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Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000310 - 2007 Annual Radiological Environmental Operating Report (NL-08-081) (May 15, 2008)
	ML12089A660
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Site:	Indian Point
Issue date:	05/15/2008
From:	Robert Walpole; Indian Point
To:	; Atomic Safety and Licensing Board Panel, Document Control Desk, Office of Nuclear Reactor Regulation
	SECY RAS
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	RAS 22135, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, NL-08-081
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ENT000310 Submitted: March 29, 2012 Indian Point Energy Center 450 Broadway, GSB

-===- Entergy.

P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 May 15, 2008 Robert Walpole Manager, Licensing Re:

Indian Point Units 1, 2 & 3 Docket Nos.50-003, 50-247, 50-286 NL-08-081

Subject:

Indian Point Nuclear Power Plants Units 1, 2 and 3 Annual Radiological Environmental Operating Report for 2007 Dear Sir or Madam; Enclosed please find one copy of the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Energy Center (IPEC) site Annual Radiological Environmental Operating Report for the period January 1, 2007 to December 31, 2007.

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.

Enclosure cc: wlo enclosure Sincerely yours,

~obert Walpo e Manager, Licensing Indian Point Energy Center Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service Mr. Paul D. Tonko, President NYSERDA 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, 2007

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:'5 3.4.1 Lower Limit of Detection and Critical Level 3-5 3.4.2 Determination of Mean and Propagated Error 3-6 3.4.3 Table Statistics 3-7

TABLE OF CONTENTS {continued}

Page 4.0 RESUL TS 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 4-7 4.11 Soil 4-8 4.12 Groundwater 4-8 4.13 Land Use Census 4-9 4.14 Conclusion 4-10

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-S A-2 Sampling Locations (Greater Than Two Miles)

A-6 A-3 Additional Sampling Locations A-7 C-1 Direct Radiation, 1997 to 2007 C-3 C-2 Radionuclides in Air - Gross Beta, 1997 to 2007 C-S C-3 Hudson River Water-Tritium, 1997 to 2007 C-7 C-4 Drinking Water - Tritium, 1997 to 2007 C-9 C-S Radionuclides in Shoreline Soil, 1997 to 2007 C-11 C-6 Broad Leaf Vegetation - Cs-137, 1997 to 2007 C-13 C-7 Fish and Invertebrates - Cs-137, 1997 to 2007 C-1S 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, 2007 8-2 8-1a 2007 Air Sampling Deviations 8-3 8-1b 2007 TLD Deviations 8-3 8-1c 2007 Other Media Deviations 8-3 8-2 ODCM Annual Summary, 2007 8-4 8-3 2007 Direct Radiation, Quarterly Data 8-9 8-4 Direct Radiation, 1997 through 2007 Data 8-10 8-5 2007 Direct Radiation, Inner and Outer Rings 8-11 8-6 Environmental Airborne Particulate Samples - 2007 Gross 8eta Activity 8-12 8-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples, 2007 8-14 8-8 Environmental Charcoal Cartridge Samples - 2007 1-131 Activity 8-16 8-9 Concentrations of Gamma Emitters in Surface Water Samples, 2007 8-18 8-10 Concentrations of Tritium in Surface Water Samples, 2007 8-20 8-11 Concentrations of Gamma Emitters in Drinking Water Samples, 2007 8-21 8-12 Concentrations of Tritium in Drinking Water Samples, 2007 8-23 8-13 Concentrations of Radionuclides in Shoreline Soil Samples, 2007 8-24 8-14 Concentrations of Gamma Emitters in 8road Leaf Vegetation Samples, 2007 8-26 iv

LIST OF TABLES (Continued)

TABLE TITLE Page 8-15 Concentrations of Radionuclides in Fish Samples, 2007 8-35 8-16 Concentrations of Gamma Emitters in Aquatic Vegetation Samples, 2007 8-40 8-17 Concentrations of Gamma Emitters in 8ottom Sediment Samples, 2007 8-41 8-18 Concentrations of Radionuclides in Rainwater Samples, 2007 8-43 8-19 Concentrations of Gamma Emitters in Soil Samples, 2007 8-45 8-20 Concentrations of Gamma Emitters in Surface Water Samples, 2007 8-46 8-21 Concentrations of Radionuclides in Monitoring Well Samples, 2007 8-49 8-22 Milch Animal Census, 2007 8-62 8-23 Land Use Census, 2007 8-64 C-1 Direct Radiation Annual Summary, 1997 to 2007 C-2 C-2 Radionuclides in Air, 1997 to 2007 C-4 C-3 Radionuclides in Hudson River Water, 1997 to 2007 C-6 C-4 Radionuclides in Drinking Water, 1997 to 2007 C-8 C-5 Radionuclides in Shoreline Soil, 1997 to 2007 C-10 C-6 Radionuclides in 8road Leaf Vegetation, 1997 to 2007 C-12*

C-7 Radionuclides in Fish and Invertebrates, 1997 to 2007 C-14 0-1 QA Program Schedule 0-2 0-2 Ratio of Agreement 0-3 0-3 Interlaboratory Comparison Program 0-5 v

SECTION I EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report (AREOR) contains descriptions and results of the 2007 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 s'uch, 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 thermolumines~ent 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 soil. 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 2007 AREOR also contains summaries and discussions of the results of the 2007 program, treild analyses, potential impact on the environment, land use census, and interlaboratory comparisons.

During 2007, a total of 1312 analyses were performed. Table 8-1 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 2007. 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, as well as gamma spectroscopy analysis. These wells (MW-40 and MW-S1) were designated as REMP sample stations 104 and 105. In addition, a change was made to the existing fish and invertebrate samples and shoreline soil 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 2007. These changes are captured in the ODeM. Groundwater sample results for 2001' are summarized in Table 8-21.

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 2007 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 2007; however, residual radioactivity from atmospheric weapons tests and naturally occurring radioactivity were the predominant sources of radioactivity in the samples collected. Analysis of the 2007 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 fishlinvertebrate 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, Inc.,

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 laborator!es.

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 (i.e., total integrated exposures in milliroentgen, 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 (A 1), 5 (A4), 22, 27, 29, 44, 94 (A2), and 95 (A3). The locations are shown 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.

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, gross beta, and 1-131. 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-3 show 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 and for strontium-90.

In 2007, additional sampling of fish was performed further upstream in the Hudson River, to confirm the acceptability of Roseton as the control location. Samples from all three locations were split with the US NRC and the New York State Department of Environmental Conservation. The results of this effort are described in Section 4.0 of this report 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 are 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, strontium-90 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

The milch animal census is used to identify animals producing milk for human consumption within 5 miles (8 km) of Indian Point. The 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). 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 aDCM allows sampling of vegetation in two sectors near the site boundary in lieu of a garden census.

3.4 Statistical Methodology There are 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 (LLDl 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 used to calculate the LLD is:

LLD = 4.66 K Sb, where:

Sb = standard deviation of the background count rate, 3-5

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 aDCM program, LLDs are used to ensure that minimum 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 aDCM required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are usually much lower since the aDCM required LLDs represent the maximum allowed.

The critical level (Lc) 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.

where:

Lc = ka Sb (1 + T tlTsl* 5 in cpm 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 Lc value are considered not detected, and the Lc value is reported as the "less than" value, unless otherwise noted. Values above the Lc 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, 3-6

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 propagated error (PE) are calculated using the following equations:

where:

N LXi X=~

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

L(ERRJ PE =

-,--,-i=...:....1 __

N ERR; = 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 "<" 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 3-7

beta radioactivity in air, which show positive monitoring results throughout the year.

In the data tables 8-6 through 8-21, 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 "<" 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 1997 through 2006.

The 2007 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 2007 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 2007 and assessed the significance of the findings.

A summary of the results of the 2007 REMP is presented in Table 8-2. 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, 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 2007 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 2007, the detected radionuclide that may be attributable to past atmospheric weapons testing consisted of Cs-137 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 2007 REMP comprises those that may be attributable to current plant operations.

During 2007, Cs-137, 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 5 of 45 samples at levels which were much lower than the required Lower Limit of Detection (3000 pCi/Liter); 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 2007. Cs-137 is ubiquitous in the environment from atmospheric testing debris and a lesser amount from the Chernobyl accident. Strontium-90 (Sr-90) is also present in the environment from atmospheric testing debris. In 2007, there were several detections of Cs-137 in shoreline soil (2 indicator samples and one control sample),

aquatic vegetation (1 indicator station sample), bottom sediment (6 indicator and one control sample), soil (1 indicator location) and 5 groundwater samples. The fact that there was no Cs-134 present (recent plant releases 4-2

would contain Cs-134) and that there were detections also at control locations indicates that the activity was likely due to atmospheric weapons testing, with some contribution from plant releases from several years past.

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 annual reports. 1-131 was not detected in 2007.

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 2007 REMP, though they (Co-58 and Co-60) can be observed in historical tables.

In the following sections, a summary of the results of the 2007 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 Framatome via the JAF Laboratory.

In 2007, 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 1997 through 2006.

The 2007 means are also presented in Table 8-4. Table 8-5 presents the 2007 TLD data for the inner ring and outer ring of TLDs.

The 2007 mean value for the direct radiation sample points was 14.3 mR per standard quarter. The mean value for the period 2000 through 2006 was 14.3 mR per standard quarter. At those locations where the 4-3

2007 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-17 to 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 14.4 mR per standard quarter and also average for the outer ring was 14.6 mR per standard quarter.

The control location* average for 2007 was 18.8 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 2007 averages are consistent with the historical data. The 2007 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 2007 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 0.013 pCi/m3 and the average for the control location was 0.013 pCilm3. 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 samples showed that no reactor-related radionuclides were detected and that only.

naturally-occurring radionuclides were present at detectable levels.

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 2007 gross beta concentration was consistent with historical levels.

Cs-137 has not 4-4

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 8-8.

"Less than" values are presented as sample critical level (Lc). There was no 1-131 detected (LLD = 0.07 pCi/m3) 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 operation of Indian Point was detected in 2007.

4.3 Hudson River Water A summary of the radionuclides detected in the Hudson River water is contained in Table 8-2. Data resulting from analysis of monthly Hudson River water samples for gamma emitters, and H-3 analysis of quarterly composites, are presented in Tables 8-9 and 8-10, 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 2007 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 8-12. 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 8-2. Table 8-13 contains the results of the gamma spectroscopic and strontium-90 analyses of the shoreline soil samples.

In addition to the naturally occurring radionuclides, Cs-137 was identified in the Hudson River shoreline soil samples in 2007. Cs-137 was detected at the Verplank location in both samples from that location, for a total of two positive values out of eight samples from 4-5

indicator locations. Cs-137 was detected at the control location (Manitou Inlet) in one out of two samples. The average concentration for the indicator locations that had positive indication of Cs-137 was 106 pCi/kg-dry with a maximum concentration of 149 pCilkg-dry. The control location with one positive sample indicated 357 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 Broad Leaf Vegetation Table B-2 contains a summary of the broad leaf vegetation sample analysis results. Data from analysis of the 2007 samples are presented in Table B-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 2007.

4.7 Fish and Invertebrates A summary of the fish and invertebrate sample analysis results is presented in Table B-2. Table B-15 contains the results of the analysis of fish and invertebrate samples for 2007. There were no plant related radionuclides detected as a result of the GSA.

Strontium-90 was added to the analyte list in 2007. An intensive one-time sampling and analysis program was undertaken in the Spring to confirm the use of Roseton as a control location. Seven fish samples were taken from the indicator location and 5 from the control location.

An additional 5 samples were taken further upstream near Catskill, NY.

There were no plant related radionuclides or Strontium-90 detected in the samples above background. The US NRC and NYSDEC obtained splits of samples from all three locations and also analyzed them for strontium-90.

Their results were consistent with those obtained by Entergy. '

4-6

This intensive one time sampling and analysis program shows that there is no measurable impact on fish and invertebrates from Indian Point releases and that Roseton is a satisfactory control location. 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.

4.8 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 2007.

Cs-137 was detected at one of one indicator station samples, and neither of the two control station samples. The concentration of Cs-137 in the indicator sample was 31 pCi/kg. Cs-134 was not detected in any aquatic vegetation samples.

While it is possible that the Cs-137 is from plant origin, the lack of Cs-134 suggests that the primary source of the Cs-137 is residual weapons test fallout.

This detection of Cs-137 in aquatic vegetation at the indicator location at such a low concentration is consistent with historical levels.

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 2007. Cs-137 was detected at 6 of 6 indicator station samples, and at one 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.

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 2007 are consistent with but slightly lower than historical levels.

4.10 Precipitation A summary of the precipitation sample analysis results is presented in Table B-2. Table B-18 contains the results of the precipitation samples for 2007. Other than naturally occurring radionuclides, no radionuclides were detected in precipitation samples.

4-7

A review of historical data over the last 10 years indicates tritium had been detected in both indicator and control preCipitation samples in 1997; 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 B-

2. Table B-19 contains the results of the soil samples for 2007. Other than naturally occurring radionuclides, only Cs-137 was detected in any of the soil samples. It was detected in one of two indicator samples at 136.5 pCi/kg, and not in the control sample. No Cs-134 was detected in any soil 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: This is also consistent with historical results over the last 10 years.

4~ 12 Groundwater A summary of the groundwater samples for 2007 is contained in Table B-2.

Data resulting from analysis of the groundwater samples for gamma emitters, tritium analysis, and Sr-90 are presented in Table B-

21.

Tritium was detected at very low concentrations in 5 of the 45 groundwater samples analyzed. The amount detected ranged from 176

- 223 pCilL and averaged 194 pCilL which was well below the required LLD of 3000 pCi/L.

Other than tritium, Cs-137 and Ru-106 were the only other potentially plant-related radionuclides detected in the groundwater samples.

Cesium-137 was present in 5 of the 45 samples taken at an average concentration of 11.5 pCilL.

The 5 positive Cs-137 sample results were all from MW-51 all on the same sample date. This data was investigated by Entergy and the offsite laboratory. No apparent reason for these positive results could be determined.

Follow-up samples collected a month later were all non-detect. Therefore these data are considered anomalous.

There was only one positive Ru-106 sample result out of the 45 samples taken. Since no other positive radionuclides were present in the sample, this result is also considered anomalous.

Sporadic detection of H-3, Sr-90 and Cs-137 is expected as these radionuclides are normally present in the environment as "background 4-8

radioactivity" as a consequence of both natural radioactivity and man-made activities un-related to the plant 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 result of plant activities. Additionally, these detected concentrations well below any applicable or relevant regulatory standards.

4.13 Land Use Census Environmenti:lI Monitoring Land Use Census.

Methodology:

A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2007 Spring, Summer and Fall months in accordance with the ODCM.

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.

Information was obtained from the New York Agricultural Statistic Service on milching animals within the 5-mile area surrounding Indian Point Energy Center.

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 4 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.

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

4-9

Results:

A census was performed in the vicinity of Indian Point in 2007. This census consisted of a milch animal and a residence census. Results of this census are presented in Tables 8-22 and 8-23.

The results of the 2007 census were generally same as' the 2006 census results. There were no animals producing milk for human consumption found within 5 miles (8 km) of the plant or listed in the New York Agricultural Statistic Service. 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 2007 land use census indicated there were no new residences that were closer in proximity to IPEC.

The Indian Point REMP does not include a garden census.

aDCM allows the sampling of broad leaf vegetation in two sectors at the site boundary in lieu of performing a garden census. Analysis res,ults 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 2007 REMP reveal that operations at the station did not result in an adverse impact on the environment.

The 2007 REMP results demonstrate the relative contributions of different radionutlide 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-gO in environmental 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.

4-10

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, Augusf 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 Manuals, 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 2007 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 limifs 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 8-22 and 8-23 for the milch animal and land use census.

A-1

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 3

DR8 Service Center Building 4

A1 Algonquin Gas Line A1 A4 5

A4 NYU Tower DR10 7

Wb1 Camp Field Reservoir 8

Croton Reservoir 9

Wa1 Plant Inlet (Hudson River Intake)*

10 Wa2 Discharge Canal (Mixing Zone) 14 DR7 r Meter House 17 Off Verplanck 20 DR38 Cortlandt Yacht Club (AKA Montrose Marina) 22 Lovett Power Plant A5 A5 23 DR40 Roseton*

Ic3 Ib2 25 Ib1 Downstream 27 Croton Point DR41 28 DR4 Lent's Cove 29 Grassy Point DR39

= Control location

- = Locations listed do not have sample designation locations specified in the aDCM HR = Hudson River R1S = Reuter Stokes A-2 Onsite -

0.35 Mi (SSE) at 158 0

Onsite - 0.28 Mi (SW) at 234 0

Onsite - 0.88 Mi (SSW) at 208 0

3.4 Mi at 51 0

6.3 Mi (SE) at 124 0

Onsite -

0.16 Mi (W) at 273 0

Onsite -

0.3 Mi (WSW) at 249 0

Onsite -

0.3 Mi (SE) at 133 0

1.5 Mi (SSW) at 202.5" 1.5 Mi (S) at 180 0

1.6 Mi (WSW) at 244 0

20.7 Mi (N) at 357" Downstream 6.36 Mi (SSE) at 156 0

0.45 Mi (ENE) at 069 0

3.37 Mi (SSW) at 196 0

Direct Gamma Air Particulate Radioiodine Air Particulate Radioiodine Direct Gamma Drinking Water Drinking Water HR Water HR Water HR Bottom Sediment Direct Gamma HR Aquatic Vegetation HR Shoreline Soil HR Bottom Sediment Direct Gamma Air Particulate Radioiodine Precipitation Air Particulate, Radioiodine Direct Gamma Broad Leaf Vegetation Soil Fish & Invertebrates Fish & Invertebrates Air Particulate Radioiodine Direct Gamma HR Shoreline Soil Direct Gamma HR Bottom Sediment HR on Air Particulate Radioiodine Direct Gamma

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 33 DR33 Hamilton Street (Substation) 34 DR9 South East Corner of Site 35 DR5 Broadway & Bleakley Avenue 38 DR34 Furnace Dock (Substation) 44 Peekskill Gas Holder Bldg 50 Wc2 Manitou Inlet*

53 Wc1 DR11 White Beach 56 DR37

- Broadway & 6th Street 57 DR1 Roa Hook 58 DR17 Route 90 - Garrison 59 DR2 Old Pemart Avenue 60 DR18 Gallows Hill Road & Sprout Brook Road 61 DR36 Lower South Street & Franklin Street 62 DR19 Westbrook Drive (near the Community Center) 64 DR20 Lincoln Road - Cortlandt (School Parking Lot) 66 DR21 Croton Avenue - Cortlandt 67 DR22 Colabaugh Pond Road - Cortlandt 69 DR23 Mt. Airy & Windsor Road 71 DR25 Warren Ave - Haverstraw 72 DR26 Railroad Avenue & 9W - Haverstraw IVVIllOW Grove Road & Captain 73 DR27 Faldermeyer Drive 74 DR12 IWest Shore Drive - South 75 DR31 Palisades Parkway 76 DR13 IWest Shore Drive - North 77 DR29 Palisades Parkway 78 DR14 Rt. 9W across from RlS #14 79 DR30

__, '" 'v, '1 Wayne Park

= Control location

- = Locations listed do not have sample designation locations specified in the ODCM A-3 HR = Hudson River RlS = Reuter Stokes 12.88 Mi (NE) at 053 0

IOnsite -

10.52 Mi (S) at 179 0

Onsite -

0.37 Mi (E) at 092 0

3.43 Mi (SE) at 141 0

1.84 Mi (NE) at 052 0

4.48 Mi (NNW) at 34r 0.92 Mi (SW) at 226 0

1.25 Mi (SSW) at 202 0

2 Mi (N) at 005 0

5.41 Mi (N) at 358 0

1.8 Mi (NNE) at 032 0

5.02 Mi (NNE) at 029 0

1.3 Mi (NE) at 052 0

5.03 Mi (NE) at 062 0

4.6 Mi (ENE) at 06r 4.87 Mi (E) at 083 0

4.5 Mi (ESE) at 114 0

4.97 Mi (SE) at 12r 4.83 Mi (S) at 188 0

14.53 Mi (SSW) at 203 0

4.97 Mi (SW) at 226 0

1.59 Mi (WSW) at 252 0

14.65 Mi (NW) at 225 0

1.21 Mi (W) at 276 0

4.15 Mi (W) at 272 0

1.2 Mi (WNW) at 295 0

4.57 Mi (WNW) at 296 0

Direct Gamma Direct Gamma Direct Gamma Direct Gamma Precipitation Air Particulate Radioiodine HR Shoreline Soil HR Shoreline Soil Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma Direct Gamma

TABLE A-1 INDIAN POINT REMP SAMPLING STATION LOCATIONS 81 DR28 82 DR16 83 DR32 Route 9W - Fort Montgomery 84 Cold Spring

88 DR6 RlS Pole #6 89 DR35 Highland Ave & Sprout Brook Road (near rock cut) 90 DR3 Charles Point 92 DR24 Warren Road - Cortlandt A2 94 A2 IPEC Training Center Ic2 A3 95 A3 Meteorological Tower Ic1 104 MW-40 Boundary Well, lower parking lot 105 MW-51 Boundary Well, middle parking lot

= Control location

- = Locations listed do not have sample designation locations specified in the aDCM A-4 HR = Hudson River RlS = Reuter Stokes 4.96 Mi (WSW) at 310 0

1.01 Mi (NNW) at 334 0

4.82 Mi (NNW) at 339 0

10.88 Mi (N) at 356 0

0.32 Mi (ESE) at 118 0

2.89 Mi (NNE) at 025 0

0.88 Mi (NE) at 047" Mi (SSE) at 149 0

Onsite- 0.39 Mi (S) at 193 0

Onsite -

Mi (SSW) at 208 0

Onsite - 0.21 mi (SW)

Onsite - 0.18 mi (SSW)

Direct Gamma Direct Gamma Direct Gamma HR Aquatic Vegetation HR Shoreline Soil HR Bottom Sediment Direct Gamma Direct Gamma Direct Gamma Direct Gamma Air Particulate Radioiodine Broad Leaf Vegetation Soil Air Particulate Radioiodine Broad Leaf Vegetation Soil Groundwater Groundwater

FIGURE A-1 SAMPLING LOCATIONS Within Two Miles of Indian Point Rockland County Indian.&r-pOint~A:

Key:

rn (7)

(3)121 Ic1 IC2 11 9

@rn I::J. - Waterborne: Surface (HR) Wa#

Buchanan o -Direct Radiation Sample Location DR#

o -Air Particulate & Radioiodine A#

<> - HR Shoreline Sediment Wc#

A-5 Peekskill Westchester County 1 mile Ic# - Broadleaf Vegetation Ib1 - Fish and Invertebrates (where available downstream)

Key:

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

~ Roseton (20.7 mJ. N), 0 @ Ic3 Upstream:

Ib2 Orange County Bear Mountain Bridge

(@

@)

Rockland County o -Direct Radiation Sample Location DR#

o -Air Particulate & Radioiodine A#

0- HR Shoreline Sediment Wc#

o -Waterborne: Drinking Wb#

A-6

@)

Putnam County 5 miles Westchester County Ic3 - Broadleaf Vegetation Ib2 - Fish and Invertebrates (where available upstream)

FIGURE A-3 SAMPLING LOCATIONS Additional Sampling Locations N

.~

Orange C()unty Bear Mountain Bridge 10:

17:...

<>r-------f-;.

22:. --.......

29:. ___

Rockland County Key:

- Air Particulate & Radioiodine

'f - Aquatic Vegetation

- HR Bottom Sediment p - Precipitation dw - Drinking Water A-7 Roseton (20.7 mi: N): 23 : p +

Rutnam County Cold Spring (10.88 mi. N) : 84 :'f

+'

-104/105 :gw Westchester County 27: *

°8: dw

,/

5 miles

<>- HR Shoreline Sediment

+-Soil

\\g# - Ground Water Boundary Monitoring (see detailed site map)

TABLE A-2 LOWER LIMIT OF DETECTION (LLD) REQUIREMENTS FOR ENVIRONMENTAL SAMPLE ANALYSIS (a) (b)

(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 pCi/L may be used.

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

A-8

H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65*

r-Nb-95 1-131 Cs-134 Cs-137 8a-La-140 Sr-90 TABLE A-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 20,000 (a) 1,000 30,000 400 10,000 1,000 30,000 300 10,000 300 20,000 400 2 (b) 0.9 3

30 10 1,000 60 50 20 2,000 70 200 300 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-9 100 1,000 2,000

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS

SUMMARY

APPENDIX B B.1 2007 Annual Radiological Environmental Monitoring Program Summary The results of the 2007 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 2007. The format of this summary table conforms to the reporting requirements of the ODCM, NRC Regulatory Guide 4.8 (Reference 4),

and NRC Branch Technical Position to Regulatory Guide 4.8 (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 anaiysis was performed for the following radionuclides; Be-7, K-40, Mn-S4, Co-S8, Co-60, Fe-S9, Zn-6S, Zr-9S, Nb-9S, Ru-103, Ru-106, 1-131, Cs-134, Cs-137, Ba/La-140, Ce-141, Ce-144, Ra-226 and AclTh-228. 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.S.2 and IP3-2.8 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 SO 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 2007, environmental sampling was performed for 12 media types addressed in the ODCM and direct radiation.

A total of 1322 samples/measurements were obtained. Of the scheduled samples, 99.3% were collected and analyzed for the program. Sampling deviations are summarized in Table B-1; discussions of the reasons for the deviations are provided in Table B-1a for air samples, B-1b for TLDs and B-1c for other environmental media.

B.4 Analytical Deviations There were no analytical deviations for 2007.

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

B-1

TABLE B-1

SUMMARY

OF SAMPLING DEVIATIONS 2007 MEDIA PARTICULATES IN AIR 468 99.8%

CHARCOAL FIL TER 466 2

99.6%

TLD 164 2

99%

HUDSON RIVER WATER 32 0

100%

DRINKING WATER 24 0

100%

ORELINE SOIL 20 4

80%

LEAF VEGETATI 54 0

100%

H & INVERTEBRATES 27 0

100%

UATIC VEGETATION 3

0 100%

8 0

100%

IL 3

0 100%

PRECIPITATION 8

0 100%

GROUNDWATER SAM 45 0

100%

ALS 1322 9

99.3%

TOTAL NUMBER OF ANALYSES REPORTED =

1313

Samples not collected or unable to be analyzed.

B-2 See Table B-1a See Table B-1a See Table B-1b N/A N/A See Table B-1c N/A N/A N/A N/A N/A N/A N/A

TABLE B-1a I B-1b/B-1c TABLE B-1a 2007 Air Sampling Deviations

~J~li!r;:: ',:Ll:i.e.* ~:;A;ii!f:J!'V!;§<.!~i~~\\r;:l:i<: ::j:~:~!:e~fi?§I!E¥JJi!'<:;1iI~~\\"f;~~e~V~!;~E~.Y~R§~g.~;:I;f~';r ",','J; LOVETT 01/16/2007 We lost about 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months of sample this past week. The pump had failed.

LOVETT LOVETT LOVETT LOVETT TRAINING BLDG PEEKSKILL GAS HOLDER TRAINING BLDG GRASSY POINT

~1~'9111*;r:,

TLD 200 & 212 HUDSON RIVER INLET HUDSON RIVER OUTLET LENT'S COVE WHITE BEACH MANITOU INLET COLD SPRING LENTS COVE VERPLANCK AREA 03/12/2007 04/16/2007 04/23/2007 05/21/2007 06/12/2007 07/30/2007 11/13/2007 12/26/2007 10/18/2007 02/16/2007 02/16/2007 06/06/2007 06/07/2007 06/06/2007 06/06/2007 09/06/2007 09/06/2007 The Lovett air sample lost 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sample time last week. It was running when we left it last week and it was running when we changed it this week.

The Lovett air sample lost 1 05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of sample time last week. It was running when we left it last week and it was running when we changed it this' week.

The Lovett air sample was not running when we went to change it out on 412312007. According to the hour meter it stopped running 30 minutes after we left on 4/16/2007. We have no air 'sample for the past week. Power was restored to the station, The Lovett air sample lost 118,8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of sample time last week. II was running when we left it last week and it was r~nning when we changed it this week.

The Training Bldg air sample pump failed this past week and we lost 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months of sample. We replaced the pump.

The Peekskill Gas Holder air sample was not running when we went to change it out. The pump had failed and we lost 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months of sample this past week, The Training Bldg air sampler lost 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months of sample time last week. It was running when left the week berofre and it was running when changed out again.

The Grassy Point air sample lost 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months of sample last week, It was running when we left it last week and it was running when we changed it this week.

TABLE B-1b 2007 TLD Deviations Q~~B:t~I!; :\\2:_I:r:Bg~~gJ~1:i&Q.11!:l!lj;:!Qj~l!~,!gMIJB~e:~IJB.RENgJ;",~.,.,

Two of the 10 CFR20 140CFR190 TLD locations on site had the TLD's missin.

TABLE B-1c 2007 Other Media Deviations The dock was snow covered and ice covered and unsafe to go out and get the

sample, The hose was frozen and there was no sample for the week, Shoreline soil sample not analyzed for Sr-90 Shoreline soil sample not analyzed for Sr-90 Shoreline soil sample not analyzed for Sr-90 Shoreline soil sample not analyzed for Sr-90 No aquatic vegetation was found in this area No aquatic vegetation was found in this area 8-3

TLD Reads (mR 1 standard quarter)

N/A 8-3 164 AIR PARTICULATES AND RADIOIODINE G8 (467)

(pCi/m3) 8-6, 8-7, 8-8 1-131 (466) 0.07 r.::C::.d {':l~\\

0.05 I

0.06 L.S-1"1 SURFACE HUDSON I

RIVER WATER (pCi/L)

H-3 (8)

I 3000 (c) 8-9,8-10 GSA (24}

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

TABLE B-2 ODeM ANNUAL

SUMMARY

- 2007 14.3 (160/160) /

West Shore Drive - North I 18.8 (4/4) /

1.21 Mi (W) at 276:. DR13 I

0 9.5 - 22.2 20.0 (4/4) / 18.3 - 21.6 17.4-21.5 (415/416) /

22 Lovett Power Plant 0.013 1.6 Mi (WSW) at 244 0 I 0.013 (52152) /

I 0

0.003 - 0.026 0.014 (51/52) 1 0.003-0.023 0.003-0.023

<Lc

<L(

<Lc

<Lc 0

<Lc*

<Lc

<Lc 0

<Lc I

0

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc 0

<Lc*

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc.

<Lc 0

<Lc

<Lc 0

<Lc

<Lc B-4

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr/Nb-95 1-131 Cs-134 Cs-137 Ba/La-140 (pCilkg -dry) B-13 I GSA (10)

Cs-134 Cs-137 Sr-90 (6)

(a) Positive values above L"; Groundwater above MDC (b) Required a priori LLD; see Table A-2 15 15 30 15 c 30 15*

15 15 18 15 150 180 5000 (c) Not a drinking water pathway; the required LLD is 3000 pCilL

TABLE B-2 aDeM ANNUAL

SUMMARY

- 2007

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

<Lc

<Lc 0

106 (2/6) 1

17 Off Verplanck

50 Manitow Inlet 1.5 Mi (SSW) at 202.5" 357 (114) /

I 0

63.3 - 149 106 (2/2) 1 63.3 - 149 357 - 357

<Lc

<Lc '

0 8-5

(a) Positive values above Lc; Groundwater above MDC (b) Required a priori LLD; see Table A-2 (c) Not a drinking water pathway; the required LLD is 3000 pCilL TABLE B-2 ODeM ANNUAL

SUMMARY

- 2007 8-6

BOTTOM SEDIMENT I (pCi/kg - DRY)

GSA(8)

Co-60 NONE Cs-134 150 Cs-137 180 SOIL GSA(3)

(pCilkg - DRY)

Co-60 NONE Cs-134 150 Cs-137 180 PRECIPITATION GSA(8)

(pCi/L)

H-3 3000 (c)

Co-60 Cs-134 Cs-137 (a) Positive values above Lc; Groundwater above MDC (b) Required a priori LLD; see Table A-2 15 15 18 (c) Not a drinking water pathway; the required LLD is 3000 pCiJL TABLE B-2 aDeM ANNUAL

SUMMARY

- 2007

<Lc

<Lc 0

<Lc

<Lc 0

28 Lents Cove

84 Cold Spring 221 (6/6) /

0.45 Mi (ENE) at 069 0

20.7 Mi (N) at 356 0 I 0

95.0 - 373.7 291.5 (2/2) 1 254.8 (1/2) /

373.7 - 209.2 254.8 - 254.8

<Lc

<Lc 0

<Lc

<Lc 0

94 Training Center

94 Training Center 0.45 Mi (SSW) at 208 0

0.45 Mi (SSW) at 208 0

<Lc 0

136.5 (1/2) 1 136.5 (1/1) 1 136.5 - 136.5 136.5 - 136.5

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc 0

<Lc

<Lc 0

8-7

GROUNDWATER GSA(45)

(pCilL)

H-3 (45) 3000 (c)

Co-60 (45)

Cs-134 (45)

Cs-137 (45)

Sr-90(41)

(a) Positive values above Lc; Groundwater above MDC (b) Required a priori LLD; see Table A-2 15 15 18 (c) Not a drinking water pathway; the required LLD is 3000 pCiIL TABLE B-2 aDeM ANNUAL

SUMMARY

- 2007

105 MW-51 194 (5/45) I 0.18 mi -ssw N/A 0

176 - 223 203 (3/26) I 187 - 223

<Lc

<Lc N/A 0

<Lc

<Lc N/A 0

105 MW-51 11.5 (5/45) 1 0.18 mi - ssw N/A 0

5.15 - 21.6 11.5 (5/26) 1 5.15-21.6

<Lc

<Lc N/A 0

8-8

DR-02 DR-03 NE DR-04 ENE DR-05 E

DR-06 ESE DR-07 SE DR-08 SSE DR-09 S

DR-10 SSW DR-11 SW DR-12 WSW DR-13 W

DR-14 WNW DR-15 NW DR-16 NNW DR-17 N

DR-18 NNE DR-19 NE DR-20 ENE DR-21 E

DR-22 ESE DR-23 SE DR-24 SSE DR-25 S

DR-26.

SSW DR-27 SW DR-28 WSW DR-29 W

DR-30 WNW DR-31 NW DR-32 NNW DR-33 NE DR-34 SE DR-35 NNE DR-36.

DR-37 DR-38 DR-39 TABLE B-3 2007 DIRECT RADIATION, QUARTERLY DATA (mR per STANDARD QUARTER) 15.69 14.00 +/-

0.55 15.4 13.24 +/- 0.7 14.54 11.91

+/-

0.77 12.9 +/- 0.7 10.47 +/- 0.7 11.75 13.03 +/-

0.65 15.0 +/- 0.8 12.57 +/- 0.7 13.63 13.29 +/-

0.75 15.2 +/- 0.7 13.24 +/- 0.8 14.20 13.99 +/-

0.53 15.7 +/- 0.7 12.79 +/- 0.7 14.41 15.44 +/-

0.73 18.5 +/- 0.7 14.73 +/- 0.8 15.96 11.70 +/-

0.55 1~.6 +/- 0.7 11.38 +/- 0.8 12.04 12.81

+/-

0.71 14.3 +/- 0.8 12.46 +/- 0.9 13.43 13.28 +/-

0.62 15.2 +/- 1.1 13.64 +/-.0.9.

14.53 10.35 +/-

0.57 12.3 +/- 0.8 9.96 +/- 0.6 10.63 16.39 +/-

0.77 19.5 +/- 0.9 16.86 +/- 0.9 15.52 18.34 +/-

0.78 21.6

+/- 1.1 19.49 +/- 1.5 20.74 12.51

+/-

0.69 15.5 +/- 1.2 13.39 +/- 1.1 12.86 12.95 +/-

0.66 15.4 +/- 0.6 12.59 +/- 0.7 13.88 13.82 +/-

0.61 16.9 +/- 0.6 14.78 +/- 0.7 15.08 14.27 +/-

0.78 17.3 +/- 1.0 14.49 +/- O.

13.53 +/-

0.66 16.2 +/- 0.9 12.85 +/- 0.7 14.50 14.89 +/-

1.28 16.7 +/- 0.9 13.47 +/- 1.0 15.17 12.58 +/-

0.58 14.6 +/- 0.7 12.37 +/- 0.8 13.71 13.27 +/-

0.71 15.5 +/- 0.6 12.09 +/- 0.8 13.94 11.42 +/-

0.65.

13.1

+/- 0.9 9.52

+/- 0.6 11.63 13.28 +/-

0.47 16.3 +/- 1.0 12.q4 +/- 0.7 13.97 13.87 +/-

0.85 16.4 +/- 0.8 13.68 +/- 0.7 14.93 12.17 +/-

0.56 15.5 +/- 1.0 11.51

+/- 0.8 13.42 13.58 +/-

0.61 16.9 +/- 0.7 13.70 +/- 1.2 14.73 13.01

+/-

0.91 17.3 +/- 2.2 12.61

+/- 0.8 13.65 18.05 +/-

0.66 22.2 +/- 0.9 18.57 +/- 0.9 20.06 13.12 +/-

0.68 17.9 +/- 1.3 13.43 +/- 0.7 14.27 13.55 +/-

0.58 18.8 +/- 1.0 14.42 +/- 0.7 14.56 15.57 +/-

0.67 19.8 +/- 0.9 15.46 +/- 1.1 16.59 12.97 +/-

0.50 16.1

+/- 0.9 12.31

+/- 0.7 13.33 13.12 +/-

0.88 15.8 +/-

.7

+/- 0.7 13.50 12.24 +/-

0.50 15.5 +/- 0.9 11.28 +/- 0.6 12.21 12.95 +/-

0.62 15.4 +/- 0.8 11.63 +/- 0.6 13.01 14.28 +/-

0.76 17.6 +/- 2.3 13.07 +/- 0.8 14.91 12.75 +/-

0.61 15.4 +/- 0.6 12.17 +/- 1.6 14.60 11.71

+/-

0.58 14.5 +/- 0.7 11.60 +/- 0.7 13.59 14.46 +/-

0.70 18.1

+/- 2.2 13.79 +/- 0.7 14.94 1.03 0.69 14.3 57

+/- 0.82 11.8 47

+/- 0.70 13.6 54

+/- 0.82 14.0 56

+/- 0.63 14.2 57

+/- 0.79 16.2 65

+/- 0.55 12.2 49

+/- 0.82 13.3 53

+/- 0.78 14.2 57

+/- 0.69 10.8 43

+/- 0.79 17.1 68

+/- 1.07 20.0 80

+/- 0.99 13.6 54

+/- 0.86 13.7 55

+/- 0.82 15.2 61

+/- 1.35 15.3 61

+/- 0.93 14.3 57

+/- 0.85 15.0 60

+/- 0.87 13.3 53

+/- 0.76 13.7 55

+/- 0.70 11.4 46

+/- 1.20 14.0 56

+/- 0.73 14.7 59

+/- 0.91 13.1 53

+/- 1.18 14.7 59

+/- 0.84 14.1 57

+/- 1.19 19.7 79

+/- 0.88 14.7 59

+/- 0.63 15.3 61

+/- 0.89 16.9 67

+/- 0.68 13.7 55

+/- 0.59 12.8 51

+/- 0.95 13.2 53

+/- 1.34 15.0 60

+/-. 0.86 13.7 55

+/- 0.66 12.8 51

+/-

15.3 61

64.4 48.2 53.9 54.5 53.8 DR-07 63.7 DR-08 52.1 DR-09 51.6 DR-10 55.3 DR-11 45.3 DR-12 67.0 DR-13 76.2 DR-14 54.4 DR-18 57.0 DR-19 60.0 DR-20 54.8 DR-21 55.2 DR-22 46.8 DR-23 56.1 DR-24 55.7 DR-25 49.7 DR-26 55.2 DR-27 55.3 DR-28 64.8 DR-29 66.8 DR-30 63.9 DR-34 53.5 DR-35 57.4 DR-36 61.8 DR-37 55.2 DR-38 52.2 DR-39 62.8 TABLE B-4 DIRECT RADIATION, 1997 THROUGH 2007 DATA (mR per Standard Quarter) 53.7 43.8 3.7 46.8 2.6 48.3 3.1 46.2 3.7 55.6 2.6 47.1 3.6 44.1 6.0 39.2 2.2 40.8 3.7 62.4 4.0 67.8 3.5 49.8 4.1 46.5 55.2 2.6 52.2 2.8 55.1 3.7 47.4 3.2 49.8 3.6 40.2 2.9 49.5 2.9 49.2 2.5 44.7 2.5 50.4 3.9 46.8 6.5 57.2 8.7 54.6 6.3 52.2 5.8 62.1 3.4 45.9 4.7 43.2 4.1 48.6 5.0 52.5 3.3 48.9 2.8 48.6 6-10 50.4 47.0 58.6 54.3 58.0 55.9 57.6 56.9 68.6 64.6 56.3 48.7 55.2 53.0 59.8 56.7 48.5 43.3

.76.0 68.3 80.2 60.7 57.1 63.6 60.2 59.2 53.3 60.6 54.8 51.9 45.7 58.9 56.1 59.8 58.9 53.2 52.6 58.9 58.9 61.5 56.6 77.1 78.9 58.8 61.3 60.7 51.2 61.2 52.9 70.5 59.9 60.0 54.9 58.4 51.4 66.8*

61.3

l TABLE B-5 2007 DIRECT RADIATION INNER AND OUTER RINGS (mR per Standard Quarter) 8-11

';WeekEnd

',', ~,

Week 1-

,A',*

Number,. 'Date'-

1 01/02/2007 0.012 +/- 0.001 2

01/0912007 0.013 +/- 0.001 3

01116/2007 0.011 +/- 0.001 4

01/23/2007 0.017 +/- 0.001 5

01/3012007 0.015 +/- 0.001 6

02/06/2007 0.020 +/- 0.002 7

02/13/2007 0.015 +/- 0.001 8

0212012007 0.017 +/- 0.001

9 02127/2007 0.010 +/- 0.001 10 03/06/2007 0.011 +/- 0.001 11 03113/2007 0.018 +/- 0.001 12 03/20/2007 0.015 +/- 0.001 13 0312712007 0.010 +/- 0.001 14 04/03/2007 0.011 +/- 0.001 15 0411012007 0.004 +/- 0.001 16 04/17/2007 0.004 +/- 0.001 17 04/2412007 0.011 +/- 0.001 18 05101/2007 0.008 +/- 0.001 19 05108/2007 0.008 +/- 0.001 20 05/15/2007 0.009 +/- 0.001 21 05122/2007 0.009 +/- 0.001 22 05129/2007 0.015 +/- 0.001 23 06/05/2007 0.012 +/- 0.001 24 06/12/2007 0.009 +/- 0.001 25 06/19/2007 0.009 +/- 0.001 L-26_ ~/26/2007 (J.013 +/- O.()()l

- Control sample location TABLE B-6 IPEC ENVIRONMENTAL AI~BORNE PARTICULATE SAMPLES - 2007 GROSS BETA ACTIVITY pCiI m3 +/- 1 Sigma SAMPLE STATION #

.i, I?,:

95'"

\\

t;f,.;"

'-~'-T:~ ~ :

'-!~D;

..,:.;t:~~:;,',:

' W~~~;,

. I' 1

Numbe'i 0.013 +/- 0.001 0.015 +/- 0.001 0.010 +/- 0.001 0.014 +/- 0.001 1

0.016 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 2

0.013 +/- 0.002 0.012 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001.0.012 +/- 0.001 0.011 +/- 0.001 3

0.012 +/- 0.002 0.013 +/- 0.001 0.013 +/- 0.001 0.016 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 4

O.oI 8 +/- 0.002 0.016 +/- 0.001 0.017 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 5

0.017 +/- 0.002 0.017 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0.001 O.oI5 +/- 0.001 0.017 +/- 0.001 6

0.020 +/- 0.002 0.019 +/- 0.001 0.011 +/- 0.001 0.017 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 7

0.013 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 O.oI5 +/- 0.001 0.009 +/- 0.001 8

0.016 +/- 0.001 0.014 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.012 +/- 0.001 9

0.012 +/- 0.001 0.010 +/- 0.00 I 0.008 +/- 0.001 0.007 +/- 0.001 0.009 +/- 0.001 0.008 +/- 0.001 10 0.008 +/- 0.001 0.010 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.001 0.017 +/- 0.001 0.021 +/- 0.001 11 0.022 +/- 0.002 0.016 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0:001 0.016 +/- 0.001 0.014 +/- 0.001 12 0.015 +/- 0.001 0.017 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 13 0.015 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.011 +/- 0.001 14 0.012 +/- 0.001 0.008 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.005 +/- 0.001 0.003 +/- 0.001 15 0.003 +/- 0.001 0.003 +/- 0.001 0.005 +/- 0.001 0.005 +/- 0.001 0.007 +/- 0.001 0.005 +/- 0.001 16 0.008 +/- 0.002 0.006 +/- 0.001 0.008 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 0.010 +/- 0.001 17 See Deviation Report 0.010 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 0.007 +/- 0.001 18 0.005 +/- 0.001 0.006 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.008 +/- 0.001 0.007 +/- 0.001 19 0.009 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.006 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 20 0.006 +/- 0.001 0.009 +/- 0.001 0.007 +/- 0.001 0.012 +/- 0.001 6.011 +/- 0.001 0.009 +/- 0.001 21 0.021. +/- 0.003 0.012 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.002 0.014 +/- 0.001 0.018 +/- 0.001 22 0.017 +/- 0.001 0.019 +/- 0.001 0.013 +/- 0.001 0.012 +/- 0.001 0.012 +/- 0.001 0.017 +/- 0.002 23 0.015 +/- 0.002 0.011

+/- 0.001 0.012 +/- 0.001 0.0 I 0 +/- 0.002 0.013 +/- 0.001 0.010 +/- 0.001 24 0.008 +/- 0.001 0.011 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.010 +/- 0.001 0.009 +/- 0.001 25 0.009 +/- 0.001 0.010 +/- 0.001 Jl.OI~OO! Jl.(J!O +/- 0.004 0.011 +/- 0.001 0.009 +/- 0.00 I 26 0.010 +/- 0.001 0.011 +/- 0.001 8-12 b,:'~J{-'." ~

4:;~::'....,'

0.016 +/- 0.001 0.012 +/- 0.001 0.011 +/- 0.001 O.oI 5 +/- 0.002 0.010 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.014 +/- 0.001 0.016 +/- 0.001 0.016 +/- 0.001 0.020 +/- 0.001 '0.023 +/- 0.002 I 0.011 +/- 0.001 0.014 +/- 0.001 0.015 +/- 0.001 0.016 +/- 0.001 0.013 +/- 0.001 0.010 +/- 0.001 I

0.009 +/- 0.001 0.009 +/- 0.001 I

0.020 +/- 0.001 0.018 +/- 0.001' 0.016 +/- 0.001 0.015 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 0.011 +/- 0.001 0.012 +/- 0.001 0.004 +/- 0.001 0.004 +/- 0.001 0.005 +/- 0.001 0.009 +/- 0.001 0.012 +/- 0.001 0.006 +/- 0.001 0.007 +/- 0.001 0.008 +/- 0.00 I !

0.008 +/- 0.001 0.008 +/- 0.001 0.006 +/- 0.001 0.009 +/- 0.001 0.012 +/-O.OOI 0.013 +/- 0.001!

0.015 +/- 0.001 0.020 +/- 0.001 0.015 +/- 0.001 0.013 +/- 0.001 I

0.008 +/- 0.001 0.010 +/- 0.001 I

0.010 +/- 0.001 0.009 +/- 0.001 0.011 +/- 0.001 0.013 +/- 0.001 I

I weeki* WeekEnd I

4 I Number.'

Date 27 07/02/2007 0,010 +/- 0,001 28 07/1012007 0,016 +/- 0,001 29 07/17/2007 0,016 +/- 0.001 30 07124/2007 0,010 +/- 0,001 31 07/3112007 0.015 +/- 0.001 32 08/07/2007 0,021

+/- 0.002 33 08/14/2007 0.017 +/- 0.001 34 0812112007 0.013 +/- 0,001 35 08/28/2007 0.011

+/- 0,001 36 09/04/2007 0.016 +/- 0.001 37 0911112007 0,018 +/- 0,001 38 09118/2007 0.010 +/- 0.001 39 09/2512007 0,020 +/- 0,002 40 10/02/2007 0.017 +/- 0,001 41 10/09/2007 0,015 +/- 0,001 42 1011612007 0,005 +/- 0.001 43 10/23/2007 0,024 +/- 0,002 44 10/30/2007 0,011

+/- 0,001 45 11/06/2007 0.019 +/- 0,002 46 11113/2007 0,011

+/- 0.001 47 11119/2007 0,016 +/- 0.002 48 11127/2007 0,011

+/- 0,001 49 12/04/2007 0,014 +/- 0,001 50 12/1112007 0.013 +/- 0,001 51 12118/2007 0,016 +/- 0.001 52 12/24/2007 0,018 +/- 0,002

- Control sample location TABLE B-6 ENVIRONMENTAL AIRBORNE PARTICVLATE SAMPLES - 2007 GROSS BETA ACTIVITY pCiI m3 +/- I Sigma SAMPLE STATION #

I';'

. 'I

',;,I****.. '23**: ' 11~:~t~rff' 22,::~. 'I '

5 94 95 27,

'... ~

0,009 +/- 0,00 I 0,013 +/- 0,001 0.013 +/- 0.001 0.016 +/- 0,001 27 0,016 +/- 0.001 0,013 +/- 0,001 0,014 +/- 0.001 0.016 +/- 0,001 0.016 +/- 0.001 0,012 +/- 0,001 28 0,012 +/- 0.001 0.014 +/- 0.001 0.010 +/- 0,001 0,014 +/- 0,001 0,016 +/- 0,001 0.017 +/- 0,001 29 0,018 +/- 0,002 0,010 +/- 0,001 0.011

+/- 0,001 0,009 +/- 0.001 0.011

+/- 0,001 0,012 +/- 0.001 30 0.012 +/- 0.001 0.012 +/- 0.001 0,014 +/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.011

+/- 0,001 31 0.011

+/- 0.001 0.013 +/- 0,001 0.017 +/- 0.001 0.018 +/- 0.001 0.019 +/- 0.002 0.018 +/- 0,001 32 0,018 +/- 0.002 0.020 +/- 0.002 0.013 +/- 0,001 0,017 +/- 0,001 0,017 +/- 0.002 0,015 +/- 0.001 33 0,018 +/- 0.002 0.014 +/- 0.001 0.011

+/- 0.001 0.Dl5 +/- 0,00 I 0.011

+/- 0,001 0.013 +/- 0.001 34 0,016 +/- 0.002 0.012 +/- 0.001 0,007 +/- 0.001 0,009 +/- 0,00 I 0.007 +/- 0,001 0.012 +/- 0.001 35 0,007 +/- 0.001 0.012 +/- 0.001 0,017 +/- 0.001 0,017 +/- 0.001 0.017 +/- 0,002 0.016 +/- 0.001 36 0.017 +/- 0.001 0,016 +/- 0.001 0,016 +/- 0.001 0.017 +/- 0.001 0.018 +/- 0.002 0.019 +/- 0,002 37 0.020 +/- 0.002 0.018 +/- 0.001 0.010 +/- 0.001 0.007 +/- 0,001 0,009 +/- 0.001 0,007 +/- 0,001 38 0,007 +/- 0.00 I 0,006 +/- 0.001 0.016 +/- 0,001 0,021

+/- 0,002 0.021

+/- 0,002 0,012 +/- 0,001 39 0.012 +/- 0.001 0.018 +/- 0.001 0,021

+/- 0.002 0,022 +/- 0.002 0.021

+/- 0,002 0.019 +/- 0.002 40 0.023 +/- 0.002 0,017 +/- 0.001 0,013 +/- 0.001 0.011

+/- 0.001 0.017 +/- 0.002 0.017 +/- 0.001 41 0.014 +/- 0.001 0,011

+/- 0,001 0.007 +/- 0.001 0.005 +/- 0.00 I 0.008 +/- 0.001 0.005 +/- 0,001 42 0,006 +/- 0.001 0.007 +/- 0.001 0.022 +/- 0.002 0.026 +/- 0,002 0,025 +/- 0.002 0,023 +/- 0,002 43 0,020 +/- 0.002 0.020 +/- 0.002 0.009 +/- 0.001 0,010 +/- 0.001 0,011

+/- 0,001 0,015 +/- 0.001 44 0.012 +/- 0.001 0.010 +/- 0.001 0,019 +/- 0.001 0.019 +/- 0.001 0.020 +/- 0,002 0.020 +/- 0.001 45 0.017 +/- 0.001 0,019 +/- 0,001 0,011

+/- 0.001 0.012 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0,001 46 0,017 +/- 0.001 0,012 +/- 0,001 0.014 +/- 0,001 0.0]8 +/- 0,002 0,018 +/- 0.002 0,013 +/- 0,001 47 0,0]7 +/- 0,002 0.015 +/- 0.00]

0.011

+/- 0,001 0,011

+/- 0.001 0,013 +/- 0.001 0,012 +/- 0.001 48 0.016 +/- 0.001 0.011

+/- 0.001 0.013 +/- 0.001 0.015 +/- 0.001 0.018 +/- 0,001 0.017 +/- 0.001 49 0.017 +/- 0.001 0,015 +/- 0.001 0,015 +/- 0.001 0,015 +/- 0,001 0.012 +/- 0.001 0.013 +/- 0.001 50 0.013 +/- 0.001 0.017 +/- 0,001 0.018 +/- 0.001 0.021

+/- 0.001 0,015 +/- 0.001 0,016 +/- 0,001 51 0.020 +/- 0,002 0.017 +/- 0.001 0.018 +/- 0,002 0,018 +/- 0.002 0,019 +/- 0,002 0,018 +/- 0,001 52 0.019 +/- 0.002 0.017 +/- 0,001 8-13 l'

29' I

44 0.013 +/- 0,001 0.017 +/- 0.001 0.012 +/- 0,001 0,010 +/- 0,001 I

0.015 +/- 0,001 0.016 +/- 0.001 0,009 +/- 0.001 0.016 +/- 0.001 0.012 +/- 0.001 0.010 +/- 0,002 0.017 +/- 0,001 0.Dl8 +/- 0.002 0.018 +/- 0.001 0,015 +/- 0.001 0,012 +/- 0.001 0.013 +/- 0.001 0,010 +/- 0.001 0.009 +/- 0.001 0.018 +/- 0.001 0.015 +/- 0,001 0.017 +/- 0.001 0,020 +/- 0.002 0.008 +/- 0.001 0,009 +/- 0.001 0,017 +/- 0.001 0.021

+/- 0.002 0.021

+/- 0.001 0,018 +/- 0,002 0.013 +/- 0.001 0.012 +/- 0,001 0.007 +/- 0.001 0.004 +/- 0.001 0,020 +/- 0.001 0.021

+/- 0.002 0.011

+/- 0.001 0.022 +/- 0,002 0.019 +/- 0.001 0,017 +/- 0,002 0.014 +/- 0,001 0.013 +/- 0.001 0,015 +/- 0,001 0.017 +/- 0.002 0.014 +/- 0.001 0,013 +/- 0,001 0.015 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0,001 0.012 +/- 0.001 0,019 +/- 0,001 0.019 +/- 0.002 0.020 +/- 0,001 0.019 +/- 0.002

Nuclide Algonquin Sta #4 Be-7 57.5 +/-

20.2 C5-134

< 1.5 C5-137

< 0.8 Zr-95

< 2.6 Nb-95

< 2.5 Co-58

< 2.2 Mn-54

<\\.2 Zn-65

< 3.0 Co-60

<\\.7 K-40

< 18.7

- Control Sample Location

, Nuclide Be-7 C5-134 C5-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 A}gonquin Sta #4 13 L5 +/-

17.0

< 0.7

< 0.5

< 1.6

< 1.5

< 0.7

< 0.8

< 2.9

< 1.0

< 8.5

- Control Sample Location NYU Tower #5 84.2 +/-

20.5

< 1.6

< 0.7

< 3.0

< 2.7

< 1.4

< 1.0

< 3.8

< \\.2

< 13.4 TABLE B-7 CONCENTRA TIONS OF GAMMA EMITTERS IN QVARTERL Y COMPOSITES OF SITE AIR PARTICVLATE SAMPLES - 2007 Results in Vnits of 10E-3 pCiI m j +/- 1 Sigma SAMPLE LOCATIONS -1ST QTR 2007

,s*

Roseton#23<',

Croton Point.#27 Training Bldg #94 ' Met Tower #95' Loyett#22;~* :

. !'I-,

122.4 +/-

29.3 115.3 +/-

23.7 95.7 +/-

24.3 108.5 +/-

25.5 112.2 +/-

21.2

< 1.5

< L1

< 1.9

< 1.5

< 1.4

< 1.3

< 1.0

< 0.8

< LI

< 1.6

< 3.5

< 2.8

< 3.0

< 5.3

< 2.5

< 2.9

< 2.5

< 2.7

< 2.4

< 2.3

< 1.7

< 1.6

< 2.5

<1.5

< 1.5

<\\.2

< 1.2

<\\.2

< 1.5

< 4.5

< 2.8

< 3.3

< 3.0

< 3.2

< 2.2

< 1.6

< 1.7

< \\.7

< 24.2

< 14.1

< 17.6

<; 18.6

< 17.1 NYU_Tower #5

,Croton Point~~7:

103.3 +/-

12.7 110.1 +/-

14.6

< 0.6

< 0.4

< 0.3

< 0.4

< 1.8

< 1.6

< 0.6

< LI

< 0.7

< 0.6

< 0.9

< 1.6

<\\.2

< 0.5

< 0.8

< 5.7

< 7.2 SAMPLE LOCATIONS - 2ND QTR 2007 Tiaining,Bldg#941 'My,tTo>>,erif95.

125.5 +/-

< 0.9

< 0.6

< 1.4

< 0.8

< 0.7

< 0.8

< 1.4

< 0.8

< 7.5 14.6 I 136.0 +/-

< 0.7

< 0.3

< 0.9

< 1.5

< 0.7

< 0.5

<1.3

< 0.5

< 6.8 8-14 14.1

_, ;' I:,6ve~#22 **'

107.1 +/-

15.0

< 0.9

< 0.6

< 2.4

< 0.9

< 0.6

< 2.0

< 0.6

< 7.1 Roseton #23.

137.1 +/-

17.2

< 0.5

< 0.4

< 2.0

< 1.4

< 0.9

< 0.5

< 2.2

< 0.9

< 9.4 Grassy,Point #29 Peekskill #44 :', '

91.4 +/-

17.8

< 26.8

< 0.9

< 1.6

< 0.5

< 1.2

< 1.9

< 3.8

< 2.0

< 3.1

< Ll

< 2.5

< 0.8

< 1.7

< 3.0

< 4.9

< 1.0

< 2.6

< 10.3

< 24.4

,Q~assY~~int: ;291. Peekskill#44 131.3 +/-

12.31109.5 +/-

15.1

< ~3

< ~6

< 0.6

< \\.2

< 1.2

< 1.0

< 1.4

< 0.4

< 0.7

< 0.6

< 0.7

< 1.2

< 1.5

< 0.8

< 4.1

< 7.5

Nuclide Algonquin Sta #4 Be-7 132.7 +/-

13.6 Cs-134

< 0.6 Cs-137

< 0.5 Zr-95

< 1.4 Nb-95

< 1.1 Co-58

.< 0.4 Mn-54

< 0.3 Zn-65

< 1.3 Co-60

< 0.5 K-40

< 6.5

- Control Sample Location TABLEB-7 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF SITE AIR PARTICULATE SAMPLES - 2007 Results in Units of 10E-3 pCi/ m3 +/- 1 Sigma

..... a.*.. &~&.J........... -....~..................

~.~_ --- --~.

NYU Tower #5 *. Croton p,oint #27 T~airiingBl?g #94 ';'MetOTower #95 Lovett #2i.~*

R6seton#23'.';

130.1 +/-

13.2 116.9 +/-

13.6 104.3 +/-

15.0 112.5 +/-

13.9 143.8 +/-

14.9 130.6 +/-

13.2

< 0.8

< 0.5

< 0.8

< 0.3

< 0.9

< 0.6

< 0.3

< 0.5

< 0.3

< 0.6

< 0.4

< 0.9

< 1.9

< 1.6

< 1.9

< 1.4

< 1.7

< 1.6

< 0.9

< 1.6

< 1.4

< 1.7

< 0.5

< 0.7

< 1.0

< 0.7

< 0.5

< 1.1

< 0.7

< 0.5

< 0.7

< 0.3

< 0.4

< 0.3

< 1.0

< 1.5

< 1.2

< 1.6

< 0.9

< 1.6

< 0.5

< 0.8

< 0.5

< 5.1

< 9.6

< 7.2

< 5.9

< 5.0 39.4 +/-

8.9 SAMPLE LOCA nONS - 4TH QTR 2007 Grassy Point #29 136.5 +/-

15.1

< 0.5

< 0.4

< 1.2

< 1.0

< 0.8

< 0.5

<1.3

< 0.6

< 7.5 Nuclide I Algonquin Sta#4INYU Tower #5 I Croton Point #27 I Training Bldg #941 Met 'rower #95 L~v~ri#22**:"1 Ro~eton ~~3 :;d Grassy POint #29 Be-7 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 109.9 +/-

< 0.7

< 0.4

< 1.4

< l.l

< 0.5

< 0.7

< 1.9

< 0.8 11.9 45.2 +/-

8.9

- Control Sample Location 105.0 +/-

< 0.7

< 1.6

< 1.0

<1.3

< 0.9

< 2.3

< 0.9

< 8.2 15.2 89.4 +/-

< 0.3

< 0.2

< 0.8

<1.3

< 0.8

< 0.5

< 0.8

< 5.2 12.1 119.6 +/-

< 0.4

< 0.5

< 1.8

< 2.0

< 1.0

< 0.5

< 2.5

< 0.8

< 10.2 14.9 102.8 +/-

< 0.4

< 0.6

< 1.2

< 1.4

< 1.0

< 0.7

< 2.1

< 0.6

< 6.0 8-15 13.4 99.4 +/-

< 0.6

< 1.7

< 1.6

< 1.0

< 0.8

< 1.7

< 0.6

< 6.9 13.0 109.2 +/-

< 0.5

<1.7

< 0.9

< 0.4

< 1.5

< 0.7 12.4 27.8 +/-

7.6 96.1 +/-

< 0.6

< 0.4

< 1.0

< 1.6

< l.l

< 0.4

< 1.3

< 0.7

< 7.6 13.5 Peekskill #44.

112.5 +/-

13.5

< 0.8

< 0.3

< 1.5

< 0.7

< 1.0

< 0.6

< 2.2

< 1.1

< 10.5 Peekskill #44 102.2 +/-

< 1.0

< 0.4

< 1.5

< 1.7

< 1.0

< 0.7

< 1.8

< 0.5

< 5.5 12.9

Week Number I

2 3

4 5

6 7

8 9

10 II 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 WeekEnd I

Date' 01102/07 01109107 01116/07 01/23/07 01130107 02/06/07 02/13/07 02/20107 02/27/07 03/06107 03113/07 03120107 03/27/07 04/03/07 04110107 04117/07 04/24/0?-

05101/07 05/08/07 05/15/07 05122107 05129107 06/05/07 06112107 06/19107 06126107 TABLE B-8

}PEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCiI m3 +/- 1 Sigma SAMPLE STATION #

94' I,' --"--, ','

4,

5

'(:>-;

-23**

,22

-'27-

",~,

':'j,

< 0.025

< 0.023

< 0.022

< 0.018

< 0.028

< 0.022

< 0.029

< 0.019

< 0.024

< 0.031

< 0.036

< 0.067

< 0.020

< 0.033

< 0.032

< 0.035

< 0.039

< 0.023

< 0.041

< 0.023

< 0.022

< 0.020

< 0.023

< 0.029

< 0.034

< 0.046

< 0.022

< 0.014

< 0.025

< 0.027

< 0.033

< 0.030

< 0.031

< 0.019

< 0.026

< 0.017

< 0.022

< 0.023

< 0.026

< 0.034

< 0.014

< 0.056

< 0.024

< 0.027

< 0.047

< 0.039

< 0.058

< 0.035

< 0.023

< 0.025

< 0.032

< 0.040

< 0.017

< 0.027

< 0.019

< 0.051

< 0.036

< 0.030

< 0.042

< 0.029

< 0.046

< 0.035

< 0.023

< 0.016

< 0.024

< 0.023

< 0.039

< 0.032

< 0.027

< 0.022

< 0.036

< 0.024

< 0.015

< 0.032

< 0.038

< 0.026

< 0.033

< 0.028

< 0.031

< 0.021

< 0.036

< 0.044

< 0.027

< 0.017

< 0.021

< 0.024

< 0.030

< 0.028

< 0.020

< 0.022

< 0.044

< 0.023

< 0.035

< 0.031

< 0.Q28

< 0.028

< 0.030

< 0.029

< 0.031

< 0.024

< 0.019

< 0.022

< 0.027

< 0.013

< 0.038

< 0.027

< 0.032

< 0.026

< 0.036

< 0.068

< 0.025

< 0.021

< 0.030

< 0.026

< 0.023

< 0.026 Deviation Report

< 0.026

< 0.023

< 0.016

< 0.023

< 0.038

< 0.023

< 0.028

< 0.026

< 0.030

< 0.038

< 0.030

< 0.031

< 0.034

< 0.041

< 0.029

< 0.042

< 0.041

< 0.014

< 0.031

< 0.039

< 0.033

< 0.027

< 0.028

< 0.009

< 0.027

< 0.030

<0.031

< 0.049

< 0.017

< 0.036

< 0.024

< 0.031

< 0.039

< 0.016

< 0.018

< 0.022

< 0.024

< 0.021

< 0.019

< 0.022

< 0.036

< 0.035

< 0.017

< 0.030

< 0.024

< 0.044

< 0.035

< 0.037

< 0.033

< 0.026

< 0.035

< 0.021

< 0.026

< 0.030

< 0.033

< 0.029

< 0.022

< 0.024

< 0.055

< 0.025

< 0.027

< 0.052

< 0.022

- Control sample location B-16 i':

I>,':,

39,:'

'-t,':';,

< 0.020

< 0.021

< 0.020

< 0.034

< 0.022

< 0.025

< 0.013

< 0.007

< 0.019

< 0.033

< 0.026

< 0.023

< 0.030

< 0.045

< 0.020

< 0.029

< 0.033

< 0.011

< 0.013

< 0.019

< 0.018

< 0.023

< 0.017

< 0.025

< 0.022

< 0.027

< 0.022

< 0.017

< 0.021

< 0.032

< 0.017

< 0.029

< 0.013

< 0.017

< 0.023

< 0.032

< 0.017

< 0.020

< 0.032

< 0.019

< 0.028

< 0.020

< 0.031

< 0.039

< 0.031

< 0.023

< 0.027

< 0.028

< 0.029

< 0.032

< 0.017

< 0.024

Week

. Number 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53

. Week End Date 07/02/07 07110107 0711 7/07 07124/07 07/31/07 08/07/07 08/14/07 08/2I107 08/28/07 09104/07 09/11/07 09118107 09125107 10102/07 10109107 10/16/07 10/23107 10/30107 1 II06/07 11/13107 11/19107 11127107 12104/07 12111107 12/18/07

-12/24/07 12/31/07 TABLEB-8 IPEC ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 2007 1-131 ACTIVITY pCiI m3 +/- 1 Sigma SAMPLE STATION #

94

- . ***.. **C*95:

4 5

23**

... 22

< 0.030

< 0.031

< 0.024

<.0.028

< 0.030

< 0.036

< 0.027

< 0.030

< 0.029

< 0.022

< 0.024

< 0.037

< 0.032

< 0.005

< 0.020

< 0.032

< 0.025

< 0.035

< 0.022

< 0.023

< 0.020

< 0.037

< 0.024

< 0.021

< 0.023

< 0.028

< 0.020

< 0.006

<0.031

< 0.034

< 0.029

< 0.030

< 0.033

< 0.027

< 0.030

< 0.035

< 0.025

< 0.028

< 0.022

< 0.027

< 0.053

< 0.029

< 0.016

<.0.020

< 0.028

< 0.042

< 0.027

< 0.032

< 0.021

< 0.034

< 0.010

< 0.037

< 0.032

< 0.006

< 0.032

< 0.021

< 0.029

< 0.028

< 0.035

< 0.028

< 0.021

< 0.033

< 0.022

< 0.033

< 0.027

< 0.029

< 0.033

< 0.031

< 0.034

< 0.021

< 0.028

< 0.021

< 0.029

< 0.027

< 0.028

< 0.016

< 0.030

< 0.036

< 0.035

< 0.031

< 0.029

<.0.037

< 0.007

< 0.036

< 0.034

< 0.029

< 0.033

<0.030

< 0.032

< 0.045

< 0.036

< 0.027

< 0.034

< 0.027

< 0.036

< 0.030

< 0.031

< 0.028.

< 0.029

< 0.031

< 0.028

< 0.025

< 0.029

< 0.037

< 0.025

< 0.030

< 0.022

< 0.033

< 0.025

< 0.026

< 0.029

< 0.040

< 0.030

< 0.024

< 0.026

< 0.010

< 0.028

< 0.025

< 0.040

< 0.046

< 0.029

< 0.008

< 0.030

< 0.023

< 0.038

< 0.036

< 0.030

< 0.024

< 0.007

< 0.022

< 0.023

< 0.044

< 0.007

< 0.033

< 0.028

< 0.032

< 0.031

0.032

< 0.028

< 0.024

< 0.025

< 0.026

< 0.025

< 0.039

< 0.042

< 0.037

< 0.046

< 0.028

< 0.037

< 0.035

< 0.022

< 0.031

< 0.048

< 0.026

< 0.034

- Control sample location B-17

C".

I iT "

29.

.' 44

< 0.025

< 0.016

< 0.024

< 0.018

< 0.022

< 0.009

< 0.023

< 0.010

< 0.021

< O.oJ8

< 0.016

< 0.036

< 0.011

< 0.036

< 0.024

< 0.018

< 0.021

< 0.025

< 0.009

< 0.031

< 0.022

< 0.034

< 0.022

< 0.021

< 0.029

< 0.026

< 0.025

< 0.021

< 0.027

. < 0.016

< 0.031

< 0.019

< 0.037

< 0.023

< 0.031

< 0.027

< 0.025

< 0.028

< 0.027

< 0.014

< 0.027

< 0.031

< 0.023

< 0.039

< 0.019

< 0.D21

< 0.022

< 0.020

< 0.024

< 0.038

< 0.024

< 0.022

< 0.028

< 0.033

< 0.031

< 0.023

< 0.040

< 0.020

< 0.030

< 0.021

< 0.022

< 0.035

< 0.032

< 0.026

< 0.028

< 0.034

< 0.023

< 0.044

< 0.020

< 0.022

< 0.030

< 0.024

< 0.027

< 0.035

< 0.033 Deviation Report

< 0.034

Date

.. NUCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 2n-65 Co-60 K-40 BalLa-140 Date:

NUCLIDE 1-131 Cs-134 Cs-137 2r-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 BalLa-1 40 TABLE B-9 CONCENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma

9 PLANT INLET (HUDSON RIVER INTAKE) 01126/2007.< ;'.02/23/2007 "

"~03/3012007 0412712007..,.

.. 0512512007

'.:\\.>" ',.' "

< 6.03

< 4.09

< 5.78

< 7.03

< 6.91

< 0.75

< 1.01

< 0.75

< 1.78

< 1.27

< 0.94

< 0.79

< 1.00

< 1.35

< 1.22

< 2.09

< 1.84

< 1.94

< 3A3

< 2.64

< IA2

< 1.29

< 1.51

< 2.16

< 1.72

< 1.07

< 1.00

< 1.30

< 1.59

< 1.24

< 0.90

< 0.89

< 1.12

< 1.71

< 1.14

< 2.97

< 2.99

< 3.36

< 5.19

< 4.03

< 2.12

< 1.06

< 2.55

< 2.01

< 2.95

< 0.76

< 0.90

< 1.01

< 1.47

< 1.25 106.5 +/- 9.51 321.7 +/- 12A3 157.9 +/- 11.24 349.6 +/- 21.96 127.3 +/- 12.77

< 3.13

< 2A8

< 3.11

< 3.82

< 4.20 07/2712007.

08/3112007.

'..09/28/2007

"10126/2007'.

1113012007.'.

Y 0612912007

< 5.70

< 1.10

< 0.63

< 2.19

< 1.08

< 1.29

< 1.10

< 3A7

< 1.38

< 0.99 326.4 +/- 13.70

< 3.65 12/31/2007.

.....,\\...........

I*/~:

.. ~.. ".

< 5.34

< 7.00

< 6.87

< 6.72

< 6.89

< 6.75

< 1.41

< 1.37

< IA5

< 1.09

< 1.14

< 1.98

< 1.18

< 1.14

< 1.84

< 1.54

< 1.05

< 1.88

< 2.65

< 2.70

< 4.08

< 2.94

< 2.23

< 3.06

< 1.70

< 2.12

< 2.65

< lAO

< 1.47

< 2.30

< lAO

< 1.56

< 1.95

< 1.77

< 1.14

< 2.19

< 1.34

< 1.25

< 2.05

< lAI

< 0.96

< 1.63

< 4.27

< 4A9

< 5.08

< 4.31

< 3.94

< 5.69

< 1.69

< 1.57

< 4.72

< 1.91

< 1.41

< 4.72

< 1.44

< 1.24

< 2.11

< 1.33

< 1.12

< 1.96 361.6 +/- 18.82 348.3 +/- 17.84 365.1 +/- 27.71 190.2 +/- 14.55 337.6 +/- 14.56 163.9 +/- 20.54

< 4.15

< 4.10

< 5.35

< 3.73

< 3.89

< 4.09 8-18

Date NUCLIDE...

1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 BalLa-140 Date

. NUCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 BalLa-140 TABLE B-9 CONCENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units ofpCiIliter +/- 1 Sigma

10 DISCHARGE CANAL (MIXING ZONE) 01l26!2007 02123/2007 03/30/2007 04/27/2007.

0512512007 '..

< 6,91

< 4,02

< 6.75

< 6.57

< 6.42

< 1.22

< 0.68

< 0.87

< 0.81

< 1.32

< 1.45

< 1.09

< 1.30

< 1.24

< 1.29

< 3.33

< 2.02

< 2.81

< 2.44

< 2.30

< 2.04

< 1.40

< 2.07

< 1.94

< 1.90

< 1.86

< 1.23

< 1.61

< 1.41

< 1.49

< 1.75

< 1.06

< 1.21

< 1.43

< 1.29

< 4.00

< 3.51

< 5.05

< 4.47

< 4.21

< 3.89

< 2.56

< 3.44

< 1.79

< 3.04

< 1.40

< 1.27

< 1.58

< 1.24

< 1.23 128 +/- 14.77 271.2 +/- 14.85 162.4 +/- 15.84 122 +/- 13.66 293.2 +/- 17.84

< 3.55

< 4.01

< 5.30

< 3.96

< 3.82 07/27/2007.*.*.

.***. 08/3112007

... 09/2812007 10/26/2007 '.,

.. 11130/2007'

-*:.i 1/>

,;:.~f'_

.. :.. ~..

< 5.19

< 5.74

< 6.41

< 6.59

< 0.72

< 0.79

< 1.70

< 1.84

< 1.45

< 1.08

< 0.69

< 1.56

< 1.81

< 1.33

< 2.09

< 1.65

< 2.99

< 4.03

< 2.43

< 1.56

< 1.20

< 2.24

< 2.73

< 1.75

< 1.14

< 0.93

< 1.81

< 1.89

< 1.77

< 1.07

< 0.75

< 1.58

< 1.36

< 3.05

< 2.70

< 4.17

< 4.95

< 4.53

< 1.35

< 0.95

< 3.49

< 3.31

< 3.06

< 0.94

< 0.72

< 1.47

< 1.63

< 1.26 171.5 +/- 11.44 322.5 +/- 10.33 203.9 +/- 20.17 385.3 +/- 24.76 163.2 +/- 15.73

< 3.15

< 3.26

< 4.16

< 5.77

< 4.53 8-19

'0612912007

< 6.95

< 1.50

< 1.36

< 3.21

< 2.17

< 1.87

< 1.55

< 4.85

< 1.80

< 1.34 277.1 +/- 19.80

< 4.13 12/3112007..

.*.. F-::::~

< 5.42

< 1.03

< 1.21

< 2.75

< 1.86

< 1.55

< 1.48

< 4.58

< 3.34

< 1.41 136.5 +/- 15.47

< 4.37

TABLE B-I0 CON CENTRA TIONS OF TRITIUM IN.sURFACE WATER SAMPLES - 2007 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pC ill +/- 1 Sigma STATIONCODE" PERIOD

>> '?::' DATE"

',,',il;"

":%TRITIlJM;:,,,

First Quarter 12/29/06 03/30/07

<476 PLANT INTAKE (HUDSON RIVER)

Second Quarter 03/30/07 06/29/07

<443 (09, INLET) **

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

<449 Fourth Quarter 09/28/07 12/31107

<439 First Quarter 12/29/06 03/30/07

<476 DISCHARGE CANAL Second Quarter 03/30/07 06/29/07

<443 (l0, MIXING ZONE)

Third Quarter 06129107 09128/07

<449 Fourth Quarter 09/28/07 12/31107

<439

- Control Sample location 8-20

Date NUCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Date.

1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58

'Mn-54 Fe-59 Zn-65 Co-60 K-40 8a/La-140 TABLE B-ll CONCENTRA nONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma CAMP FIELD RESERVOiR

< 0.25

< 0.26

< 0.37

< 0.35

< 0.27

< 2.23

< 3.52

< 3.96

< 4.42

< 3.57

< 2.73

< 3.68

< 2.95

< 2.50

< 3.18

< 3.24

< 5.06

< 6.19

< 5.39

< 5.92

< 2.78

< 3.97

< 4.24

< 4.49

< 3.37

< 2.13

< 3.51

< 3.98

< 4.44

< 3.60

< 2.16

< 2.97

< 4.11

< 4.00

< 5.15

< 9.96

< 10.92

< 8.47

< 12.62

< 5.21 -

< 6.54

< 8.03

< 9.12

< 7.78

< 1.74

< 5.52

< 5.04

< 2.30

< 4.42 321.2 +/- 35.25 231.5 +/- 45.77

< 42.91 275.6 +/- 48.57 89.5 +/- 31.21

< 0.33

< 0.31

< 0.38

< 0.32

< 2.59

< 2.84

< 1.94

< 2.51

< 1.63

< 2.62

< 2.12

< 3.58

< 3.15

< 2.38

< 4.35

< 4.60

< 5.99

< 4.86

< 3.65

< 2.91

< 2.71

< 4.46

< 3.16

< 2.16

< 2.23

< 2.49

< 4.50

< 3.36

< 2.16

< 2.80

< 1.90

< 4.28

< 3.49

< 1.94

< 6.52

< 7.41

< 9.80

< 8.79

< 3.99

< 6.36

< 6.05

< 13.23

< 6.39

< 6.45

< 2.42

< 2.84

< 3.90

< 3.97

< 2.25 197.3 +/- 31.68 133.6 +/- 30.08 326.8 +/- 47.02 85.98 +/- 32.57 131 +/- 22.62

< 3.49

< 3.06

< 2.35

< 3.13

. < 3.23 8-21

< 0.41

< 2.52

< 2.45

< 4.18

< 2.83

< 2.31

< 2.24

< 5.16

< 4.50

< 2.21 99.1 +/- 26.92

< 1.93

< 2.77

< 3.94

< 2.32

< 2.88

< 2.41

< 8.78

< 9.14

< 2.58 215 +/- 32.21

< 3.44

Date NUCLIDE f-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140

Date,

,NUCLIDE

~.

f-\\31 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140 TABLE B-11 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma NEW CROTON RESERVOIR

,"., :'/"",'.,"

'...... ': 'J';"

< 0,26

< 0.23

< 0.34

< 0.32 c

< 0.34

< 3.65

< 3.50

< 2.84

< 3.64

< 2.81

, < 3.17

< 3.53

< 2.90

< 3.89

< 2.88

< 5.16

< 6.50

< 6.03

< 5.77

< 5.99

< 3.60

< 4.16

< 2.68

< 3.53

< 3.65

< 2.62

< 3.71

< 2.24

< 3.49

< 3.90

< 2.70

< 3.22

< 2.49

< 3.19

< 4.28

< 7.57

< 6.41

< 5.37

< 12.84

< 9.82

< 9.\\3

< 3.31

< 6.83

< 8.86

< 11.53

< 3.08

< 3.60

< 2.31

< 4.21

< 4.21 221.9 +/- 38.95

< 40.52 177 +/- 32.14 243.1 +/- 47.97 347.2 +/- 53.88

< 4.62

< 4,21

< 2.23

< 6.23

< 5.28 07/10/2007

'08/07/2007 09111/2007 10/09/2007.. '

11119/2001"

/'

,. ~~.:'.

,,:c'\\'<

< 0.30

< 3.26

< 2.52

< 4.92

< 3.05

< 2.88

< 2.97

< 9.08

< 7.41

< 2.66 137.6 +/- 27.55

< 3.96 12/18/2007

.,,"C.

"c',:

I:,"':.

,;\\.,.

< 0.29

< 0.25

< 0,31

< 0.30

< 2.35

< 2.38

< 3.40

< 2.51

< 1.78

< 2.89

< 2.45

< 2.19

< 3.29

< 2.29

< 1.96

< 2.39

< 4.43

< 3.78

< 3.75

< 5.18

< 4.34

< 5.13

< 2.62

< 2.89

< 3.69

< 2.78

< 3.00

< 3.19

< 2.59

< 2.61

< 2.49

< 3.11

< 2.52

< 3.00

< 2.88

< 2.85

< 3.62

< 3.42

< 2.30

< 2.54

< 8.76

< 6.30

< 7.84

< 7.54

< 6.24

< 7.14

< 5.36

< 7.96

< 5.91

< 3.12

< 7.29

< 3.02

< 2.47

< 2.38

< 2.76

< 2.32

< 2.06 139.6 +/- 29.84 315.7 +/- 35.43 201 +/- 42.41 277.3 +/- 41.09 146.9 +/- 27.10 142.8 +/- 29.31

< 4.33

< 3.04

< 3.82

< 3.81

< 3.35

< 3.46 8-22

TABLE B-12 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES - 2007 (QUARTERLY COMPOSITE SAMPLES)

Results in Units of pCiIl +/- 1 Sigma

. *.STATION.CODE

..,: *. ;...* :.,:i*c* :.

PERlOD" DATE I"TRITIUM' First Quarter 12/12/06,

03/06107

,< 461.00 CAMP FIELD RESERVOIR Second Quarter 03/06107 06112107

< 436.00 Third Quarter 06112/07 09/11/07

<448 F ourtb Quarter 09/11/07 12/18/07

<433 First Quarter 12/12106 03/06107

< 461.00 NEW CROTON RESEVOIR Second Quarter 03/06107 06/12/07

< 436.00 Third Quarter 06112/07 09/11/07

<448 Fourth Quarter, 09/11/07 12/18/07

<433 B-23

Sample, location Date Client ID Radionuclide 1 Req. CL Be-7 1-131 Cs-134 75 Cs-137 90 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 BalLa-140 Ru-103 Ru-106 Ce-141 Ce-l44 AcTh-228 Ra-226 K-40 Sr-90 5000 TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- I Sigma 1-COLDSpRING

'SHORELINE 06/06/2007 ISS842307 234.9 44.2 31.4 26.0 46.6 34.6 30.3 28.7 92.4 95.9 37.9 40.3*

20.6 298.9 45.9 164.1 468.4

+/-

98.0 593.0

,LENTS COVE SHORELINE

'06/,06/2007 '

ISS282307 319.8 80.7 46.2 54.7 82.9 68.6 39.5 49.1 52.5 143.4 41.0 96.6 44.6 381.1 63.6 259.6 1052.0

+/-

187.2 2250.0

+/-

702.7 MANITOU SHORELINE

','06/06/2007 ISS502307 448.6 118.3 36.2 357.0

+/-

33.4 62.3 55.3 47.8 46.4 115.3 125.4 49.4 59.0 51.2 555.5 86.0 341.1 806.3

+/-

154.1 2006.0

+/-

737.3 VERPLANCK,.

WRITE'BEACH ISH~~ELl~.~: ;: 'SHORELINE 06;07l200~i',

06/0712007 ISSI72307 ISS532307 165.3 176.4 39.9 30.3 11.3 11.2 63.3

+/-

18.1 19.6 41.3 35.7 30.0 26.3 22.2 18.6

'15.1 20.0 54.8 61.3 53.6 60.2 22.1 15.5 45.4 30.9 20.4 22.2 264.8 202.5 39.8 30.7 150.2 104.7 194.3

+/-

64.0 61.5 1194.0

+/-

388.5 979.4

+/-

314.7 36000.0

+/-

1070.0 115770.0

+/-

1077.0 124470.0

+/-

1177.0 I 5423.0

+/-

411.2 9411.0

+/-

598.1 140 8-24

Sample Location Date Client ID Radionuclide Be-7 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 BalLa-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Req. CL 75 90 Sr-90 5000 TABLE B-13 CONCENTRATIONS OF RADIONUCLIDES IN SHORELINE SOIL SAMPLES - 2007 Results in Units of pCilkg +/- I Sigma

. I

,COLD SPRING SH9RELIN.Ji:

09/06/2007 ISS843607 312.9 46.4 24.2 38.3 70.0 38.2 37.7 33.6 68.5 147.0 50.9 57.0 32.3 268.8 51.7 167.4 691.6

+/-

138.8 1508.0

+/-

492.5 31600.0

+/-

1200.0 300 LENT"SCOVE SH()RELINE 09/06/2007 ISS283607 332.2 57.6 39.9 37.3 59.9 52.4 43.3 37.3 46.1 107.0 39.5 55.1 39.7 309.3 58.8 235.8 992.0

+/-

151.6 3924.0

+/-

683.2 4540.0

+/-

894.9 350 8-25 MANITOU; SHORELINE-'

09/06/2007 ISS503607 615.1 86.9 58.2 67.0 107.1 78.1 32.7 48.7 198.1 98.2 39.9 114.6 52.4 383.3 80.1 324.0 1380.0

+/-

284.0 2561.0

+/-

1041.0 10230.0

+/-

1239.0 370

"'VERPLANcK. 'I:" WHITE BEACH

'SHOREqN~.

.'. <';SHORE~INE,'.

'. 09/07/2007: ;'

.,09/07/2007 ISS I 73607R 1 ISS533607 175.9 167.6 30.9 26.5 23.4 18.5 149.0

+/-

22.6 19.2 36.7 30.8 20.1 27.2 18.6 20.7 24.7 20.3 58.9 66.3 57.7 51.6 21.2 28.4 22.2 24.2 24.4 18.8 163.2 191.8 31.8 23.7 123.3 112.0 141.9

+/-

71.2 77.8 748.8

+/-

371.0 397.7 8613.0

+/-

624.5 8537.0

+/-

586.

270

< 1200

'SamJ)le 1\\',:,"

Location '"

Date Client ID Radionuclide Req. CL Be-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007

'MET TOWER*;'

05/2412007 IBV952107S3 MULLEN 73.05 18.99 11.49 9.71 14.46 9.44 11.60 10.51 29.73 30.05 8.62 13.10 9.16 91.08 12.72 48.86 34.94 146.30

~.O~ 2~

Results in Units of pCilkg +/- 1 Sigma

95 Meteorological Tower

}','*METTOWER "

MEri:T()WE~<:

';" 05;25;2~07 "

'MJi1l'TOWER 0$124/2007 '.',

,;06126/2007.

IBV952107S2 IBV952107S1 IBV952607S I RAGWEED MOTHERS WORT GRAPE LEA YES 441,1

+/-

812 357,1

+/-

73.5 394.1

+/-

53.9 16.52 27.21 727 13.43 11.74 8.34 9.92 8.97 6.35 14.50 15.75 11.71 11.31 13.31 7.76 9.71 13.34 7.53 11.30 10.59 7.54

< 28.85

< 31.51 19.45

< 46.86

< 48.51 19.06 12.01 8.51 6.92 18.44 28.56 6.74 9.82 12.63 6.23

< 93.88

< 120.90 74.87 12.38 16.66 9.80

< 42.50 58.89 41.41

< 37.75 46.54 25.89

< 150.70 312.4

+/-

131.1 218.8

+/-

121.9 6498.0

+/-_300.7.... '--- 4962.0

+/-

320.2 4307.0

+/-

203.4 8-26 I' 'ijE)'.JOWE~.

'0612612007:..

IBV952607S2 RAGWEED 681.3

+/-

84.9 10.59 13.63 10.15 19.55 12.38 13.16 11.54 29.27 42.10 16.93 13.62 10.93 94.36 11.93 47.90 48.41 280.2

+/-

138.6 10580.0

+/-

386.5 i;'tlMln TOWER

~*'<:ri6/2612~07.

IBY952607S3 MULLEN 422.9

+/-

82.2 13.44 14.78 11.96 19.25 10.99 11.02 11.06 29.20 32.25 16.49 11.06 10.39 120.80 14.98 58.53 53.57

< 210.50 7602.0

+/-

395.4

Sample.

. Location Date',

Client ID Radionuclide Req. CL Be-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 BalLa-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma

95 Meteorological Tower

. I\\1ET TOWER*

METTOWER *.... ' METTOWER

< MET 'TOWER.. ".

}i Mirf'TOWER

~" ~.. 08/14)2~0;

.**.* '~\\08/l4~2007.'

07/24/2007 07/24/2007 07/24/2007" lBV953007S I IBV953007S2 IBV953007S3 IBV953307S I lBV953307S2 GRAPE LEAVES RAGWEED MULLEN GRAPE LEAVE RAGWEED 491.8

+/-

77.3 1007.0

+/-

99.2 1258.0

+/-

131.6 746.5

+/-

73.1 2332.0

+/-

121.1 12.16 17.77 18.01 16.82 16.43 9.64 8.67 7.73 8.73 11.80 9.37 9.48 12.30 6.74 9.00 20.83 22.03 17.45 13.15 16.85 10.04 13.02 13.63 9.27 12.70 9.49 11.87 12.23 7.84 9.80 10.05 13.38 11.92 7.96 9.31 32.62 31.94 36.43 18.90 30.37 33.42

< 35.49 41.73 25.76 32.09 9.03 11.71 13.49 9.40 9.52 18.70 16.44 11.31 11.85 17.74 11.85 10.24 11.49 7.43 9.68 96.38

< 109.60

< 111.90 89.75 93.88 11.69 17.94 13.90 11.84 12.37 43.14

< 69.45 55.13 44.93 42.83 40.90

< 40.06

.< 44.84 25.64 34.75

< 175.60

< 225.80

< 212.60

< 139.50 340.6

+/-

97.3 3716.0

+/-

264.0 8313.0

+/-

343.1 6807.0

+/-

380.4 4246.0

+/-

205.8 7933.0

+/-

300.7 8-27

' ; MET TO""ER 08/14/2007

IBV953307S3 CATALPA 1047.0

+/-

95.8 18.17 12.56 10.80 19.57 12.71 11.56 12.17 36.59 37.74 16.51 23.26 10.86 95.17 15.04 46.99

< _43.88 366.8

+/-

133.1 6510.0

+/-

288.6

Sample

Location

, Date Client ID Radionuclide Req. CL Be-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60.

Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma

95 Meteorological Tower MET TOWER METT()WER

. MET-TOWER

. i'lVIEtTOWER-1'; <~MET-TOWER';;""

"0,:

".. ;';./.... ;'

0911'8/2007

.~

~f,f \\ 10/1~i2.j()7..........,

09/1812007 0911812007'.

.. 10/16/2007 IBV953807S1 IBV953807S2 IBV953807S3 IBV954207S I IBV954207S2 GRAPE LEAVES RAGWEED MULLEIN GRAPE LEAVES RAGWEED 929.3

+/-

94.6 1715.0

+/-

118.3 362.2

+/-

85.9 1214.0

+/-

96.9 2203.0

+/-

157.3 9.79 12.14 13.83 12.85 14.82 13.59 13.33 9.17 8.50 18.55 7.73 9.84 14.32.

6.62 13.55 14.96 18.34 23.08 14.97 23.41 10.44 10.14 16.12 10.20 13.46 11.80 12.51 15.19 8.45 17.00 10.44 11.69 15.53 8.22 13.48 23.10 27.20 44.00 21.80 32.83 23.00 28.69 48.12 20.26 40.10 12.11 9.10 21.25 12.40 20.87 11.41 9.33 16.40 6.78 17.40 8.41 8.92 10.75 8.10 12.76 103.00 99.95

< 117.90 75.51 133.60 13.27 13.78 15.38 12.01 17.88 56.27 64.28 57.44 53.08 82.95 34.20 46.23 56.26 31.59 54.58 299.2

+/-

179.2 200.70

< 250.10

< 174.80 510.8

+/-

216.9 3719.0

+/-

249.0 7667.0

+/-

347.4 7117.0

+/-

373.7 4006.0

+/-

228.4 8246.0

+/-

454.5 8-28

.~ETTOWER.

"10/16/2007.:;

IBV954207S3 MULLEIN 755.2

+/-

94.1 11.32 12.13 9.82 16.86 12.26 8.66 10.57 26.33 35.01 12.86 12.12 8.35 108.80 11.26 49.55 35.01 190.40 6177.0

. +/-. 309.9

Sample

. Location I

Date Client ID Radionuclide Req. CL 6e-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 6a/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40

.. Control Sample Location TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma

23 Roseton **

ROSETON ROSETON

RDSETON, ROSETON:,

RPSETON"

,>,: 06/25J201)7.*. <.

05/24/2007*

05/24/2007

.0512412007 I.'

06125/2007 lBV232107S1 IBV232107S2 lBV232107S3 lBV232607S I IBV232607S2 RAGWEED BURDOCK MULLEN RAGWEED BURDOCK 406.5

+/-

95.8 389.9

+/-

59.2 165.9

+/-

64.9 1084.0

+/-.

105.7 1352.0

+/-

83.5 27.19 16.65

< 23.51 12.27 8.19 12.10 9.90 12.94 13.35 10.85 10.85 6.89 9.67 11.65 8.25 21.42 17.45

< 16.28 18.80 14.73 14.49 9.31 11.56 12.70 7.45 12.42 7.19 11.21 12.95 8.47 13.49 9.65 9.25 10.63 8.71 31.73

< 30.83

< 22.32 29.58 23.68 57.99

< 24.10

< 33.86 41.95 26.95 13.58*

9.40 9.70 15.35 8.44 9.90 15.22 19.09 11.92 12.88 10.99 6.78 12.63 10.31 7.76 99.86

< 62.41

< 110.00 126.00 82.92 17.01 9.87 12.25 12,39 9.39 66.45 33.14

< 46.19 59.93 32.27 37.64

< 29.74

< 34.95 47.51 28.42

< 208.30

< 115.40

< 155.70 208.70

< 130.50 8773.0

+/-

406.3 5144.0

+/-

249.1 3757.0

+/-

252.3 10020.0

+/-

412.2 6088.0

+/-

248.3 8-29

ROSETON 06/251io07 IBV232607S3 MULLEN 1130.0

+/-

135.4 17.41 17.92 15.90 24.09 15.30 9.28 19.39 46.40 44.85 16.27 16.78 11.72 138.00 17.78 74.82 53.33 385.0

+/-

213.4 5830.0

+/-

402.7

,.... III".. '....

I nr.:dinn

.;. Date Client ID Req. CL Radionuclide (pC i)

Be-7

/-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40

-- Control Sample Location TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma

23 Roseton **

ROSETON ROSETON...

ROSETON';.*

. ' ':ROS12!ON,::~\\

ROSETON' 07/23/2007 07123/2007,

.07/23/2007,.'

.:08/13/2007.',

08/1312007 IBV233007S 1 IBV233007S2 IBV233007S3 IBV233307S1 IBV233307S2 CATALPA BURDOCK MULLEN GRAPE LEA YES RAGWEED 141.5

+/-

71.0 1411.0

+/-

107.5 504.4

+/-

82.2 541.5

+/-

88.5 1990.0

+/-

144.4 13.77 14.60 18.33 23.19 26.68 11.49 9.97 11.34 13.95 17.31 9.32 6.86 11.06 12.91 11.74 11.35 11.77 18.85 19.02 24.50 8.55 6.61 8.87 12.49 15.12 11.24 7.95 11.34 12.11 16.73 8.06 9.92 9.94 8.51 14.63 17.59

< 23.96

< 29.01 33.00 46.81 32.87

< 23.90

< 33.82 22.92 52.13 9.29

< 11.90 15.87 15.42 21.23 6.85 10.46 8.64 17.60 24.23 11.55 8.32 9.01 11.06 13.27 66.64

< 85.69

< 96.44 85.24

< 124.30 10.71 12.36 13.70 12.54 17.30 39.73

< 42.25

< 61.21 42.12 53.71 22.66

< 30.64

< 42.01 40.03 48.92

< 157.10

< 155.70

< 192.40

< 181.20

< 220.00 2478.0

+/-

211.3 6527.0

+/-

298.3 4840.0

+/-

277.8 3640.0

+/-

246.0 7920.0

+/-

358.9 8-30

ROSETON,

, 08/13/2007 IBV233307S3 MULLEN 2027.0

+/-

139.7 25.24 13.58 10.15 11.85 17.40 8.45 9.53 15.40 37.44 10.64 24.24 12.54 110.80 16.31 59.70 36.33 183.90 3590.0

+/-

243.8

,.Sample L.ocation Date Client ID Radionuclide Req. CL 8e-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 CO-58 Mn-54 Zn-65 Fe-59 Co-60 8a/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40

.. Control Sample Location

/

TABLE B-14 CON CENTRA TIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma

23 Roseton **

\\icROSETON

,:. ROSETON,>:,

ROSETON

'ROSETON ROSETON i 0/15/~oki;:

I***::*'

09117/2007 09/17/2007 0911712007 Hi/15/2007 IBV233807S1 IBV233807S2 IBV233807S3 IBV234207S1 IBV234207S2 MULLEIN RAGWEED CATALPA MULLEN RAGWEED 1589.0

+/-

142.8 994.1

+/-

114.0 693.1

+/-

87.2 1679.0

+/-

185.7 1961.0

+/-

140.4 17.12 11.84 10.81 21.35 15.31 16.78 12.18 12.76 21.33 1220 14.27 12.29 8.32 17.33 12.82 23.44 22.37 18.96 19.63 23.40 16.53 11.41 7.72 21.11 13.88 14.47 11.52 11.48 16.56 12.36 15.07 11.84 8.76 18.93 12.90 44.37 26.80 27.74 56.50 16.03 49.21 39.91 26.74 54.21 36.91 17.12 11.39 12.00 25.33 14.26 21.48 13.69 5.36 20.04 14.25 9.53 10.93 9.59 12.89 10.09 145.10 111.30 88.46 175.50 106.50 20.31 13.53 14.15 22.65 15.18 68.00 56.57 51.31 100.40 47.94 58.61 44.71 30:05 126.5

+/-

59.9 42.54 226.20 226.70 151.90 334.90 241.70 4950.0

+/-

363.5 6742.0

+/-

380.3 3412.0

+/-

245.5 8119.0

+/-

494.8 7434.0

+/-

366.0 8-31 If:'I~OSETON:,

10115/2007 IBV234207S3 CATALPA 1771.0

+/-

94.1 11.14 823 7.78 12.55 7.76 5.86 7,08 17.21 21.02 6.57 9.19 6.94 88.35 11.39 48.36 30.34 146.90 3715.0

+/-

188.1

TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma

94 IPEC Training Center

. to:~~~en TRAINING BLDG TJM.INING.HLDG~. TRAINING BLDG 'l'RAININGlJl,P<;, :'TRAlN~~~ BLDG TJWNINGBLD<;

Date 05/24/20Q7 <

05/24/2007

'05/24/2007 0612612007 06/26/2007<'

.:06126/2007 Client ID IBV942I07S1 IBV942I07S2 IBV942I07S3 IBV942607S1 IBV942607S2 IBV942607S3 I

Radionuclide Req. CL BURDOCK MULLEN RAGWEED GRAPE LE MULLEN RAGWEED I

Be-7 613.8

+/-

84.1 235.4

+/-

90.5 293.2

+/-

67.0 560.2

+/-

63.8 538.7

+/-

80.2 997.7

+/-

108.9 1-131 50 24.59

< 21.68 20.77 7.01 8.50 13.35 Cs-134 50 9.18 15.91 9.46 8.56 14.08 15.96 Cs-137 50 9.04 11.65 7.21 7.01 9.97 12.42 Zr-95 16.48

< 21.08 20.03 11.11 18.57 23.32 Nb-95 11.32 15.40 13.04 8.35 12.47 14.33 Co-58 9.56 12.65 10.68 7.62 10.30 15.06 Mn-54 9.27 11.05 10.46 7.48 11.54 10.40 Zn-65 29.95

< 34.24 23.90 20.38 34.46 36.27 Fe-59 31.31

< 45.19 29.75 20.44 36.16 47.44 Co-60 10.02 15.16 5.96 7.36 15.97 15.50 Ba/La-140 5.54 21.45 16.18 7.10 11.37 13.31 Ru-103 7.76 12.27 8.52 6.14 10.25 9.42 Ru-106 77.09

< 104.90 79.41 72.78 91.08 112.30 Ce-141 11.10 16.79 14.55.

9.68 12.53 14.83 Ce-144 47.63

< 61.57 53.33 40.26 46.90 66.81 AcTh-228 32.40

< 43.30 30.89 28.87 44.82 44.78 Ra-226

< 148.50

< 209.90

< 139.00 260.3

+/-

108.4

< 179.00 227.20 K-40 7976.0

+/-

291.2 6472.0

+/-

333.8 7224.0

+/-

281.2 4342.0

+/-

197.8 7540.0

+/-

331.3 10130.0

+/-

467.0 6-32

~am"le Location Date*

Client ID Radionuclide I Req. CL Be-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 BalLa-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 TABLE B-14 CONCENTRA nONS OF GAMMA EMITTERS IN BROADLEAF VEGET A nON SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma

94 IPEC Training Center TRAINING BLDG I TRAINING BLDG I TRAINiNG BL))G

'07/2412007.

.,'... *,'07/2~/2007*"

.';~; '07;;4;2007 TRAINING BLDd,I,JRAIN~GBLPG 08114/2007

.. 08/14/2007.

IBV943007S 1 IBV943007S2 IBV943007S3 IBV943307S 1 IBV943307S2 GRAPE LEAVES MULLEN RAGWEED GRAPELE BURDOCK 831.5

+/-

118.61 1097.0

+/-

104.5 916.9

+/-

125.3 1 1585.0

+/-

105.1 346.4

+/-

92.5 14.37 16.38 19.93 18.16 20.72 12.89 10.47 19.76 9.82 15.78 9.26 10.50 16.32 8.77 12.85 15.66 21.68 23.25 16.52 25.16 14.83 15.56 14.67 10.05 15.95 10.96 9.88 12.37 10.39 10.47 14.32 13.09 17.46 10.83 10.73 25.76 16.40

< 43.55' 25.86 27.85 33.86 33.51 57.00 31.31 52.61 14.54 10.25

<.13.80 10.48 10.08 20.05 13.78 30.32 18.13 26.26 9.86 10.29 13.65 8.90 12.52 92.23

< 90.79

< 150.10 85.99

< 149.40 12.52 16.13 18.07 14.03 16.79 58.37

< 65.13 55.64 49.71 52.33 31.12 45.20 46.22 30.53' 58.82

< 166.60 362.0

+/-

175.2

< 230.70 256.0

+/-

129.6 253.5

+/-

145.7 4100.0

+/-

293.0 7202.0

+/-

328.7 9241.0

+/-

482.9 4136.0

+/-

231.0 5268.0

+/-

396.7 8-33 TRAINING Bu~G '

08/i4/2007 :'

IBV943307S3 RAGWEED 1492.0

+/-

134.5 26.73 13.85 12.31 23.18 14.79 15.48 14.65

< ' 25.77 55.43 14.28 18.79 13.34 108.50 17.93 69.60 50.57 234.60 8102.0

+/-

404.9

Sample Location *..

. Date' Client ID Radionuclide I Req. CL Be-7 1-131 50 Cs-134 50 Cs-137 50 Zr-95 Nb-95 Co-58 Mn-54 Zn-65.

Fe-59 Co-60 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 TABLE B-14 CONCENTRATIONS OF GAMMA EMITTERS IN BROADLEAF VEGETATION SAMPLES - 2007 Results in Units ofpCilkg +/- 1 Sigma

.. TRAINING BLQG 09/18/2007.

IBV943807S I GRAPE.LEA YES 1345.0

+/-

105.7 12.91 11.06 9.24 17.68 11.46 9.74 10.97 29.70 25.02 12.39 15.63 9.51 115.00 14.60 63.04 32.22 203.30 6580.0

+/-

309.2

94 IPEC Training Center

. TRt\\,iNING BLDG 09/18/2007 TRAINI~GBLDG I*** TRA~iN!~(;BLD(;:1 :TRAI~~~G;BiDG*1 TRAINU;.JG BLDG 09/18/2007.

...>10/16/2007>*..

.10~16/2007***

10/16/2007 IBV943807S2 IBV943807S3 IBV944207S 1 IBV944207S2 IBV944207S3 MULLEIN RAGWEED GRAPELE MULLEN RAGWEED 539.2

+/-

83.5 1440.0

+/-

146.5 2445.0

+/-

164.7 314.8

+/-

54.4 2255.0

+/-

147.3 26.90 14.73 12.31 7.31 12.15 12.41 10.65 12.05 8.90 14.17 8.45 13.38 13.34 6.91 11.70 19.26 30.52 22.31 13.52 23.37 12.49 20.10 13.74 8.15 13.93 10.82 16.24 12.24 6.64 13.63 10.12 18.94 13.22 8.48 12.65 30.89 58.15 30.11 21.11 30.71 35.04 56.13 34.50 28.90 42.12 10.57 21.37 9.60 7.22 18.43 18.94 25.72 8.65 8.32 10.32 10.06 15.31 13.29 8.36 12.73 92.89

.161.70 145.50 91.07 136.70 15.71 18.53 15.71 8.63 15.01 57.79 70.35 58.49 40.61 56.59 52.2

+/-

27.3 59.71 36.52 24.55 54.05 180.00 269.20 204.60 213.7

+/-

106.8 223.10 7892.0

+/-

291.2 7873.0

+/-

455.9 3811.0

+/-

327.3 4757.0

+/-

228.5 6010.0

+/-

337.7 B-34

-Sample Location.-

Date Client ID Radionuclide Reg. CL Be-7 1-131 Cs-134 65 Cs-137 75 Zr-95 Nb-95 Co-58 65 Mn-54 65 Zn-G5 130 Fe-59 130 Co-GO 65 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Sr-90 5_

TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

25 Downstream (Hudson River)

'VOP FISH' VOP FISH:

Vo,PFISH.?

\\,OPFISH.

'c!':",'"

06/06/2007

. 06/06/2007."

06/07/2007",

' 06/08/2007....

IFH252407S6 IFH252407S4 IFH252407S2 IFH252407S5 CRABS WHITE PERCH STRIPED BASS CARP 289.1 322.6 214.0 255.9

< 1042.0 1360.0 972.2 971.1 23.1 23.5 20.5 17.9 18.9 17.6 15.7 15.7 59.6 54.7 41.9 44.7 50.1 50.4 39.9 38.5 38.1 26.5 26.0 29.5 20.4 25.0 16.6 19.5 50.3 59.7 41.1 46.4 90.9 99.1 83.5 95.5 23.9 29.7 17.8 23.5 442.3 254.7 268.1 252.2 49.2 49.8 35.1 32.1 217.1 250.7 186.4 212.9 75.9 77.0 46.5 56.0 115.8 135.6 102.1 103.8 62.9 74.8 66.3 50.5 361.6 429.1 295.3 723.7

+1-245.7 VOPFlSH 06(08/2007.

IFH252407S3 CATFISH 269.8 857.3 17.8 17.5 48.1 39.6 26.0 19.2 49.7 69.9 17.9 193.5 37.6 173.1 50.9 88.6 52.7 286.8 3784.0

+/-

373.4 4656.0

+/-

484.3 3680.0

+/-

333.1 4399.0

+/-

331.8 3913.0

+/-

343.2

_~_Jl

~

~--

6 6.8 7.7 8-35 VOPFISH' 06/11/2007 IFH252507S7 SUNFISH 373.3 1023.0 24.6 22.6 73.4 56.8 29.9 I

28.8 64.7 107.5 22.9 360.2 54.5 274.8 73.5 134.4 97.6 I

1001.0

+/-

376.6 7191.0

+/-. 468.2 14

Sample Location

'Date' Client ID Radionuclide I Req. CL Be-7 1-131 Cs-134 65 Cs-137 75 Zr-95 Nb-95 Co-58 65 Mn-54 65 Zn-65 130 Fe-59 130 Co-60 65 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Sr-90 5

VOPFISH 06/13/2007 IFH252507S I AMERICAN EEL 306.7 658.1 22,8 25.8 67.6 42.7 21.6 22.6 60.1 86.5 28.8 267,7 39,7 232.3 66.4 103.0 93,5 401.0 3629.0

+/-

422.8 6.6 TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units ofpCilkg +/- I Sigma

25 Downstream (Hudson River)

VOPFISH 08/16/2007 IFH254407S I BLUE CRAB 203.3 5898.0 8,9 9.6 28,7 35.5 17.4 9.9 25.2 80.7 9,8 583,5 34.9 104.3 58.1 57.8 95.8

+/-

292 707.8

+/-

155.2 4690.0

+/-

183.9 7.1

- NOPFISH" 08/16/2007 IFH254407S5 WHITE PERCH 309.0 10980.0 10,6 14.0 53,1 56.7 29,3 17.4 24.3 114.6 14,7 774.0 53,9 160.5 98.2 100,6 219.5

+/-

41.4 580.8

+/-

209.5 4539.0

+/-

206.2 6.5 9-36 VOP FISH;;~"

08/20/2007 j".

IFH254407S4 AMERICAN EEL 223.4 5610,0 10,9 12.3 38.8 52.9 23,9 13.6 18.3 90.4 12.6 645.4 38,8 132.0 70.2 71.4 99.4

+/-

33.0 521.0

+/-

187.4 5245.0

+/-

222.3 6.3

VO~FISH

,.., },"";VOP,FISH;.

... 08/24/200,7... '~: '08/29/2007*

IFH254407S3 IFH254407S2 CATFISH SUN FISH 213.8 267.5 4142,0 3583.0 7,1 10,0 10.9 152 342 44.4 45.4 50.8 20,7 26,2 13.5 18.0 20.2 23.0 88.3 90,7 12.4 15.7 479.7 395,1 38,5 41.2 143.1 172.6 62.5 75,8 73.3 98.9 48,6

+/-

29.9 55.0 456.1

+/-

158.1 968.4

+/-

215.9 4154,0

+/-

219.7 4196.0

+/-

196.3 6,8 52

Sample Location:,

Date Client ID Radionuclide Req. CL Be-7 1-131 Cs-134 65 Cs-137 75 Zr-95 Nb-95 Co-58 65 Mn-54 65 Zn-65 130 Fe-59 130 Co-60 65 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Sr-90 5

TABLE B-15 CONCENTRA nONS OF RADJONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton (Control)

ROSETON FISH' "':;l{qSETO~"FlS!l', "ROSET()N FISH *. '

ROSET()N)ISH:: tROSETONFisH' 06/07/2007 ':'.

'06/07/2007 0610712007

06/07/2007'

. 06/13/2007.

IFH232407S I IFH232407S3 IFH232407S4 IFH232407S5 IFH232507S2 AMERICAN EEL CARP CATFISH WHITE PERCH SUNFISH 194.6 210.0 190.2 238.9 169.6 744.3 896.0 855.9 999.5 476.2 16.2 20.0 14.0 15.5 16.5

.17.2 18.0 12.5 15.0 15.2 43.1 46.9 33.4 41.6 38.5 36.6 41.9 35.0 43.8 29.0 21.7 25.1 23.0 22.0 21.3 15.3 22.3 15.0 11.9 16.6 35.8 48.9 32.5 41.5 34.2 86.7 106.4 68.7 71.9 53.3 18.2 21.3 14.6 16.3 20.8 197.4 329.7 158.8 235.4 140.9 33.1 42.3 27.1 26.7 23.0 156.4 162.9 132.6 151.1 173.2 43.0 47.0 44.2 41.1 23.1 77.4 12.8 79.0 78.0 73.0 52.4 66.3 41.2 59.0 44.6 251.6 833.9

+/-

240.7 232.9 267.7 667.5

+/-

178.4 3849.0

+/-

276.6 4407.0

+/-

342.6 5490.0

+/-

266.8 3751.0

+/-

280.4 3405.0

+/-

303.4 7.2 9.5 5.2 8.3 7.2 8-37

><.ROSETO~FISH.

'::Gt~ OS/14/2'()07.

IFH234407S4 WHITE PERCH 359.8 14910.0 17.6 15.9 63.5 79.6 39.0 17.3 28.5 107.8 19.8 1306.0 63.8 200.2 98.6 92.3 66.5 617.1

+/-

268.4 5439.0

+/-

308.5 6.8

Sample."

, Location' Date Client ID TABLE B-15 CONCENTRATIONS OF RADIONUCLIDES IN FISH SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma

23 Roseton (Control)

ROSI;TON FISH

, 08/15/2007 R~:8jf~;:;jSH'*: R?:::~2::;SH ?IM;';:::i~:':SH' IFH234407S3 IFH234407S2 IFH234407S5 IFH234407S 1 AMERICAN EEL SUNFISH Radionuclide I Reg. CL BLUE CRAB CATFISH Be-7 228.9 252.5 215.3 216.4 1-131 7870.0 4760.0 4582.0 2880.0 Cs-134 65 13.2 14.7 8.0 14.9 Cs-137 75 11.0 16.1 12.5 15.5 Zr-95 38.4 51.0 45.1 47.3 Nb-95 48.1 51.5 45.8 52.1 Co-58 65 23.4 26.9 25.9 26.6 Mn-54 65 11.9 18.4 16.2 19.4 Zn-65 130 30.0 38.8 38.8 38.7 Fe-59 130 92.3 96.9 104.3 99.7 Co-60 65 12.3 13.6 16.5 20.7 Ba/La-140 709.6 590.6 875.6 490.9 Ru-103 45.7 44.6 42.2 35.9 Ru-106 119.0 151.9 140.7 184.0 Ce-141 66.5 71.3 60.5 67.0 Ce-144 63.4 86.0 75.5 77.8 AcTh-228 35.5 61.0 127.1

+/-

46.5 64.2 Ra-226 419.9

+/-

130.3 511.5

+/-

182.0 599.8

+/-

185.3 796.7

+/-

210.3 K-40 4044.0

+/-

209.8 5483.0

+/-

285.2 5276.0

+/-

264.1 5481.0

+/-

310.0 Sr-90 5

6.9 6.5 6.7 7.6 8-38

Sample, Location Date Client lD Radionuclide Be-7 1-131 Cs-134 65 Cs-137 75 Zr-95 Nb-95 Co-58 65 Mn-54 65 Zn-65 130 Fe-59 130 Co-60 65 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Sr-90 5

TABLE B-15 CONCENTRA nONS OF RADlONUCLlDES IN FISH SAMPLES - 2007 Results in Units of pCilkg +/- 1 Sigma Catskill C":17'h;o:'S~1 CA~r;h~;;Is.~C,(:~:!~o~S>> c~~~itt'~HJ CA~7::!~S:j IFHCA T2407SS IFHCA T2407S2 IFHCAT2407S3 IFHCAT2407S4 IFHCA T2607S I CARP AMERICAN EEL WHITE PERCH CATFISH SUNFISH 199.4 254.2 182.8 207.1 201.6 849.4 971.4 999.4 999.6 421.5 16.4 13.8 14.3 9.4 18.7 15.0 18.1 13.1 15.0 14.9 36.6 46.7 37.8 44.0 37.0 33.1 47.2 32.1 37.1 31.2 24.5 26.1 19.6 19.3 22.3 18.0 19.9 13.4 15.0 18.6 45.1 48.1 37.5 20.2 40.6 98.9 83.9 80.4 74.5 61.3 16.7 16.3 16.1 13.7 16.5 249.5 340.8 224.0 203.0 129.5 30.4 37.3 27.8 32.1 31.2 170.2 157.9 139.2 164.2 177.9 44.0 60.2 46.1 54.6 44.8 62.5 91.1 77.1 82.8 107.1 46.9 54.1 47.8*

48.7 133.0

+/-

42.9 504.3

+/-

180.1 702.6

+/-

266.5 427.1

+/-

167.9 831.8

+/-

254.8 580.1

+/-

250.4 4487.0

+/-

293.7 3331.0

+/-

320.6 5681.0

+/-

273.5 4671.0

+/-

234.7 3946.0. +/-

258.2 6.1 6.8 7.9 7.8 6.6 8-39

TABLE B-16 CONCENTRATIONS OF GAMMA EMITTERS IN AQUATIC VEGETATION SAMPLES-2007 Results in Units of pCilkg +/- 1 Sigma L<,," ",":'

'COLD SPRING'"

'~ERPLANCK SalllP'eLcication (;::;\\,,:';',':

COLDSPRING '

/:2";"D~te':>

>;.:*i

",,):',',.

09/06j2()07 06/07/2007,., '

i' "

'06/()6ti()07< "

', I Client ID IAV842307 IAV843607 IAVI72307 Aquatic W A TERMILFOIL Aquatic Radionuclide Req. CL Be-7 230.2

+/-

46.4 90.5 445.3

+/-

75.0

/-131 30 10.9 14.0 17.1 Cs-134 30 4.9 6.6 11.7 Cs-137 40 6.2 12.6 31.0

+/-

6.4 Zr-95 9.1 18.9 16.5 Nb-95 6.3 15.4 11.9 Co-58 8.7 12.0 11.0 Mn-54 7.7 13.1

< ' 11.2 Zn-65 19.3 33.8 29.9 Fe-59 23.5 35.6 35.5 Co-60 8.8 8.7 9.8 Ba/La-140 16.2 9.7 18.7 Ru-103 6.9 11.0 9.1 Ru-106 66.7 115.1 100.6 Ce-141 8.7 13.0 15.3 Ce-144 30.2 50.3 56.1 AcTh-228 21.3 89.3

+/-

32.7 190.1

+/-

36.0 Ra-226 317.2

+/-

84.1 435.0

+/-

170.1 210.0 K-40 2500.0

+/-

157.2 1749.0

+/-

212.7 4320.0

+/-

279.3

,B-40

Sample Location Date Client lD Radionuclide Be-7 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Fe-59 Co-60 Ba/La-140 Ru-103 Ru-106 Ce-141 Ce-144 AcTh-228 Ra-226 K-40 Req. CL 75 90 TABLE B-17 CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma COLD SPRING:*

06/06/2007

'COLD SPRING 09106/2007 ;;.

1';.06i06/2007 LENTS COVE

. LENTSCOV]i;*'.VERPLANCK 1.;t'¥,ERPLANCK

";01)(06/20(jj", ;

06/07/2007

'>:09/07/2007.'.

IBS842307 I

IBS843607 I

IBS282307 I

IBS283607 I

IBSI72307 I

IBSI73607

~

423.0 234.0 399.4 339.4 417.3 309.8 108.6 48.9 112.3 54.1 86.0 55.5 31.3 38.3 32.9 54.1 48.5 39.4 254.8

+/-

44.1 34.9 373.7

+/-

58.4 209.2

+/-

41.1 252.7

+/-

49.6 217.1

+/-

41.0 68.5 56.1 121.4 77.0 100.1 70.3 64.8 25.4 83.2 47.0 44.8 51.5 43.6 36.4 54.1 45.0 56.7 27.2 50.9 40.7 62.4 42.1 45.1 42.8 133.6 93.9 167.7 149.8 131.5 100.4 133.0 114.8 171.8 143.4 175.8 130.9 47.3 26.1 56.1 77.3 46.6 40.6 101.9 57.5 151.2 101.2 36.0 47.6 47.5 35.0 54.3 36.7 43.8 42.9 393.5 399.4 599.5 379.5 463.1 392.2

<. 84.9 45.3 79.7 58.0 72.1 56.5 322.1 183.0 268.5 231.0 260.2 211.0 1045.0

+/-

170.7 960.5

+/-

141.8 1214.0

+/-

237.0 658.1

+/-

152.0 1143.0

+/-

176.9 728.1

+/-

134.6 3153.0

+/-

869.8 2009.0

+/-

581.3 2263.0

+/-

908.4 1630.0

+/-

603.7 2008.0

+/-

792.1 1796.0

+/-

668.7 20630.0

+/-

1052.0 33510.0

+/-

1219.0 20430.0

+/-

1464.0 14160.0

+/-

1041.0 19610.0

+/-

1193.0 16900.0

+/-

1017.0 B-41

TABLE B-17 CONCENTRA TIONS OF GAMMA EMITTERS IN BOTTOM SEDIMENT SAMPLES -

2007 Results in Units of pCilkg +/- 1 Sigma Sample

., I***'.....

l,6cation DISCHARGE CANAL DISCHARGECANAL I.

l'*,.*,

'ii'.*;,i,Datc. t.

0'6107/2007

'j 09/07/.7007 '.* >

Client ID IBSI02307 IBSI03607 Radionuclide Req. CL Be-7 208.8 233.1 1-131 43.8 55.6 Cs-134 75 15.0 41.1 Cs-137 90 177.3

+/-

31.3 95.0

+/-

34.9 Zr-95 49.1 49.7 Nb-95 31.6 37.6 Co-58 25.6 26.1 Mn-54 34.0 38.4 Zn-65 94.1 94.1 Fe-59 95.3 140.5 Co-50 22.6 26.5 Ba/La-140 60.6 83.9 Ru-103 30.8 34.9 Ru-106 401.0 404.4 Ce-141 35.1 46.3 Ce-144 138.8 183.6 AcTh-228 176.0

+/-

104.1 148.6 Ra-226 1248.0

+/-

425.1 659.0 K-40 15430.0

+/-

912.1 14730.0

+/-

1065.0 8-42

TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2007 Results in U nits of pCilL +/- 1 Sigma

'~~~~1\\i!"

':"::'i,':',

~OSETbN,

,;"::,,,iROSETON!

ii!i~ROSEl'ON '.'

..,J{()~Et()~,*,

RAINWATER

',i{AINWATEJ{

. *~iNWATER.(1; RAINWATER"":!"

h');'!;':i;ii,.'."'.

';,"',,"Y:

."()6/28/20oi' 1"\\ '" Da:te.,.*..

""12/3112007'

. 03/26/2007

':i'

.10/011200,7 I Client ID IRF23QI07 IRF23Q207 IRF23Q307 IRF23Q407 Radionuclide Req, CL H-3 474.0 443.0 448.0 439.0 Be~7 39.4 49.5 62.2 34.4 1-131 28.1 28.3 35.9 24.4 Cs-134 7.5 1.9 3.1 3.4 3.2 Cs-137 9

2.5 2.3 4.5 2.8 Zr-95 6.0 7.3 11.9 7.1 Nb-95 5.4 6.7 10.0 5.3 Co-58 3.9 5.1 6.4 4.1 Mn~54 2.9 3.0 5.8 2.0 Zn-65 3.3 7.7 17.5 7.2 Fe-59 8.3 14.0 13.4 16.1 Co-60 7.5 2.6 2.3 6.0 3.1 Ba/La-140 21.9 21.4 37.4 12.4 Ru-103 5.5 6.4 8.3 5.2 Ru-106 29.0 26.7 39.3 30.1 Ce-141 12.2 10.8 13.7 1.0 Ce-144 25.1 23.3 26.9 21.0 AcTh-228 11.2 10.7 15.0 10.4 Ra-226 128.0

+1-55.4 59.9 86.0 58.6 K-40 126.6

+/-

25.9 98.7

+/-

27.7 55.4 277.6

+/-

34.2 8-43

TABLE B-18 CONCENTRATIONS OF RADIONUCLIDES IN RAINWATER SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma

';i'SamplE!

PEEKSKIE[;:

PEEKSKILL' I'.','p~l,j)~SI<.!"'L.

PEEK~KILL

~oca~i~~'e:*

',RAINWA.TER

> 'RAINWATER. ;,.RAINWAT:E.R,. RAINWATER Date"

. '.' 10/01/2007 I"

\\'"

,.03/26/2007

.' 06/28/2007 1213112007 Client ID IRF44QI07 IRF44Q207 IRF44Q307 IRF44Q407 Radionuc1ide Req. CL H-3 474.0 443.0 448.0 443.0 8e-7 43.3 48.0 44.9 40.2 1-131 39.0 35.1 34.9 39.5 Cs-134 7.5 3.3 2.0 4.3 2.4 Cs-137 9

3.5 3.9 4.5 3.2 Zr-95 11.3 8.7 9.3 4.1 Nb-95 8.6 7.7 8.7 7.9 Co-58 4.9 4.9 4.9 6.1 Mn-54 3.4 3.2 4.3 4.6 Zn-65 7.1 5.0 7.4 3.3 Fe-59 12.1 17.7 21.6 21.6 Co-60 7.5 4.0 3.1 5.8 4.3 8a/La-140 15.4 35.6 36.4 32.4 Ru-103 6.0 6.8 8.6 8.8 Ru-106 25.5 27.5 37.0 42.6 Ce-141 9.4 11.3 14.1 11.2 Ce-144 21.5 21.1 26.6 22.8 AcTh-228 10.9 10.3 12.8 16.9 Ra-226 70.2 70.4 77.1 81.1

+/-

51.3 K-40 194.6

+/-

39.3 198.5

+/-

38.0 182.2

+/-

46.7 42.7 8-44

TABLE B-19 CONCENTRA TIONS OF GAMMA EMITTERS IN SOIL SAMPLES - 2007 Results in Units of pCi/kg +/- 1 Sigma.

SalTlpl~',

ROSETON MET JOWER

. TRAINING BLDG I',, Location

- - " *. *Dafel

",".* i".'"" i

.,.r 10/01l2()07 10/02/2007 10/02/2Q07 Client ID IS0234007 IS0954007 IS0944007 Radionuclide Req. CL Be-7 876.0

+/-

195.2 1596.0

+/-

252.1 1458.0

+/-

206.2 1-131 31.7 31.0 33.1 Cs-134 75 33.2 33.4 32.9 Cs-137 90 27.3 27.4 136.5

+/-

22.5 Zr-95 49.5 54.2 52.8 Nb-95 36.0 33.4 38.9 Co-58 32.8 30.8 31.8 Mn-54 28.9 31.0 26.6 Zn-65 37.9 94.0 42.4 Fe-59 70.3 117.6 84.3 Co-60 21.8 42.1 37.0 Ba/La-140 36.4 40.9 25.4 Ru-103 28.2 24.5 24.4 Ru-106 279.4 316.8 261.0 Ce-141 39.2 38.4 43.2 Ce-144 169.6 185.4 187.0 AcTh-228 829.1

+/-

117.3 694.9

+/-

126.3 1037.0

+/-

128.4, Ra-226 1965.0

+/-

526.2 2193.0

+/-

490.7 2293.0

+/-

505.4 K-40 13870.0

+/-

701.3 16750.0

+/-

938.9 23110.0

+/-

854.3 8-45

Date

Nl,JCLlI)E 1-/31 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140 Date'

~UCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140 TABLE B-20 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCilliter +/- 1 Sigma ALGONQUIN OUTFALL

'0\\/23/2007 "0211312007 I'. 03120/2001:

0411612007 051\\5/2007.

.. '.()6(l9/2007.'.

':>>"E,:

< 3.73

< 5.28

< 2.82

< 3.31

< 4.09

< 3.67

< 4.28

< 3.22

< 2.58

< 1.57

< 3.70

< 2.66

< 3.79

< 3.05

< 2.32

< 2.77

< 3.78

< 3.08

< 6.07

< 6.10

< 4.02

< 3.78

< 5.08

< 4.19

< 2.66

< 3.47

< 2.48

< 1.81

< 4.44

< 3.23

< 3.63

< 3.15

< 2.52

< 2.61

< 2.85

< 3.16

< 2.76

< 3.33

< 2.39

< 2.50

< 3.54

< 3.22

< 7.14

< 6.88

< 6.20

< 5.73

< 7.99

< 4.62

< 4.68

< 4.26

< 4.81

< 2.75

< 3.87

< 4.02

< 3.06

< 2.73

< 2.66

< 2.35

< 3.42

< 2.97 389.6 +/- 45.28 259.7 +/- 38.73 183.9 +/- 26.41 109.4 +/- 22.55 253.6 +/- 39.58 170.5 +/- 30.22

< 4.81

< 5.81

< 2.85

< 2.66

< 3.54

< 2.15 07/\\7/2007 08/2112007 09125/2007

,"":j::.. '

< 3.60

< 3.27

< 3.82

< 3.21

< 3.05

< 3.15

< 2.93

< 3.15

< 4.10

< 5.07

< 4.47

< 6.16

< '3.96

< 3.23

< 2.20

< 3.14

< 2.67

< 3.73

< 3.14

< 2.60

< 2.74

< 6.63

< 7.10

< 8.63

< 3.84

< 8.31

< 2.92

< 3.48

< 2.27

< 3.28 126.2 +/- 30.28 191.2 +/- 33.92 115 +/- 30.54

< 3.97

< 2.54

< 3.03 B-46 I

Date NUCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140

. Date

.. :NUCLIDE 1-I31 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-I 40 TABLE B-20 CON CENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma GYPSUM PLANT 01/2312007.**.**.

02/1312007...

03120/2007 04/16/2007 (j5/15/200T.

06/19/2007

i

* ** :": i.,

< 5.06

< 5.75

< 4.01

< 3.29

< 3.11

\\

< 2.91

< 3.90

< 3.93

< 3.44

< 2.86

< 2.92

< 2.57

< 2.38

< 4.38

< 1.54

< 2.61

< 3.50

< 2.94

< 6.75

< 6.64

< 6.22

< 4.11

< 5.91

< 4.76

< 2.75

< 2.63

< 2.73

< 2.60

< 3.07

< 3.15

< 4.81

< 3.78

< 4.21

< 2.48

< 2.64

< 2.81

< 3.78

< 3.29

< 3.97

< 2.77

< 3.46

< 2.99

< 9.55

< 11.75

< 7.81

< 6.81

< 6.51

< 9.63

< 5.26

< 4.39

< 4.86

< 3.76

< 6.35

< 9.20

< 4.99

< 3.65

< 3.63

< 1.94

< 2.42

< 3.44 244.5 +/- 46.13 130.7 +/- 35.72 149.7 +/- 31.47 300 +/- 35.31 129.6 +/- 37.81 266.3 +/- 42.45

< 4.75

< 5.39

< 4.44

< 3.20

< 3.01

< 4.17 07117/2007 /

08/21/2007:\\*

!.09/2512007

~t2.81....

i!';:*

I';

< 2.49

< 3.43

< 2.12

< 3.39

< 2.35

< 2.24

< 1.70

< 2.67

< 4.03

< 5.22

< 5.07

< 2.16

< 2.65

< 3.43

< 2.06

< 1.88

< 2.04

< 2.42

< 3.14

<2.69

< 6.56

< 7.04

< 8.12

< 6.06

< 4.02

< 6.05

< 3.02

< 3.73

< 2.84 402.3 +/- 38.66 169.5 +/- 27.58 197.4 +/- 32.26

< 2.89

< 3.02

< 4.35 8-47

Date NUCLIDE

[-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 BalLa-140

, Date

'NUCLIDE 1-131 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Zn-65 Co-60 K-40 Ba/La-140 TABLE B-20 CON CENTRA nONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 2007 Results in Units of pCi/liter +/- 1 Sigma TRAP ROCK QUARRY

< 3.12

< 4.34

< 2.56

< 3.64

< 3.95

< 1.78

< 3.27

< 1.91

< 2.24

< 3.30

< 2.67

< 2.90

< 2.28

< 2.35

< 3.97

< 4.02

< 5.16

< 3.90

< 4.58

< 5.03

< 1.98

< 3.00

< 2.04

< 3.37

< 4.16

< 2.72

< 3.15

< 2.20

< 1.81

< 2.94

< 2.50

< 3.04

< 2.06

< 3.59

< 3.22

< 5.85

< 9.25

< 5.05

< 7.48

< 4.53

< 5.31

< 8.64

< 4.96

< 6.74

< 9.37

< 1.51

< 4.38

< 1.95

< 2.74

< 2.38 122.5 +/- 26.20 267.9 +/- 38.23 277.1 +/- 29.28 103.8 +/- 30.27 134.9 +/- 37.84

< 3.29

< 4.53

< 3.12

< 3.89

< 2.07

< 2.65

< 3.07

< 3.65

< 5.28

< 5.03

< 4.89

< 3.15

< 2.79

< 3.01

< 2.90

< 3.63

< 3.08

< 3.25

< 2.81

< 2.72

< 8.01

< 9.26

< 6.54

< 7.91

< 4.08

< 11.33

< 3.24

< 3.03

< 3.97 234.6 +/- 39.31 218.6 +/- 43.43 241.2 +/- 45.51

< '5.37

< 6.14

< 4.80 8-48

< 3.87

< 4.33

< 3.63

< 4.59

< 3.13

< 4.60

< 2.74

< 4.91

< 7.21

< 4.24 127.7 +/- 36.36

< 4.53

Monitoring We',,:

Sample Name:'

Sarnple Date:

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCilL +/- 1 Sigma MW::51' MW:40.

MW-51 MW-40

'I' MW"51-012.*.*

MWAO-01t*

MW-51~012.

.... MW"40-011 02/21/2007.

< '. 02/21/2007 06/26/2007.

06/26/2007.

Client 10 IMW51 0707 IMW400707 IMW512607 IMW402607 Radionuclide Req. MDC Result Result Result Result H-3 467.00 467.00 444.00 444.00 Be-7 24.13 32.89 22.14 21.13 K-40 197.3

+/-

26.5 191.8

+/-

35.5 115.8

+/-

31.4 173.7

+1-33.9 Mn-54 1.76 3.52 2.83 2.48 Co-58 1.68 2.29 2.66 2.39 Fe-59 7.45 8.61 10.66 9.38 Co-60 2.98 4.07 4.72 4.19 Zn-65 3.37 4.46 5.19 4.95 Sr-90 1

1.5 1.5 Nb-95 1.83 2.84 3.71 2.59 Zr-95 4.83 6.57 7.10 7.04 Ru-103 2.70 3.94 4.25 4.00 Ru-106 25.65 33.20 39.68 34.76 1-131 5.52 7.04 4.85 5.13 Cs-134 15 3.05 3.52 4.46 3.93 Cs-137 18 1.37 1.99 2.28 2.41 Ba/La-140 4.69 6.69 5.59 5.05 Ce-141 5.88 6.78 9.16 7.58 Ce-144 22.65 26.74 39.34 31.12 Ra-226 104.9

+1-63.3 99.42 122.10 118.50 AcTh-228 10.07 13.36 14.74 19.4

+1-11.5 Note 1: Less than values "<" are the Critical Level values Note 2: A sample is positive if the result is greater than the critical level BA9

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma MonitoringWell:

C'c'c MW:40;,

MW-40' Sample Name:

'c; MW40~27~(001),

MW40~27~(002),

Sample Date:

" 06/05/2007

. 07123/2001'1:' "c;,

Radionuclide Req. MDC Result Result H-3

< 163

< 169 Be-7

< 64.4

< 37.7 K40

< 37.8

< 56.4 Mn-54

< 3.09

< 3.71 Co-58

< 5.51

< 4.05 Fe-59

<17.4

< 9.58 Co-60

< 3.17

< 3.83 Zn-65

< 6.93

< 8.51 Sr-90 1

< 0.85

< 0.662 Nb-95

< 10.8

< 4.68 Zr-95

< 10

< 6.03 Ru-106

< 30.1

< 32.1 Cs-134 15

< 3.66

< 4.36 Cs-137 18

< 3.39

< 3.88 Ba-140

< 346

< 33.1 La-140

< 117

< 11.1 Ce-141

< 18.3

< 8.84 Ce-144

< 24.4

< 26.7 Ac-228

< 13.6

< 14.9 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-50

TABLE B-21 CONCENTRATIONS OF RAOIONUCLIOESIN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma MonitoririgWell:

MW~40.:'... >.: *. ;:.... MWC:40:.. :**

.. MW~40;'

Sample Name:< ': ::.....

'" MW-40~46~(OO1): MW":40~46-(002):

MW~40~46'-(OO3).

SampleOate:.:

. }.,;':;...... :...

06/05/2007 07/23/200]..:'..

. 10/1'2/2007

.::'::"'::'1';:.

Radionuclide Req. MOC Result Result Result H-3

< 166

< 171

< 174 Be-7

< 60.6

< 40.4

< 40.1 K-40

< 40.8

< 47

< 37.4 Mn-54

< 3.59

< 3.43

< 4.09 Co-58

< 4.95

< 5.22

< 4.31 Fe-59

< 15.7

< 8.52

< 10.1 Co-60

< 2.27

< 2.9

<4.26 Zn-65

< 7.33

< 7.05

< 8.08 Sr-90 1

< 0.888

< 0.628

< 0.685 Nb-95

< 10.8

< 6.17

< 7.06 Zr-95

< 8.89

< 7.9

< 7.58 Ru-106

< 27.3

< 35.2

< 33.5 Cs-134 15

< 3.95

< 3.94

< 4.46 Cs-137 18

< 3.39

< 4.09

< 3.59 Ba-140

< 324

< 30.7

< 37.5 La-140

< 118

< 12

< 15.2 Ce-141

< 19.2

< 9.35

< 9.68 Ce-144

< 23.6

< 29.4

< 28.7 Ac-228

< 12.3

< 17

< 16.1 Note 1: Less than values n<n are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-51

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pC ilL +/- 1 Sigma Monitoring Well:

MW~40........ '..*

'1.:

MW~40 J MW-40,'

SainpleName:.'

MW:::40-.81~(001 ).

MW-40~8H002).'* MW-40-.8t*(003)

Sample Date:.

,'j' 06/05/2007"<,

07 /23/200T', '..

10/12/2007.......* '

Radionuclide Req. MDC Result Result Result H-3

< 163

< 172

< 173 8e-7

< 56.4

< 42.3

<44.2 K-40

< 38.1

< 69.8

< 48.7 Mn-54

< 3.35

< 3.69

< 3.89 Co-58

< 5.01

< 5.22

< 3.58 Fe-59

<15.2

< 10.8

< 8.81 Co-60

< 3.62

< 4.95

< 4.64 Zn-65

< 7.49

< 8.1

< 10.5 Sr-90 1

< 0.911

< 0.694

< 0.71 Nb-95

< 11

< 6.65

< 7.32 Zr-95

< 11.7

< 8.64

< 8.14 Ru-106

< 30.2

< 37.6

< 35.2 Cs-134 15

< 3.88

< 4.47

< 4.12 Cs-137 18

< 3.22

< 5.2

< 4.48 8a-140

< 330

< 39

< 37.5 La-140

< 150

< 11.1

<12.4 Ce-141

< 21.2

< 11.2

< 10.2 Ce-144

< 27.5

< 35.8

< 30.7 Ac-228

< 12.1

<18.4

< 16.3 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

8-52

TABLE B-21 CONCENTRATIONS OF RAOIONUCLIOESIN MONITORING WELL SAMPLES - 2007 Results in Units of pCilL +/- 1 Sigma MonitoringWell: "..,.;.,.,.',.. ::::';.;;.' MW~40:i';

MW-40 ;";;' ;"'.,.i'**** MW~40;<.

Sample;Nanie:.,

. '.... :,.";;>. MW"40;;*1 OO~(OO~) MW-40::'100-(002):' MW'-40"tOO,-(003).

SampleOate:

.:;' 06/05/2007 '.

07/23/2007..*. ;..,'" :10/12/2007

.,,., ',.i Radionuclide Req. MOC Result Result Result H-3 176 +/- 53.5

< 175

< 173 8e-7

< 64.6

< 20.4

< 40.3 K-40

< 49.7

< 25

< 39.3 Mn-54.

< 3.55

< 2.16

< 3.78 Co-58

< 6.59

<: 2.11

< 4.02 Fe-59

< 19.1

< 5.09

< 8.19 CO-60

< 3.59

< 2.2

< 3.61 Zn-65

< 7.93

< 4.47

< 8.16 Sr-90 1

< 0.694

< 0.696

< 0.769 Nb-95

< 11.9

< 2.92

< 6.55 Zr-95

<12.4

' < 4.15

< 7.79 Ru-106

< 35.3

< 18.2

< 34.4 Cs-134 15

< 4.19

< 2.34

< 4.06 Cs-137 18

< 3.04

< 2.1

< 3.87 8a-140

< 377

< 17.9

< 35.6 La-140

< 115

< 6.81

< 14.1 Ce-141

< 16.8

< 4.92

< 10.2 Ce-144

< 24.1

< 15.1

< 30.1 Ac-228

< 15.1

< 8.97

< 12.7 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and Qreater than the MOC.

8-53

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCilL +/- 1 Sigma Monitoring Well:

MW-40*

MW~40*... *

~...

MW-40***

Sample Niune:.:.

MW~40c.127-(001) MW-40-127-(002). MW~40~127-(003)

Sample Date:

06/05/2007' 07/23/2007 tQ/12/200T' Radionuclide Req. MDC Result Result Result H-3 187 +/- 54

< 168

< 164 Be-7

< 57.7

< 17.1

< 35.9 K-40

< 41.2

< 17.7

< 44.4 Mn-54

< 3.59

< 1.67

< 4.19 Co-58

< 6.06

< 1.74

< 4.49 Fe-59

< 17.7

< 4.06

< 9.26 Co-60

< 3.26

< 1.77

< 3.79 Zn-65

< 7.83

< 3.57

< 8.23 Sr-90 1

< 0.571

< 0.573

< 0.624 Nb-95

< 11.3

< 2.41

< 5.09 Zr-95

< 10.8

< 3.5

< 7.84 Ru-106

< 31.8

< 16.3

< 38 Cs-134 15

< 3.98

< 2.01

< 5.04 Cs-137 18

< 3.41

< 1.76

< 4.06 Ba-140

< 359

< 15.5

< 40 La-140

< 118

< 5.48

< 13.9 Ce-141

< 20.8

< 4.03

< 10.1 Ce-144

< 27.6

< 13.1

< 30.7 Ac-228

<16.4 30.3 +/- 3.71 30 +/- 8.75 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and Qreater than the MOC.

8-54

TABLE B-21 CONCENTRATIONS OF RAOIONUCLIOES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

MW-40' MW-40 MW"40*,

Sample Name:

MW~40-162~(00 1) MW-40-162-(002)

MW~40-162-(003)

Sample Date:

06/05/2007 07/23/2007 1 0112/2007L.

Radionuclide Req. MOC Result Result Result H-3

< 164

< 173

< 169 8e-7

< 76

< 16.6

< 36.1 K-40

< 37.1

< 22.5

< 33.1 Mn-54

< 5.44

< 1.65

< 3.57 Co-58

< 8.48

< 1.74

< 3.71 Fe-59

< 21.9

< 3.88

< 8.41 Co-60

< 4.53

< 1.69

< 3.47 Zn-65

< 10.2

< 3.4

<9 Sr-90 1

< 0.504

< 0.507

< 0.819 Nb-95

< 17

< 2.43

< 5.24 Zr-95

<14.4

< 3.43

< 7.49 Ru-106

< 45.6

< 14.7

< 30.3 Cs-134 15

< 5.48

< 1.99

< 4.47 Cs-137 18

< 4.95

< 1.75

< 4.05 8a-140

< 433

< 14.8

< 30.7 La-140

< 172

< 4.85

<12.4 Ce-141

< 17.5

< 3.92

< 9.42 Ce-144

< 25.8

< 12.1

< 27 Ac-228

< 15.2 33.1 +/- 4.42 35.5 +/- 6.5 Note 1: Less than values "<" are the MDC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MDC.

8-55

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

... MW-51..

MW~51 MW-51.

MW~51 Sample Name: '. '

MW-51-40-(001 ).

MW-51":40-(002)

MW~51-40-(003)

MW-5.1-40-(004)'

Sample Date:

.' 05/30/2007'*;

07/24/2007. ';','

10102/2007 ;, '. "

11109/2001' Radionuclide Req. MDC Result Result Result Result H-3 198 +/- 55 223 +/- 53

< 196

< 170 Be-7

< 37.7

< 36.8

< 29.1

< 33 K-40

< 46.7

< 35.3

< 37.3

< 50.5 Mn-54

< 3.14

< 3.71

< 2.68

< 2.95 Co-58

< 3.51

< 3.54

< 2.43

< 3.39 Fe-59

< 8.68

< 8.97

< 7.36

< 7.2 Co-60

< 3.77

< 4.13

<2.55

< 3.49 Zn-65

< 7.33

< 7.48

< 5.37

< 7.15 Sr-90 1

< 0.982

< 0.538

< 0.373

< 0.452 Nb-95

< 5.39

< 6.14

< 3.44

< 4.88 Zr-95

< 6.6

< 7.41

< 4.98

< 6.97 Ru-106

< 32.4

< 30.1

< 21.3 24.2 +/- 6.35 Cs-134 15

< 3.49

< 3.97

< 2.63

< 3.68 Cs-137 18

< 3.77

< 3.85 5.15+/-1.35

< 3.52 Ba-140

< 28.6

< 33.5

< 27.2

< 33.7 La-140

< 11.1

< 11

< 7.96

< 15.1 Ce-141

< 8.24

< 7.66

< 7.13

< 8.15 Ce-144

< 26.1

< 26.4

< 21.5

< 21.4 Ac-228

< 13.7

< 15.6

< 10.6

< 12.7 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-56

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCilL +/- 1 Sigma MonitorintrWell:

, MW-5J'".'

... MW-51 MW-5t;******

MW-51 Sample Name::.. '

~".

MW~51-79-(001 );.

MW~51"79-(002)

MW~51-79~(003)..

MW"5t~79-(004)*:.

Sample Date: ; ';"

05/30/2007

.',..... :

07/24/2007 '.::. *10/02/2007.:

11/09/200T Radionuclide Req. MDC Result Result Result Result H-3

< 172

< 167

< 194

< 171 Be-7

< 34.3

< 41.6

< 36.8

< 45.4 K-40

< 32.5

< 65.4

< 28.7

< 50 Mn-54

< 3.06

< 4.51

< 3.35

< 4.22 Co-58

< 4.45

< 4.15

< 3.61

< 4.66 Fe-59

< 7.97

< 10.7

< 7.74

< 9.73 Co-60

< 3.76

< 4.93

< 3.27

< 4.45 Zn-65

< 7.16

< 9.78

< 6.51

< 7.85 Sr-90 1

< 0.956

< 0.615

< 0.327

< 0.352 Nb-95

< 4.58

< 4.87

< 5.49

< 6.5 Zr-95

< 7.26

< 6.89

< 6.48

< 7.83 Ru-106

< 31.4

< 33.4

< 29.5

< 34 Cs-134 15

< 4.15

< 4.49

< 3.92

< 4.21 Cs-137 18

< 3.9

< 4.21 5.37 +/- 1.69

< 3.56 Ba-140

< 33.3

< 34.1

< 36.2.

< 52.3 La-140

< 10.9

< 13.6

< 10.7

< 17.8 Ce-141

< 7.46

< 10.9

< 8.04

< 11 Ce-144

< 22

< 32.1

< 23.5

< 28.1 Ac-228

< 13.6

< 18.5

< 10.9.

< 16.3 Note 1: Less than values n<n are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and Qreater than the MOC.

8-57

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

1'<.

. MW-51

..". MW.51 MW-51.

MW-51 Sample Name:.

MW-51-104-(001) MW.51-104:"(002) MW.51:"104-(003) MW-S1-1 04-(004)

Sample Date:"!.

05/30/2007 '.

07/24/2007'..

10102/2007.

11/09/2007 Radionuclide ReJ). MDC Result Result Result Result H-3

< 171

< 164

< 194

< 170 ge-7

< 31.2

< 49.4

< 41.7

< 28 K-40

< 40.1

< 41.2

< 55.9

< 40.8 Mn-54

< 3.15

< 4.33

< 4.42

< 2.77 Co-58

< 3.21

< 5.71

< 4.55

< 2.97 Fe-59

< 7.38

< 10.8

< 9.58

< 7.36 Co-60

< 3.62

< 5.33

< 3.68

< 3.18 Zn-65

< 6.8

< 10.7

< 9.79

< 7.06 Sr-90 1

< 0.99

< 0.541

< 0.508

< 0.386 Nb-95

< 4.48

< 5.92

< 7.41

< 4.72 Zr-95

< 5.79

< 9.53

< 8.29

< 5.02 Ru-106

< 29.7

< 44.8

< 34.6

< 25.9 Cs-134 15

< 3.24

< 6.04

< 4.9

< 3.3 Cs-137 18

< 3.35

< 3.92

< 4.25

< 2.92 9a-140

< 29.3

< 37

< 39.1

< 34.7 La-140

< 11.2

< 14.2

< 15.3

< 12.1 Ce-141

< 7.93

< 10.9

< 10.1

< 7.33 Ce-144

< 24.1

< 36.1

< 30.7

< 18.6 Ac-228

< 15.3

< 22.8

< 13.7 17.6 +/- 4.72 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-58

TABLE B-21 CONCENTRATIONS OF RAOIONUCLIOES IN MONITORING WELL SAMPLES - 2007 Results in Units of pCi/L +/- 1 Sigma Monitoring Well:

'\\....,

MWl::51

',' 'U:'

MW,5t

.:" MW~51;X::;".',

MW-5.1~';;:,':) :.:;;

SanipleName:,:;:;::r: ;,<

':1~')::' MW-51:135"(001): MW~51'~ 135:::(002)

MW~51":135~(OO3) MW"51~135-(004 )

SamplejOate:

.::(

05/30/2001'*.' ::: *. **:il, 07/24/2007',:T 10/02/2007 11/09/2007,;::';:":

Radionuclide Req. MOC Result Result Result Result H-3

< 170

< 159

< 196

<.172 Be-7

< 42

< 39.7

< 27.3

< 37.8 K-40 v

< 52

< 33

<25.7

< 51.8 Mn-54

< 3.94

<4.4

< 2.69

< 3.79 Co-58

< 4.27

< 5.18

< 3.22

< 3.96 Fe-59

< 10.2

< 8.49

< 6.97

< 7.85 Co-60

< 4.48

< 3.84

< 2.92

< 3.66 Zn-65

< 6.69

< 11.1

< 6.38

< 6.88 Sr-90 1

< 0.84

< 0.576

< 0.549

< 0.318 Nb-95

< 6.3'

< 5.32

< 3.22

< 5.59 Zr-95

< 7.32

< 8.52

< 5.35

< 7.11 Ru-106

< 28.6

< 40

< 23.7

< 34.5 Cs-134 15

< 4.37

< 5.09

< 3.05

< 4.13 Cs-137 18

< 4.03

< 4.36 21.6+/-1.92

< 3.7 Ba-140

< 36.3

< 34.7

< 27.6

< 40.2 La-140

< 14.2

< 14.9

< 9.69

< 16.1 Ce-141

< 9.95

< 10.1

< 5.45

< 9.56 Ce-144

< 29.1

< 30.1

< 15.9

< 29.4 Ac-228

<19.4

< 14.1 18 +/- 4.89 '

22.6 +/- 6.95 Note 1: Less than values n<n are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-59

TABLE B-21 CONCENTRATIONS OF RADIONUCLIDESIN MONITORING WELL SAMPLES - 2007 Results in Units of pC ilL +/- 1 Sigma Monitoring Well:

MW-51 MW-5f MW-51 MW~51 Sample Name:

MW-51-163~(001 r MW-51~163-(002) MW-51-163~(003), MW~51

~ 163~(004)

Sample Date:

05/30/2007,'

07/24/2007 10/02/2007::, "

, 11/09/2007" Radionuclide ReJi. MDC Result Result Result Result H-3

< 169

< 166

< 196

< 171 Be-7

< 32.2

< 42

< 44.4

< 33.3 K-40

< 33.3

< 45.8

< 51.4

< 50.5 Mn-54

< 2.92

< 4.04

< 4.94

< 3.41 Co-58

< 3.83

< 4.01

< 5.49

< 3.91 Fe-59

< 9.68

< 8.47

< 11.4

< 8.56 Co-60

< 3.2

< 3.63

< 4.89

< 3.11 Zn-65

< 7.44

< 9.18

< 7.87

< 6.11 Sr-90 1

< 1.36

< 0.521

< 0.364

<0.312 Nb-95

< 5.71

< 5.38

< 6.74

< 5.5 Zr-95

< 6.32

< 7.51

< 9.42

< 7.59 Ru-106

< 32.9

< 40.5

< 41.6

< 31.8 Cs-134 15

< 3.89

< 3.82

< 5.88

< 4.27 Cs-137 18

< 3.45

< 3.78 11.6 +/- 2.4

< 3.51 Ba-140

< 33.2

< 33.6

< 47.2

< 39.2 La-140

< 12.5

< 10.2

< 13.9

< 14.3 Ce-141

< 7.26

< 9.32

< 7.63

< 8.57 Ce-144

< 24.8

< 29.3

< 22.8

< 23.5 Ac-228

< 15.1

< 20.1 24.4 +/- 7.8 23.7 +/- 6.1 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-60

TABLE B-21 CONCENTRATIONS OF RAOIONUCLIOES IN MONITORING WELL SAMPLES - 2007 Results in Units of pC ilL +/- 1 Sigma Monitoring Well: ',.'

MW-51 MW-51 MW.51 C'".... MW-51 Sample Name: ',".

/-:, ':"'"

MW_51-189~(001 )

MW-51~ 189~(002) MW~51-189-(003) MW.51 ~}89~(004),

Sample.Date:..

05/30/2007, 07/24/2007

... 10/0212007.; ;<C,' 1,1/09/2007' "

Radionuclide Req. MOC Result Result Result Result H-3 187 +/- 55.5

< 163

< 196

< 171 Be-7

< 44.4

< 38.2

< 31.8

< 44.9 K-40

< 57

< 45.4

< 37

< 50.9 Mn-54

< 4.26

< 3.93

< 3.21

< 4.38 Co-58

< 4.25

< 4.08

< 3.6

< 4.56 Fe-59

< 10.9

< 8.91

< 8.28

<10.4 Co-60

< 4.63

< 4.31

< 3.04

< 4.05 Zn-65

< 10.3

< 6.95

< 5.9

< 8.58 Sr-90 1

< 1.11

< 0.448

< 0.258

< 0.408 Nb-95

< 6.32

< 4.62

<: 5.27

< 6.12 Zr-95

< 8.85

< 7.7

< 5.88

< 7.78 Ru-106

< 39.7

< 30.3

< 30.6

< 29.7 Cs-134 15

< 4.86

<4.07

< 3.3

< 4.8 Cs-137 18

< 3.82

< 3.58 13.8+/-1.81

< 4.07 Ba-140

< 38.1

< 26.5

< 34.8

< 50.2 La-140

< 15.5

< 9.8

< 12.9

< 16.3 Ce-141

< 9.6

< 7.8

< 8.07

<10.4 Ce-144

< 29.1

< 26

< 23.1

< 28.1 Ac-228

< 18.6

< 15.6

< 15.1

< 17.7 Note 1: Less than values "<" are the MOC values Note 2: A sample is positive if the result is both greater than 3 standard deviations and greater than the MOC.

8-61

TABLE B-22 MILCH ANIMAL CENSUS 2007 THERE ARE NO ANIMALS PRODUCING MILK FOR HUMAN CONSUMPTION WITHIN FIVE MILES OF INDIAN POINT.

8-62

LAND USE CENSUS DESCRIPTION 2007 A comprehensive survey of the of the 5 mile (8 kilometer) area surrounding the Indian Point Site was conducted during the 2007 Spring, Summer and Fall months in accordance with the ODCM Section D 3.5 Radiological Environmental Monitoring Land Use Census Methodology:

Visual inspections were made of the 5-mile area around the Indian Point Site during routine sample collections and emergency plan equipme-nt inspections in the area throughout the year.

Obtained information from the New York Agricultural Statistic Service on milching animals within the 5-mile area surrounding Indian Point Energy Center.

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: This was done while performing quarterly environmental badge change out and field inspections through out the 4 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.

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

Results:

The 2007 land use census indicated there were no new residences that were closer in proximity to IPEC.

NEM performed a complete nearest residence survey with updated distances.

No milch animals were observed during this reporting period within the 5-mile zone or listed in the New York Agricultural Statistic Service.

8-63

/

TABLE B-23 LAND USE CENCUS 2007 INDIAN POINT ENERGY CENTER UNRESTRICTED AREA BOUNDARY AND NEAREST RESIDENCES 2007 Distance to

,Distance to site Distance to site nearest resident, Boundary from Boundary.from from Unit 1 Unit 2 Plant Vent Unit 3 Plant Vent superheater Address' of nearest resident, Dec Point 2004 Census N

RIVER RIVER 1788.1 n SI.

550 636 1907.3 ENE 1478.2 101 E

662 785 1370.9 1103 Lower South SI. Peekskill ESE 569 622 715,2 461 Buchanan SE 553 564 1168.2 223 First SI.

SSE 1239.7 5 Pheasant's Run Buchanan S

700 566 1132.5 320 SSW 755 480 1573.5 240 Eleventh SI.

SW 544 350 301 WSW RIVER RIVER 21 Cove W

RIVER RIVER 1918.7 712 RI. 9W RIVER RIVER 1752.4 NW RIVER RIVER 1692.7 807 RI. 9W Tomkins Cove NNW RIVER RIVER 1609.3 4 River Rd. Tomkins Cove B-64

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 2007 data with historical values. Although other samples were taken and analyzed, values were only tabulated and ploUed 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

1997 1998 1999 2000 200.1 2002 2003 2004 2005 2006 2007 TABLE C-1 DIRECT RADIATION ANNUAL

SUMMARY

1997 - 2007 15.0 15.0 18.0 14.0 15.0 16.0 15.0 15.0 16.0 14.0 15.0 16.0 15.0 15.0 17.0 15.0 15.0 14.0 14.3 13.9 14.7 13.0 13.0 14.0 14.1 14.1 15.9 13.9 14.3 17.5 14.4 14.6 18.8 14.3 14.5 16.2 C-2

FIGURE C-1 DIRECT RADIATION 40.0 1997._ --_.

35.0 30.0

u 25.0 1:

ns

I a

0::: 20.0 E

e-ns Q)

~ 15.0 10.0 5.0 0.0 1997 1998 1999 2000 2001 2002 C-3 2003

~Inner Ring DOuter Ring Control Location 2004 2005 2006 2007

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 TABLE C-2 RADIONUCLIDES IN AIR 1997 to 2007 0.01 0.01 0.02 0.01 0.02 0.01 0.01

. 0.01 0.02 0.02 0.02 0.02 0.01 0.01 0.01 0.01 0.02 0.02 0.01 0.01 0.01 0.01 0.01 0.01 Critical Level (Lc) is less than the aDCM required LLD.

<Lc indicates no positive values above sample critical level.

C-4

< Lc

FIGURE C-2 RADIONUCLIDES IN AIR - GROSS BETA 1997 to 2007 0.051------;----------.:~~==-----------------.

0.04 0.03

~

(3 c.

0.02 0.01 0.00 1997 1998 1999

Includes aDCM and non-aDCM indicator locations.

Gross Beta aDCM required LLD = 0.01 pCi/m 3 2000 2001 2002 c-s t?AJ All aDeM Indicator Locations Control Location 2003 2004 2005 2006 2007

TABLE C-3 RADIONUCLIDES IN HUDSON RIVER WATER 1997 to 2007 (pCi/L) 1997

< Lc 430

< Lc 1998

< Lc 220

< Lc 1999 191 318

< Lc 2000 190 267

< Lc 2001

< Lc 323

< Lc 2002 432 562

< Lc 2003

< Lc

< Lc 2004

< Lc 553

< Lc 2005

< Lc 618

< Lc 2006

< Lc 386

< Lc 2007

< Lc

< Lc 271 409

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

<Lc indicates no positive values above sample critical level.

C-6

.< Lc

< Lc

2000 1800 1600 1400 1200

...J

~ 1000

a.

800 600 400 200 0

1997 1998 1999 Tritium ODCM required LLD = 3000 pCilL FIGURE C-3 HUDSON RIVER WATER - TRITIUM 1997 to 2007 2000 2001 2002 2003 C-7 e1J Inlet (H-3)

~ Discharge (H-3) 2004 2005 2006 2007

TABLE C-4 RADIONUCLIDES IN DRINKING WATER 1997 to 2007 (pC ilL) 1997

< Lc 1998

< Lc 1999

< Lc 2000

< Lc 2001

< Lc 2002

< Lc 2003

< Lc 2004

< Lc 2005

< Lc 2006

< Lc 2007

< Lc

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

<Lc indicates no positive values above sample critical level.

C-8

< Lc

<Lc

< Lc

2000 1800 1600 1400 1200

...J i3 1000 Q,

800 600 400 200 0

1997 1998 1999 Tritium ODCM required LLD = 2000 pCi/L FIGURE C-4 DRINKING WATER - TRITIUM 1997 to 2007 NO IDENTIFIED TRITIUM IN PREVIOUS TEN YEAR 2000 2001 2002 2003 e-g 2004 2005 2006 2007

TABLE C-5 RADIONUCLIDES IN SHORELINE SOIL 1997 to 2007 (pCi/Kg, dry) 1997

< Lc

< Lc 203 1998

< Lc.

< Lc 143 1999 46

< Lc 200 2000 58

< Lc 179 2001 45

< Lc 230 2002

< Lc

< Lc 221 2003

< Lc

< Lc 124 2004

< Lc

< Lc 104 2005

< Lc

< Lc 2006

<Lc

< Lc 120 2007

< Lc

< Lc 156 50

< Lc

,168 Critical Level (Lc) is less than the RETS required LLD.

<Lc indicates no positive values above sample critical level.

C-10 340

< Lc 238 231

.427 238 73 138 174

< Lc

< Lc 232

FIGURE C-5 RADIONUCLIDES IN SHORELINE SOIL 750 1997 to 2007 650 550 450

~

en 350

~ -

(3 c..

250 150 50 1997 1998 1999 2000 2001 2002 2003

~

Indicator (Cs-134)

EB Control (Cs-134)

IiIIlndicator (Cs-137)

Control (Cs-137) 2004 2005 2006 2007

-50~----------------------------------~----------------------------------------------------~

'Cs-134 aDCM required LLD = 150 pCilKg, dry Cs-137 aDCM required LLD = 175 pCi/Kg, dry C-11

TABLE C-6 RADIONUCLIDIES IN BROAD LEAF VEGETATION 1997 to 2007 (pCi/Kg, wet) 1997

< Lc

< Lc 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 15 22 Critical Level (Lc) is less than the aDCM required LLD.

<Lc indicates no positive values above sample critical level.

C-12

Q) ;:

C)

~ -

(3 Co FIGURE C-6 BROAD LEAF VEGETATION - Cs-137 1997 to 2007 100~--------------------------------------------------------------------------------------.

80 60 40 20 IS) Indicator (Cs-137) 121 Control (Cs-137) 01

[::di~

I§l

~<>J

~

j i

I 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 aDCM required LLD = 80 pCi/Kg, wet C-13

TABLE C-7 RADIONUCLIDES IN FISH AND INVERlEBRATES 1997 to 2007 1997

< Lc

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

<Lc indicates no positive values above sample critical level.

C-14

200 180 160 140 120 Q;

~

c; 100

~

U Q.

80 60 40 20 0

1997 1998 1999 FIGURE C-7 FISH AND INVERTEBRATES - Cs-137 1997 to 2007 NO IDENTIFIED Cs-137IN PREVIOUS TEN YEAR HISTORY 2000 2001 2002 2003 Cs-137 ODCM required LLD = 150 pCilKg, wet C-15

~ Indicator (Cs-137)

EJ Control (Cs-137) 2004 2005 2006 2007

,.: -~. ~;

APPENDIX D INTERLABORATORY COMPARISON PROGRAM

APPENDIX 0 0.1 PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM),- Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include. sample media for which samples are routinely collected and for which comparison samples are commercially available.

Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring.

To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of two independent laboratories to provide quality assurance comparison samples. The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S. Department of Commerce's National Institute of Standards and Technology (NIST) in Gaithersburg, Maryland.

Analytics supplies 'sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are' prepared and analyzed by the JAF Environmental Laboratory using standard laboratory procedures.

Analytics issues a statistical summary report of the results.

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

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

The samples are prepared by NIST to present specific challenges to participating laboratories. NIST supplies sample media as blind sample spikes.

These samples are prepared and analyzed by the JAF Environmental Laboratory and the results are submitted to the Entergy Nuclear representative for evaluating the laboratory's performance.

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

The 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.

0-1

Laboratory blank results are analyzed using control charts.

0.2 PROGRAM SCHEDULE TABLE 0-1 QA PROGRAM SCHEDULE Water Gross Beta 1

Water Tritium 3

Water 1-131 4

Water Mixed Gamma 4

Air Gross Beta 3

Air 1-131 4

Air Mixed Gamma 2

Milk 1-131 3

Milk Mixed Gamma 3

Soil Mixed Gamma 1

Vegetation Mixed Gamma 2

TOTAL SAMPLE INVENTORY 30 0.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the a<;:curacy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

0.3.1 SAMPLE RESULTS EVALUATION 1

1 2

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

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 0.3.1 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

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

>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is 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 Analytics and NIST Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

0-3

0.4 PROGRAM RESULTS

SUMMARY

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

0.4.1 ANAL YTICS QA SAMPLES RESULTS Thirty QA blind spike samples were analyzed as part of Analytics 2007 Interlaboratory Comparison,Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131 Air Particulate Filter: Mixed Gamma Emitters, Gross Beta 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 126 individual analyses on the 30 QA samples. Of the 126 analyses performed, 126 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2007 program.

0.4.2 NIST QA SAMPLES RESULTS In 2007, JAF Environmental Laboratory participated in the NEI/NIST Measurement Assurance Program. Two QA blind spike samples were analyzed. The following sample media were evaluated as part of the comparison program.

Air Particulate Filter: Mixed Gamma Emitters Water: Mixed Gamma Emitters The JAF Environmental Laboratory performed 8 individual analyses on the two QA samples. Of the 8 analyses performed, 8 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no non-conformities in the 2007 program.

D-4

0.4.3 NUMERICAL RESULTS TABLES TABLE 0-3 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE 10 NO.

MEDIUM 06/14/2007 E5352-05 Filter 06/14/2007 E5346-09 Filter 12/06/2007 E5767-05 Filter (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable ANALYSIS GROSS BETA GROSS BETA GROSS BETA pCi +/-1 sigma pCi +/-2 sigma 78.3

+/-

2.2 79.6

+/-

2.3 72.8 2.43

+/-

76.6

+/-

2.2 Mean =

78.2

+/-

1.3 78.0

+/-

2.2 82.0

+/-

2.3 75~0 3

+/-

80.0

+/-

2.3 Mean =

80.0

+/-

1.3 76.6

+/-

2.2 82.2

+/-

2.3 73.8 2.46

+/-

76.8

+/-

2.2 Mean =

78.5

+/-

1.3 D-5 RATIO (1) 1.07 A 1.07 A 1.06 A

SAMPLE DATE IDNO.

MEDIUM 3/22/2007 E5331-05 Water 12/6/2007 E5542-09 Water 12/6/2007 E5543-09 Water (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable TABLE 0*3 (Continued)

Tritium Analysis of Water JAF ELAB RESULTS ANALYSIS pCi/liter +/-1 sigma H-3 5510 177 5584 179 5490 178 Mean =

5528

+/-

103 H-3 9671

+/-

208 9901

+/-

210 Mean =

9786

+/-

148 H-3 9684

+/-

209 9843

+/-

210 Mean =

9764

+/-

148 D-6 REFERENCE LAB* RATIO

. pCi/liter +/-2 sigma (1 )

5010

+/-

167 1.10 A 9000

+/-

300 1.09 A 9000

+/-

300 1.08 A

SAMPLE DATE 10 NO.

MEDIUM 11109/2007 A21998-0S Water (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable TABLE 0-3 (Continued)

Gross Beta Analysis of Water JAF ELAB RESULTS ANALYSIS pCilliter +/-1 sigma 9.11E+OS

+/- 1.S0E+04 GROSS 8.9SE+OS

+/- 1.49E+04 BETA 8.91E+OS

+/- 1.48E+04 Mean = 8.99E+OS

+/- 8.60E+03 D-7 REFERENCE LAB*

RATIO pCi/liter +/-2 sigma (1 )

9.30E+05 +/-

0.97 A S.S8E+04

TABLE 0-3 (Continued) 1-131 Gamma Analysis of Ai~ Charcoal SAMPLE.

DATE 10 NO.

MEDIUM E5315-09 3/22/2007 Air E5355-05 6/14/2007 Air E5466-05 9/13/2007 Air E5446-09 9/13/2007 Air (1) Ratio = Reported/Analytics.

,

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable ANALYSIS 1-131 1-131 1-131 1-131 JAF ELAB RESULTS pCi +/-1 sigma 66.8

+/-

4.46 69.8

+/-

4.55.

61.7

.+/-

3.99 72.7

+/-

5.2 Mean =

67.8

+/-

2.29 72.7

+/-

4.22 79.7

+/-

5.09 83.0

+/-

4.16 Mean =

78.5

+/-

2.60 74.4

+/-

3.46 65.7

+/-

3.92 64.5

+/-

3.13 Mean =

68.2

+/-

2.03 67.8

+/-

3.34 61.8

+/-

3.27 66.3

+/-

3.18 Mean =

65.3

+/-

1.88 D-8 REFERENCE LAB* RATIO pCi +/-2 sigma (1 )

70.0

+/-

2.3 0.97 A

.79.0

+/-

2.63 0.99 A

69.6

+/-

2.32 0.98 A

70.0

+/-

2 0.93 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM G

A I

fW t amma nalysis 0 a er SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO.

MEDIUM ANALYSIS pCilliter +/-1 sigma 4/18/2007 E5332-05 Water 153 Ce-141 151 148 Mean =

151 115 Cr-51 139 Mean =

127 83.0 Cs-134 94.3 102 Mean =

93.1 201 Cs-137 195 197 Mean =

198 65.6 Co-58 67.0 59.8 Mean =

64.1 168 Mn-54 146 154 Mean =

156 63.1 Fe-59 58.1 58.6 Mean==

59.9 830 Zn-65 817 825 Mean==

824 123 Co-60 128 129 Mean =

127 100 99.4 1-131 **

90.9 104 Mean==

98.6 (1) Ratio = Reported/Analytlcs.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A==Acceptable U==Unacceptable 0-9

+/-

pCi/liter +/-2 sigma 7.98 2.4 3.63 140

+/-

4.65 3.0 12.1 15.4 104 3.47 9.8 6.11 2.03 2.43 91.2

+/-

3.04 2.3 7.53 2.41 196

+/-

6.53 3.08 2.8 6.04 1.71 63.5

+/-

2.12 2.27 2.2 7.48 2.36 144

+/-

4.79 2.89 2.8 6.4 2.26 2.5 58.0

+/-

1.93 2.4 23 7.46 9.26 776

+/-

25.9 8.6 4.79 1.6 1.95 126

+/-

4.2 1.8 4.75 4.9 4.32 89.8

+/-

2.99 4.32 2.3 RATIO (1 )

1.08 A 1.22 A 1.02 A 1.01 A

1.01 A

1.08 A 1.03 A 1.06 A 1.01 A

1.10 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 a er G

A fW t SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO.

MEDIUM ANALYSIS pCilliter +/-1 sigma 6/14/2007 E5345-09 Water 158 Ce-141 181 169 Mean =

169

, 428 Cr-51 420 461 Mean =

436 208 Cs-134 204 202 Mean =

205

'132 Cs-137 141 140 Mean =

138 164 Co-58 166 170 Mean =

167 147 Mn-54 154 159 Mean =

153 141 Fe-59 145 130 Mean =

139 277 Zn-65 293 300 Mean =

290 192 Co-60 195 189 Mean =

192 108 1-131**

102 103 Mean =

104 (1) Ratio = Reported/Analytlcs.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-10

+/-

pCilliter +/-2 sigma 3.78 3.47 9.27 160

+/-

5 3.5 20.1 16.3 52.3 411

+/-

14 19.5 3.6 2.73 10.3 194

+/-

6 3.7 2.99 2.34 135

+/-

5 8.12 3.0 3.3 2.49 8.93 159

+/-

5 3.3 3.32 2.41 133 8.67

+/-

4 3.2 4.05 2.81 10.4 134

+/-

4 3.8 7.04 5.05 268

+/-

9 18.7 6.9 2.79 2

191

+/-

6 7.36 2.7 B.97 2.13 102

+/-

3 2.37 3.2 RATIO (1 )

1.06 A 1.06 A 1.05 A 1.01 A

1.05 A 1.15 A 1.03 A 1.08 A 1.01 A

1.02 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 a er G

A I

fW t SAMPLE JAF ELAB RESUL TS REFERENCE LAB*

DATE IDNO.

MEDIUM ANALYSIS pCilliter+/-1 sigma 9/13/2007 E5463-05 Water 198 179 Ce-141 188 Mean =

188 253 Cr-51 245 200 Mean =

233 134 Cs-134 134 150 Mean =

139 105 Cs-137 107 109 Mean =

107 103 Co-58 103 86.5 Mean =

97.5 173 Mn-54 161 158 Mean =

164 105 Fe-59 106 117 Mean =

109 204 Zn-65 212 208 Mean =

208 121 Co-60 128 144 Mean =

131 83.5 1-131**

80.3 86,1 Mean =

83.3 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 0-11

+/-

pCi/liter +/-2 sigma 9.06 9.53 182

+/-

6.05 10.8 5.7 37.5.

41.3 249

+/-

8.29 42.5 23.4 8.9 9.08 8.93 127

+/-

4.22 5.2 6.75 7.68 7.87 112

+/-

3.74 4.3 6.62 7.11 7.35 98.1

+/-

3.27 4.1 8.22 8.73 8.93 144

+/-

4.8 5.0 7,93 8,51 95.1 9,07

+/-

3,17 4.9 13,8 15.9 174

+/-

5,8 16,3 8.9 5,3 6.28 6.72 127

+/-

4.24 3.5 1.77 2.51 80.1 2.38

+/-

2.67 1,3 RATIO (1 )

1.03 A 0.93 A 1.10 A 0.96 A 0.99 A

1.14 A 1.15 A 1.20 A 1.03 A 1.04 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM G

A I

fW t am rna nalysis 0 a er SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO.

MEDIUM ANALYSIS pCilliter +/-1 sigma 12/6/2007 E5544-09 Water 156 Ce-141 155 153 Mean =

155 657 Cr-51 557 611 Mean =

608 168 Cs-134 155 161 Mean =

161 191 Cs-137 177 172 Mean =

180 214 Co-58 223 202 Mean =

213 240 Mn-54 228 231 Mean =

233 177 Fe-59 182 169 Mean =

176 296 Zn-65 287 278 Mean =

287 229 Co-60 228 237 Mean =

231 73.7 1-131**

74.5 76.3 Mean =

74.8 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable 0-12

+/-

pCi/liter +/-2 sigma 10.7 8.47 11.5 157

+/-

5 5.9 52 40.6 58.7 572

+/-

19 29.4 8.91 7.61 9.97 153

+/-

5 5.1 8.36 7.05 185

+/-

6 9.27 4.8 8.97 7.81 10.1 194

+/-

6 5.2 9.27 7.81 10.9 212

+/-

7 5.4 9.99 8.84

.11.6 166

+/-

6 5.9 16.6 14.3 261

+/-

9 19.3 9.7 6.95 6.05 8.36 236

+/-

8 4.1 3.53 1.97 72.0

+/-

2 3.37 1.8 RATIO (1 )

0.99 A 1.06 A 1.05 A 0.97 A 1.10 A 1.10 A 1.06 A 1.10 A 0.98 A 1.04 A

TABLE 0*3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 I

G A

fM"lk SAMPLE JAF ELAB RESULTS DATE 10 NO.

MEDIUM ANALYSIS pCilliter +/-1 sigma 3/22/2007 E5316-09 MILK 304 Ce-141 304 293 Mean =

300 227 Cr-51 204 227 Mean =

219 110 Cs-134 111 107 Mean =

109 227 Cs-137 232 232 Mean =

230 95.6 Co-58 101 98.0 Mean =

98.2 189 Mn-54 189 189 Mean =

189 114 Fe-59 127 114 Mean =

118 1040 Zn-65 1090 1050 Mean =

1060 144 Co-60 146 144 Mean =

145 97 1-131**

91.2 95.5 Mean =

94.6 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-13

+/-

.+/-

+/-

4.2 5.4 5.5 2.9 16.6 22.1 22.9 12.0 2.8 3.2 3.5 1.8 3.5 4.1

. 4.7 2.4 3.1 3.3 3.8 2.0 3.6 3.9 4.5 2.3 3.8 4.1 4.6 2.4 11.6 12.9 14.7 7.6 2.4 2.6 3.0 1.5 3.9 4.1 5.3 2.6 REFERENCE LAB*

. pCi/liter +/-2 sigma 297

+/-

9.9 245

+/-

8.2 112

+/-

3.7 234

+/-

7.8 99.0

+/-

3.3 182

+/-

6.1 106

+/-

3.5 1000

+/-

33.3 152

+/-

5.1 85.0

+/-

2.8 RATIO (1 )

1.01 A

0.90 A 0.98 A 0.98 A 0.99 A

1.04 A 1.12 A 1.06 A 0.95 A 1.11 A

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysls 0 I

G A

fM"lk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO.

MEDIUM ANALYSIS pCilliter +/-1 sigma 6/14/2007 E5353-05 MILK 209 Ce-141 205 192 Mean =

202 519 Cr-51 575 543 Mean =

546 249 Cs-134 257 260 Mean =

255 162 Cs-137 169 170 Mean =

167 198 Co-58 211 208 Mean =

206 177 Mn-54 185 185 Mean =

182 184 Fe-59 182 181 Mean =

182 352 Zn-65 379 354 Mean =

362 237 Co-60 242 240 Mean =

240 65.4 1~131**

65.9 65.9 Mean =

65.7 (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A=Acceptable U=Unacceptable D-14

+/-

pCilliter +/-2 sigma 4.33 5.94 4.16

200,

+/-

6.66 2.82 22.1 26.9 512 19.2

+/-

17.1 13.3 4.19 4.55 242 3.47

+/-

8.06 2.36 3.45 3.86 3.06 169

+/-

5.63 2.00 3.81 4.14 198 3.30

+/-

6.61 2.17 3.55 3.94 166 3.19

+/-

5.53 2.06 4.42 4.75 167 3.78

+/-

5.56 2.50 7.63 10.6 334

+/-

11.1 6.73 4.90 3.02 3.27 2.62 238

+/-

7.93 1.72 2.07 2.29 1.87 70.1

+/-

2.34 1.20 RATIO (1 )

1.01 A

1.07 A 1.06 A 0.99 A

1.04 A 1.10 A 1.09 A 1.08 A 1.01 A

0.94 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 I

G A

fM"lk SAMPLE JAF ELAB RESUL TS REFERENCE LAB*

DATE 10 NO.

MEDIUM ANALYSIS pCi/iiter +/-1 sigma 9/13/2007 E5465-05 MILK 188 Ce-141 239 198 Mean :::

208 200 Cr-51 250 320 Mean :::

257 150 Cs-134 156 149 Mean :::

152 109 Cs-137 144 126 Mean :::

126 86.5 Co-58 127 111 Mean :::

108 158 Mn-54 176 184 Mean :::

173 117 Fe-59 113 117 Mean :::

116 208 Zn-65 226 232 Mean :::

222 144 Co-60 151 139 Mean :::

145 77.6 1-131**

76.4 72.7 Mean :::

75.6 (1) Ratio::: Reported/Analytics.

Sample provided by Analytics, Inc.

- Result determined by Resin Extraction/Gamma Spectral Analysis.

A:::Acceptable U:::Unacceptable 0-15

+/-

pCi/liter +/-2 sigma 10.8 10.5 211 9.94

+/-

7.04 6.02 42.5 41.4 289 42.1

+/-

9.65 24.3 8.93 8.74 147

+/-

4.91 8.69 5.07 7.87 8.32 7.38 131

+/-

4.35 4.54 7.35 8.17 7.19.

114

+/-

3.80 4.38 8.93 9.18 8.60 168

+/-

5.59 5.14 9.07 9.94 8.44 111

+/-

3.69 5.29 16.3 17.5 15.7 202

+/-

6.74 9.54 6.72 6.83 5.89 148

+/-

4.94 3.75 2.52 2.34 3.10 85.2

+/-

2.84 1.54 RATIO (1) 0.99 A 0.89 A

1.03 A 0.96 A 0.95 A 1.03 A 1.04 A 1.10 A 0.98 A 0.89 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 Ir a leu a e I er G

A I

fA* P rf I t F" It SAMPLE JAF ELAB RESUL TS REFERENCE LAB*

DATE IDNO.

MEDIUM 3/22/2007 E5333-05*

FILTER (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable ANALYSIS Ce-141 Mean =

Cr-51 Mean =

Cs-134 Mean =

Cs-137 Mean =

Co-58 Mean =

Mn-54 Mean =

Fe-59 Mean =

Zn-65 Mean =

Co-60 Mean =

0-16 pCi +/-1 sigma pCi +/-2 sigma 234

+/-

3.01 230

+/-

2.54 233

+/-

7.78 246

+/-

8.32 237

+/-

3.07 206

+/-

15.8 197

+/-

15.6 192

+/-

6.41 230

+/-

40.0 211

+/-

15.3 95.8

+/-

1.99 76.8

+/-

3.02 87.9

+/-

2.93 95.6

+/-

5.43 89.4

+/-

2.17 188

+/-

2.43 179

+/-

2.04 185

+/-

6.15 186

+/-

6.48 184

+/-

2.41 76.9

+/-

2.18 77

+/-.

2.09 77.7

+/-

2.59 76.4

+/-

6.07 76.8

+/-

2.26 160

+/-

2.62 150

+/-

2.17 144

+/-

4.78 157

+/-

6.71 156

+/-

2.51 93.1

+/-

3.46 84.2

+/-

2.94 83.1

+/-

2.77 93.1

+/-

8.98 90.1

+/-

3.35 870

+/-

8.82 852

+/-

7.55 787

+/-

26.2 856

+/-

23.5 859

+/-

8.74 114

+/-

1.69 118

+/-

1.46 120

+/-

3.99 111

+/-

4.42 114

+/-

1.65 RATIO (1 )

1.02 A 1.10 A 1.02 A 1.00 A 0.99 A 1.08 A 1.08 A 1.09 A 0.95 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM amma nalysis 0 Ir a leu a e I er G

A fA" P rf I t Fit SAMPLE JAF ELAB RESUL TS REFERENCE LAB*

DATE 10 NO.

MEDIUM 9/13/2007 E5464-05 FILTER (1 ) RatiO = Reportedl Analytlcs.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable ANALYSIS Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi +/-1 sigma 195

+/-

194

+/-

209

+/-

Mean =

199

+/-

238

+/-

256

+/-

307

+/-

Mean =

267

+/-

163

+/-

151

+/-

177

+/-

Mean =

164

+/-

117

+/-

123

+/-

120

+/-

Mean =

120

+/-

109

+/-

112

+/-

113

+/-

Mean =

111

+/-

179

+/-

166

+/-

168

+/-

Mean =

171

+/-

117

+/-

130

+/-

110

+/-

Mean =

119

+/-

211

+/-

239

+/-

237

+/-

Mean =

229

+/-

141

+/-

140

+/-

135

+/-

Mean =

139

+/-

D-17 pCi +/-2 sigma 5.84 5.05 6.01 207

+/-

6.90 3.3 27.9 23 33.5 284

+/-

9.46 16.4 8.66 6.52 145 10.2

+/-

4.82 5.0 6.54 5.42 7.64 128

+/-

4.27 3.8 7

5.44 7.41 112

+/-

3.73 3.9 8.69 6.59 164

+/-

5.48 9.02 4.7 8.96 7.02 9.8 108

+/-

3.61 5.0 15.1 12.6 198

+/-

6.61 18.5 9.0 6.38 4.88 145

+/-

4.84 7

3.6 RATIO (1 )

0.96 A 0.94 A 1.13 A 0.94 A 0.99 A 1.04 A 1.10 A 1.16 A 0.96 A

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM SAMPLE DATE 10 NO.

MEDIUM 6/14/2005 E5354-05 SOIL (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable am rna nalYSIS 0 01 G

A fS "I JAF ELAB RESUL TS ANALYSIS pCi/g +/-1 sigma 0.164

+/-

0.007 Ce-141 0.144

+/-

0.014 0.190

+/-

0.012 Mean =

0.166

+/-

0.007 0.413

+/-

0.041 Cr-51 0.401

+/-

0.071 0.387

+/-

0.057*

Mean =

0.400

+/-

0.033 0.218

+/-

0.007 Cs-134 0.218

+/-

0.013 0.220

+/-

0.009 Mean =

0.219

+/-

0.006 0.242

+/-

0.007 Cs-137 0.249

+/-

0.013 0.251

+/-

0.008 Mean =

0.247

+/-

0.006 0.166

+/-

0.006 Co-58 0.154

+/-

0.012 0.169

+/-

0.007 Mean =

0.163

+/-

0.005 0.137

+/-

0.006 Mn-54 0.161

+/-

0.011 0.152

+/-

0.007 Mean =

0.150

+/-

0.005 0.141

+/-

0.009 Fe-59 0.147

+/-

0.016 0.144

+/-

0.009 Mean =

0.144

+/-

0.007 0.315

+/-

0.013 Zn-65 0.305

+/-

0.023 0.306

+/-

0.014 Mean =

0.309

+/-

0.010 0.201

+/-

0.005 Co-60 0.192

+/-

0.010 0.196

+/-

0.005 Mean =

0.196

+/-

0.004 D:-18 REFERENCE LAB*

pCi/g +/-2 sigma 0.178

+/-

0.006 0.456

+/-

0.015 0.215

+/-

0.007 0.248

+/-

0.008 0.176

+/-

0.006 0.148

+/-

0.005 0.148

+/-

0.005 0.297

+/-

0.010 0.212

+/-

0.007 RATIO (1 )

0.93 A

0.88 A 1.02 A 1.00 A 0.93 A

1.01 A

0.97 A 1.04 A 0.93 A

TABLE D-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM SAMPLE DATE IDNO.

MEDIUM 6/14/2007 E5356-05 VEG (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable.

amma nalysis 0 ege a Ion G

A tv t f JAF ELAB RESUL TS ANALYSIS pCi/g +/-1 sigma 0.158

+/-

0.010 Ce-141 0.145

+/-

0.005 0.154

+/-

0.007 Mean =

0.152

+/-

0.004 0.404

+/-

0.050 Cr-51 0.349

+/-

0.028 0.388

+/-

0.043 Mean =

0.380

+/-

0.024 0.210

+/-

0.010 Cs-134 0.215

+/-

0.006 0.222

+/-

0.009 Mean =

0.216

+/-

0.005 0.132

+/-

0.008 Cs-137 0.134

+/-

0.005 0.126

+/-

0.008 Mean =

0.131

+/-

0.004 0.145

+/-

0.010 Co-58 0.151

+/-

0.005 0.173

+/-

0.008 Mean =

0.156

+/-

0.005 0.144

+/-

0.009 Mn-54 0.137

+/-

0.005 0.138

+/-

0.008 Mean =

0.140

+/-

0.004 0.122

+/-

0.013 Fe-59 0.141

+/-

0.007 0.143

+/-

0.011 Mean =

0.135

+/-

0.006 0.241

+/-

0.021 Zn-65 0.275

+/-

0.011 0.279

+/-

0.018 Mean =

0.265

+/-

0.010 0.188

+/-

0.008 Co-60 0.182

+/-

0.004 0.193

+/-

0.007 Mean =

0.188

+/-

0.004 D-19..

REFERENCE LAB*

pCi/g +/-2 sigma 0.161

+/-

0.005 0.413

+/-

0.014 0.195

+/-

0.007 0.136

+/-

0.005 0.160

+/-

0.005 0.133 +/-

0.004 0.135

+/-

0.005 0.270 +/-

0.009 0.192

+/-

0.006 RATIO (1 )

0.95 A 0.92 A 1.11 A

0.96 A

0.98 A

1.05 A 1.00 A 0.98 A

0.98 A

TABLE 0*3 (Continued)

INTERLABORATORY COMPARISON PROGRAM SAMPLE DATE 10 NO.

MEDIUM 9/13/2007 E5447-09 VEG (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc.

A=Acceptable U=Unacceptable amma nalysis 0 ege a Ion G

A tV t f JAF ELAB RESULTS ANALYSIS pCi/g +/-1 sigma 0.342

+/-.

0.016 Ce-141 0.298

+/-

0.015 0.312

+/-

0.014 Mean =

0.317

+/-

0.009 0.409

+/-

0.070 Cr-51 0.392

+/-

0.068 0.433

+/-

0.063 Mean =

0.411

+/-

0.039 0.269

+/-

0.026 Cs-134 0.221

+/-

0.018 0.243

.+/-

0.016 Mean =

0.244

+/-

0.012 0.224

+/-

0.015 Cs-137 0.206

+/-

0.014 0.220

+/-

0.014 Mean =

0.217

+/-

0.008 0.161

+/-

0.013 Co-58 0.166

+/-

0.014 0.179

+/-

0.013 Mean =

0.169

+/-

0.008 0.282

+/-

0.016 Mn-54 0.275

+/-

0.016 0.240

+/-

0.014 Mean =

0.266

+/-

0.009 0.178

+/-

0.017 Fe-59 0.169

+/-

0.019 0.185

+/-

0.017 Mean =

0.177

+/-

0.010 0.346

+/-

0.032 Zn-65 0.392

+/-

0.031 0.379

+/-

0.029 Mean =

0.372

+/-

0.018 0.244

+/-

0.012 Co-60 0.235

+/-

0.012 0.235

+/-

0.012 Mean =

0.238

+/-

0.005 D-20 REFERENCE LAB*

pCi/g +/-2 sigma 0.333.+/-

0.011 0.457 +/-

0.015 0.233 +/-

0.008 0.206 +/-

0.007 0.180 +/-

0.006 0.265 +/-

0.009 0.175 +/-

0.006 0.319 +/-

0.001 0.234 +/-

0.008 RATIO (1 )

0.95 A 0.90 A

1.05 A 1.05 A 0.94 A

1.00 A 1.01 A

1.17 A 1.02 A

TABLE 0-3 (Continued)

INTERLABORATORY COMPARISON PROGRAM SAMPLE DATE 10 NO.

MEDIUM 4123/2007 1911-4 Water (1) Ratio = Reported/Analytics.

Sample provided by NIST A=Acceptable U=Unacceptable amma nalysis 0 G

A I

fNISTW ater JAF ELAB RESULTS ANALYSIS Bq/g +/-1 sigma 300.8

+/-

2.09 Co-57 299.7

+/-

2.09 303.4

+/-

2.10 Mean =

301.3

+/-

1.21 306.4

+/-

2.38 Ba-133 312.7

+/-

2.35 312.3

+/-

2.27 Mean =

310.4

+/-

1.35 283.8

+/-

2.32 Cs-137 290.1

+/-

2.31 291.9

+/-

2.22 Mean =

288.6

+/-

1.32 190.6

+/-

1.69 Co-60 196.5

+/-

1.69 193.9

+/-

1.57 Mean =

193.6

+/-

0.95 0-21 REFERENCE LAB*

Bq/g +/-2 sigma 310.7 +/-

2.05 326.7 +/-

3.1 308.4 +/-

2.31 202.4 +/-

1.01 RATIO (1 )

0.97 A

0.95 A 0.94 A 0.96 A

TABLE 0*3 (Continued)

INTERLABORATORY COMPARISON PROGRAM SAMPLE DATE 10 NO.

MEDIUM 4/23/2007 1912-11 Filter (1) Ratio = Reported/Analytics.

Sample provided by NIST A=Acceptable U=Unacceptable G

A I

f NIST Fit amma narysrs 0 r er JAF ELAB RESUL TS ANALYSIS Bq/filter +/-1 sigma 1077

+/-

Co-57 1073

+/-

1143

+/-

Mean =

1098

+/-

1006

+/-

Ba-133 1003

+/-

1006

+/-

Mean =

1005

+/-

743.7

+/-

Cs-137 725.2

+/-

777.0

+/-

Mean =

748.6

+/-

969.4

+/-

Co-60 962.0

+/-

976.8

+/-

Mean =

969.4

+/-

D-22 REFERENCE LAB*

Bq/filter +/-2 sigma 4.0 4.6 4.8 1089 +/-

10.9 2.6 5.2 6.0 1048 5.4

+/-

10.5 3.2 4.9 5.7 5.0 766.1

+/-

7.7 3.0 5.2 6.1 4.9 987.0 +/-

9.9 3.1 RATIO (1 )

1.01 A

0.96 A 0.98 A 0.98 A

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).

0-23

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