.036 < 0.049 < 0.029 < 0.037 24 06117/08 < 0.Q]8 < 0.036 < 0.031 < 0.036 < 0.032 < 0.022 < 0.Q]8 < 0.026 25 06/24/08 < 0.032 < 0.041 < 0.028 < 0.023 < 0.036 < 0.017 < 0.025 < 0.038 26 07/01108 < 0.033 < 0.016 < 0.034 < 0.036 < 0.037 < 0.025 < 0.028 < 0.035

• • Control sample location B-16

TABLE B-8 (Continued)

IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2008 3

1-131 ACTIVITY pCil m +/- 1 Sigma 07/15/08 < 0.033 < 0.043 < 0.022 < 0.027 < 0.038 < 0.027 < 0.022 < 0.044 29 07/22/08 < 0.020 < 0.035 < 0.023 < 0.024 < 0.024 < 0.033 < 0.028 < 0.044 30 07/29/08 < 0.013 < 0.026 < 0.010 < 0.025 < 0.033 < 0.014 < 0.020 < 0.035 31 08/05/08 < 0.052 < 0.025 < 0.032 < 0.030 < 0.056 < 0.020 < 0.015 < 0.029 32 08/11/08 < 0.043 < 0.031 < 0.030 < 0.028 < 0.026 < 0.047 < 0.028 < 0.024

\

33 08119108 < 0.032 < 0.031 < 0.026 < 0.021 < 0.039 < 0.029 < 0.045 < 0.049 34 08/26/08 < 0.024 < 0.016 < 0.032 < 0.026 < 0.028 < 0.017 < 0.023 < 0.037 35 09/02/08 < 0.032 < 0.026 < 0.019 < 0.006 < 0.025 < 0.020 < 0.020 < 0.024 36 09/09/08 < 0.042 < 0.014 < 0.023 < 0.020 < 0.034 < 0.027 < 0.038 < 0.027 37 09/16/08 < 0.032 < 0.025 < 0.021 < 0.022 < 0.028 < 0.022 < 0.027 < 0.023 38 09/23/08 < 0.038 < 0.021 < 0.016 < 0.025 < 0.032 < 0.025 < 0.039 < 0.019 39 09/30108 < 0.030 < 0.023 < 0.023 < 0.022 < 0.028 < 0.010 < 0.028 < 0.024 40 10107/08 < 0.029 < 0.021 < 0.029 < 0.025 < 0.040 < 0.022 < 0.033 < 0.038 41 10/14108 < 0.022 < 0.030 < 0.025 < 0.Ql8 < 0.039 < 0.034 < 0.Ql5 < 0.Ql8 42 10/21108 < 0.023 < 0.021 < 0.031 < 0.023 < 0.035 < 0.025 < 0.046 < 0.037 43 10/28/08 < 0.037 < 0.049 < 0.028 < 0.023 < 0.033 < 0.052 < 0.025 < 0.057 44 11104108 < 0.036 < 0.028 < 0.027 < 0.030 < 0.039 < 0.023 < 0.016 < 0.032 45 11110108 < 0.039 < 0.034 < 0.036 < 0.030 < 0.035 < 0.038 < 0.023 < 0.028 46 11118/08 < 0.028 < 0.041 < 0.013 < 0.026 < 0.033 < 0.024 < 0.033 < 0.057 47 11124/08 < 0.028 < 0.025 < 0.021 < 0.024 < 0.024 < 0.019 < 0.019 < 0.019 48 12/02/08 < 0.021 < 0.022 < 0.005 < 0.019 < 0.040 < 0.022 < 0.041 < 0.029 49 12/09/08 < 0.023 < 0.038 < 0.023 < 0.021 < 0.037 < 0.016 < 0.030 < 0.036 50 12115108 < 0.031 < 0.030 < 0.021 < 0.023 < 0.026 < 0.024 < 0.014 < 0.019 51 12/23/08 < 0.052 < 0.023 < 0.029 < 0.041 < 0.030 < 0.030 < 0.025 < 0.053 52 12/30108 < 0.021 < 0.026 < 0.036 < 0.033 < 0.028 < 0.036 < 0.044 < 0.031

• • Control sample location 8-17

TABLE B-9 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2008 Results in Units ofpCilliter +/- 1 Sigma

1. 9 PLANT INLET (HUDSON RIVER INTAKE) 1-131 < 5.96 < 6.97 < 4.85 < 7.03 < 7.16 < 5049 Cs-134 < 1.50 < 1046 < 1.37 < 0.91 < 0.70 < 0.95 Cs-137 < 1.32 < 1.35 < 1.17 < 1.50 < 0.95 < 1.21 Zr-95 < 3.18 < 2.67 < 2.33 < 2.97 < 1.98 < 2.70 Nb-95 < 2.29 < 1.90 < 1.70 < 1.80 < 1.51 < 1.66 Co-58 < 1.76 < 1048 < 1.28 < 1.66 < 1.09 < 1.36 Mn-54 < 1.69 < 1.17 < 0.98 < 1.53 < 1.01 < 1.37 Fe-59 < 5.38 < 3.77 < 3.51 < 3.98 < 3.23 < 3.55 Zn-65 < 3.31 < 3.l6 < 2.75 < 1.58 < 1.28 < 3.58 Co-60 < 1.72 < 0.90 < 1.18 < 1.28 < 0.87 < lAO K-40 183.9 +/- 19.01 97.05 +/- 12.98 26.52 +/- 9.28 < 12.83 44.l1 +/- 8.56 53.3 +/- 12.75 BalLa-140 < 4.74 < 4.25 < 3.63 < 4.12 < 4.00 < 3.75 1-131 < 6.96 < 4.90 < 4.60 < 6.67 < 6.73 < 4.06 Cs-134 < 1.09 < 1.25 < 0.80 < 0.80 < 1.01 < 0.86 Cs-137 < 1.75 < 1.06 < 1.14 < 1.19 < 0.85 < 0.76 Zr-95 < 3043 < 2.02 < 2.l4 < 2.62 < 1.99 < 1.55 Nb-95 < 2.65 < 1.28 < 1.01 < 1.72 < 1.39 < 1.15 Co-58 < 2.10 < 1.25 < 1.39 < 1048 < 1.15 < 0.80 Mn-54 < 1.71 < 1.18 < 1.20 < 1.28 < 0.91 < 0.73 Fe-59 < 5.57 < 3.00 < 3.72 < 4.05 < 3.08 < 2047 Zn-65 < 4044 < 2.28 < 1.59 < 1.58 < 1.34 < 0.93 Co-60 < 1.90 < 1.02 < 1.23 < 1.18 < 1.01 < 0.78 K-40 194.3 +/- 19.76 4804 +/- 10043 109.7 +/- 12.89 393 +/- 17.62 120.7 +/- 10.99 41043 +/- 6.39 BalLa-140 < 5.27 < 4.00 < 2.52 . < 4.04 < 3043 < 2046 8-18

TABLE B-9 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES-2008 Results in Units of pCi/liter +/- 1 Sigma

1. 10 DISCHARGE CANAL (MIXING ZONE) 1-131 < 5.35 < 6.86 < 5.42 < 6.81 < 6.19 < 6.90 Cs-134 < 0.92 < 1.47 < 0.80 < 1.12 < 0.92 < 1.17 Cs-137 < 1.17 < 1.31 < 1.04 < 1.44 < 1.21 < 1.68 Zr-95 < 2.61 < 2.40 < 2.09 < 2.64 < 2.14 < 3.24 Nb-95 < 1.68 < 2.17 < 0.98 < 1.99 < 1.82 < 2.20 Co-58 < 1.54 < 1.51 < 1.18 < 1.57 < 1.54 < 1.95 Mn-54 < 1.36 < 1.18 < 1.09 < 1.31 < 1.25 < 1.69 Fe-59 < 4.16 < 4.27 < 3.09 < 4.47 < 3.65 < 4.71 Zn-65 < 1.62 < 3.69 < 1.54 < 2.02 < 1.70 < 2.46 Co-60 < 1.26 < 1.41 < 1.15 < 1.26 < 1.29 < 1.72 K-40 150.8 +/- 15.35 63.96 +/- 12.47 102 +/- 10.85 307.4 +/- 18.34 329 +/- 16.70 439.3 +/- 24.30

< 3.17 < 3.67 < 3.68 < 4.08 1-131 < 6.52 < 5.18 < 5.04 < 6.39 < 5.87 < 5.42 Cs-134 < 1.01 < 0.75 < 0.90 < 1.14 < 0.87 < 0.70 Cs-137 < 1.35 < 0.89 < 1.08 < 0.96 < 1.17 < 0.97 Zr-95 < 2.79 < 2.08 < 1.99 < 2.17 < 2.31 < 2.29 Nb-95 < 1.91 < 1.35 < 1.53 < 1.43 < 1.74 < U5 Co-58 < 1.65 < 1.15 < 1.29 < 1.27 < 1.39 < 1.19 Mn-54 < 1.31 < 0.96 < 1.14 < 1.05 < 1.18 < 1.04 Fe-59 < 4.42 < 3.49 < 4.18 < 3.25 < 3.67 < 3.73 Zn-65 < 2.09 < 1.19 < 3.03 < 2.42 < 1.62 < 2.29 Co-60 < 1.39 < 0.96 < 1.29 < 1.06 < 1.08 < 1.08 K-40 400.8 +/- 20.29 83.0 +/- 9.65 71.07 +/- 11.74 65.45 +/- 9.12 391.9 +/- 17.97 141.8 +/- 11.51 Ba/La-140 < 4.15 < 2.78 < 3.76 < 3.86 < 3.59 < 3.73 8-19

TABLE B-I0 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES - 2008 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCi/l +/- 1 Sigma

. ,'<SrATIONJ::;QDE ,... .. :" ..... ': ...

First Quarter 12/31/07 03/28/08 <450 PLANT INTAKE (HUDSON RIVER) Second Quarter 03/28/08 06/27/08 <440 (09, INLET) ** Third Quarter 06/27/08 09/26108 <427 Fourth Quarter 09/26108 12/31/08 <424 First Quarter 12/31/07 03/28/08 <450 DISCHARGE CANAL Second Quarter 03/28/08 06/27108 <440 (10, MIXING ZONE) Third Quarter 06/27/08 09/26108 <427 Fourth Quarter 09/26108 12/31/08 <424

• • Control Sample location 8-20

TABLE B-ll CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2008 Results in Units of pCiIL +/- 1 Sigma CAMP FIELD RESERVOIR 1-131 < 3.51 < 2.82 < 2.22 < 2.20 < 3.66 < 2.45 Cs-134 < 2.05 < 3.17 < 2.10 < 2.16 < 2.02 < 2.73 Cs-137 < 3.05 < 2.69 < 1.97 < 1.66 < 2.93 < 1.33 Zr-95 < 4.04 < 4.31 < 2.55 < 3.37 < 4.32 < 3.73 Nb-95 < 3.45 < 1.92 < 1.75 < 1.92 < 2.92 < 2.77 Co-58 < 3.27 < 3.09 < 1.68 < 2.28 < 3.13 < 2.53 Mn-54 < 3.45 < 2.32 < 1.88 < 1.65 < 3.07 < 2.27 Fe-59 < 7.60 < 7.38 < 5.25 < 5.47 < 7.26 < 6.05 Zn-65 < 3.41 < 5.88 < 5.73 < 5.71 < 9.41 < 5.16 Co-60 < 3.26 < 2.58 < 1.70 < 2.44 < 2.41 < 2.92 K-40 307.2 +/- 40.54 122.9 +/- 28.08 < 24.82 < 14.86 328.3 +/- 39.19 < 30.59 BalLa-140 < 5.56 < 4.32 < 2.42 < 2.61 < 4.07 < 3.93 1-131 < 2.70 < 2.89 < 2.63 < 3.29 < 2.01 < 2.09 Cs-134 < 1.43 < 2.81* < 1.67 < 1.93 < 1.72 < 1.32 Cs-137 < 2.50 < 2.50 < 2.22 < 3.48 < 1.83 < 2.02 Zr-95 < 3.59 < 3.63 < 2.96 < 3.87 < 2.64 < 3.15 Nb-95 < 2.36 < 2.94 < 1.97 < 2.40 < 1.62 < 1.64 Co-58 < 2.78 < 2.80 < 2.08 < 2.37 < 1.64 < 2.12 Mn-54 < 1.96 < 2.54 < 2.08 < 2.46 < 1.60 < 1.55 Fe-59 < 4.94 < 5.79 < 4.99 < 7.21 < 4.17 < 4.35 Zn-65 < 7.29 < 7.11 < 5.41 < 7.69 < 4.47 < 4.82 Co-60 < 2.61 < 2.61 < 2.60 < 2.92 < 1.73 < 2.27 K-40 < 29.19 < 30.59 76.75 +/- 23.49 110.4 +/- 33.44 < 15.30 < 18.17 BalLa-140 < 3.20 < 3.66 < 3.94 < 3.58 <.2.47 < 1.87 8-21

TABLE B-ll (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2008 Results in Units of pCiIL +/- 1 Sigma NEW CROTON RESERVOIR 1-131 < 2.81 < 2.96 < 1.84 < 2.92 < 3.30 < 2.46 Cs-134 < 3.26 < 3.11 < 1.91 < 3.14 < 5.04 < 2.11 Cs-137 < 3.32 < 2.82 < 1.90 < 2.57 < 2.27 < 2.22 Zr-95 < 5.07 < 4.62 < 2.88 < 3.44 < 4.55 < 3.34 Nb-95 < 2.04 < 2.78 < 2.01 < 2.61 < 2.71 < 1.97 Co-58 < 3.11 < 2.62 < 1.71 < 2.22 < 3.28 < 2.15 Mn-54 < 3.57 < 2.17 < 1.25 < 2.40 < 3.40 < 2.39 Fe-59 < 5.21 < 5.70 < 3.56 < 7.11 < 4.85 < 4.74 Zn-65 < 7.82 < 5.44 < 3.71 < 6.23 < 7.55 < 6.05 Co-60 < 2.89 < 2.06 < 2.01 < 2.10 < 3.63 < 2.50 K-40 < 34.61 169.2 +/- 29.43 90.65 +/- 18.35 < 29.94 < 33.93 < 21.55 BalLa-140 < 5.93 < 3.47 < 1.89 < 2.66 < 3.14 < 2.54 1-131 < 2.56 < 2.76 < 3.21 < 3.26 < 1.69 < 3.39 Cs-134 < 2.03 < 2.61 < 1.68 < 3.51 < 1.01 < 2.12 Cs-137 < 2.52 < 2.31 < 3.17 < 2.23 < 1.45 < 2.42 Zr-95 < 4.38 < 3.13 < 4.21 < 4.39 < 2.19 < 5.38 Nb-95 < 2.44 < 1.80* < 2.90 .< 3.16 < 1.44 < 3.02 Co-58 < 2.02 < 2.78 < 2.26 < 3.12 < 1.65 < 3.43 Mn-54 < 2.33 < 2.50 < 2.56 < 3.65 < 1.52 < 2.83 Fe-59 < 4.73 < 6.00 < 5.37 < 7.08 < 3.63 < 4.55 Zn-65 < 3.02 < 2.62 < 7.87 < 7.32 < 3.89 < 9.91 Co-60 < 2.04 < 2.04 < 3.42 < 3.19 < 1.30 < 3.04 K-40 96.07 +/- 23.12 105.1 +/- 22.44 200.6 +/- 34.10 358.4 +/- 41.89 82.11 +/- 13.90 469 +/- 49.27 BalLa-140 < 2.53 < 2.86 < 3.26 < 3.37 < 1.67 < 4.60 8-22

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2008 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCiIL +/- 1 Sigma First Quarter 12118/07 03/11108 <452 CAMP FIELD RESERVOIR Second Quarter 03/11108 06/17/08 <442 Third Quarter 06117108 09123/08 <416 Fourth Quarter 09123/08 12/15/08 <413 First Quarter 12/18/07 03111108 <452 NEW CROTON RESERVOIR Second Quarter 03111/08 06/17/08 <442 Third Quarter 06117108 09123/08 <416 Fourth Ouarter 09123/08 12115/08 <413 8-23

TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2008 Results in Units ofpCilkg +/- 1 Sigma 8-24

TABLE B-13 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2008 Results in Units of pCifkg +/- 1 Sigma Client ID Req. CL 8-25

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 95 Meteorological Tower 8-26

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 95 Meteorological Tower METtoWER,;\: METT'OWElf' : ; M E T TOWER'" METiTQWER*

~~~~P~..J£¥~:':~":::':~::"6~J2~4!G/2~O~'~!'~~':'....J~ill  ::t:::>;<f6!i4;~~6~::~":':'::':n'7dil~9,Q~,,,;: .'.

"::<:?id/22/2008 Client ID IBV952608S 1 IBV952608S2 IBV952608S3 IBV953008S 1 IBV953008S2 IBV953008S3 Reg. CL GRAPE LEAYES RAGWEED MULLEN GRAPELEAYES RAGWEED MULLEN Radionuclide I (pCi)

Be-7 512.3 +/- 59.9 152.0 +/- 110.9 1258.0 +/- 128.0 598.7 +/- 78.1 1754.0 +/- 158.5 1149.0 +/- 123.3 1-131 50 < 7.49 < 11.45 < 13.47 < 8.12 < 15.93 < 16.11 Cs-134 50 < 5.42 < 7.97 < 18.09 < 9.62 < 10.44 < 11.15 Cs-137 50 < 6.81 < 14.68 < 12.70 < 7.42 < 12.76 < 11.69 Zr-95 < 11.04 < 14.26 < 20.14 < 16.47 < 22.06 < 20.49 Nb-95 < 7.76 < 10.82 < 15.26 < 8.86 < 15.14 < 10.46 Co-58 < 5.90 < 8.70 < 12.47 < 8.58 < 14.22 < 11.98 Mn-54 < 7.57 < 12.82 < 13.10 < 6.03 < 14.15 < 11.14 Zn-65 < 17.80 < 30.14 < 35.59 < 22.38 < 36.43 < 35.50 Fe-59 < 16.77 < 40.84 < 32.34 < 21.86 < 42.08 < 33.72 Co-60 < 8.21 < 14.18 < 12.95 < 8.70 < 17.70 < 13.41 Ba/La-140 < 7.23 < 16.80 < 9.63 < 9.69 < 9.80 < 7.33 Ru-103 < 5.38 < 7.91 < 12.78 < 9.25 < 14.59 < 13.18 Ru-106 < 73.95 < 122.10 < 126.00 < 87.53 < 148.30 < 129.10 Ce~141 < 10.42 < 12.43 < 17.02 < 11.88 < 15.52 < 16.27 Ce-144 < 42.89 < 53.53 < 81.78 < 51.41 < 74.80 < 70.61 AcTh-228 < 23.69 < 41.22 < 49.28 < 22.95 < 56.04 < 49.23 Ra-226 265.3 +/- 118.2 < 219.30 < 249.00 307.0 +/- 121.8 316.7 +/- 192.8 395.9 +/- 193.8 K-40 3958.0 +/- 181.2 7965.0 +/- 366.0 6479.0 +/- 344.6 2515.0 +/- 173.4 8579.0 +/- 434.8 7965.0 +/- 354.4 B-27

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma

1. 95 Meteorological Tower

'*"""~~S'~~~~.:*;; " '**'***',~~IT()\VER. *:i:.,*. "'ET1TOW:J!i:R;':':..... 'l\fETTOWERiii:'i:,::,  :":'M~T]J)W~R<~

. Date~:;""91r§/2(l0 9/16/2008',* "j""':',:T9/t~7~()Q~'i,,::;,~j'i:::'::'~' '1'0/712'008' '" "

Client ID I Req. CL IBV953808S 1 IBV953808S2 IBV953808S3 IBV9541 08S 1 IBV954108S2 IBV954108S3 GRAPE LEAVES RAGWEED MULLEN GRAPE LEAVES RAGWEED MULLEIN Radionuc1ide I (pCi)

Be-7 749.2 +/- 83.5 1597.0 +/- 109.2 996.3 +/- 114.2 741.3 +/- 96.0 1197.0 +/- 129.9 1734.0 +/- 135.0 1-131 50 < 10.33 < 10.39 < 12.35 < 13.22 < 13.70 < 14.26 Cs-134 50 < 12.39 < 11.70 < 13.92 < 9.42 < 20.66 < 19.61 Cs-137 50 < 7.89 < 9.08 < 9.97 < 12.84 < 13.02 < 13.90 Zr-95 < 16.28 < 16.35 < 17.98 < 24.73 < 22.32 < 25.31 Nb-95 < 10.44 < 8.57 < 11.75 < 12.45 < 13.63 < 13.78 Co-58 < 7.12 < 9.93 < 11.81 < 12.86 < 13.71 < 12.97 Mn-54 < 11.39 < *9.39 < 12.41 < 10.65 < 13.74 < 13.69 Zn-65 < 27.76 < 23.37 < 31.10 < 30.49 < 33.88 < 35.30 Fe-59 < 25.09 < 24.98 < 30.40 < 38.73 < 41.97 < 32.94 Co-60 < 7.74 < 8.92 < 12.37 < 14.31 < 13.28 < 13.09 BalLa-140 < 11.21 < 8.93 < 14.61 < 15.60 < 12.58 < 12.41 Ru-103 < 7.23 < 8.23 < 11.05 < 11.93 < 13.54 < 13.03 Ru-106 < 97.13 < 92.86 < 114.80 < 126.80 < 153.20 < 122.10 Ce-141 < 11.12 < 12.30 < 15.27 < 14.36 < 18.02 < 18.59 Ce-144 < 48.47 < 58.56 < 67.29 < 60.65 < 78.51 < 76.79 AcTh-228 < 22.49 < 40.29 < 52.79 < 43.66 < 55.31 < 45.67 Ra-226 < 181.40 < 191.50 537.5 +/- 187.2 < 239.60 < 244.60 511.5 +/- 205.4 K-40 3895.0 +/- 245.3 7485.0 +/- 296.9 7038.0 +/- 360.5 3974.0 +/- 271.5 7481.0 +/- 380.2 7038.0 +/- 313.0 8-28

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units ofpCilkg +/- 1 Sigma

1. 94 IPEC Training Center 8-29

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 94 IPEC Training Center

"~6~~~~e;,<..... '~~~NtN9"1l~DG **;;taiNil;,iM*BED~.:::..".~MYY~Nqj*~*~fi!c*;i '[I'~INJNg.i~PI)G ':;T:~INING:~.~I>G:

• t ... ** D~t~' .,... '. ~jii~ji'o:08*i!:i. 6/24/2008 **":.::i*i'i!!"~Z~'4/i()08*** '. *****7/22/2008* . . "7/22/2008 Client ID I IBV942608S 1 IBV942608S2 IBV942608S3 IBV943008S 1 I IBV943008S2 I IBV943008S3 Radionuc1ide Req. CL (pCi)

BURDOCK MULLEN RAGWEED BURDOCK I MULLEN I RAGWEED Be-7 1001.0 +/- 71.8 1422.0 +/- 134.2 1427.0 +/- 186.9 1249.0 +/- 101.1 1477.0 +/- 111.6 1041.0 +/- 105.7 1-131 50 < 7.78 < 16.24 < 21.21 < 9.98 < 11.34 < 14.99 Cs-134 50 < 7.67 < 20.55 < 25.22 < 7.26 < 7.44 < 14.29 Cs-137 50 < 7.92 < 14.78 < 24.17 < 8.73 < 9.08 < 12.90 Zr-95 < 10.75 < 27.96 < 44.85 < 15.20 < 15.46 < 20.69 Nb-95 < 5.53 < 14.53 < 26.24 < 9.15 < 9.73 < 12.48 Co-58 < 7.63 < 14.37 < 27.81 < 10.67 < 11.91 < 11.23 Mn-54 < 8.17 < 13.65 < 25.40 < 9.63 < 9.57 < 11.38 Zn-65 < 11.56 < 39.80 < 68.29 < 30.14 < 30.82 < 37.17 Fe-59 < 23.93 < 42.12 < 78.79 < 25.59 < 32.07 < 35.26 Co-60 < 9.00 < 18.02 < 26.97 < 10.12 < 9.96 < 13.86 BalLa-140 < 12.01 < 21.19 < 22.57 < 10.03 < 9.40 < 10.67 Ru-103 < 7.55 < 14.42 < 23.16 < 8.38 < 10.09 < 12.60 Ru-106 < 77.06 < 185.30 < 262.10 < 93.46 < 102.30 < 120.10 Ce-141 < 9.86 < 22.27 < 32.26 < 14.63 < 12.35 < 18.49 Ce-144 < 45.29 < 83.81 < 124.80 < 59.14 < 60.77 < 80.58 AcTh-228 < 27.40 < 56.18 196.6 +/- 74.0 < 35.36 < 37.91 < 54.60 Ra-226 244.3 +/- 128.2 1238.0 +/- 283.2 < 402.40 432.6 +/- 146.7 < 168.50 436.3 +/- 174.2 K-40 5205.0 +/- 216.0 9223.0 +/- 402.2 14870.0 +/- 723.5 8254.0 +/- 305.0 8656.0 +/- 357.9 9519.0 +/- 371.2 8-30

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 94 IPEC Training Center 8-31

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 23 Roseton **

Control 8-32

TABLE B-14 (Continued)

CONCENTRAnONS OF GAMMA EMITTERS IN BROADLEAF VEGETA nON SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma

1. 23 Roseton **

8-33

TABLE B-14 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma

1. 23 Roseton **

SalTl~le ROSE TON ' ROSET()N:' ROSETON ROSETON"I'''''C

Location Date 9/1'$1200~H', 9/15/2008 9/15/2008 1'0/6/2008

---'-'---'-"'-==

Client ID I IBV233808S 1 IBV233808S2 IBV233808S3 IBV234108S1 IBV234108S2 IBV234108S3 Req. CL BURDOCK RAGWEED CATALPA BURDOCK MULLEIN CATALPA Radionuclidel (PCi)

Be-7 823.4 +/- 125.1 2208.0 +/- 138.1 1668.0 +/- 132.1 1838.0 +/- 131.4 1848.0 +/- 182.2 1642.0 +/- 132.6 1-131 50 < 17.68 < 12.79 < 14.04 < 14.72 < 21.88 < 16.84 Cs-134 50 < 13.09 < 9.27 < 8.91 < 8.63 < 27.25 < 10.32 Cs-137 50 < 11.85 < 12.20 < 3.34 < 12.27 < 19.99 < 13.10 Zr-95 < 27.27 < 21.04 < 16.04 < 22.58 < 44.43 < 18.27 Nb-95 .< 13.69 < 12.11 < 10.27 < 13.77 < 23.57 < 13.50 Co-58 < 17.03 < 12.93 < 9.58 < 11.80 < 19.81 < 15.59 Mn-54 < 14.87 < 11.51 <: 10.05 < 11.74 < 18.84 < 13.27 Zn-65 < 41.75 < 34.37 < 25.43 < 41.07 < 63.04 < 13.35 Fe-59 < 47.20 < 38.01 < 26.73 < 49.50 < 53.71 < 32.49 Co-60 < 10.32 < 14.01 < 10.88 < 13.25 < 26.49 < 16.06 Ba/La-140 < 14.63 < 13.98 < 13.38 < 22.03 < 24.59 < 12.56 Ru-103 < 15.95 < 9.79 <. 9.36 < 13.17 < 19.31 < 13.55 Ru-106 < 161.90 < 108.90 < 110.10 < 119.00 < 217.40 < 133.00 Ce-141 < 20.54 < 15.43 < 12.98 < 15.69 < 25.81 < 19.40 Ce-144 < 80.51 < 60.10 < 43.83 < 67.63 < 105.50 < 78.85 AcTh-228 < 50.60 < 42.11 < 28.89 < 52.48 < 65.67 < 47.51 Ra-226 < 252.20 < 195.60 < 199.40 < 286.90 < 344.30 510.4 +/- 226.2 K-40 5990.0 +/- 408.2 8648.0 +/- 352.5 3637.0 +/- 287.8 8737.0 +/- 396.1 11470.0 +/- 564.2 6161.0 +/- 302.5

• • Control Sample Location 8-34

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 25 Downstream (Hudson River) 6/6/2008 Client ID IFH252408S6 IFH252408S5 IFH252408S1 IFH252408S2 IFH252408S3 IFH252408S4 Req. CL WHITE PERCH BLUE CRAB SUNFISH CATFISH AMERICAN EEL STRIPED BASS 8-35

TABLE B-15 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2008 Results in Units ofpCilkg +/- 1 Sigma

1. 25 Downstream (Hudson River)

"':~:::~alTipl~f'"

":LocatIon Date lL£ill1L1~8Ji!L~~~llii

'-~i,!::"qr'FISH:""'"

8/)J3/2008

.";~ht~~:::: ,"Iii~~~;: \i~YQrI':'i'~!r!!:: .~

Client ID IFH253308S4 IFH253308S2 IFH253308S3 IFH253308S5 IFH253308S1 IFH253308S6 Req. CL SUNFISH CATFISH EEL WHITE PERCH BLUE CRAB STRIPED BASS Radionuclidel (pC i)

Be-7 < 259.7 < 365.2 < 184.8 < 265.3 < 251.9 < 248.1 1-131 < 1641.0 < 1613.0 < 646.0 < 486.5 < 181.3 < 139.7 Cs-134 65 < 17.7 < 15.1 < 11.0 < 17.5 < 19.0 < 12.1 Cs-137 75 < 14.2 < 23.1 < 14.7 < 25.9 < 21.0 < 25.9 Zr-95 < 45.7 < 61.9 < 32.0 < 48.0 < 39.9 < 53.6 Nb-95 < 46.8 < 64.9 < 34.9 < 51.5 < 28.7 < 34.7 Co-58 65 < 27.7 < 33.9 < 21.8 < 30.5 < 22.8 < 34.3 Mn-54 65 < 17.3 < 23.9 < 12.4 < 23.5 < 19.4 < 27.3 Zn-65 130 < 46.3 < 63.1 < 39.2 < 70.8 < 50.7 < 68.4 Fe-59 130 < 82.1 < 112.4 < 75.0 < 98.9 < 85.7 < 88.8 Co-60 65 < 17.9 < 24.5 < 15.7 < 15.5 < 16.0 < 25.3 BalLa-140 < 300.1 < 355.0 < 178.9 < 234.1 < 83.6 < 80.8 Ru-103 < 42.0 < 61.7 < 26.7 < 37.3 < 27.1 < 35.3 Ru-106 < 160.7 < 223.2 < 171.7 < 253.9 < 224.4 < 273.1 Ce-141 < 58.4 < 91.9 < 42.2 < 59.2 < 33.4 < 50.2 Ce-144 < 94.8 < 135.8 < 93.1 < 119.0 < 106.7 < 141.2 AcTh-228 < 50.3 < 84.9 < 64.3 < 79.2 < 91.5 < 82.9 Ra-226 568.2 +/- 208.3 1573.0 +/- 391.0 1 486.9 +/- 224.1 < 363.8 1 - 600.6 +/- 285.9 1 997.3 +/- 353.2 K-40 3435.0 +/- 267.4 7504.0 +/- 402.7 13708.0 +/- 319.1 7143.0 +/- 445.9 1 4515.0 +/- 384.0 110430.0 +/- 549.7 Sr-90 5 < 5.0 7.3 +/- 1.9 < 3.9 10.3 +/- 2.7 < 3.8 < 6.7 Ni-63 < 97.0 < 96.0 < 95.0 < 92.0 < 98.0 < 88.0 8-36

TABLE B-15 (Continued)

C.oNCENTRATI.oNS .oF RADI.oNUCLIDES IN FISH SAMPLES - 2008 Results in Units of pCilkg +/- 1 Sigma

1. 23 Roseton (Control)

. SamPle

~ .~: liilijii;.j~.oSET.o~.:.~~!~~.~

L()cati()n R.oSET.oNFISH R.oSET.oNFISH R.oSETONFISH ROSETQN:i:f: ISH .

• 1 Date .~ 61412008**;**********;* .;:.i,. 6/4/2008 *ii:i.[: .6/4120tis 6/4/2008 .. 6/5/2008 Client ID IFH232408S1 IFH232408S2 IFH232408S4 IFH232408S5 IFH232408S3 Req. CL CATFISH AMERICAN EEL WHITE PERCH SUNFISH STRIPED BASS Radionuclide (pCi)

Be-7 < 202.6 < 251.8 < 226.9 < 275.4 < 184.2 1-131 < 1347.0 < 1636.0 < 1654.0 < 1729.0 < 1219.0 Cs-134 65 < 13.2 < 9.8 < 17.9 < 10.4 < 14.5 Cs-137 75 < 15.0 < 15.1 < 13.2 < 14.8 < 10.5 Zr-95 < 48.5 < 45.2 < 41.6 < 52.7 < 29.9 Nb-95 < 38.4 < 42.6 < 44.2 < 44.8 < 32.6 I I

Co-58 65 < 23.5 < 24.1 < 26.0 < 23.7 < 18.8 ,

Mn-54 65 < . 13.9 < 16.8 < 16.5 < 17.4 < 12.3 .

Zn-65 130 < 42.9 < 38.0 < 39.3 < 40.0 < 34.1 Fe-59 130 < 89.2 < 78.4 < 79.4 < 90.0 < *77.2 Co-60 65 < 16.0 < 16.0 < 21.2 < 16.9 < 13.4 BalLa-140 < 349.4 < 275.8 < 298.7 < 342.8 < 170.8 Ru-103 < 33.1 < 41.7 < 46.7 < 48.9 < 31.3 Ru-106 < 156.6 < 181.8 < 181.2 < 212.1 < 145.3 Ce-141 < 53.9 < 63.6 < 53.5 < 69.8 < 41.5 Ce-144 < 83.0 < 103.2 < 97.1 < 100.8 < 56.1 AcTh-228 < 56.0 156.2 +/- 45.2 < 56.6 185.2 +/- 47.5 < 45.7 Ra-226 716.8 +/- 204.0 1250.0 +/- 263.5 518.6 +/- 209.6 < 377.7 357.7 +/- 161.2 K-40 4600.0 +/- 278.8 6287.0 +/- 277.0 3450.0 +/- 287.1 3768.0 +/- 272.0 3614.0 +/- *255.3 Sr-90 5 < 9.2 Ni-63 < 92 8-37

TABLE B-15 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

1. 23 Roseton (Control)

Client ID IFH233308S5 IFH233308S4 IFH233308S2 IFH233308S6 IFH233308S3 Req. CL SUNFISH WHITE PERCH EEL BLUE CRAB STRIPED BASS Radionuclide (pC i)

Be-7 < 210.9 < 283.8 < 231.8 < 180.6 < 138.9 1-131 < 1317.0 < 657.2 < 753.6 < 111.5 < 43.4 Cs-134 65 < 19.2 < 20.2 < 18.3 < 16.3 < 15.1 Cs-137 75 < 19.0 < 19.3 < 15.9 < 18.7 < 13.4 Zr-95 < 46.3 < 51.1 < 37.5 < 32.9 < 27.1 Nb-95 < 51.9 < 35.9 < 40.9 < 25.6 < 18.4 Co-58 65 < 28.5 < 29.5 < 21.7 < 17.8 < 14.0 Mn-54 65 < 20.8 < 15.1 < 15.0 < 13.8 < 13.3 Zn-65 130 < 58.6 < 49.9 < 41.3 < 38.2 < 39.3 Fe-59 130 < 94.9 < 111.4 < 87.9 < 52.4 < 42.4 Co-60 65 < 14.2 < 23.9 < 17.8 < 19.1 < 15.1 Ba/La-140 < 248.1 < 347.1 < 161.1 < 75.0 < 41.2 Ru-103 < 42.3 < 45.0 < 30.1 < 26.6 < 19.8 Ru-106 < 211.3 < 220.2 < 98.2 < 151.9 < 138.7 Ce-141 < 62.8 < 59.0 < 48.2 < 35.9 < 22.9 Ce-144 < 100.6 < 111.1 < 82.1 < 102.4 < 72.1 AcTh-228 < 63.8 < 62.7 < 63.7 < 57.6 < 49.0 Ra-226 348.9 +/- 206.6 1107.0 +/- 286.1 < 330.1 972.8 +/- 277.5 < 249.6 K-40 6355.0 +/- 393.1 4400.0 +/- 385.8 3322.0 +/- 320.8 4762.0 +/- 292.7 4483.0 +/- 297.2 Sr-90 5 12.0 +/- 1.6 20.6 +/- 2.8 < 7.7 < 8.9 < 10.0 Ni-63 < 98.0 < 96.0 < 86.0 < 92.0 < 95.0 8-38

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma

'§aropli:!. ",:>' .'::,. . ,.,., .,....... " ", 'i.:.:';'::""'''''''''':''''''' . ' *,:,;:

.:!:t>cllti6ti'  :;"':GOl.mSPRItlG '. ',C8!:JD SPRINGi ,: :~"l-~N17S:'GOY.E '. ~~:~AN~:~I:;::'::~~:RFtAN'CK"

:' ,Qa't~ 6/11'12008::'; . . . "/9/3/2008" . j:':9/~j2()08 ""'"' ,ii:'(Miih008';';'  :':;:'::~/4i2008C::;

Client ID IA V842508 IAV843608 IAV283608 IAVl72508 IAV173608 MYRO MYRO MYRO MYRO MYRO Req. CL Radionuc1idel (pCi)

Be-7 222.3 +/- 55.6 < 53.7 < 46.4 163.2 +/- 34.6 < 37.2 1-131 30 < 11.7 35.0 +/- 5.1 < 8.5 < 8.8 53.7 +/- 6.0 Cs-134 30 < 10.1 < 6.4 < 4.4 < 3.8 < 6.5 Cs-137 40 < 8.1 < 5.4 < 4.2 < 4.6 < 5.5 Zr-95 < 12.4 < 10.4 < 7.8 < 9.2 < 9.7 Nb-95 < 7.5 < 7.9 < 5.9 < 5.2 < 5.5 Co-58 < 8.1 < 6.3 < 5.1 < 4.1 < 6.0 Mn-54 < 7.9 < 6.3 < 4.7 < 5.1 < 5.3 Zn-65 < 22.0 < 16.2 < 12.7 < 13.3 < 12.8 Fe-59 < 19.6 < 20.1 < 12.7 < 12.8 < 13.5 Co-60 < 8.4 < 5.0 < 4.7 < 5.4 < 5.8 BalLa-140 < 11.8 < 8.7 < 9.5 < 6.4 < 9.3 Ru-103 < 6.6 < 5.8 < 6.0 < 5.2 < 5.1 Ru-106 < 76.4 < 60.0 < 50.8 < 58.9 < 45.5 Ce-141 < 12.0 < 9.0 < 8.1 < 7.1 < 7.4 Ce-144 < 39.7 < 36.7 < 31.2 < 31.5 < 31.7 AcTh-228 88.9 +/- 26.2 135.6 +/- 21.6 61.7 +/- 17.8 70.4 +/- 16.9 100.7 +/- 18.5 Ra-226 232.8 +/- 123.1 251.6 +/- 85.7 201.1 +/- 77.8 < 101.5 175.5 +/- 83.9 K-40 2560.0 +/- 157.4 2129.0 +/- 133.7 1937.0 +/- 118.7 1812.0 +/- 106.9 2181.0 +/- 133.7 8-39

TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma

!EOLDSPRING \"'F' 'COLD SPRING

.':*"'9/3/2008 Client ID IBS842508 IBS843608 IBS282508 IBS283608 IBSl72508 IBS173608 Req. CL 8-40

TABLE B-17 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2008 Results in Units ofpCi/kg +/- 1 Sigma DJSCHARGEi!' DISCHARGE S~m~t~Location

'CANAL CANAL Da!~ 6112/2008 914120,08 Client ID IBSI02508 IBS103608 Radionuc1ide Req. CL Be-7 < 235.5 < 238.1 1-131 < 45.6 < 54.1 Cs-134 75 < 31.6 < 41.0 Cs-137 90 137.3 +/- 29.1 171.7 +/- 31.9 Zr-95 < 49.1 < 63.3 Nb-95 < 30.1 < 37.0 Co-58 < 21.9 < 29.6 Mn-54 < 21.3 < 24.9 Zn-65 < 123.5 < 115.5 Fe-59 < 82.1 < 108.2 Co-60 < 30.7 < 29.1

, Ba/La-140 < 44.3 < 45.0 Ru-103 < 28.2 < 32.5 Ru-106 < 287.1 < 293.0 Ce-141 < 34.5 < 47.8 Ce-144 < 167.3 < 185.5 AcTh-228 397.2 +/- 97.7 296.7 , +/- 102.0 Ra-226 1091.0 +/- 479.6 1025.0 +/- 422.9 K-40 15980.0 +/- 930.8 15710.0 +/- 873.2 B-41

TABLEB-18 CONCENTRAnONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2008 Results in Units of pCiIL +/- 1 Sigma B-42

TABLE B-18 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2008 Results in Units of pCiIL +/- 1 Sigma '-

8-43

TABLE B-19 CONCENTRATIONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2008 Results in Units of pCi/kg +/- 1 Sigma

'\.~~~I:

L:ocation . . J~,:';:lili...

, Date,,'*,

.... ROSETON liE'iil".: 9/29/200'8"'; .'

MET'T,OWER

' ;9/30/2008 TRAINING BLDG' lilii;m.:,+9/30/2om~;:i; <.... .

Client ID IS0234008 IS0954008 IS0944008 Req. CL Radionuc1ide (pCi)

Be-7 1074.0 +/- 275.9 1007.0 +/- 227.0 664.3 +/- 197.3 1-131 < 38.1 < 31.9 < 24.3 Cs-134 75 < 38.9 < 21.1 < 29.2 Cs-137 90 < 48.0 < 36.0 < 27.9 Zr-95 < 62.0 < 51.8 < 36.2 Nb-95 < 29.9 < 29.5 < 24.9 Co-58 < 36.5 < 38.5 < 28.6 Mn-54 < 40.6 < 34.9 < 19.6 Zn-65 < 61.2 < 107.8 < 90.9 Fe-59 < 127.1 < 86.4 < 69.5 Co-60 < 44.6 < 31.6 < 26.6 Ba/L:a-140 < 63.0 < 34.3 < 38.4 Ru-103 < 47.9 < 26.0 < 27.4 Ru-106 < 373.2 < 245.6 < 300.9 Ce-141 < 56.3 < 44.5 < 34.0 Ce-144 < 248.1 < 199.5 < 161.4 AcTh-228 1259.0 +/- 162.9 480.9 +/- 116.0 662.2 +/- 114.5 Ra-226 1743.0 +/- 572.5 1092.0 +/- 546.8 < 640.5 K-40 20170.0 +/- 1132.0 18100.0 +/- 983.9 14130.0 +/- 814.1 8-44

TABLE B-20 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma 159.0 I <

Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-45

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-46

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma

<, . , ,"; "in ""., '11\ " ' / " ' , , , I>, '!llIlAI An jiic:!j I: '.'.n !llIlAI An.*.**..  :~'i

'., '. 'l::F!".""":<',:": ." ': "E..":;' .::....; Ip,'; ***** CT-".... C_ l.'"

k,>'*~***~~;*.'I'ITl**:PI~.'.~I'a'*i:ITfe:.;*.*'.*** . . : ' " . :(.. '."", ';',.: *0..,:;;"',;,'::.n .;:~; ." .n.  :. "i'.'

~.;, "(.

", c', ,.'.

j'" ""i");' ..i" "',..'" UU5 ., , ' . ' ,

'." ;';' ".,. ' " ",;,'.,. "':"<',';~*d Zl 1Fii"-:' '" <i'I",* ""/~ i.',* I;'i' .,. . )8;:~'! 'i'i:! 1i i:!~iji!:lil

,,:,:,;,;,.;.:1,.'" .::.;,.;;;:..** 1::"';",:;""

1 . ,

""'." .'ii. "..... ,., "f': [i',,': I, (

lil!:::::;,./,! ",.,',",::". ).' . . . '. ,( '.. ,. "*"n',::.m'i::,***:.,m:i;;,'*l" ', ' .*}';;*;:.I]..;,:,.:':*!>, .">: Ii\ "" 'c.....".' "..".".'. .*..... '*.,

Radionuclide Req. MDC H*3 < 181.0 242.0 +/- 171.0 < 193.0 Be-7 < 27.8 < 33.0 < 75.4 Cs-134 15 < 2.4 < 3.0 < 7.1 Cs-137 18 < 2.4 < 2.8 < 6.2 Zr-95 < 4.9 < 6.7 < 14.6 Nb-95 < 3.7 < 4.9 < 13.1 Co-58 < 2.8 < 3.1 < 8.8 Mn-54 < 2.3 < 2.8 < 6.0 I

Zn-65 < 4.4 < 5.5 \ < 12.2 Fe-59 < 6.2 < 6.1 < 21.7 Co-60 < 2.0 < 3.3 < 7.3 Sr-90 1 < 0.8 < 0.7 < 0.6 Ba-140 < 32.3 < 39.8 < 224 La-140 < 11.4 < 12.0 < 91.5 Ru-106 < 20.9 < 27.5 < 59.8 Ce-141 < 6.9 < 7.9 < 19.4 Ce-144 < 17.2 < 20.5 < 34.9 AcTh-228 < 9.1 < 12.4 < 24.4 K-40 < 24.8 < 39.1 < 87.6 N-63 < 19.2 < 26.9 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-47

TABLE B-20 (Continued)

CON CENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCifL +/- 3 sigma, Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-48

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L+/- 3 sigma H-3 < 179.0 < 163.0 < 170.0 < 195.0 8e-7 < 31.7 < 36.0 < 28.5 < 91.3 Cs-134 15 < 3.2 < 4.3 < 2.9 < 8.9 Cs-137 18 < 2.8 < 3.4 < 2.8 < 6.9 Zr-95 < 6.4 < 7.0 < 5.8 < 20.5 Nb-95 < 4.5 < 4.1 < 4.7 < 17.0 Co-58 < 3.4 < 3.4 < 2.9 < 12.1 Mn-54 < 2.9 < 3.0 < 2.7 < 8.6 Zn-65 < 5.5 < 6.7 < 5.0 < 17.7 Fe-59 < 6.5 < 7.5 < 7.8 < 21.8 Co-60 < 2.6 < 3.6 < 2.5 < 7.7 Sr-90 1 < 0.7 < 1.0 < 0.4 < 0.8 8a-140 < 39.5 < 29.4 < 39.1 < 271 La-140 < 11.2 < 8.1 < 11.9 < 105.0 Ru-106 < 25.5 < 32.2 < 24.3 < 68.7 Ce-141 ~ 7.9 < 6.3 < 7.8 < 25.8 Ce-144 < 19.7 < 22.7 < 19.9 < 44.7 AcTh-228 33.1 + /- 16.8 21.7 + /- 11.8 37.0 + /- 9.3 < 45.6 K-40 < 31.2 < 32.6 < 27.3 < 66.5 Ni-63 < 20.1 < 19.3 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-49

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/-3 sigma MW40, H-3 < 182.0 230.0 + /- 162.0 < 196.0 8e-7 < 31.8 < 35.9 < 84.2 Cs-134 15 < 3.0 < 4.4 < 9.1 Cs-137 18 < 2.9 < 4.2 < 6.3 Zr-95 < 6.5 < 7.4 < 18.9 Nb-95 < 4.9 < 5.9 < 15.1 Co-58 < 3.4 < 3.8 < 7.7 Mn-54 < 2.8 < 3.6 < 6.6 Zn-65 < 6.5 < 7.7 < 14.6 Fe-59 < 7.0 < 7.3 < 18.8 Co-60 < 2.7 < 4.1 < 7.3 Sr-90 1 < 0.4 < 0.8 < 0.7 8a-140 < 48.3 < 49.2 < 227 La-140 < 17.5 < 12.3 < 85.3 Ru-106 < 26.1 < 30.9 < 56.2 Ce-141 < 8.2 < 9.9 < 20.8 Ce-144 < 21.4 < 26.3 < 37.4 AcTh-228 < 15.1 33.4 + /- 13.7 < 33.6 K-40 < 35.8 < 43.8 < 86.9 Ni-63 < 21.6 < 20.4 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-50

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma

< 240.0 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-51

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi!L+/- 3 sigma MVV~S1 Radionuclide H-3 < 179.0 < 161.0 < 201.0 < 199.0 Be-7 < 28.6 < 36.0 < 41.7 < 69.7 Cs-134 15 < 2.8 < 4.5 < 3.6 < 7.0 Cs-137 18 < 2.4 < 4.8 < 3.8 < 5.8 Zr-95 < 5.3 < 9.4 < 8.4 < 13.2 Nb-95 < 4.1 < 6.0 < 6.8 < 14.3 Co-58 < 3.0 < 4.3 < 4.2 < 7.2 Mn-54 < 2.7 < 5.1 < 3.3 < 4.0 Zn-65 < 6.0 < 9.9 < 7.2 < 12.9 Fe-59 < 6.4 < 11.6 < 10.8 < 20.7 Co-60 < 2.7 < 4.3 < 4.0 < 6.4 Sr-90 1 < 1.0 < 1.0 < 0.5 < 0.8 Ba-140 < 33 < 32.9 < 57.2 < 224 La-140 < 13.2 < 12.9 < 21.6 < 85.1 Ru-106 < 22.3 < 41.2 < 34.7 < 46.0 Ce-141 < 7.1 < 6.9 < 10.8 < 17.5 Ce-144 < 18.4 < 22.6 < 28.5 < 34.6 AcTh-228 < 8.7 < 22.1 < 15.3 < 23.2 K-40 < 34.2 < 44.8 < 30.2 < 59.7 Ni-63 < 19.3 < 20.2 Note 1: Less than values "<" are Minimum Detectable Concentration (MOC) values.

Note 2: A sample is positive if the result is greater than or equal to the MOC.

8-52

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/- 3 sigma H-3 < 178.0 282.0 + /- 233.0 < 149.0 Be-7 < 24.6 < 37.8 < 106.0 Cs-134 15 < 2.7 < 3.9 < 8.1 Cs-137 18 < 2.3 < 3.6 < 8.5 Zr-95 < 4.9 < 6.2 < 19.6 Nb-95 < 4.1 < 5.9 < 15.7 Co-58 < 2.8 < 3.6 < 11.0 Mn-54 < 2.3 < 3.1 < 8.2 Zn-65 < 4.8 < 6.6 < 14.8 Fe-59 < 6.4 < 7.9 < 21.8 Co-60 < 2.5 < 3.4 < 8.3 Sr-90 1 < 0.9 < 0.8 < 0.6 Ba-140 < 36.5 < 45.2 < 32.2 La-140 < 11.8 < 16.0 < 106.0 Ru-106 < 19.3 < 31.1 < 65.5 Ce-141 < 6.3 < 9.3 < 23.6 Ce-144 < 16.0 < 24.9 < 46.2 AcTh-228 < 7.1 < 11.8 < 33.3 K-40 < 18.6 < 46.3 < 110.0 Ni-63 < 23.6 < 21.2 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-53

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/-3 sigma MoniJ~ti~~vV~Jf Sam~f~ . NarTt~*:*::*i:;

.*S~~:pt~iq~~~

< ;::;". "' j~::

Radionuclide Req. MDC H-3 < 180.0 209.0 + I- 199.0 < 199.0 Be-7 < 22.6 < 35.4 < 88.5 Cs-134 15 < 2.6 < 3.7 < 9.2 Cs-137 18 < 2.1 < 3.3 < 5.6 Zr-95 < 4.4 < 6.6 < 16.1 Nb-95 < 3.4 < 5.3 < 18.0 Co-58 < 2.6 < 3.8 < 10.0 Mn-54 < 2.1 < 3.1 < 6.0 Zn-65 < 4.4 < 6.4 < 14.0 Fe-59 < 5.4 < 9.1 < 22.8 Co-60 < 1.9 < 3.3 < 7.7 Sr-90 1 < 0.9 < 0.5 < 0.7 Ba-140 < 30.1 < 50.6 < 254 La-140 < 10.0 < 16.5 < 90.1 Ru-106 < 18.3 < 27.4 < 61.8 Ce-141 < 5.3 < 8.9 < 20.6 Ce-144 < 13.9 < 23.4 < 36.9 AcTh-228 22.0 + I- 13.6 22.1 + I- 18.6 < 35.8 K-40 < 17.2 < 33.6 < 85.5 Ni-63 < 20.2 < 20.1 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-54

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCi/L +/-3 sigma

~,~3~jJr~'~~r~',' r~~~~~~~~~~~r~lmll~

I'*** ':H'E,'Mw*51'"

M0~:~'~':mi:~;~jk66~;:'"

";~~I'!lpl~:b~tt{r""'" ,10/2712008**'

." E': ** '.:::"?";:. [f;:;~~~;:::.;;;.~ . :"::*::::'

Radionuclide R~ MDC H-3 < 182.0 < 140.0 < 195.0 8e-7 < 27.6 < 38.8 < 9.1 Cs-134 15 < 3.1 < 4.1 < 8.6 Cs-137 18 < 2.5 < 3.6 < 6.7 Zr-95 < 5.3 < 7.2 < 17.9 Nb-95 < 4.2 < 5.5 < 15.8 Co-58 < 2.9 < 4.1 < 9.6 Mn-54 < 2.5 < 3.5 < 6.4 Zn-65 < 5.0 < 7.6 < 13.4 Fe-59 < 6.3 < 9.2 < 25.1 Co-60 < 2.4 < 3.4 < 6.3 Sr-90 1 < 0.9 < 0.5 < 0.7 8a-140 < 37.7 < 59.6 < 27.7 La-140 < 12.5 < 22.6 < 80.7 Ru-106 < 23.8 < 32.8 < 63.6 Ce-141 < 7.4 < 10.4 < 25.2 Ce-144 < 18.3 . < 26.6 < 43.6 AcTh-228 25.1 + 1- 17.4 32.3 + 1- 18. < 36.3 K-40 < 25.6 < 30.7 < 55.5 Ni-63 < 21.5 < 21.4 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-55

TABLE B-20 (Continued)

CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES Results in pCiIL +/- 3 sigma Radionuclide I Req. MOC I H-3 < 177.0 < 143.0 < 199.0 Be-7 < 24.6 < 33.5 < 95.4 Cs-134 15 < 2.3 < 3.5 < 7.6 Cs-137 18 < 2.5 < 3.1 < 7.3 Zr-95 < 4.4 < 6.7 < 20.5 Nb-95 < 3.6 < 5.7 < 18.0 Co-58 < 2.8 < 4.3 < 10.2 Mn-54 < 2.1 < 3.7 < 7.3 Zn-65 < 4.5 < 7.3 < 15.5 Fe-59 < 6.4 < 8.5 < 24.4 Co-60 < 2.4 < 3.6 < 7.6 Sr-90 1 < 0.9 < 0.7 < 0.8 Ba-140 < 33.5 < 51.1 < 300 La-140 < 11.0 < 19.8 < 116.0 Ru-106 < 18.4 < 30.2 < 59.3 Ce-141 < 6.2 < 9.9 < 28.1 Ce-144 < 16.0 < 26.6 < 45.5 AcTh-228 11.0 +/- 12.8 < 14.7 < 29.6 K-40 < 30.7 < 40.2 < 106.0 Ni-63 < 20.4 < 21.7 Note 1: Less than values "<" are Minimum Detectable Concentration (MDC) values.

Note 2: A sample is positive if the result is greater than or equal to the MDC.

8-56

Table 8-21 LAND USE CENSUS - RESIDENCE and MILCH ANIMAL RESULTS 2008 The 2008 land use census indicated there were no new residences that were closer in proximity to IPEG. NEM maintains a complete nearest residence surveywith updated distances.

No milch animals were observed during this reporting period within the 5-mile zone nor were listed in the New York Agricultural Statistic Service. There are no animals producing milk for human consumption within five miles of Indian Point.

8-57

TABLE B-22 LAND USE CENSUS 2008 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES N RIVER RIVER 1788 41 River Road Tomkins Cove NNE RIVER RIVER 3111 Chateau Rive . John St. Peekskill NE 550 636 1907 122 Lower South St. Peekskill ENE 600 775 1478 1018 Lower South St. Peekskill E 662 785 1371 1103 Lower South St. Peekskill ESE 569 622 715 461 B Buchanan SE 553 564 1168 223 First St.

SSE 569 551 1240 5 Pheasant's Run Buchanan S 700 566 1133 320 nck SSW 755 480 1574 240 Eleventh St. nck SW 544 350 3016 8 St. Tomkins Cove WSW RIVER RIVER 2170 9 West Shore Dr. Tomkins Cove W RIVER RIVER 1919 712 Rt. 9W Tomkins Cove WNW RIVER RIVER 1752 770 Rt. 9W Tomkins Cove NW RIVER RIVER 1693 807 Rt.9W Tomkins Cove NNW RIVER RIVER 1609 4 River Rd. Tomkins Cove 8-58

APPENDIX C .

HISTORICAL TRENDS

APPENDIX C The past ten years of historical data for various radionuclides and media are presented both in tabular form and in graphical form to facilitate the comparison of 2008 data with historical values. Although other samples were taken and analyzed, values were only tabulated and plotted where positive indications were present.

Averaging only the positive values in these tables can result in a biased high value, especially, when the radionuclide is detected in only one or two quarters for the year.

'C-1

TABLE C-1 DIRECT RADIATION ANNUAL SURVEY 1998 to 2008 1998 14.0 15.0 16.0 1999 15.0 15.0 16.0 2000 14.0 15.0 16.0 2001 15.0 15.0 17.0 2002 15.0 15.0 14.0 2003 14.3 13.9 14.7 2004 13.0 13.0 14.0 2005 J4.1 14.1 15.9 2006 13.9 14.3 17.5 2007 14.4 14.6 18.8 2008 14.5 14.2 17.3 14.3 14.5 16.0 C-2

FIGURE C-1 DIRECT RADIATION 1998 to 2008 40.0~1---------------------------------------------------------------------------------------------------,

_Inner Ring 35.0 DOuter Ring

- Control Location 30.0

~ 25.0 1'0

I CJ 0::: 20.0 E

'2 1'0 Q)

~ 15.0 10.0 5.0 0.0 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 C-3

TABLE C-2 RADIONUCLIDES IN AIR 1998 to 2008 (pCi/m3) 1998 0.02 0.01 < Lc < Lc 1999 0.02 0.01 < Lc < Lc 2000 0.01 0.01 < Lc < Lc 2001 0.02 0.02 < Lc < Lc 2002 0.02 0.02 < Lc < Lc 2003 0.01 0.01 < Lc < Lc 2004 0.01 0.01 < Lc < Lc 2005 0.02 0.02 < Lc < Lc 2006 0.01 0.01 < Lc < Lc 2007 0.01 0.01 < Lc < Lc 2008 0.01 0.01 < Lc < Lc 0.02 0.01 < Lc < Lc Critical Level (Lc) is less than the aDCM required LLD.

<Lc indicates no positive values above sample critical level.

C-4

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1998 to 2008 0.05 ~--------------------------------------------------------------------------------------------------------------,

~ All Indicator Locations

- Control Location 0.04 0.03

~

uc.

0.02 0.01 0.00 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 This Figure includes ODCM and non-ODCM indicator locations 3

ODCM Required LLD for Gross Beta = 0.01 pCilm C-5

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1998 to 2008 (pC ilL) 1998 < Lc 220 < Lc < Lc 1999 191 318 < Lc < Lc 2000 190 267 < Lc < Lc 2001 < Lc 323 < Lc < Lc 2002 432 562 < Lc < Lc 2003 < Lc < Lc < Lc < Lc 2004 < Lc 553 < Lc < Lc 2005 < Lc 618 < Lc < Lc 2006 < Lc 386 < Lc < Lc 2007 < Lc < Lc < Lc < Lc 2008 < Lc < Lc < Lc < Lc 271 406 < Lc < Lc Critical Level (Ld is less than the aDCM required LLD.

<Lc indicates no positive values above sample critical level.

C-6

FIGURE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1998 to 2008 (pC ilL) 2000

~ Inlet (H-3) 1800

~ Discharge (H-3) 1600 1400 1200

...J

~ 1000 a.

800 600 400 200 0

1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 C-7

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1998 to 2008 (pC ilL) 1998 < Lc < Lc 1999 < Lc < Lc 2000 < Lc < Lc 2001 < Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc

< Lc < Lc Critical Level (Lc) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-8

FIGURE C-4 RADIONUCLIDES IN DRINKING WATER 1998 to 2008 (pCi/L) 2000 1800 1600 1400 1200

...J

~ 1000 Co NO IDENTIFIED NUCLIDES IN PREVIOUS TEN YEAR HISTORY 800 600 400 200 0

1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 C-9

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1998 to 2008 (pCi/kg, dry) 1998 < Lc < Lc 143 < Lc 1999 46 < Lc 200 238 2000 58 < Lc 179 231 2001 45 ,< Lc 230 427 2002 < Lc < Lc 221 238 2003 < Lc < Lc 124 73 2004 < Lc < Lc 104 138 2005 < Lc < Lc 156 36 2006 < Lc < Lc 120 < Lc 2007 < Lc < Lc 190 < Lc 2008 < Lc < Lc 187 < Lc 50 < Lc 167 197 Critical Level (Lc) is less than the ODCM required LLD.

<Lc indicates no positive values above sample critical level.

C-10

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 1998 to 2008 (pCi/kg, dry) 750T'--------------------------------------------,

~ Indicator (Cs-134) 650 I2Z] Control (Cs-134)

W Indicator (Cs-137) 550

-Control (Cs-137) 450

~

'C c) 350

~

(3 c.

250 150 50 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008

-50L-------------------------------------------------------------------------------------------------~

Cs-134 ODCM required LLD = 150 pCi/kg, dry Cs-137 ODCM required LLD = 175 pCilkg, dry C-11

TABLE C-6 BROADLEAF VEGETATION - Cs-137 1998 to 2008 (pCilkg, wet) 1998 < Lc < Lc 1999 < Lc 27 2000 28 < Lc 2001 7 .< Lc 2002 14 16 2003 14 < Lc 2004 10 < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc 15 22 Critical Level (Lc) is less than the aDCM required LLD.

<Lc indicates no positive values above sample critical level.

C-12

FIGURE C-6 Broad Leaf Vegetation - Cs-137 1998 to 2008 100.-------------------------------------------------------------------------------------------------~

~ Indicator (Cs-137)

D Control (Cs-137) 80 60 Q)

~

r::n

~

uc..

40 20 0 I ..... 1 <I..:s:,~~

I~~ 1""1 <.

I~"II 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008

. ODCM required LLD = 80 pCilkg, wet C-13

TABLE C-7 FISH AND INVERTEBRATES - Cs-137 1998 to 2008 (pCi/kg, wet) 1998 < Lc < Lc 1999 < Lc < Lc 2000 < Lc < Lc 2001 < Lc < Lc 2002 < Lc < Lc 2003 < Lc < Lc 2004 < Lc < Lc 2005 < Lc < Lc 2006 < Lc < Lc 2007 < Lc < Lc 2008 < Lc < Lc

< Lc < Lc Critical Level (Ld is less than the ODeM required LLD.

<Lc indicates no positive values above sample critical level.

C-14

FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1998 to 2008 200

~ Indicator (Cs-137) 180 D Control (Cs-137) 160 140 120 cu

~

cl 100

~

U C-80 NO IDENTIFIED Cs-137IN PREVIOUS TEN YEAR HISTORY 60 40 20 0

1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 aDCM required LLD = 150 pCilkg, wet C-15

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIXD D.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section D 3.5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are

. performed as part 'of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an InterlaboratorY Comparison Program, the JAF Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.

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 JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

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

It is important to note that the JAF Environmental Laboratory has participated in the NEI/NIST MAP for several years. There were 2 NIST samples included as part of the blind samples received each year. The JAF Environmental Laboratory was not able to participate in the program for 2008. This program is no longer sponsored by NEI. The NIST program has been cut back and did.not meet our QC needs for 2008. We are still working with NIST to stay involved in the NIST MAP for 2009, if it can meet our QC needs.

D-l

0.2 PROGRAM SCHEDULE TABLE 0-1 QA PROGRAM SCHEDULE SAMPLE LABORATORY SAMPLE PROVIDER MEDIA ANALYSIS* ANALYTICS Water Gross Beta 3 Water Tritium 5 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 1 Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 0.3 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.

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

D-2

An Environmental Laboratory analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

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

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

The value for the ratio is then calculated.

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

TABLE 0*2 RATIO OF AGREEMENT ERROR RESOLUTION RATIO OF AGREEMENT

<4 No Comparison 4to 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 acceptance criteria are contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QAJQC program report when results are unacceptable.

D-3

0.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 0-3.

0.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2008 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

• Air Charcoal Cartridge: 1-131

• Air Particulate Filter: Mixed Gamma Emitters, Gross Beta

• Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta

• Soil: Mixed Gamma Emitters

• Milk: 1-131, Mixed Gamma Emitters

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

There were no non-conformities in the 2008 program.

D-4

0.4.3 NUMERICAL RESULTS TABLES TABLE 0-3 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE 10 NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma (1 )

57.0 +/- 1.9 06/19/2008 E5914-05 Filter Gross Beta 57.8 +/- 1.9 52.2 +/- 0.871 1.07 A 52.9 +/- 1.9 Mean = 55.9 +/- 1.1 51.7 +/- 0.8 E5940-09 Filter Gross Beta 51.4 +/- 0.8 06/19/2008 49.2 +/- 0.822 1.04 A 51.0 +/- 0.8 Mean = 51.4 +/- 0.5 123.6 +/- 1.9 E6368-05 Filter Gross Beta 125.5 +/- 1.9 12/11/2008 113 +/- 1.89 1.09 A 119.9 +/- 1.9 Mean = 123 +/- 1.1 (1) Ratio = Reported/Analytics.

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

TABLE 0*3 (Continued)

Tritium Analysis of Water SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma (1 )

4265 +/- 170 4244 +/- 170 3/20/2008 E5822-05 Water H-3 4010 +/- 67 1.06 A 4201 +/- 169 Mean = 4237 +/- 98 860 +/- 136 994 +/- 137 6/19/2008 E5913-05 Water H-3 843 +/- 14.1 1.06 A 832 +/- 136 Mean = 895 +/- 79 1017 +/- 134 978 +/- 134 9/18/2008 E6248-05 Water H-3 996 +/- 16.6 0.98 A 937 +/- 134 Mean = 977 +/- 77 10501 +/- 207 10401 +/- 207 12/11/2008 E6359-09 Water H-3 1.02E+04 +/- 1.70E+02 1.02 A 10441 +/- 207 Mean = 10448 +/- 120 10483 +/- 207 10564 +/- 208 12/11/2008 E6360-09 Water H-3 1.02E+04 +/- 1.70E+02 1.03 A 10355 +/- 206 Mean = 10467 +/- 120 (1) Ratio = Reported/Analytics.

• Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable D-6

TABLE 0-3 (Continued)

Gross Beta Analysis of Water SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE IDNO. MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma (1 )

2.26E+02 +/- 2.30E+00 03/20/2008 E5822-05 Water Gross Beta 2.29E+02 +/- 2.30E+00 2.30E+02 +/- 3.84E+00 0.98 A 2.23E+02 +/- 2.30E+00 Mean = 2.26E+02 +/- 1.33E+00 1.38E+02 +/- 1.80E+00 1.40E+02 +/- 1.80E+00 06/19/2008 E5919-05 Water Gross Beta 1.49E+02 +/- 2.49E+00 0.93 A 1.37E+02 +/- 1.70E+00 Mean = 1.38E+02 +/- 1.02E+00 2.76E+02 +/- 2.60E+00 2.76E+02 +/- 2.60E+00 09/18/2008 E6253-05 Water Gross Beta 2.90E+02 +/- 4.85E+00 0.95 A 2.75E+02 +/- 2.60E+00 Mean = 2.76E+02 +/- 1.50E+00 (1) Ratio = Reported/Analytics.

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

TABLE 0*3 (Continued) 1*131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REF. LAB* RATIO DATE 10 NO. MEDIUM ANALYSIS pCi +/-1 sigma . pCi +/-1 sigma (1 )

65.8 +/- 2.95 E5845-09 Air 1-131 63.7 +/- 2.88 60.0 +/- 1.0 1.06 A 3/20/2008 61.7 +/- 3.13 Mean = 63.7 +/- 1.73 79.8 +/- 4.1 81.4 . +/- 3.02 6/19/2008 E5917-05* Air 1-131 84.8 +/- 1.42 0.97 A 85.8 +/- 3.51 Mean = 82.3 +/- 2.06 87.4 +/- 2.6 85.3 +/- 2.62 9/18/2008 E6301-09 Air 1-131 87.7 +/- 1.46 1.01 A 92.5 +/- 2.86 Mean = 88.4 +/- 1.56 83.6 +/- 3.29 90.1 +/- 2.57 9/18/2008 E6252-05 Air 1-131 82.0 +/- 1.37 1.04 A 83.1 +/- 2.69 Mean = 85.6 +/- 1.66 (1) Ratio = Reported/Analytics.

• Sample provided by Eckert & Ziegler Analytics A:::Acceptable U:::Unacceptable D-8

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 fW ater Gamma A nalysis REF. LAB*

SAMPLE JAF ELAB RESULTS pCilliter +/-1 RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1 )

3/20/2008 E5820-05 Water 208 +/- 5.87 200 +/- 8.89 Ce-141 198 +/- 3.31 1.04 A 210 +/- 8.46 Mean = 206 +/- 4.5 320 +/- 27.1 280 +/- 34.8 Cr-51 286 +/- 4.77 1.11 A 349 +/- 33.4 Mean = 316 +/- 18.4 105 +/- 3.89 109 +/- 6 Cs-134 99.7 +/- 1.67 1.08 A 109 +/- 5.42 Mean = 108 +/- 3.0 120 +/- 4.23 137 +/- 6.1 Cs-137 116 +/- 1.94 1.07 A 116 +/- 5.64 Mean = 124 +/- 3.1 55.7 +/- 3.55 Co-58 66.1 +/- 4.81 56.4 +/- 0.941 1.03 A 51.8 +/- 4.76 Mean = 57.9 +/- 2.5 79.6 +/- 3.87 84.7 +/- 4.98 Mn-54 75 +/- 1.25 1.10 A 84 +/- 5.18 Mean = 82.8 +/- 2.7 97.2 +/- 5.38 Fe-59 75.8 +/- 6.29 81.4 +/- 1.36 1.07 A 87.8 +/- 6.72 Mean = 86.9 +/- 3.6 108 +/- 7.79 129 +/- 10.6 Zn-65 109 +/- 1.82 1.05 A 106 +/- 10.3 Mean = 114 +/- 5.6 198 +/- 4.15 Co-60 180 +/- 5.46 188 +/- 3.14 1.02 A 198 +/- 5.56 Mean = 192 +/- 2.9 72.9 +/- 1.9 1-131**

72.2 +/- 1.88 70.4 +/- 1.18 1.04 A 73.8 +/- 3.6 Mean = 73.0 +/- 1.5 (1) RatiO = ReportedlAnalvtlcs. A=Acceptable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-9

TABLE 0*3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 fW ater Gamma Analysis REF. LAB*

SAMPLE JAF ELAB RESUL TS pCi/liter +/-1 RATIO DATE IDNO. MEDIUM ANALYSIS pCi/liter +/-1 sigma siQma (1 )

6/19/2008 E5939-09 Water 252 +/- 3.35 Ce-141 235 +/- 7.01 237 +/- 3.96 1.04 A 252 +/- 2.93 Mean = 246 +/- 2.8 213 +/- 13.8 Cr-51 192 +/- 23.4 188 +/- 3:14 1.10 A 215 +/- 13.1 Mean = 207 +/- 10.1 112 +/- 1.71 Cs-134 115 +/- 4.29 104 +/- 1.74 1.08 A 109 +/- 1.58 Mean = 112 +/- 1.6 160 +/- 1.95 Cs-137 154 +/- 4.46 158 +/-. 2.64 1.00 A 161 +/- 1.84 Mean = 158 +/- 1.7 90 +/- 1.66 Co-58 91 +/- 3.85 84 +/- 1.41 1.G6 A 89 +/- 1.59 Mean = 90 +/- 1.5 208 +/- 2.22 Mn-54 192 +/- 4.95 184 +/- 3.07 1.10 A 207 +/- 2.11 Mean = 202 +/- 1.9 139 +/- 2.48 Fe-59 136 +/- 5.47 125 +/- 2.08 1.09 A 133 +/- 2.51 Mean = 136 +/- 2.2 192 +/- 3.29 Zn-65 185 +/- 7.78 172 +/- 2.88 1.08 A 180 +/- 3.12 Mean = 186 +/- 3.0 147 +/- 1.4 Co-60 145 +/- 3.3 142 +/- 2.37 1.03 A 148 +/- 1.35 Mean = 147 +/- 1.3 47 +/- 4.17 37 +/- 2.24 1-131** 44 +/- 1.04 45.3 +/- 0.756 0.92 A 40 +/- 2.5 Mean = 42 +/- 1.4 (1) Ratio = Reported/Analvtlcs. A=Acceptable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-lO

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 fW ater Gamma Analysis REF. LAB*

SAMPLE JAF ELAB RESULTS pCi/liter +/-1 RATIO DATE IDNO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1 )

9/18/2008 E6249-05 Water 108 +/- 6.03 113 +/- 4.98 Ce-141 109 +/- 4.9 107 +/- 1.78 1.04 A 115 +/- 4.42 Mean = 111 +/- 2.6 335 +/- 31.3 268 +/- 20.8 Cr-51 297 +/- 23.3 279 +/- 4.65 1.08 A 307 +/- 20.7 Mean = 302 +/- 12.2 197 +/- 5.89 143 +/- 8.08 Cs-134 168 +/- 4.9 154 +/- 2.56 1.11 A 176 +/- 4.14 Mean = 171 +/- 3.0 116 +/- 5.11 114 +/- 3.98 Cs-137 102 +/- 3.88 107 +/- 1.79 1.03 A 110 +/- 3.46 Mean = 111 +/- 2.1 128 +/- 5.16 125 +/- 3.98 Co-58 119 +/- 4 118 +/- 1.97 1.06 A 128 +/- 3.77 Mean = 125 +/- 2.1 122 +/- 5.4 118 +/- 4.02 Mn-54 131 +/- 4.24 110 +/- 1.84 1.13 A 127 +/- 3.68 Mean = 125 +/- 2.2 111 +/- 6.1 105 +/- 4.37 Fe-59 103 +/- 4.5 96 +/- 1.6 1.13 A 115 +/- 4.11 Mean = 109 +/- 2.4 218 +/- 10.9 217 +/- 8.18 Zn-65 239 +/- 8.68 211 +/- 3.53 1.05 A 216 +/- 7.7 Mean = 223 +/- 4.5 162 +/- 4.47 149 +/- 3.39 Co-60 158 +/- 3.52 155 +/- 2.59 1.02 A 163 +/- 3.08 Mean = 158 +/- 1.8 109 +/- 2.21 102 +/- 2.06 1-131** 105 +/- 1.75 1.00 A 105 +/- 2.03 Mean = 105 +/- 1.2 (1) Ratio = Reoorted/Analvtlcs. A=Acceotable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-ll

TABLE 0*3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 fW ater Gamma Analysis ..

REF. LAB*

SAMPLE JAF ELAB RESUL TS pCilliter +/-1 RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1')

12/11/2008 E6361-09 Water 240 +/- 4.38 Ce-141 229 +/- 5.95 224 +/- 3.74 1.06 A 244 +/- 4.4 Mean = 238 +/- 2.9 324 +/- 20.5 Cr-51 274 +/- 26.6 288 +/- 4.81 0.99 A 254 +/- 22.8 Mean = 284 +/- 13.5 169 +/- 2.4 Cs-134 162 +/- 3.46 157 +/- 2.62 1.05 A 165 +/- 2.76 Mean = 165 +/- 1.7 139 +/- 2.2 136 +/- 2.95 Cs-137 140 +/- 2.34 0.99 A 140 +/- 2.63 Mean = 138 +/- 1.5 123 +/- 2.29 Co-58 126 +/- 3.24 122.0 +/- 2.03 1.02 A 125 +/- 2.71 Mean = 124.7 +/- 1.6 189 +/- 2.59 Mn-54 183 +/- 3.43 178 +/- 2.97 1.04 A 183 +/- 3.01 Mean = 185 +/- 1.7 136 +/- 3.26 Fe-59 122 +/- 4.29 117.0 +/- 1.96 1.09 A 126 +/- 3.97 Mean = 128 +/- 2.2 222 +/- 4.54 228 +/- 6.06 Zn-65 214 +/- 3.57 1.06 A 230 +/- 5.21 Mean = 227 +/- 3.1 163 +/- 1.79 162 +/- 2.36 Co-60 156 +/- 2.6 1.04. A 160 +/- 2.16 Mean = 162 +/- 1.2 74.8 +/- 7.12 1-131**

58.3 +/- 4.07 +/- 1.03 64.1 1.07 A 64.1 +/- 7.2 Mean = 65.7 +/- 3.6 (1) Ratio = Reported/Analvtlcs. A=Acceptable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-12

TABLE 0*3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis I " 0 fM"lk I REF. LAB*

SAMPLE JAF ELAB RESULTS pCi/liter +/-1 RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1 )

3/20/2008 E5846-09 Milk 240 +/- 13.8 245 +/- 11.9 Ce-141 249 +/- 4.2 0.97 A 236 +/- 6.8 Mean = 240 +/- 6.5 371 +/- 65.6 384 +/- 50.4 Cr-51 359 +/- 6.0 1.04 A 370 +/- 30.2 Mean = 375 +/- 29.4 115 .+/- 11.4 121 +/- 8.0 Cs-134 125 +/- 2.1 0.96 A 124 +/- 6.0 Mean = 120 +/- 5.1 147 +/- 10.9 143 +/- 8.9 Cs-137 146 +/- 2.4 0.97 A 135 +/- 5.1 Mean = 142 +/- 5.0 70.2 +/- 10.1 64.2 +/- 7.2 Co-58 71.0 +/- 1.2 0.96 A 70.4 +/- 4.6 Mean = 68.3 +/- 4.4 95.2 +/- 10.6 107 +/- 8.1 Mn-54 94 +/- 1.6 1.08 A 102 +/- 4.7 Mean = 101 +/- 4.7 120 +/- 15.2 125 +/- 10.6 Fe-59 102 +/- 1.7 1.12 A 98 +/- 6.6 Mean = 114 +/- 6.6 119 +/- 27.3 158 +/- 15.1 Zn-65 137 +/- 2.3 0.99 A 128 +/- 9.9 Mean = 135 +/- 10.9 239 +/- 10.9 225 +/- 8.4 Co-60 236 +/- 4.0 0.98 A 229 +/- 5.1 Mean = 231 +/- 4.9 59.6 +/- 8.6 61.7 +/- 6.5 1-131 ** 60.0 +/- 1.0 1.01 A 60.7 +/- 5.5 Mean = 60.7 +/- 4.0 (1) Ratio::: Reported/Analvtlcs. A=Acceptable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-13

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis I " 0 fM"lk I REF. LAB*

SAMPLE JAF ELAB RESULTS pCi/liter +/-1 RATIO DATE IDNO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1 )

6/19/2008 E5915-05 Milk 173 +/- 6.4 177 +/- 7.9 Ce-141 174 +/- 2.91 1.01 A 177. +/- 6.8 Mean = 176 +/- 4.1 185 +/- 24.7 163 +/- 30.8 Cr-51 138 +/- 2.31 1.21 A 152 +/- 30.7 Mean = 167 +/- 16.7 81 +/- 3.6 Cs-134 80 +/- 5.3 77 +/- 1.28 1.07 A 85 +/- 4.4 Mean = 82 +/- 2.6 113 +/- 4.1 Cs-137 114 +/- 5.5 116 +/- 1.94 1.00 A 122 +/- 5.0 Mean = 116 +/- 2.8 59.6 +/- 3.6 Co-58 54.9 +/- 4.3 61.9 +/- 1.03 0.99 A 70.1 +/- 4.4 Mean = 61.5 +/- 2.4 145 +/- 4.5 146 +/- 6.1 Mn-54 135 +/- 2.26 1.09 A 149 +/- 5.5 Mean = 147 +/- 3.1

.94 +/- 4.9 99 +/- 6.9 Fe-59 92 +/- 1.53 1.05 A 97 +/- 5.7 Mean = 97 +/- 3.4 120 +/- 7.5 132 +/- 10.1 Zn-65 127 +/- 2.12 0.98 A 123 +/- 9.3 Mean = 125 +/- 5.2 111 +/- 3.2 104 +/- 4.1 Co-60 104 +/- 1.74 1.04 A 108 +/- 3.8 Mean = 108 +/- 2.1 58.9 +/- 2.7 1-131**

66.6 +/- 2.9 71 +/- 1.19 0.88 A 62.1 +/- 3.0 Mean = 62.5 +/- 1.7 (1) Ratio = Reoorted/Analvtlcs. A=Acceotable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-14

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis I " 0 fM"lk I REF. LAB*

SAMPLE JAF ELAB RESUL TS pCi/liter +/-1 RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/liter +/-1 sigma sigma (1 )

9/18/2008 E6251-05 Milk 168 +/- 7.29 Ce-141 172 +/- 7.69 161 +/- 2.69 1.05 A 168 +/- 6.76 Mean = 169 +/- 4.19 411 +/- 34.9 429 +/- 37.2 Cr-51 421 +/- 7.03 1.03 A 456 +/- 32.0 Mean = 432 +/- 20.1 241 +/- 7.47 241 +/- 7.81 Cs-134 232 +/- 3.87 1.03 A 236 +/- 6.49 Mean = 239 +/- 4.20 167 +/- 5.86 173 +/- 6.86 Cs-137 162 +/- 2.71 1.02 A 155 +/- 5.23 Mean = 165 +/- 3.48 188 +/- 6.03 177 +/- 6.60 Co-58 179 +/- 2.98 1.01 A 177 +/- 5.34 Mean = 181 +/- 3.47 193 +/- 6.24 Mn-54 189 +/- 7.16 166 +/- 2.77 1.14 A 184 +/- 5.65 Mean = 189 +/- 3.68 150 +/- 6.92 143 +/- 7.97 Fe-59 144 +/- 2.41 1.04 A 158 +/- 3.63 Mean = 150 +/- 3.72 326 +/- 13.3 302 +/- 15.1 Zn-65 319 +/- 5.33 1.01 A 342 +/- 11.9 Mean = 323 + 7.79 242 +/- 5.31 242 +/- 6.25 Co-60 234 +/- 3.91 1.02 A 231 +/- 4.75 Mean = 238 + 3.16 61.3 +/- 2.17 61.6 +/- *1.73 1-131** 67.9 +/- 1.13 0.89 A 59.3 +/- 1.75 Mean = 60.7 + 1.09 (1) RatIO = Reoorted/Analvtlcs. A=Acceotable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable

• • Result determined by Resin Extraction/Gamma Spectral Analysis.

D-15

TABLE 0*3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REF. LAB* RATIO DATE 10 NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma (1 )

3/20/2008 E5821-05 Filter 204 +/- . 2.42 Ce-141 192 +/- 4.23 179 +/- 2.99 1.09 A 189 +/- 4.24 Mean = 195 +/- 2.15 305 +/- 10.7 300 +/- 18.0 Cr-51 259 +/- 4.32 1.15 A 289 +/- 20.9 Mean = 298 + 9.86 102 +/- 2.64 107 +/- 4.06 Cs-134 90.2 +/- 1.51 1.18 A 110 +/- 4.50 Mean = 106.3 +/- 2.20 115 +/- 2.40 116 +/- 3.81 Cs-137 105 +/- 1.75 1.11 A 120 +/- 4.42 Mean = 117 +/- 2.10 57 +/- 2.00 56.4 +/- 3.06 Co-58 51.0 +/- 0.852 1.10 A 55.5 +/- 3.48 Mean = 56.3 +/- 1.68 80.6 +/- 2.18 85.3 +/- 3.48 Mn-54 67.8 +/- 1.13 1.23 A 85.1 +/- 4.19 Mean = 84 +/- 1.96 94.7 +/- 3.03 86.3 +/- 4.94 Fe-59 73.7 +/- 1.23 1.22 A 88.9 +/- 5.80 Mean = 90.0 + 2.73 116 +/- 4.59 Zn-65 124 +/- 7.13 98.6 +/- 1.65 1.19 A 111 +/- 8.56 Mean = 117 +/- 4.02 182 +/- 2.55 Co-60 181 +/- 3.91 170 +/- 2.84 1.06 A 176 +/- 4.65 Mean = 180 +/- 2.20 (1) RatiO = Reported/Analytics.

• Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable D-16

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE IDNO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma (1 )

9/18/2008 E6250-05 Filter 170 +/- 4.28 Ce-141 170 +/- 3.6 159 +/-' 2.65 1.07 A 172 +/- 3.95 Mean = 171 +/- 2.3 431 +/- 25.1 452 +/- 21.2 Cr-51 415 +/- 6.92 1.11 A 497 +/- 21.6 Mean = 460 +/- 13.1 267 +/- 7.48 257 +/- 6.33 Cs-134 229 +/- 3.82 1.16 A 270 +/- 6.1 Mean = 265 +/- 3.8 163 +/- 5.88 163 +/- 4.96 Cs-137 160 +/- 2.67 1.02 A 162 +/- 4.71 Mean = 163 +/- 3.0 179 +/- 6.18 200 +/- 5.36 Co-58 176 +/- 2.93 1.08 A 191 +/- 4.91 Mean = 190 +/- 3.2 185 +/- 6.69 196 +/- 5.68 Mn-54 164 +/- 2.73 1.18 A 199 +/- 5.21 Mean = 193 +/- 3.4 169 +/- 7.73 164 +/- 6.55 Fe-59 142 +/- 2.37 1.16 A 160 +/- 5.79 Mean = 164 +/- 3.9 345 +/- 14 371 +/- 12.6 Zn-65 314 +/- 5.25 1.15 A 366 +/- 10.8 Mean =. 361 +/- 7.2 228 +/- 5.87 238 +/- 4.89 Co-60 231 +/- 3.85 1.01 A 231 +/- 4.45 Mean = 232 +/- 2.9 (1) Ratio = Reported/Analytics.

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

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM G amma A nalysis I " 0 fS"1 01 SAMPLE JAF ELAB RESULTS REF. LAB* RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-1 sigma (1 )

6/19/2008 E5916-05 Soil 0.359 +/- 0.015 0.364 +/- 0.014 Ce-141 0.381 +/- 0.008 0.380 +/- 0.006 0.98 A 0.386 +/- 0.013 Mean = 0.373 +/- 0.006 0.345 +/- 0.089 0.276 +/- 0.056 Cr-51 0.346 +/- 0.035 0.302 +/- 0.005 1.03 A 0.277 +/- 0.059 Mean = 0.311 +/- 0.031 0.173 +/- 0.011 0.167 +/- 0.010 Cs-134 0.164 +/- 0.005 0.167 +/- 0.003 1.03 A 0.182 +/- 0.006 Mean = 0.172 +/- 0.004 0.317 +/- 0.012 0.324 +/- 0.012 Cs-137 0.334 +/- 0.006 0.340 +/- 0.006 0.96 A 0.333 +/- 0.007 Mean = 0.327 +/- 0.005 0.117 +/- 0.011 0.122 +/- 0.009 Co-58 0.118 +/- 0.005 0.135, +/- 0.002 0.89 A 0.123 +/- 0.006 Mean = 0.120 +/- 0.004 0.289 +/- 0.013 0.301 +/- 0.012 Mn-54 0.314 +/- 0.006 0.295 +/- 0.005 1.02 A 0.294 +/- 0.007 Mean = 0.300 +/- 0.005 0.173 +/- 0.015 0.194 +/- 0.014 Fe-59 0.185 +/- 0.007 0.200 +/- 0.003 0.93 A 0.190 +/- 0.010 Mean = 0.186 +/- 0.006 0.257 +/- 0.020 0.289 +/- 0.018 Zn-65 0.281 +/- 0.009 0.277 +/- 0.005 0.98 A 0.256 +/- 0.011 Mean = 0.271 +/- 0.008 0.220 +/- 0.009 0.206 +/- 0.008 Co-60 0.214 +/- 0.004 0.228 +/- 0.004 0.93 A 0.208 +/- 0.005 Mean = 0.212 +/- 0.003 (1) Ratio = Reported/Analytlcs. A=Acceptable

• Sample provided by Eckert & Ziegler Analytics U=Unacceptable D-18

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 tVege t at'Ion Gamma A nalysis SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-1 sigma (1 )

6/19/2008 E5918-05 Vegetation 0.381 +/- 0.019 0.371 +/- 0.015 0.390 +/- 0.007 Ce-141 0.95 A 0.358 +/- 0.013 Mean = 0.370 +/- 0.009 0.311 +/- 0.081 0.371 +/- 0.065 Cr-51 0.309 +/- 0.005 1.14 A 0.378 +/- 0.054 Mean = 0.353 +/- 0.039 0.171 +/- 0.016 0.176 +/- 0.013 Cs-134 0.172 +/- 0.003 1.03 A 0.184 +/- 0.010 Mean = 0.177 +/- 0.008 0.272 +/- 0.015 Cs-137 0.257 +/- 0.013 0.260 +/- 0.004 0.98 A 0.235 +/- 0.011 Mean = 0.255 +/- 0.008 0.152 +/- 0.013 0.142. +/- 0.011 Co-58 0.138 +/- 0.002 1.03 A 0.131 +/- 0.009 Mean = 0.142 +/- 0.006 0.293 +/- 0.016 0.325 +/- 0.015 Mn-54 0.302 +/- 0.005 1.02 A 0.306 +/- 0.012 Mean = 0.308 +/- 0.008 0.207 +/- 0.018 0.215 +/- 0.017 Fe-59 0.205 +/- 0.003 1.04 A 0.219 +/- 0.014 Mean = 0.214 + 0.009 0.306 +/- 0.027 0.240 +/- 0.022 Zn-65 0.284 +/- 0.005 0.97 A 0.282 +/- 0.019 Mean = 0.276 +/- 0.013 0.216 +/- 0.011 0.235 +/- 0.011 Co-60 0.233 +/- 0.004 0.95 A 0.212 +/- 0.008 Mean = 0.221 +/- 0.006 (1) Ratio = Reported/Analytics.

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

TABLE 0-3 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM I . 0 fV egetaf Ion Gamma A nalYSIS SAMPLE JAF ELAB RESUL TS REF. LAB* RATIO DATE 10 NO. MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +/-1 sigma (1 )

9/18/2008 E6302-09 Vegetation 0.447 +/- 0.023 0.447 +/- 0.017 Ce-141 0.474 +/- 0.008 0.96 A 0.473 +/- 0.018 Mean = 0.456 +/- 0.011 1.200 +/- 0.129 1.160 +/- 0.086 Cr-51 1.240 +/- 0.021 0.95 A 1.170 +/- 0.098 Mean = 1.177 +/- 0.061 0.760 +/- 0.031 0.738 +/- 0.024 Cs-134 0.683 +/- 0.011 1.08 A 0.708 " +/- 0.026 Mean = 0.735 +/- 0.016 0.407 +/- 0.024 0.422 +/- 0.017 Cs-137 0.477 +/- 0.008 0.87 A 0.417 +/- 0.020 Mean = 0.415 +/- 0.012 0.552 +/- 0.027 0.500 +/- 0.019

" Co-58 0.525 +/- 0.009 0.98 A 0.492 +/- 0.020 Mean = 0.515 +/-" 0.013 0.467 +/- 0.027 0.503 +/- 0.019 Mn-54 0.489 +/- 0.008 1.01 A 0.518 +/- 0.022 Mean = 0.496 +/- 0.013 0.382 +/- 0.030 0.432 +/- 0.021 Fe-59 0.425 +/- 0.007 0.97 A 0.428 +/- 0.025 Mean = 0.414 +/- 0.015 0.808 +/- 0.056 0.917 +/- 0.040 Zn-65 0.939 +/- 0.016 0.94 A 0.930 +/- 0.046 Mean = 0.885 +/- 0.027 0.673 +/- 0.024 0.659 +/- 0.016 Co-60 0.690 +/- 0.012. 0.95 A 0.632 +/- 0.018 Mean = 0.655 +/- 0.008 (1) Ratio = Reported/Analytics .

.. Sample provided by Eckert & Ziegler Analytics A=Acceptable U=Unacceptable D-20

0.5 REFERENCES

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

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

D-21